· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (2024)

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (1)

~' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS)

ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina 05000400

AUTH. NANE AUTHOR AFFILIATIONZINNERNANe B. R. Carolina Power Cc Light Co.

RECIP. NANE RECIPIENT AFFILIATIONDENTONi H. R. Office of Nuclear Reactor Regulationi" Director (post 851125

SUBJECT: Forwards addi inFo re emergency operating procedures inresponse to audit conducted on Sb0710 Ze 11. Encl responsessatisfy util commitments re training program documented inBb0929 ltr 5 Sb0814 meeting.

DISTRIBUTION CODE: AOOSD COPIEB RECEIVED: LTR t ENCL J BIIE:TITLE: QR/Licensing Submittal: Suppl 1 to NUREG-0737(Generic Ltr 82-33)

NOTES: Application for permit renewal filed. 05000400

REC IP IENTID CODE/NANE

PWR-A ADTSPWR-A EICSBPWR-A PD2 LABUCKLEY, BPWR-A RBB.

E

INTERNAL: ADN/LFNBNRR BWR ADTSNRR PWR-B ADTS

REG FILES

EXTERNAL: LPDRNSIC

COPIESLTTR ENCL

1 1

2 21 1

1 i.'1

01

'1 1

1 1

1 1

1 1

1 1

RECIPIENTID CODE/NANE

PWR-A EBPWR-A FQBPWR-A PD2 PDPWR-A PBB

IE/DEPER/EPBNRR PAULSONe,'WNRR/DSRO ENRITNRR/DSRO/RSIBRGN2

NRC PDR

COPIESLTTR ENCL

1

1

7 71

3 31 1

1

1 1

1 1

1 1

TOTAL NUNBER OF COPIES REQUIRED'TTR 31 ENCL 30

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (2)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (3)

@ME,Carolina Power 8 Light Company

SENT zm SERIAL: NLS-86-379

Mr. Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationUnited States Nuclear Regulatory CommissionWashington, DC 20555

SHEARON HARRIS NUCLEAR POWER PLANTUNIT NO. 1 - DOCKET NO. 50-000EMERGENCY OPERATING PROCEDURES

Dear Mr. Denton:

Carolina Power R Light Company (CPRL) hereby submits additional informationconcerning the Shearon Harris Nuclear Power Plant (SHNPP) Emergency OperatingProcedures. The attached information (Enclosure 1) is provided in response to NRC

" concerns identified during an audit of the SHNPP Emergency Operating Proceduresconducted on 3uly 10 and 11, 1986. Resolution of these concerns was discussed in asubsequent meeting with the NRC on August 10, 1986. The attached responses satisfyCPRL's commitments concerning the training program documented in CPdcL letter datedAugust 29, 1986 and discussed in the August 10, 1986 meeting.

Several of the NRC's concerns relate to the Procedures Generation Package (PCP). Itshould be noted, however, that the PCP is not the governing document for licensedoperator training at SHNPP. Plant Training Instructions and the SHNPP FSAR providethe training requirements for operators. Emergency Operating Procedure training andevaluation have always been a requirement of these documents. The PCP will be revisedto cover the NRC's comments, but it should be recognized that the Training Instructionsand the FSAR remain the controlling documents.

,If you have any questions on this subject or require additional information, please contactme at (919) 836-6202

Yours very truly,

3HE/mf (50193DK)

Enclosure

. R. Zi mermanager

Nuclear Licensing Section

CC: Mr. B. C. Buckley (NRC)Mr. G. F. Maxwell (NRC-SHNPP)Dr. 3. Nelson Grace (NRC-RII)

Sbi00904S2 Sb100PDR *DOCK 05000400F PDR

411 Fayettevilte Street o P. O. Box 155'1 o Raleigh, N, C. 27602

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (5)

ENCLOSURE 1

Concern IA

Certain plant-specific information which is called for in theWestinghouse ERG's has not yet been provided in the Harris EOPs. Theapplicant should perform a systematic review of training to assure thatthe information that is missing has been included in the trainingprogram. Evidence that current operators have all of the required skillsand knowledge necessary to implement the EOPs should be documented forNRC review.

~Res oese

A systematic review of the SHNPP EOP network and training to support theEOP network has been completed'ttachment 1 is a WOG/SHNPP Step Matrixidentifying where, plant, specific information was not provided.Attachment 2, "Emergency Procedures and Task Training Matrix" providesdocumentation as to where training to support the "deleted plant specificinformation" was- conducted. The matrix includes both the Cold LicenseTraining Program which has been completed and the Hot License TrainingProgram which will be conducted beginning in mid 1987. The materials tosupport the Hot License Training Program are presently under developmentand are scheduled to be completed by mid 1987.

In our letter of August 29, 1986, CP&L committed to complete additionaltraining and/or EOP revision to ensure operator skill in using the EOPsprior to fuel load. Attachment 2 shows that training on plant specificinformation required to execute Emergency Operating Procedures isadequately provided in Cold License System Training, Continuing Training(1985), 'and Prelicense Review Training. CP&L considers the currentstatus of EOPs and training to be adequate to ensure operator skill inusing the EOPs. The commitments'.in Attachment 1 to revise the proceduresare'enhancements to „the training that has already been provided, and arenot necessary prior to fuel load. These revisions will be completed byDecember 12, 1986 along with the human factors update as committed to inour August 29, 1986 letter.

Three tasks have been identified for which additional training will beprovided. These tasks are considered to be minor items and are listed inAttachment 3. This training will be incorporated in the LicensedRequalification Program and completed by December 31, '1986.

Attachment 2 also shows that training on the deleted plant specificinformation is covered by the various portions of the Hot LicenseTraining Program. Specifically the Hot License EOP Training will includestep-by-step discussion of each procedure and bases for each step.Additionally, the EOPs will be fully exercised during the simulatorportion of the Hot License Training.

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (7)

Evidence that current operators have all the required skills andknowledge necessary to implement the EOPs is provided by the following:

1. The NRC licenses each operator. The licensingprocess includes a written exam, simulator exam, anda plant oral walk-through. Each exam relates in partto the emergency operating procedures. Successfulcompletion of the exam provides adequate evidencethat the operator is capable of utilizing theEmergency Operating Procedures.

2. Prior to the NRC exam, CP&L administers an NRC-stylewritten, simulator and plant oral walk-through examto ensure that the operators are well prepared tooperate safely and are ready to be licensed by theNRC.

3 ~ During, the simulator training program (approximately9 weeks for Cold License) the students are evaluatedon their performance. The scenarios include normaloperations, off"normal operations, and emergencyoperating procedures. The scenarios have single andmultiple failures included. Three examples ofsimulator scenarios are provided as Attachment 4.

4. Written exams are given throughout the classroomtraining phases. These exams also include emergencyoperating procedures.

;5. NRC Region-II conducted an Operational, ReadinessInspection during June, 1986. The training program'"" 'for"'Cold License was reviewed and it was determinedthat the training program was satisfactory with onlyminor inspector follow-up items.

6. As indicated by the matrix, all EOPs were reviewed byCold License Candidates in either the ContinuingTraining Program or Pre-license Review. Thistraining included a step-by-step discussion of theEOP's and the bases for the steps.

I

7. The training program for Cold License meets or exceedsregulatory requirements.

Concern 1B:

Develop or provide evidence of a training program that systematicallyassures that information gaps in flowcharts and textual procedures areaddressed speci'fically during future training, the program should includedevelopment of standards for the evaluation of task-level performance sothat the applicant can identify whether all operators possess theappropr'iate enabling skills and knowledge to implement the"EOPs.

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (8)

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~Res onse

As stated in response in IA above, Attachment 2 is provided showing thetask listing for the Hot License Training Program. ~ Also, as stated in IAresponse above, the programiis under development and will be completedprior to conducting Hot License Training for future operators. Theprogram is based on an INPO job task analysis. Attachment 2 will also beused to ensure that items referenced as training required for the usageof the EOPs will be included in the Hot License Program.

Evaluation of the operators to ensure they possess the appropriate skillsand knowledge to implement the EOPs, will be similar to the Cold LicenseTraining Program which is: 1) written exams during classroom training 2)evaluation during simulator exercis'es 3) CPSL (NRC style) written,simulator,. and.plant oral-,walk~through exams prior to the NRC licensingexams; 4) NRC licensed operator„exams which include written, simulator,and plant oral. walk-through. Tasks identified by the INPO task analysisare to be incorporated into the simulator scenarios now in development.The operators will be evaluated'individually on each task. The simulatorexercise guides will reference the tasks and include the criteria forevaluation. Unsatisfactory performance of an evolution requires a repeatof that particular scenario.

Training conducted. during the Cold License Training Program ContinuingTraining and Pre-license Review Training was based on present emergencyoperating procedures. As changes are made to EOPs they are formallyfactored into the training program (Refer to Response to Comment 2 fordiscussion of process).

","..sEncLosures~4 Detailed„Comments. (Trainin Pro ram)

Comment 1:

The extensive use of flowcharts in the EOPs as described in the writer'guide reduces the amount of information that procedures can provide tooperators. The training program must compensate for this lack of writteninformation, i.e., the operators knowledge of plant. procedures must begreater. A training program description must be provided whichspecifically describes how the training program will maintain the highlevel of operator knowledge necessary for-"the use of flowchart EOPs.This program description should address training program for EOPsdistinct from training on other plant operating procedures.

~Res onse

.. Plant Training Instruction 200 (TI-200), "Licensed OperatorRequalification Program", maintains operator knowledge of the EOPsthrough three portions of the program. The "On-The-Job Training" portion"requires that the EOPs be reviewed quarterly by each operator.Additionally, the "Formal Classroom Lectures" portion includes a session,on .Emergency Operating Procedures. Finally, the simulator portionrequires sixty-four (64) hours of simulator training each year for each

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (10)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (11)

licensed operator. Exercising the EOPs and ensuring operators canutilize the procedures is a major part of the simulator requalificationtraining program. A review of the EOPs, with emphasis on the plantspecific information required is scheduled for the lecture portion of theRequalification Program for 1986.

In order to ensure adequate operator knowledge, TI-200 requires that thefollowing be performed as a part of the requalification trainingprogram'. 1) Operators will be evaluated during simulator training as totheir ability to implement EOPs 2) CPSL will administer annual NRC-stylewritten requalification exams, simulator exams, and plant oral walk-throughs. Additionally, the NRC may examine selected operators yearly inconjunction with the requalification program.

.Comment 2:

The PGP "should describe a program of retraining to be used in the eventof revision of EOPs, including explicit designation. of how the need toretrain is to be determined (e.g., assignment of an individual to monitorrevisions and retraining).

~Res ense:

Plant" Training'Instruction 901A, "Dissem*nation of Training RelatedInformation" describes the mechanism for review of revisions to plantprocedures and EOPs. The instruction gives guidance for review ofrevisions and provides a tracking mechanism to ensure that theappropriate changes are included into training materials and training isconducted as appropriate. The Harris Training Unit assigns individualsas Subject„,Matter Expertseto review the material.. The material is thenrouted as appropriate and tracked to ensure that the required training iscompleted. As described in the response to Comment 1 of Enclosure 4,Plant Training Instruction TI-200 "License Operator RequalificationProgram" requires that the EOPs be reviewed, and exercised on thesimulator as a part of the training program on a continuing cycle withemphasis on any changes.

Additionally, On-Site Nuclear Safety (ONS) reviews reports (LERs, SOERS,etc.) concerning operational incidents at. SHNPP and other plants. ONS

makes recommendations as to inclusion of the information into training.HTU is a member of the ONS review group. The PGP will be reviewed andsubmitted to the NRC by April 15, 1987.

Comment 3A:

Although. the PGP states that a simulator will be used for operatortraining, the training program description should be expanded to addressthe following:

Discuss the method to be used to train the operators inareas where, the simulator is not like the control roomor does not react like the plant, and in parts of theEOPs that can not be run on the simulator.

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (13)

~Res onse:

A lesson plan titled "Simulator Differences" is used in simulatortraining programs. If parts of the EOPs can not be run on the simulator,they are discussed as"part of the lesson plan or critiqued at the end ofthe exercise. ANSI/ANS 3.5 Section 3.1 dated 1981 requires that thesimulator respond the same as the plant. The requirement goes intoeffect 18 months after the plant is in commercial operation. Until thattime, if the simulator responds differently (now or once the plant is online) the-differences will be discussed in the "Simulator Differences"lesson plan.

Comment 3B:

., Indicate the use of a wide, variety of, scenarios including mutliple(simultaneous and .sequential) failures, to fully.exercise the EOPs on thesimulator and thus expose the operators "to a wide variety of EOP uses.

.~Res onse

Attached are three (3) scenarios (including evaluation check sheets)indicating the use of a wide variety of scenarios including multiple(simultaneous and sequential) failures. This is only a sampling of thelarge number of scenarios that, we utilize in the simulator trainingprogram. The scenarios are from the Cold License Training Program thatwas conducted for the presently licensed operators.

Comment 4:

..".,The PGP."should. include. a -commitment;,to..train every, operator on .every EOP

prior to EOP 'implementation in the control room.

~Res onse

The presently licensed operators have been trained on all EOPs in theclassroom and have been evaluated on simulator scenarios fully exercisingthe EOPs. The EOP review to be conducted in the 1986 RequalificationProgram will include training on changes and the EOP User's Guide. Forfuture licensed operator training programs the operators will also betrained on all EOPs and have simulator training fully implementing theEOP procedures. The PGP will be revised to include comment 4 prior tostartup following the first refueling outage as requested.

Comment 5:

The training program should indicate that operators will perform theirassigned roles 'during training and that operators will be trained asteams.

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (14)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (15)

~Res onse:

Plant Training Instructions, TI-201, "Reactor Operator ReplacementTraining Program", TI-202, "Senior Reactor Operator Replacement TrainingProgram" and TI-200, "License Operator Requalification Program' AI 26R"Simulator Training", emphasize simulator training both in the teamconcept and in the individual role. Operators are evaluated duringsimulator exercises as a team as well as individual roles.

Comment 6:

The PGP should indicate that operators will be evaluated after trainingand that all operators will be evaluated.

~Res onse:

'As the part of the training program, operators are evaluated by writtenexams during'classroom training and during the simulator training theyare evaluated on the exercises conducted. Unsatisfactory simulatorevaluations require a repeat of the scenario. Prior to being licensed bythe NRC, CP&L conducts NRC-style written, simulator, and plant oral walk-through exams to ensure that the operators possess the required knowledgeto be licensed operators. The NRC provides written, simulator and plantoral walk-through exams to the operator prior to issuing individuallicenses. Plant Training Instructions TI-200 "Licensed OperatorRequalification Program, TI-201 "Reactor Operator Replacement TrainingProgram", and TI-202 "Senior Reactor Operator Replacement TrainingProgram" require that these evaluations be conducted. The requirement toevaluate operators will be added to the PGP by April 15, 1987.

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (17)

Attachment 1- NG/SOPP Step Natrix

Task CMments

E-O,RM) 36a

E-I,RN 11a

Try to restore offsite power to ac

emergency busses. IF offsite powercan NOT be restored, THEN load thefollowing equipment on ac emergencybusses:

GI,RNO 47a1)

Try to restore offsite power to ac

emergency busses. Verify EDGs

proper ly loaded

10

13

Procedure will be revised toindicate how to verify

proper'oading.

IEnter plant specific list) ~

E-3.RN 11

Try to restore offsite power. IFnecessary, THEN manually load thefollowing equipment on the ac

emergency busses:

[Enter plant specific list].

G2,RNO 19

Verify the following:

1) EDG properly loaded

2) Turbine X lube oil puaps-RUNNI%

3) Turbine seal oil backup puap-RUQ41%

10

13

Procedure will be revised toindicate how to verify properloadina.

4) Instrument air cm4x essors-'MI%

E-1,12a

Verify cold leg recirculatimcapability:

1) Power to low-head SI pumps-AVAILABLE

G1,66a

RHR system - CAPABLE CF COLD LEG

RECIRCULATION

PATH GUIIE will be revised toinclude list of required items.

2) IEnter plant specific Iist3

E-1,12b

Check auxiliary building radiation-NORNAL

IEnter plant specific list)

G1,66b

Check auxiliary and waste processingbuilding radiaticn - M)RNL

None.

Page 1 of 18

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N6 Ste

Attachment 1 - N5/SOAP Step matrix

SHNPP St Task Comments

E-l,RN 12b G1,RNO 66b 14

22

None.

Try to identify and isolate leakage: Try to identify and isolate leakage.

[Enter plant specific means'.

E-1,12(

Obtain samples:

[Enter plant specific 1istl

G),37G1,51

" Request Periodic Activity Samples,0fAll SGs

15

16

24

This step falls at the end ofthe LKA guideline under thehigh level step "Evaluate PlanStatus.'t this time, thiswould be directed by theTechnical Support Center vicethe Cmtrol Room.

E-1, 12d

Evaluate plant equipment:

[Enter plant specific list)

None. This step falls at the end oF

the LOCA guideline under thehioh level step "Evaluate PlanStatus.'t this time, thiswould be directed by theTechnical Support Center vicethe Control Room.

E-1,12e

Start additional plant equipment toassist in recovery:

iEnter plant specific list3

None. 24

25

26

This step falls at the end ofthe LKA guideline under thehigh level step "Evaluate PlanStatus.'t this time, thiswould be directed by theTechnical Support Center vicethe Control Room. The operatis continually evaluating thisneed and doing it.

E-1, 15b

Check SGs radiation - NORNAL

(Enter plant speciFic means)

G1,69b

Check SG radiation - NRNL

None.

Page 2 oF 18

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (20)

NS St

Attachment 1- NG/SNR'tep Hatrix

SHNPP St Task Corments

E-l, 17

At ( ) Hours After Event InitiationPrepare For Hot Leg Recirculation:

Check control room valve switches inthe following position:

[Enter plant specific list ofnormally deenergized valves used fortransfer to hot leg recirculationwith their correct position duringcold leg recirculation3

Check circuit breakers so that thefollowing valves are energized:

[Enter plant specific list of valvesused for transfer to hot legrec ir culat ion]

G1,70

At 18 Hours After Event Initiation,Align SI System For Hot LegRecirculation Using EPP-011,

"TRANSFER TO NT LEG fKCIRCULATION,"

Step 1.

This is not a tice criticalstep. There is no explicitneed to pr epare for doingEPP-011.

E-3,2

Hiah radiation from any SG blowdown

line:

G1,31

SG blowdown radiation - M3RNL

14

15

[Enter plant specific means)

E-3,RM) 19 1)

thnitcr following ccnditions For

indicatim of leakage fry PRIR

POfN:

G2,RNO 28 1)

Ihnite PRT conditions

17 The procedure will be revisedto list which parameters tomonitor.

[Enter plant specific list].

Paae 3 of 18

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (22)

NX Ste

Attachment 1- NO/SHtFP Step matrix

95PP St Task Comments

E-3,31

Ninimize Secondary System

Contamination:

G2,45

minimize Secondary System

Contamination

23 The additional detail in thisstep will also appear in theEPPs where appropriate.

[Enter plant specific aeansI a. Isolate thin Steam from

Auxiliary Steam System bylocally shutting 1%-121.

b. Isolate hotwel I spillover toCST by locally shutting

ICE-139

ICE-146

c. Establish condensate flowthrouoh condensate polishers tomaximize removal of secondaryradioactivity.

d. Place CVPETS in service.

ES-3.1,RN 5c

ES-3.2,RM 5b

ES-3.3,R% 5b

ES-3.3,8% 14c

Nanually or locally dump steam fromintact SG(s):

EPP-017, RNO 5cEPP-018,RNO 5c

EPP-019, RNO 5b

EPP-019,RNO 14c

Ihip steam with intact SG PORVs.

This step will be revised toaddress the plant OP m PORV

local operations.

o Use PORV.

o IEnter plant specific means'.

Page 4 of 18

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (24)

1(X Ste

Attachment 1- 16G/SSFP Step matrix

9(NFP St Task Corments

ECA-I. I,RNO 3b

manually or locally dusq steam fromintact SG(s):

EPP-012,RNO 3b

I)uaq steam from intact SG(s) usingPORV.

This step will be revised toaddress the plant P on PORV

local operations.

o Use PORV.

o [Enter plant specific means).

ECA-,I. I,RNO 17a

thnually or locally der@ steam atmaximum rate from intact SG(s):

EPP-012, RNO 17a

I)ump steam at maximum rate usingintact SG PORVs.

This step will be revised toaddress the plant P cn PORV

local operat its.

o Use PORV.

o (Enter plant specific meansl.

ECA-1.1,(50 18a

manually or locally dump steam fromintact SG(s) as necessary tomaintain RVLIS full range indicationat (10):

EPP-012, Rt(O 18a

Duap steam using intact SG PORVs.

This step Mill be revised toaddress the plant P cn PORV

local operatims.

o Use PNV.

o [Enter plant specific means).

Page 5 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (25)

C l

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4

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C

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (26)

MOG Ste

Attachment 1- NO/SSPP Step Natrix

SHNFP St Task Corments

KA-1~ 1,(M 21b

ECA-1.1, RNO 23b

Nanually or locally dump steam From

intact SG(s):

EPP-012, RNO 21b

EPP-012, RNO 23b

Dump steam using intact SG PORV.

This step will be revised toaddress the plant P on PORV

local operaticns.

o Use PORV.

—DR--

o (Enter plant specific means].

ECA-3.1, RNO 10c

ECA-3,2, RNO 5c

Nanually or locally duxy steam fromintact SG(s):

EPP-020, RNO 11c

EPP-021, RNO 5c

Duap steam using intact SG PORVs.

This step will be revised toaddress the plant OP an PORV

local operations.

o Use PORV.

o [Enter plant speciFic means].

ECA-3.3,(M 25b

ECA-3.3,RNO 33c

Nanually or locally dump steam fromintact SG(s):

EPP-022, RNO 26b

EPP-022,RNO RDuap steam using intact SG(s) P(WV.

This step Mill be revised toaddress the plant 8' PORV

local operations.

-CR—

o (Enter plant specific means).

Page 6 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (27)

1

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v1

~k III

h

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (28)

Attachment 1- )66/SSPP Step matrix

NK Ste SHNPP St Task

ECA-0.1,8

Establish SG Pressure Control:

EPP-002, 10

Establish SG Pressure Control:

This step will be revised toaddress the plant lP cn PORV

local operatims.

a. Set each SG PORV controller tomaintain existing SG pressure

b. Place each SG PORV controllerin automatic mode

a. Coordinate with local operatorand control SG PNVs tomaintain existing SG pressure

c. Locally return SG PNVs toremote control:

(Enter plant specific means)

ES-O. I,R)4) 4b

thnually place in.ser vice:

[Enter plant specific means).

EPP-004, None. EPP~ says to verify charginand letdown in service. Thismeans iF they are not inservice to place them inservice.

ECA-3.3,4e

Try To Establish Auxiliary Spray:

EPP-022,5

Try To Establish Auxiliary Spray:

18 None.

e. Establish auxiliary spray flow:

[Enter plant specific means]

a. Check the following:

1) CSIPs rurning

2) Auxiliary spray path linedup

3) Auxiliary spray available

W

ECA-1.2, 1c

Verify Proper Valve Alignment:

EPP-013, lc

Verify Proper Valve Alignment:

None.

c. Other paths to outsidecontainment - CLOSEO

(Enter plant specific list)

c. Check any valves which failedto align in accordance with SIverification as a possiblecoolant loss flow path.

Page 7 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (29)

f lg I

l 14'

Elkl

I

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (30)

NOO Ste

Attachment 1- N6/SSFP Step Natr ix

SHNPP St Task Corments

EGA<.0, RNO 16b

Locally dump steam using SO PNVs:

[Enter plant specific meansl

EPP-001,RNO 15b

Locally operate SO PORVs.

This step will be revised toaddress the plant (P cn PORV

local oper aticns.

ECA-1 ~ 1,7c

Alion spray For recirculaticn:

(Enter plant specific means]

EPP-012,7c

Align CNNT spray fcr recirculation

This procedure will be revisedto list requirements.-

ECA-0.2, RNO 1a

manually align valves to establishcold leg recirculation alignment:

[Enter plant specific list}.

EPP-003, RNO 1a1)

Align valves to establish cold legrecirculation.

This procedure will be revisedto list valve alignment.

ECA<.1,RNO 7aECA-0.2,Rt8 6a

Establish required AFN valvealignment:

[Enter plant specific list)

EPP-002, RNO 9a

EPP-003, Rt8 6a

Establish required AFM valve

alignment.

None.

KA-3.1,29ECA-3.2,23

KA-3.3, 17

Ninimize Secondary SystemContamination:

EPP-020,29

EPP-021, 22

EPP-022, 19

Ninimize Secondary SystemContamination

14

23

This procedure will be revisedto provide more detail. See

PATH-2 GUlDE, Step 45.

[Enter plant specific meansl

Page 8 oF 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (31)

4 ~

a

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (32)

NK Ste

Attachment 1 - NOG/SIPP Step Hatrix

SHNPP St Task Crxrments

ECA-1.2,2

Try To Identify And Isolate Break:

Sequentially close and open theFollowing valves and monitor for anRCS pressure increase:

I) Low-head SI purrp cold leginjection valves

2) fEnter plant specific Iistl

EPP-013,2

Try To Identify And Isolate Break:

a. Dispatch an operator to RAB toinvestigate.

b. Use Radiation Honitoring Systemto determine possible source ofleakage.

14

22

None.

ECA-0.0,26

Verify Service Hater System,Operation:

a. Verify valve alignment - PRI'ER

ALIGNNEHT

EPP-001,24

Check EQI System Operation:

a. Check ESW and ESN booster purrpsrunning.

This procedure will be revisedto provide more detail and toverify EQ lineup to the E16s.

[Enter plant specific list]

b. Verify pump - RlMING

ECA-3.1, RNO 7a EPP-020,RNO Sa Hone.

Try to identify and isolate leakage: PerForm the following:

[Enter plant specific meansl ~ o Try to identify and isolateleakage.

o EAL FLAG: IF RCS leakageexists outside MT, THEN

reference EAL, entry points U

and V.

Page 9 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (33)

NX Ste

Attachment 1- MK/SOAP Step Hatr ix

SHNPP St Task Ceeents

ECA-3.1,7

Initiate Evaluation Of Plant Status:

a. Check auxiliary buildinaradiation - NORNL

[Enter plant specific means)

b. ibtain samples:

Knter plant specific means3

c. Evaluate plant equipment:

[Enter plant specific list3

d. Start additional plantequipment to assist inrecovery:

(Enter plant specific listl

EPP-020,8

Initiate Evaluation OF Plant Status:

a. Check auxiliary buildingradiation - NENL

b. Obtain samples of RCS, SGs, and

CNNT sump as needed.

c. Evaluate plant equipment.

d. Start additional plantequipment to assist inrecoverye

14

15

16

24

25

26

None.

ECA-0.0, 12

; Check If SG Tubes Are Not Ruptured:.

o Condenser air ejecta'adiatim- RENAL

o SG bludwn radiation - MENL

o (Enter plant specific means]

EPP-001, 11

Identify Any Ruptured SG(s) by usingRadiation Nonita ing System.

o Condenser vacuum effluenttreatment monitcr - NCRtNL

o SG blmdtwn radiatim monita-NORNAL

o Nain steaml inc radiationMnitm - NRAL

None.

Page 10 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (34)

N5 Ste

Attachment 1 - NG/SNAP Step Natrix

SHNPP St Task Coaments

E-2,6a

Request periodic activity samples ofall SGs:

EPP-014, 7a

Request periodic activity samples ofall SGs.

16 None.

(Enter plant specific meansI

ES-0.2,3

Verify Cold Baron Shutdown

Concentration By Sampling:

[Enter plant specific means)

EPP-005,3

'erify Cold Boron %utdowConcentration By Saryling.

16 None.

ES-0.2, 17

ES-0,3,8ES-0.4,7

Naintain Required RCP Seal InjectionFlow:

(Enter plant specific meansl

EPP-005, 17

EPP-006, 18

EPP-007,17

Naintain Required RCP Seal InjectionFlv .

No specific instructions arenecessary to maintain sealinjection.

ECA-3.3,24

Naintain Required RCP Seal InjectionFlow:

IEnter plant specific meansI

EPP-022,21

Check RCP Coolina - NRNL

o RCP CQ system flow

o RCP seal injection flow

The 95PP step has the operatorcheck both seal coolingmechanisms, and the RM3 column

directs the operator to restorethem if not ncrmal.

Page 11 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (35)

I

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~ g4

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (36)

Attachment 1- NG/SOAP Step Natrix

SHNPP St Task Comments

ECA<.1,20

Try To Restore Offsite Power To AllAC Busses:

IEnter plant specific means]

EPP-002,21

Try To Restore Offsite Power To AllAC Busses. IF necessary, THEN

perform the following:

a. Verify EDGs have started.

10

13

None.

b. Verify EDGs have assumed thepraper loads,

c. Verify turbine DC emergency

bearing oil and air side sealoil backup pumps are runnina.

d. Verify adequate EDG capacityand load equipment as necessaryto establish stable canditions.

e. Determine the cause aF the lossof offsite power. IF due to a

failure of the startuptransformer, request assistancefram maintenance crews torestore power from either themain ar spare startuptransformer. If the loss afpower is the result of a lassoF grid, obtain assistance Fram

the Load Dispatcher.

Page 12 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (37)

t

J

gt

r

a

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (38)

Attachment 1- NG/SUPP Step Matrix

N6 St SHNPP St Task Comments

ES-1 ~ 1,RM) 22

ES-I.2,)M 4

ECA-2.1, RNO 30ECA-3.1,RNO 4

EPP-008, RNO 21

EPP-009, RNO 4

EPP-015,RN 31

EPP-020, RNO 4

10

13

None.

Try to restore ofFsite power. IFnecessary, %EN manually load thefollowing equipment on the ac

emergency busses:

[Enter plant specific lists

Try to restore offsite power. IFnecessary, THEN perform the

following'.

Verify EDGs have started.

b. Verify EDGs have assumed theproper loads.

c. Verify turbine DC lube oil andair side seal oil backup pumps

are running.

d. Verify adequate EDG capacityand load the followingequipment m the EKs:

1) One instrurent aircompressor

2) Battery chargers

3) PRl heaters, as needed.

e. Determine the cause of the lossof offsite power. If due to a

failure of the startuptransformer, request assistancefrom maintenance crews torestore power from either themain or spare startuptransFormer. If the loss oF

power is the result oF a lossof arid, obtain assistance frmthe Load Dispatcher.

Page 13 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (39)

Attachment 1- NG/SOAP Step matrix

NS Ste SHNPP St Task CMments

EGA<.0,5a2)

Verify ac emeroency bus

automatically energized:

EPP-001,5b

Verify AC emergency bus

automatically eneregized.

10 This step will be revised toprovide more detail.

IEnter plant specific meansl

ES-0.1.RM) 7

Perform the Following:

a., IF necessary, THEN verify *

diesel generators have assumed

the following loads:

IEnter plant specific list).

b. Try to restore offsite power:

[Enter plant specific meansl.

c. IF necessary, THEN manuallyload the following equipment mthe ac emergency busses:

(Enter plant specific list).

EPP-004, RNO 8

Perform the, following as necessary:

a. Verify EI6s'have started.

b. Verify EDGs have assuaged theproper'oads.

c. Verify turbine DC &urgencybearing oil and air side sealoil backup pumps are running.

d. Verify adequate EDG capacityand load the followingequipment on the EDGs:

1) One instruaent air'compressor

10

13

None.

2) Sattery chargers3) PRl heaters, as needed.

e. Determine the cause of the lossof offsite power. If due to a

Failure of the startuptransformer, request assistancefrom maintenance crews torestore power from either themain or spare startuptransformer. If the loss ofpower is the result of a lossof grid, obtain assistance fromthe Load Dispatcher.

Page N oF 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (40)

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (41)

Attachment 1- 16G/SNOOP Step Natr ix

WOG Ste SHNPP St Task Comments

ECA-0.0, RNO 5a1 ) -2)

1) Emergency start dieselgenerator:

EPP-001, RNO 5a1 ) -2)

1) Start EDGs by actuating SI fromthe NCD

13 None.

[Enter plant specific meansl

2) 'manually energize ac emergency

bus. IF bus can NOT be

eneroized, THEN manually tripdiesel generator and eneroizeac emergency bus using anyavailable power supply:

IF EDGs will not start, THEN goto Step Sb.

2) Energize AC emergency bus. IFbus can MT be energized, THEN

attempt to locally energizeemergency busses at switchgear.

[Enter plant specific meansl

ECA-0.1,3b1)

~ Check valve alignment and start CCW

pumps

1) Check valve alignment:

EPP-002, None. The CCW pump is started in a

following step. It will be phere to be consistent with theERGs and to provide additionalguidance on valve alignment.

[Enter plant specific list)

FRP-S.I,RNO 5a FRP-S.1, RNO 5a 19 None.

Dispatch operator to locally tripreactor:

(Enter plant specific means).

Dispatch an operata'o locally tripreactor trip breakers or rod drivesotor generate sets.

FRP-S. I,RNO 5b FRP-S.1, RNO Sb 12 None.

Dispatch operator to locally tripturbine:

Dispatch an operator to locally tripturbine.

(Enter plant specific means].

Page 15 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (42)

,a ass

n ~

1„4

1 + * IX

4

4

IC

'4

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (43)

NS Ste

Attachment 1- NG/SSPP Step Natrix

SHNFP St Task Comments

FRP-C.1,RNO 2

Start pumps and align valves as

necessary. Try to establish any

other high pressure injection:

Knter plant specific listl

FRP-C.1, RNO 2

Start pumps

Verify SI valve alignment - PROPER

ENERGENCT ALIMENT

Try to establish charging flow toRCS.

4

6o to Step 3.

Verify RHR 'valve alignment - PRB'ER

ENERGENCT ALIMENT

FRP-C.2,RNO 2a-b

a. Start pumps and align valves as

necessary. Try to estab lishany other high pressureinjection:

IEnter plant specific Iist3

b. Start pumps and align valves as

necessary. Try to establishany other high pressureinjection:

vf eqJ

IEnter plant specific list)k

FRP-C.2, RNO 2a-b

Start puris

VeriFy Sl valve alignment - PROPER

EMERGENCT ALIGQENT

Try to establish charging flow toRCS.

None.

FRP-C.1,RNO 15

FRP-C.1,RNO 22

FRP-C.2,RNO 15

Continue efforts to establish SI

flow. Try to establish any otherhigh pressure injection:

lEnter plant specific Iistl.

FRP-C.1, RNO 15

FRP-C.1, RNO 22

FRP-C.2,RNO 15

Continue efforts to establish SI

f1~. Try to establish chargingflow to RCS.

None.

Page 16 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (44)

~++

ling

4 j1

~ t t 4J

lt(

-1

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (45)

N6 Ste

Attachment 1- I)6/SOAP Step Hatrix

SHNPP St Task Coreents

FRP-C.1, 19

Try To Locally Depressurize AllIntact SGs To Atmospheric Pressure:

o Use PORV

FRP-C.1, 19

Try To Locally Depressurize AllIntact SGs Ta Atmospheric Pressure.

This step will be revised toinclude steam drains upstreamoF HSIVs, and will address the(P an local operation of SG

FORVs.

o (Enter plant specific means)

FRP-'C.2,RNO 10b

FRP,-C.2,RNO 14b

thnually or lacally dump steam fromSGs:

FRP-C.2,RNO 10b

FRP-C.2, RNO 14b

Duap steam using SG PNVs.

This step will be revised toreference the plant OP on localSG PORV oper atians.

o Use PNV.

o [Enter plant specific meansl.

FRP-H.1,5c

Establish Hain FM Flow:

(Enter plant specific means)

FRP-H.1,4c

Establish i@in FM flow.

None.

FRP-H.3,8

Establish Blowdow Fram AFfectedSG(s):

FRP-H.3,8

Establish Blowdme Fram AffectedSG(s) to Lower SG Level.

21 This step will be revised toaddress the plant (P m SG

blawdawn.

(Enter plant specific means]

Page 17 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (46)

e%% II

ta'i

I

~ ~

~ ~

t

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (47)

N6 Ste

Attachment 1- N6/SRFP Step Natrix

SNNPP St Task

FRP-l.1,3c

Verify spray system valve alignment- PROPER ENERGENCY ALIGhKNT

FRP-J. 1,3c

Verify MT spray system valves-FRPER EtERGEXT ALIMENT

This step vill be revised tolist requirements.

(Enter plant specific list forinjection and recirculation phases]

FRP-I.3, 16a

Isolate containment:

IEnter plant specific list)

FRP-I.3, 16a

Verify CNT ventilation isolation

20 This step vill be revised to1 refer to the checklist in order

to verify components.

Page 18 of 18

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (48)

I

IV

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (49)

ATTA(3DIENT l2 EMERGENCY PROCEDURES TASK TRA IN ING MATRI X

TaskNunber

Task

Check If SI Is Actuated

Cold L Icense Tralnlng

CLC-1-1-8, pp. 3 d 4

Slnulator Control Roon Di f ferences

Coen)eats

Light panels d Per)sisslve StatusPanel reviewed. Sl status Indicatedon panel.

Hot License Training

EOP-LP-3.1Path-l, EPP~4) EPP~8(In developnent)

Ccn)sents

Steps and bases for Path-1. Task

required by procedure.

CLC-2-4-1A, p. 3Review: Rx Trip Procedure

CLC-3-4-28) p. 6.Review: AOP-16, EPP-7, 8, 9 and 10

Discusses klckout to EPP-4 If Slnot required

Dlscusslon on Sl verification.

SIS-LP-3.0Safety Infection Systen

PLR-LP-3.2Energency Operating Procedures(To be developed)

COC Systens Training. Indicationsfor Sl (Pere)isslve Status Panel).

RO Procedures Review.

CLC-3-5-)A, PD. 2-4Sl Denonstratlon

Deno on SI Indications andveri f Ication. Also, each traineewalks through each role.

RO Hot License Sis)viator Scenarios Exercises Involving use of Path-I(In developnent)

CLC-3-5-18/3-5-2, p. 7

CLC-4-1-18/4-I-2A) pD ~ 7-9CLC-4-3-18/4-2 DDT 9 d 10

CLC-4-4-2, pp. 6 d 7

CLC-5-1-1 ~ pp. 5 d 6CLC-5-3-2, p. 5CLC-5-4-2, pp. 6 d 7

CLC-5-5-1, pp. 10 d 11

CLC-5-1-2, pp. 7 d 8CLC-6-1-1, pp. 6 d 7

CLC-6-)-28, p. 5CLC-6-3-2, pp. 5 d 6CLC 7 2-1, pp. 7 d 8CLC-7-2-2, p. 8CLC-7-4-2, pp. 8 d 9CLC-7-5-1 ~ pp. 8 d 9CLC-7-5-2, pp. 8 d 9CLC-8-1-1, pp. 13 d 14

CLC 8 I 2) pp ~ 9 d 10

CLC-8-2-2) pD. 5 d 6CLC-8-3-2, PD. 5 d 6CLC-9-1-1) p. 7

CLC-9-1-2, pp. 14 d 15

CLC-9-2-2, p. 4

CLC-9-3-2, pp. 8 d 9

CLC Exercises with Sl actuationexercises. SRO Hot License Siaulator Scenarios

(In developxent)

I of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (50)

ATTACWENT l2 EHERGENCY PROCEDURES TASK TRAINING HATRI X

TaskNunber

Task Cold License TrainingSS7221H

SS7222H

SS7232H

SS7241H

SS7242H

SS7251H

SS7311H

557312H

SS7322H

SS7341H

SS7342HSS742'IH

SS7422H

SS7431H

SS7441H

SS7442H

SS7451H

CouuentsPLR Exercises with Sl actuation

Hot License Training Couuents

EOP Review, Section I

Prelicense ReviewDiscussion on use ol Paths 6 EPPs.Haik through of HCB for Sl actuationIncluded.

Placing charing and letdownin service

CYCS-LP-I.OCheuical Yolune Control Systea

CLC Systeus Training. CVCS-LP-3.0Cheolca I Voluue Control Systeu( In developnent)

COC Systeus Tra I ning. Inc I udesf lowpath and Interlocks.

CLC-3-4-28

CLC-3-5-IA

EPP~ (EPP~7 In old nuuberlngsysteu) rev I awed. Requiresoperator to uanual ly aligncharging and letdown.

SI DEHO. Each operator requiredto lupleeent SI actuation 6

teralnation procedures. Requiresplacing L/D 6 Charging In service.

EOP I.P 3 IPath-l, EPP~4> 008

RO Hot License Slaulator Scenarios(In developuent)

Specific steps and bases forEPP~. Requires annualaligneent of charging andletdown.

Exercises Involving:I) EPP-004, Rx Trip Response

CLC-5-1-1CLC 5 5 I) p. 12

CLOD-1-28CLC-7-2-2CLC-9-3-2SS7242H

Sisulator Scenarios Involving Slterulnat ion procedur e. Requiresplacing L/D 6 Charging in service.

SRO Hot License SieulatorScenarios ( In dave lopuent)

2) EPP-008, Sl Terelnation(Hanual alignuent of letdownletdown and charging)

2 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (51)

ATTA(78IENT l2 EMERGENCV PROCEDURES TASK TRAINING MATRI X

TaskMvebcr

Task

Placing excess letdown Inservice

Cold License TrainingSS734IH

CVCS-LP-I.OCheslcol Voluve Control Systeo

Cceeents

CLC Systess Training. F lorpathand interlocks Included.

Hot License Training

CVCS-LP-3.0Cheslcol Voluvc Control Systcu( In developoent)

Coeutcn to

COC Systcu Tra I ning. F 1orpathand interlocks Included

CLC-3-3-18CLC-5 3-1CLC-7-4-'I

Exerc I ses requl r I ng excessletdorn be placed In service.

RO Hot License SivvlatorScenarios ( In developeent)

Exercises requiring excessletdown be placed In service.

SS7322H

SS7222HSRO Hot Licenses SiuulatorScenarios (In developvent)

Alignment of SI for Injectionond recirculation

SIS-LP-I.O, Sections 2.6.2 ond2.6.3Sl Systeo

CLC Systess Tra I ning. Includesflowpath and bases for switchover.

R%-LP-3.0, Section 2.6.2 8 2.6.3Residual Heat Reuovol Systen

COC Systcvs Training. Includesflorpoths and bases for swltchove

RW-LP-I.O, Sections 2.7.2 ond2.3.318R Systes

CLC Systeas Training. Inc I vdesf lorpaths and bases for switchover.

SIS-LP-3.0, Section 2.7.2 d 2.7.2Safety InJectlon Systex

COC Systeas Training. Includesflorpoth and bases for switchover.

PFR-LP-I.O, Sections 2.5.2 and2.5.3

Phase Four Training reviersf lowpoths ond bases for switchover.

MCO-LP»2.1, Section 2.3.3Post Accident Cooling

SRO Nltlgating Core Dauage

Training. Includes bases forsritchover.

MCO-LP-I.I, Section 2.3.3Post Accident Cooling

EOP-009

Continuing Training - 1985Meek I/Lesson 3

Bases for Switchover.

Specific Steps of EPPs 9, 10 6 11.Tosk required by procedures.

EOP-LP-3.3EPP~~ 010 01 1 g 012~ 013(In development)

Specific steps ond bases forEPPs-010 ond Oil. Task requiredby procedures.

18R SysteePrelicense Revler

I8R 8 Sl Systens (RQ86203)Requallf Ication Training - 1986

Review of I8R Systeo.

Florpaths ond interlockscephasizcd.

RO Hot License Siaulotor Scenarios(In developnent)

Exercises Involving switchover toHot Leg Recirculation.

CLC 6-1-1SS7221H

Siaulator Scenarios Involvingsritchover to H. L. Reclrc.(See Task II for all exerciseInvolving Sl actuation).

SRO Hot License Siavlotor Scenarios(In developacnt)

3 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (52)

ATTA(5afENT l2 EMERGENCY PROCEDURES TASK TRAINING MATRIX

TaskNugber

TaskAli noent of (yaIT S ra forInJection and recirculation

Cold License TrainingCSS-LP-I.OContalnaent Spray Systea

Contalnaent Spray SysteoPrelicense Review

Cocoa ntsCLC S stea Tralnln . Flow athsactuation signals and Interlocksincluded.

Euphasis on operation andresponse to accidents.

Hot License TrainingCSS-LP-3.0Containnent Spray Systea ( Indevelopaent)

EOP-LP-3.13FRP J.l, J.2

Ccxunents

COC S stea Tralnn . IncludesI lo'wp&thS actuation signals ~

and Interlocks.

Specific steps and bases forFRP-J.I. Task required byprocedure.

Conte l neent Spray (R086204)Requa I I f Ication Training-1986

EOP ReviewPrelicense Review

Eaphasis on systea oods, operationand Interlocks.

FRP-J.I reviewed.

RO Hot License Slaulator Scenarios(In developnent)

Exercises requiring SprayActuation.

EPPs~, 010, 011

Cont I nuing Training1985 Meek I/lesson 3

Review of steps and bases forEPPs 9, 10 d ll (EPP-10 addressalignment for recirculation).

SRO Hot License Slnulator Scenarios(In developaent)

CLC-5-3 ICLC-5-5-1) p. 11

CLC 6 I ICLC-8-2-2CLC-8-3-1

Siaulator Scenarios requIring useFRP-J.I or CV Spray.

SS7221H

SS7341H

SS7342H

Verify AFM Valves properlyaligned.

AFS LP-I.OAuxiliary FM Systeu

CLC Systeas Training. Includesflowpaths, interlocks 4 puapoperations.

AFS-LP 3.0Auxiliary FW Systen(ln developaent)

COC Systeus Training. Includesfiowpaths, interlocks 8 puapoperations.

ESMS-LP-I.ONorsal 8 Eoergency Service Mater

Auxiliary FW SysteaPrelicense Review

CLC Systeas Training. Eaergencywater source for AFW.

Review of AFW operations.

ESM-LP-3.0Noroal and Energency Service Mater(In developaent)

EOP-L.P-3.1Path-l, EPP-004, 008(In developaent)

CLC Systeus TrainingEaergency source for AFW.

Speclf Ic steps and Basesfor Path-1. Task required byprocedure.

Aux l I I cry FM Systen (R086205)Requal If ication Training - 1986

Interlocks and puap operationsexphaslzed.

RO Hot License Siaulator Scenarios( In developoent)

Exercises Involving AFW

failures.

4 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (53)

ATTACIaIENT F2 EMERGENCY PROCEDURES TASK TRAINING HATRI X

TaskNuuber

Task Cold License TrainingCLC 3-5-1A . 2-4

CoooentsDeno on Sl Indications d

verification. Each trainee ~elksthrough each role. (Forscenario with Sl actuation seeTask II)

Hot L I cense TrainingSRO Hot License Slaulator Scenarios(In developuent.)

~nts

Aligncent of ESW on SafetyInjection

CLC-6-3-1CLC-8-1-1SS7342H

SS7242H

ESWS-LP-I.O

Norual and Eoergency Service Mater

5 lou lator Exercises InvolvingAFM failures.

CLC Systeus Training. A I lgnuentfor Sl Included.

ESMS-LP-3.0Norual and Euergency Service Water(In developnent)

COC Systeos Tra I ning. A I Ignnentfor SI Included.

Homal and Energency Service Water Review of SW operation.Prelicense Review

SEO-LP-3.0Safeguards Sequencer

COC Systens Training. Listcouponents started In eachLoad Block.

Noraal and Euergency Service Mater(RQ86213)Requallf lcatlon Training-1986

CLC-3-5-1A, pp. 2-4Sl Deoonstratlon

Flowpaths, puap operations and

Inter locks eephas Ized.

Deuo on SI Indications andverification. Each trainee walksthrough each role. (For scenarioswith Sl actuated see Task il).

EOP-LP-3.1Path-l, EPP-004, 008(In developuent)

RO Hot License Siuulator Scenarios(In developoent)

SRO Hot License Siuulator Scenarios(In developnent)

Specific steps and bases forPath-1. Task required byby procedure.

Exercises with ESW Failures.

SS7221H

SS7341H

SS7421H

Sinulator Exercises with ESM

failures,

Halntainlng RCP Seal Injection CVCS-LP-I.OCheuical Voluue Control Systeu

CLC Systens Training.Injection and return f lowpathIncluded.

CVCS-LP-3. 0Cheulcal Volune Control Systeu(In developnent)

COC Systens Training. SealInjection and return path Included.

RCP-LP-I.OReactor Coolant Puups

CLC Systen Training. RCP Seals 6

Seal Injection discussed.

5 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (54)

ATTACIaIENT l2 EHERGENCV PROCEDURES TASK TRAINING HATR I X

TaskNuuber

Task Col d L Icense TrainingHCD-LP-I .0 . 3-6Loss of all AC

EOP RevlevPre-license Revler

CacaentsSeal De radatlon and ste s

of EPPs-l, 2 8 3 dIscussed.Task required by EPP-2.

Speci fc Steps of EPPs 1,2 6 3discussed. Task required byEPP-2.

Hot License TrainingRCS-LP-3.0

Reactor Coolant Systea

AOP-LP-3.11AOP&18, 030(To be developed)

CoeaentsCOC S stens Tralnln . RCP sealconstruction and operations ~

'ncluded.

Steps for AOP&18, AbnoraalRCR Operations. Loss of sealInJectlon discussed.

CLC-4-2-1 A Revler of AOP-018, RCP AbnorealOps. Loss of Seal Injectiondiscussed.

EOP-LP-3.7

EPP~I, 002, 003

( In dave lopaent)

Steps and bases for EPPs-001,002, 003. Task required byEPP-002.

CLOD-5-1 A Revier of AOP-014, Loss ol CCM.

CLC-4-2-18CLC-5 4-18CLC-7-2-1SS7113H

Sinululator Scenarios Involving RCP

cooling nalfunctlons.HCO-LP 2.9Loss of AI I AC

SRO Hit lgat lng Core Dauage

Loss of RCP Seal Coolingincluded.

SS7142H

SS742IH

SS7312H

Siaulator Scenarios ulth LossSea I InJect ion.

Slaulator Scenario ulth loss ofall AC.

RO Hot License Slaulator Scenarios(In developeent)

SRO Hot LIcense Sieulator Scenarios(In developoent)

Exercises Involving:I) RCP seal cooling

smalfunctlons2) Loss of seal injection3) Loss of all AC

Local ly duuplng stean usingS/G PORVs

HSSS-LP-1.0, Section 2.2.3Hain Steaa Supply Systen

CLC Systea Training.(Does not address senual ops.of S/G PORV).

HSSS-LP-3.0Hain Stean Systee(In developeent)

COC Systens Training.

HCD-LP-1.3, Section 2.4Loss of Feedvater Induced IOCAs

EOP-Review (Handout)Pre-license Reviev

FRP-H.1 rev I cued. Copy ofGener I c MOG Procedure Included.Task required by procedure.

Steps and bases revleved forFRP-C.I, C.2 d H.l.

EOP-LP-3.10FRP&.1, C.2 and C.3In developuent)

EOP-LP-3.11

FRY lg H 2p H 3» H 4 6 H 5

(In developnent)

Specific steps and bases forfor FRPs&.I and C.2. Taskrequired by procedures.

Specific steps and bases forFRP-H.I. Task required byprocedures.

EOP UpdateRequallflcation Training-1986

Hanual operation of S/G PORVs tobe included In Meek III.

HCD-LP-2.1

Smal I Break LOCA ulth NO )ffSIICC Indications and stradegles.

6 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (55)

ATTACWENT l2 ENERGENCY PROCEDURES TASK TRAINING HATR IX

TaskNuaber

Task Cold L I cense TrainingCLC-8-1-1

SS7242H

Co>anent s

8 I au Iator Scenarios I nvolv In useof FPR&.I. Task required byby procedure.

Hot License TrainingNCO LP 2.3Loss of Feedwater Induced LOCAs

CoeaentsReviews Indications and strade iesfor loss of FW

10 Verify proper operation ofthe Sequencer

85572'IIH

SEO-LP-1. 0Safeguards Sequencer

Slaulator Scenario Involving useof FRP-C.2.

CLC Systea Training.

RO Hot License Siaulator Scenarios( In deva lopaent)

SRO Hot License Slaulator Scenarios(In developnent)

SEO-LP-3.0Safeguards Sequencer

Exercises Involving:I) Use of FRP-C.1

2) Use of FRP-C.2

3) Use of FRP-H.I

4) Local control of S/G PORVs

COC Syste>s Training

Sequences Operations,Prelicense Review

Review of operations. EOP-LP-3.1Path-1, EPP-004, 008

Specific steps and bases for tPath-1. Task required byprocedure.

EOP Review

Prelicense ReviewSteps and bases for EPPs-001,002 8 003. Task required byby procedures.

EOP-LP 3.7EPP~I > 002, 003

Specific steps and bases forEPPs~i, 002 8 003. Task requiredby procedures.

CLC-3-5-1A, pp. 2-4 S I Oea>onstrat ion. Each traineepractices each role.

RO Hot License Sluulator Scenarios(In developuent)

SRO Hot License Sla>viator Scenarios(In developaent)

Exercises InvolvingI) Loss of off-site power

2) Sl actuation

CLC-3-4-1/3-4-2ACLC-5-5-1

Exercises Involving:I) Station Blackout w/EOG

functioning2) Loss of AII AC

Establ ishlng Hain FW Flow CFW-LP-I.OSections 2.2.6 through 2.2.10,2.4.6 through 2.4.10, d 2.4.13Condensate and Feedwater

CLC Systeas Training:Includes f lowpath, coaponents and

14C.

CFW-LP-3.0Condensate and Feedwater( In developaent)

COC Systeas TrainingIncludes, flowpath, coaponentspars>isslves 6 interlocks.

FW SysteaContinuing Training - 1985

Week I/Lesson 9

Flowpath, Interlocks d peralssiveseaphaslzed.

EOP-LP-3 11

FRP H I> H 2> H 3 H 4 ~ H 5

(In developaent)

Specific steps and bases forFRP-H.I. Task required byprocedure.

7ol 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (56)

ATTA(38(ENT l2 ENERGENCY PROCEDORES TASK TRAINING HATRI X

TaskNumber

Task Cold License TrainingCM) d FW S stem

ERA-0IH

Prelicense Review

Comments

E10 d Flf Review. Emphasis on valveInterlocks and permissives.

Hot License Training Comments

FW System (RO86201)Requa I lfIcat ion Training-1986

EOP Review (Handout)Prelicense Review

Emphasis on Interlocks 4

perml ss I ves.

Bases 8 steps of FRP-H.I reviewed.Task required by procedure.

HCO-LP 2.3Loss of FW Induced LOCAs

RO Hot License Simulator Scenarios( In development)

Reviews indications andstradegies for loss of FW.

ExercIses Involving use ofFRP-H. 1.

CLC-8-1-1SS1242H

Simulator Scenarios involving useof FRP-H.I.

SRO Hot License Simulator ScenarIos(In development)

12 Locally tripping turbine EHC-LP-1.0, Section 2.5.1E lectrohydraul ic Control.

CLC Systems Training.Includes Hechanlcal OverspeedTrip Hechanism and local trip.

EHC-LP-3.0Eiectrohydraulic Control(In development)

COC Systems Training.Includes Mechanical OverspeedTrip Nechanism and local trip.

TSAA-LP-1.20, Section 2.7Anticipated Transient without Trip.

Bases for FRP-S.I Included. EOP-LP-3.15FRP-S I ~ S.2(In development)

Specific steps and bases forFRP-S.I

EOP Review (Handout)Prelicense Review

Steps for FRP-S.I reviewed. Taskrequired by procedure.

CLC-2-4-1A, p.4

CLC-8-1-1

FRP-S.I reviewed.

Simulator Scenario In whichturbine falls to trip.

TdAA-LP-2.14Antlclpated Transient without Trip(In development)

RO Hot License Simulator Scenarios(In development)

ATWS analysis Included forfailure of turbine to trip.

Exercises involving ATWS withfailure of turbine to trip.

SRO Hot License Simulator Scenarios(In development)

13 Local Operation of SwltchgearBKRs

6.9 KV-LP-I.O6.9 KV Auxiliary

CLC Systems Training and OJT. 6.9KV-LP-3.06.9KV Auxiliary

COC Systems Training.

480V-LP-I.O>480V Auxiliary

CLC Systems Training and OJT. 480V-LP-3.0480V Auxiliary

COC Systems Training.

120VAC-LP-I.O

208/120 VAC

CLC Systems Training and OJT.

Bof 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (57)

ATTAOaIENT j2 EHERGENCY PROCEDURES TASK TRAINING HATRIX

TaskNumber

Task Cold License Training120V LPS-LP 1.0120V Un interrupt lb le Power

Comments

CLC S stems Trainln and OJT

Hot L Icense Training Comments

DCP-LP-I.ODC Power

CLC Systems Training and OJT.

SACP-LP-I 0Standby AC Porer

CLC System Training and OJT.Emergency Diesel Generator.

120V LP 3.0208/120VAC(In development)

COC Systems Training.

SEO-LP-I.OSafeguards Sequencer

CLC Systems Training. IPS-LP-3. 0120V UPS

COC Systems Training.

AOP&evlerRequal I I lection Training-1986

Sequencer Opcratlons,Prelicense Revler

PZR Heater Operations PrelicenseRevlcr

AOP-025, Loss of one 6.9 KV

Emergency Bus or one DC EmergencyBus. To be covered in Heck III.

Includes Load sheddingand reenergizing busses.

Effects of scquencer Operationson PZR Heater.

DCP-LP-3.0DC Power

(In development)

PLIS"LP-3.0Plant Light System

SEO-LP-3.0Safeguards Sequencer

COC Systems Training.

COC Systems Training.

COC Systems Tra lnlng.Includes Load Shedding andand reenerglzlng busses.

HCD-LP-I 10

Loss ol All AC

EPPs-l, 2 6 3 Reviewed. EOP-LP-3.7EPP~I, 002, 003(In development)

Specific steps and basesof EPPs-001, 002 6 003. Taskrequired by procedure.

AOP-004: Control Room

InaccessiblePrelicense Review

Revler of AOP~4. Malkthrough ofACP 6 Power Supplies. Requiresoperation of swltchgear

AOP-LP-3,12AOP-024x 025 '28, 029(To be developed)

Steps of AOP-25,Loss of One 6.9 KV EmergencyBus or One DC Emergency Bus.

AOP~4, (R086210)Requal i flection Training - 1986

Review of AOP~4. Requires localoperation of srltchgear.

RO Hot License Simulator Scenarios(In development)

Exercises Involving Loss of all AC.

EOP-RevlerPrelicense Revler

Includes specific steps ofspeclf ic steps of EPPs-l, 2 6 3.Task required by procedures.

SRO Hot License Simulator Scenarios(In development)

CLC-3-3-2A, pp. 4-8 Simulator Review of EPP-I, 2 6 3. AOP-LP-3.0AOP-004

Steps and bases of AOP~4.Requires manual operations ofsritchgear.

9 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (58)

ATTACHMENT j2 EMERGENCT PROCEDURES TASK TRAI NING MATRI X

TaskNumber

Task Cold License TrainingSS7312H

SS7121H

SS7442H

SS7342H-

Comments

Simulator Scenario with:I) Loss of all AC, or2) Use of AOP-25

Hot License Training Comments

14 Check radiation NORMAL forRAB, SGs, Secondary and (yaIT

RMS~I.ORadiation Monitor Ing System

CLC Systems Training. RMS-LP-3.0

Radiation Monitoring System(To be developed)

COC Systems Training. Operationsand response to alarmS.

RM-23, ll 8 80/Gen Atomics Rad

MonitorPrelicense Review

Reviews operation and responseto alarms.

AOP-LP-3.3AOP-005 (To be developed)

Steps for AOP~5. Responsefor alarms specified.

SA)q'P-I.O, pp. 1-19Sampling System

CIS-LP-I.OContainment Isolation System

LWPS-LP-I .0Liquid Waste Processing System,

CLC System Training. Iac I udesf Iowpath.

CLC Systems Training.Lists valves receiving CIAS.

CLC Systems Training.RCB Equipment Drain Subsystemincluded.

SAIS-LP-3.0Sampling System (In developrent)

CIS-LP-3.0Containment Isolation System

PASS LP-3 0Post Accident Sampling System

( In development)

COC Systems Tra I ning. Includesflowpaths.

COC Systems Training.List valves receiving CIAS.

COC System Training. Operation ofPASS.

Post Accident Sampling SystemContinuing Training - 1985

Week 2/Lesson 8

Continuing Training Lesson.Operation of PASS.

LWPS-LP-3.0

Llquld Waste Processing System(To be developed)

COC System Training.

AOP-LP-3.9APP&16, 023, 031

(To be 'developed)

Steps for AOP&16, RCS

Leakage, including leakIdentification stradegles.

CLC-1-1-18, p. 6 CLC Simulator/Site Differencesincluding RMS.

RO Hot License Simulator Scenarios(To be developed)

Exercises involving use of RMS.

SS7112H, p. 3 PLR Simulator/Std% DifferencesIncluding RMS.

SRO Hot License Simulator Scenarios,(To be developed)

CLC-3-4-28, pp. 2-5 Review AOP-16, RCS Leakage,including Leak Identificationstradegles.

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (59)

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (60)

ATTA(ta(ENT l2 ENERGENCY PROCEDURES TASK TRAINING HATRI X

TaskNunber

Task Cold License TrainingCLC 4-I-IA . 44

ConnentsReviers SGTR identification and

use of RHS.

Hot License Training Coeeents

CLC-4-4-28CLC-7-5-2CLC-8-I-2CLC-9-1-1CLC-9-1-2CLC-9-2-2CLC-5-5-2CLC-6-3-2CLC-7-2-1CLC-7-2-2CLC-8-2-2

5lnulator Scenarios Inc ludln9 useof RMS.

15 Identify a Ruptured S/G

SS7251H

SS7232H

SS7222H

SS7211H

SS7321H

SS7322H

SS7331H

SS7332H

SS7311H

SS7442H

SS7421H

SGTR: Plant ResponseContinuing Training - 1985

Meek I/Lesson 6

Path-2/EPP-16

Continuing Training - 1985

Meek I/Lesson 7

Prlnary and Secondary Responseto SGTR.

Specific steps and bases forPath 2 Including Identi I Icationof ruptured SG. Task requiredby procedure.

EOP LP-3.1Path-2) EPP 016

(In developnent)

AOP-LP-3.3AORS(In developnent)

Spec I f Ic steps and bases forfor Path-2 and EPP&16.Task required by procedure

Steps and bases for AOP~5, RMS ~

Includes reponse to RMS alarm.

SAI6'-LP-I ~ 0

Sanpllng SystenCLC System Training. AOP-LP-3.9

AOP&16 ~ 023) 031

( In deva lopnent)

Steps and bases for AOP-016,

RCS I.eakage.

11 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (61)

ATTA(3aIENT l2 EHERGENCy PROCEDURES TASK TRA I NING HATRIX

TaskNueber

Task Cold License TrainingCLC-3-4-28 . 2 6 3

CceaentsRevlers AOP-016 RCS Leaks e

Hot License TrainingSOP-LP-3.0

Including aethods of identification. Scapi lng Systen (In developaent)

CoerwntsCOC S stees Trainln

CLC-4-I-IA Revle«s SGTR Identification perPath-l.

RO Hot License Slaulator Scenarios Exercises «Ith SGTRs.

( In deva 1opaent)

CLC 4-4-2CLC-7-5-2CLC-8-1-2CLC-9-1-1CLC-9-1-2CLC-9-2-2SS7251H

SS7321H

SS7322H

SS7331H

SS7332H

SS7311H

SS7442H

Exercises «1th SGTR. SRO Hot License SInulator Scenarios(In developaent)

16 Requesting saaples froaCheaistry

SG activityRCS

Contalnoent H

RCS BoronContalnaent Suep

SOP LP 1.0Saepllng Systea

CIS-LP-I.OContalnaent Isolation Systea

LWPS LP 1.0Liquid Waste Processing Systea

CLC Systees Training. IncludesI lo«paths.

CLC Systees Tra I ning. L I stsvalves receiving CIAS.

CLC Systeas Training.Includes RCB Equi pnent DrainsSubsystea.

SOP-LP 3.0Saepling Systen (In developuent)

PASS-LP-3.0Post AccIdent Saepllng Systeu(In developnent)

CIS-LP-3.0Contalneent Isolation Systen

COC Systee Tra i ning. Includesflo«paths.

COC Systeas Training.

COC Systen Training.Lists valves receiving DIAS.

GP-LP-1.5, p. 22

HCD-LP-2. 7

Post Accident Pri naryRadlochealstry

Relates that saapling Is done bycheelstry.

SRO Hitigatlng Core Daaage

Training. Describes changes InRCS chenlstry and personnelhazards.

LWPS-LP-3.0

Liquid Waste Processing Systea(To be developed)

HCD-LP-2. 7

Post Accident PrluaryRadlocheelstry

COC Systees Tralnlng.Includes RCB Equlpuent DrainsSubsystea.

SRO Hitlgatlng Core Daaage

Training. Describes changesIn RCS cheuistry includingPersonnel hazards.

12 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (62)

ATTAI3eIENT l2 EHERGENCT PROCEDURES TASK TRAINING HATRIX

TaskNumber

Task Cold License TrainingPost Accident Sam lln S stem

Continuing Training - 1985

Week 2/Lesson 8

Comments

Cont I nuln Train l n Lesson.Includes operation of PASS.

Hot License TrainingRT LP 3.14S/D Reactivity Considerations

Comments

RO Rx Theor Trainln . IncludesSDH Calculations.

T6M-LP-).7, Section 2.5Normal Transient Analysis

Inc ludes SDM Ca I cu let lons.

RO Hot License Simulator ScenariosITo be developed)

SRO Hot License Simulator Scenarios(To be developed)

Simulator Exercises Involvinguse of Sampling System.

CLC-7-2-1, pp. 9 6 10

SS7411H

ExercIses ulth failed fuel.Relates that chemistry does

sampling.

CLC-4-4-28CLC-7-5-2CLC-8-1-2CLC 9-1 ICLC-9-1-2CLC-9-2-2CLC-5-5-2CLC-6-3-2CLC-7-2-1CLC-7-2-2CLC-8-2-2SS7251H

SS7232H

SS7222H

SS7211H

SS732IHSS7322H

SS7311H

SS7442H

SS7421H

Exercises involving uses ofsampling systems.

17 Non itor ing ConditionsIndicative of PZR PORV

Leakage

PZR-I.P-I .0Pressurizer

RCS-LP-I.OReactor Coolant System

CLC Systems Training. 16C

included.

CLC System Training. PZR and PRT

16C included.

PZR-LP-3.0Pressurizer

RCS-LP-3.0Reactor Coolant System

COC System Training. 16C

Included.

COC System Training. PZR

and PRT 16C Included.

13 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (63)

ATTACQIENT l2 EHERGENCV PROCE(XSES TASK TRAINING HATRI X

TaskNuaber

Task Cold License TrainingFF-LP-I.I Sect 2.12.2F I u1 d F low: F luld Hechan lesIn Pueps and Pipes

CoaaentsIsenthal Ic Process discussedwith exaaples using PZR PORVs

leakage.

Hot License TralnlngFF-LP-3.2 Section 2.5.2Fluid Flow: Fluid HechanlcsIn Puup and Pipes

Gonne ntsIsentha I Ic Process discussedwith exaaple using PZR PORVs.

CLC-3-3-1A Review of AOP-019, Hal function of AOP-LP-3.10of RCS Pressure Control. Includes AOP-017, 019Indication of PORT leakage. (To be developed)

Steps and bases for AOP-019,Halfunctlon of RCS PressureControl. Includes Indlcatlonsof PORV Leakage.

CLC-3-4-28 Review of AOP&16, RCS Leakage. AOP-LP-3.9AOP-016, 023, 031

Steps and bases for AOP-016,

RCS Leakage.

18 Establish Auxiliary Spray

CLC-4-5-2CLC-5-2-2CLC-7-2-2CLC-8-1-2SS7332H

CVCS-LP-I.OCheul eel Voluwe Control Systea

Exercises Involving leaking oropen PZR PORV.

CLC Systees Training. FlowpathsIncluded.

RO Hot License Siuulator Scenar los(In developwent)

SRO Hot License Slsulator Scenarios(In developwent)

CVCS-LP-3.0Cheuical Voluce Control Systeu(In developaent)

Exercises involving leaking oropen PZR PORV.

COC Systeas Training. F lowpathsI nc I u dad.

PZR-LP-1. 0Pressurizer

CLC Systees Training. Aux I I IsrySpray Included.

PZR-LP-3.0Pressurizer

COC Systeas Training. Aux SprayIncluded.

EPP&22

Continuing Training - 1985

Meek 2/Lesson 5

EPPs-005,006 d 007

Continuing Training - 1985

Meek 2/Lesson 6

Specific steps and bases forEPP&22. Task required byprocedure.

Specific steps and bases forEPPs-005, 006 d 007. Naturalcirculation cooldown requiresauxiliary spray,

EOP-LP-3. 6EPP~5, 006, 007

(In developuent)

EOP-LP-3.8EPPES, 006, 007(In developuent)

Specific steps and bases forEPPs-22. Task requiredby procedure.

Specific steps and bases forEPPs-005, 006 4 007. N.C.cooldown requires auxiliaryspray,

GP-LP-1.7Noraal Plant Cooldown

Steps include use of auxiliaryspray.

GP-LP-3.7Norcal Plant Cooldown

Steps include use of auxiliaryspray.

14 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (64)

1

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (65)

ATTACHMENT J2 EMERGENCY PROCEDURES TASK TRAINING MATRI X

TaskNueber

Task Cold License TrainingCLC-2-3CLC-9-2-1SS7121H

SS7151H

Coon»ntsExercises Involvin use ofauxiliary spray.

Hot License Training Coca»nts

19 Local tripping of Rx TripBkrs and MG sets

CLC-9-1-2SS7311H

RODCS-LP-I.O, Section 2.4.6Rod Control Systeo

Exercises requiring use ofEPP-22.

CLC Systeas Training. RODCS-LP-3. 0Rod Control Systea (In developuent)

COC Systeas Training.

EOP-Review (Handout)Pre-license Review

Steps and bases for FRP-S.I.Task required by procedure

EOP-LP-3. 15

FRP-S I, S.2Specific steps and basesfor FRP-S.I. Task requiredby procedure.

CLC-2-4-IA Review of FRP-S.I. RO Hot License Slaulator Scenarios(In develops»nt)

Exercises using FRP-S.I.

CLC-2-5-28CLC-4-2-18CLC-4-3 IB/4-3 2CLC-6-2CLC-8-1-1

Exercises Involving use ofFRP-S.I.

SRO Hot License Slaulator Scenarios(In develops»nt)

Verification of C alT

I sol at I onCVS-LP-I.OContains»nt Ventilation Systeu

CLC Systems Training. Responseto DIAS Included.

CVS-LP-3.0Contalnaent Ventilation Systea

COC Systeas Training. Response'o

DIAS Included.

CAPES-LP-I .0Contalnuent Atoosphere Purge andExhaust

CLC Systeos Tra I ning. Responseto CIAS Included.

CIS-LP-3.0 COC Systeas Training. List ofvalves receiving CIAS included.

C IS-I.P-I .0Contains»nt Isolation Systea

CLC Systeos Training. List ofvalves receiving DIAS included.

EOP-LP-3. 12

FRP-I.I, 1.2, 1.3Specific steps and bases ofFRP-I.3. Task required byprocedure.

Contalna»nt Ventilation SysteoPrelicense Review

Includes operations and Plant Nods. RO Hot License Slaulator Scenarios(In developaent)

Exercises with Sl actuation.(See Task 4'I).

EOP-Rev I ex

Prelicense ReviewSpecific steps for FRP-I.3discussed. Task required byprocedure.

SRO Hot License Slaulator Scenarios(In develops»nt)

15 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (66)

ATTA(3a(ENT l2 EMERGENCY PROCEDURES TASK TRAINING MATRI X

TaskNueber

Task Cold License TrainingCLC-3-5-IA

CoeedntsSl Dceonstrntion. Each traineewalks through each role for Slactuation. (See Task ll forexercises with Sl actuation).

Hot License Training Coeecnts

21 Establ lshing Blowdown froeS/Gs.

SGBS-LP-I .08/G B lowdown Systee

CLC Systees Training. SGBS-LP-3.0S/G Blordown Systee

COC Systees Training.

SG-LP-I.OStean Generator

CLC Systees Training. SG-LP-3.0Stead Generators

COC Systees Training.

EPPs-017, 018, 019

Continuing Tra i ning-1985Mack I/Lesson 8

EOP-Review (Handout)Prelicense Revier

Steps and bases of EPP418 reviered. EOP-LP-3.11

BD used to depressurize ruptured FRY.I, H.2, H.3, H.4 4 H.5S/G.

Steps for FRY.5, Reponse to S/GHigh Level. Task required byprocedure.

Specific steps nnd bases forFRP-H.5. Task required byprocedure.

22 Try to Identify 8 Isolate lenk CLC-3-4-28, pp. 2 d 3 Rcvldw of AOP 16'CS Ldakage, and EOP-LP-3.5discussion ot edthods of Identifying EPPs-20 4 21

leakage (In developednt)

Specific steps and bases fortor EPP-20. Task requiredby procedure.

RMS-HO- I . 0 CLC Systces Training. RMS-LP-3.0Radiation Honltorlng Systee(In developeent)

COC Systees Training.RMS used In leak Identltication;

RM-23, 11 6 80/Gen Atoelc Rnd

MonitorsPrelicense Revier

Operation ot RMS rdvldred. Haikthrough Included.

AOP-LP-3.9AOPs&16, 023, 031

(To be developed)

Steps for AOP-16, RCS Leakage.Leak identification strategiesincluded.

EPP-20 d 21

Cont inuing Train 1ng-1985iteck 2/Lesson 4

Specific Steps of EPPs-20.Task required by procedure.

AOP-LP-3.3AOP-005 (To be developed)

Steps tor AOP~5 ~ RHSr

Response tor alares specified.

CLC-7-5-2CLC-8-1-2CLC-9-2-2SS7322H

557331M

Sleulator Scenarios in whichEPP-20 iep leeentcd.

RO Hot License Sleuiator Scenarios Exercises requiring use ot(In developeent) tEPP-20.

SRO Hot License Sleulator Scenarios(In developeent)

16 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (67)

ATTA(38IENT l2 'ENERGENCT PROCE(XSIES TASK TRAINING HATRIX

TaskNu88er

TaskNinlalze secondhrcoatee I n at I on

Cold License TrainingSGTR: Radial Ical Conse uencesContinuing Training - 1985

Week I/Lesson 3

Hot License TrainingEOP-LP-3.2

CoaaentsIncludes nechanl sos of radionucl Id@

transport and actions to minlelze. Path-2/EPP-16 (In developuent)

Cccuxants

S eclfic ste s and bases forPath-2. Task requIred byprocedure.

RM-23, ll 6 80/Gen Atoalcs Rad

MonitorPrelicense Revle«

HSSS-LP-I.OHain Stean Systea

SDS-LP-I.OStean Duup Systen

CLC Systees Training.Secondary Systees effected bycontaalnatlon. Kno«ledge offlo«paths aids operator In takingaction to accoapllsh task.

AOP-LP-3.3AOP~5

HSSS-LP-3.0Nein Stean Systea

SDS-LP-3.0Stean Duep Systeu

Steps revle«ed for AOP-005.AOP-005 Includes actions thatminimize contaalnatlon

CLC Systeas Training.Secondary Systees potentiallyeffected by contaulnation.Kno«ledge of flo«paths aidsoperator In taking action toacccepllsh task.

CFW-LP-I .0(28) and FW SysteasHSR LP-I.OHSR d FW HTRS

CFW-LP-3.0(28) and F'W SysteesHSR LP 3.0NSR and FW HTRS

HOES-LP-I.OMain Condenser Evacuation Systea

HOES-LP-3.0Main Condenser Evacuation Systea

NTSS-LP-I.DHain Turbine Sealing Stean andExhaust

HTSS-LP-3.0Hain Turbine Sealing Stean and Exhaust

CPDS LP I.OCondensate Pollshln9 6Dealneralizlng Systea

CPDS-LP-3.0Condensate Pol lshing 8 Denineral IzingSystea

Path-2/EPP-016

Continuing Training - 1985Week I/Lesson 7

Specific steps and bases for RO Hot License Siaulator Scenarios Exercises «Ith SGTRs.Path-2. Task required by procedure. ( In developoent)

EOP UpdateRequallficatlon Training-1986

Actions added to proceduresdiscussed. Included In Week III.

SRO Hot License Siaulator Scenarios( In developeent)

17 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (68)

ATTAOaIENT l2 EHERGENCT PROCEDURES TASK TRAINING HATRIX

TaskNuuber

Task Cold License TrainingCLC-4-4-2CLC-7-5-2CLC-8-1-2CLC-9-1-1CLC-9-1-2CLC-9-2-2SS7251H

SS7321H

SS7322H

SS7331H

SS7332H

SS7311H

SS7442H

ContentsExercises Involvin SGTRs.

CLC-9-1-1 Involves a SGTR with theassociated HSIV stuck open. Path-2specifies actions that einlulzessecondary contaulnatlon for thatsituation. Soee of the actions areapplicable for SGTRs In general.

Hot License TrainingRWO al CardsI) OC 05.84H Perforaance 111.152) OC 08.80H Perforfssnce 111.5

AO Oual Card

CoeaentsSte s to:I) Isolate Hain Stean to Auxiliary

Stean2) Place ChD Polishing Systea In

service

Steps to:I) Isolate Hain Stean to Auxiliary

Steaa2) Isolate Hotwell spillover to

CST

3) Place CVPETS In service

24 Evaluate Plant Status GP-LP-I.O, Sections 2.24 8 2.25Conduct of Operations

Procedures Training on Conduct ofOperations. Continual evaluation ofplant status and use of redundantinstruuentation ls enphaslzed.

PP-LP-3.00M~I, 009

RO Procedures Training. 0 af-),Conduct of Operations, discussesContinual evaluation of plantstatus and euphaslzes use ofredundant Instruaent.

CLC-1-1-2, pp. 2-5

Cover sheet for siaulator ExerciseGuides

Conduct of Operations Reviewed.

Evaluates shift Conduct ofOperation for each exercise.

ADOP-LP-2.0,SRO Duties and Responsibilities

SRO Advanced Operating ProceduresTraining. Conduct of Operationsrevle«ed.

HCD-LP-I.IPost Accident Cooling

Hit lgatlng Cora Dauage Coursedescribes:I) plant response to accidents2) strategies for assessing dauage3) strategies for recovery4) equlpuent required to lapleeent

recovery strategIes

CO-LP-2.)Post Accident Cooling

Hitlgatlng Core Daaage Coursedescribes:I) plant response to accidents2) strategies for assessing de«age

3) strategies for recovery4) equip«ant required to lapleuent

recovery strategies

HCO-LP-1.2Snail Bkr LOCA «1th no IaISI

HCD-LP-2.2Seal l Bkr LOCA «1th no HISI

HCD-LP-1. 3

Loss of FW Induced LOCAs

HCD-LP 2.3Loss of FW Induced LOCA

HCO-LP-1. 4

Vita I Process Instruuentat ionHCO-LP-2. 4

Vital Process Instruuentation

18 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (69)

ATTACfaIENT l2 EHERGENCY PROCEDURES TASK TRAI NING HATRI X

TaskNuober

Task Cold License TrainingHCO LP-1.5Accident Response of IncoreInstruuentatlon

Coceents Hot License TrainingHCO-LP-2 5

Accident Response of IncoreInstrunentatlon

Ccneents

HCO-LP-I.6Accident Response of ExcoreInstrunentatlon

HCO-LP-2.6A«cldent Response of ExcoreInstruuentatlon

HCO-LP-1.7Post Accident Priaary Radlocheulstry

HCO-LP-2.7Post Accident Pr leery Radiocheulstry

HCO-LP- I . 8

Radloioglca I Aspects of Core DauageHCO LP-2.8Radiological Aspects of Core Danage

HCD-LP-I .9Loss of AII AC Po»er

HCD-LP 2 9Loss of All AC Po»er

HCO-LP-I . 10

Class 9 Events

HCO LP I 11

Instrunent Oualif Ication andAccident Response

EOP&20 8 021

Continuing Training - 1985Meek 2/Lesson 4

Steps and bases for EPP-20.Task required by procedure.

EOP-LP-3.5EPPs&20, 021

Specific steps and bases forEPP-020. Task required byprocedure.

CLC-7-5-2CLC-8 1-2CLC-9-2-2$$7322H

$$7331H

8lnulator Scenarios requiring useof EPP-20. (Note: Alnost a I I

sloulator exercises requIre useof task).

RO Hot License Sluulator Scenarios(In developnent)

SRO Hot License Slnulator Scenarios( In developnent)

Exercises Involving EPP-020.(Note: Alnost all sieuatorexercises require use of task.)

25 Evaluate Plant Equi puent CLC Systens TrainingContinuing Training - 1985

Pre I Icense Rev le» Tra I ningRequa I i f I cation Training-1986

Operations of all systeo covered InCLC Training. Revle»s and updatescovered In Continuing Training,Prelicense Revle» and Requalif icationTraining.

COC Systens Training Operations of all systens,Including the OperatingProcedures, covered in COC

Training.

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (70)

t

'1

,C

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (71)

ATTACISIENT d2 EMERGENCY PROCEDURES TASK TRAINING MATRIX

TaskNuober

Task Cold License TrainingHCO-LP-I.IPost Accident Cooling

CoonentsHltl atln Core Dana e CoursedescribeslI) plant response to accidents2) strategies for assessing daoago

3) strategies for recovery4) equlpoont required to inpleoont

recovery strategies

Hot License TrainingMCO-LP 2.1Post Accident Cooling

CoooentsHlti atln Core Dana e Course

descrlbeslI) plant response to accidents2) strategies fol assessing danago

3) stl'atogios for l'ecovel y4) equlpeent required to lnpleoent

recovery strategies

MCO-LP-1. 2

Seal I Bkr LOCA with no ISISIHCO-LP-2. 2

Seal I Bkr LOCA xlth no HISI

HCO-LP-I . 3

Loss of FW Induced LOCAs

HCO-LP-2. 3

Loss of FM Induced LOCA

MCO-LP 1.4Vital Process Instrueentat ion

MCO-LP-2. 4

Vital Process I nstruoentat ion

HCO-LP- I . 5

Accident Response of IncoreInstruoentatlon

MCO-LP-2.5,Accident Response of IncoreInstruwentat ion

HCO-LP-I . 6Accident Response of ExcoreInstruoentatlon

HCD-LP-2. 6Accident Response of Excore.Instruoentatlon

HCO-LP-1.7Post Accident Prlnary Radlocheslstry

HCO-LP-2. 7

Post Accident Pr leery Radiocheolstry

HCO-LP-1.8Radiological Aspects of Core Danage

HCO-LP-2. 8

Radiological Aspects of Core Daoage

HCO-LP-1.9

Loss of All AC PowerHCO-LP 2.9Loss of All AC Poxer

HCO-LP-1. 10

Class 9 Events

MCO-LP-1. 11

Instrunent Oval lflcatlon andAccident Response

20 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (72)

ATTA(3CIENT l2 EMERGENCY PROCE(WAS TASK TRAINING HATRI X

TaskNucbcr

Task Cold License TrainingEPP~ 6 021

Continuing Training - 1985'Week 2/Lesson 4

CocrrentsSte s and bases of EPP-20.Task required by procedure.

Hot License Training Cocracnts

SS7114H

SS7121HSirrufator Scenarios Involvingsultiple failures of IWR, CCW, etc.Operators are required to evaluateequlprrent status and Initiaterecovery «1th available systecs.

EOP-LP-3.5EPP&20, 021

(ln developccnt)

Specific steps and bases forEPP-20. Task required by procedure.

CLC-7-5-2CLC-8-1-2CLC-9-2-2

Slsulstor Scenarios In «hlchEPP-20 Is required. (Note: Afcostall slsvlstor exercises requiretask.)

SRO Hot License Slrsulator Scenarios(In developcent)

26 Start additional plantequlpcent to assist Inrecovery

CLC Systcsrs Training Each accident requires operationof s unique sct of systccs. Anysystcs that aright be required lstaught In systecs training.

COC Systcrrrs Training Each accident requires s uniqueset of systecs be put Intooperation. Any systcrs that eightbe required is taught In COC

Systecs Training Includingassociated OPs and AOPs,

HCO-LP-1. IPost Accident Cooling

Hit i gating Core Oacage Coursedescribes:I) plant response to accidents2) strategies for assessing dacage3) strategies for recovery4) eqvlpcent required to lsrplcccnt

recovery strategies

HCO-LP-2. IPost Accident Cooling

Mitigating Core Oacage CoursedescrlbesrI) plant response to accidents2) strategies fol'ssessing dscage3) strategies for recovery4) equlpcent required to Isplecent

recovery strategies

MCO-LP-I 2Seal I Bkr LOCA «Ith no ICISI

HCO-LP-2 2Seel I Bkr LOCA «1th no ISISI

HCO-LP-1. 3

loss of FW Induced LOCAs

HCO-LP-2. 3

loss of FW Induced LOCA

MCO-LP-I,4

Vital Process InstruccntstionHCO-LP-2. 4

Vital Process I nstrurrentat ion

HCO-LP-I 5

Accident Response of IncoreInstrucentation

HCO-LP-2. 5

Accident Response of IncoreInstruoentatlon

21 of 22

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (73)

ATTACWENT l2 ENERGENCY PROCEDURES TASK TRAINING HATRIX

TaskNunber

Tas'k Cold License TrainingHCD-LP-1.6

Accident Response of ExcoreInstrusentatfon

Coooents Hot License TrainingHCO-LP-2.6

Accident Response of ExcoreInstrunentatlon

Conments

HCO-LP-1. 7

Post Accident Prlnary RadiochenlstryNCO-LP-2. 7

Post Accident Prinary Radlochexl stry

HCD-LP-1. 8Radiological Aspects of Cote Danage

HCD-LP-2. 8Radiological Aspects of Core Danage

HCO-LP-I.9Loss of All AC Power

HCO-LP-2.9

Loss of All AC Power

HCO-LP-1.10Class 9 Events

HCD-LP-1. I IInstrunent Oval I f I cation andAccident Response

EPP-20

Continuing TrainingMeek 2/Lesson 4

SS7114H

SS712'IHt

CLC-7-52

Specific steps of EPP-20.Tasks required by procedure.

Six(viator Scenarios Involvingaultlple failures of 18R, CCII,etc. Operators are required toevaluate plant status and initiaterecovery with available systeas.

Sinulator scenarios In whichEPP-20 Inple((ented. (Host six(ulatorscenarios require task).

EOP-LP-3.5EPP-20 6 '21

( In developnent)

RO Hot License Sinulator Scenerios(In developnent)

Specific steps and bases forEPP-20. Tasks required forprocedure.

Exercises requiring use ofEPP-20. (Host sinulator scenariosrequire task).

CLC-8-1-2CLC-9-2-2SS7322H

SS7331H

SRO Hot LIcense Sinulator Scenarios(In developnent)

22 of 22

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ATTACHMENT 3ADDITIONAL COLD LICENSE TRAINING

Task Comments

Locally Dumping steamusing S/G PORVs

Manual operation of S/G PORVs will bedescribed and procedure reviewed. Awalkthough of operations will be conducted.Local operations on the S/G PORV have beenincorporated into the applicable nonlicenseQualification Card.

, Minimize SecondaryContamination

, Actions that are being incorporated in therevised EOPs will be described. Manualactions that .require local operations havebeen incorporated into the applicable non-licensed Qualification Cards.

Local Operation ofSwitchgear BKRs

Electrical plant response to SI and LOSPwill be discussed including requirement tomonitor conditions and manipulate switchgear

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (75)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (76)

ATTACHMENT4.-'IMULATORSCENARIOS

1. CLCL-7-2-2: Load Rejection/ATWS/RCS Depressurization

2. CLCL-7-5-2:

3. SS7421H:

S/G Tube Leak/Rupture/ATWS/S/G =PORV Failed Open

Inadvertent SI/SW Malfunctions/LOCA without CSIPs

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (78)

11/10/83SHNPP SIMULATOR EXERCI IDE

EXERCISE: Load Rej ecti on/ATWS/RCS FILE NO. CLC-7-2-2 TIME: 4 hoursDepressur ization

OMECTIVES: .Upon conpletion of this exercise, the student will be able to:0 I t 12 tl 10 I 2 01

limits.

2. Take appropriate actions on load rejection without steam dumps to stabilizeplant in a safe condition.

3. Identify an ATWS event and take actions to prevent core damage andradioactive releases to the environment.

4. Identify a failed open PZR PORV and take corrective actions to stop RCS

depressurization.RELATED LER's, UER's, POER's, etc:

a em P , - Breakers failed open (UV part of mechanicallatch)

INITIAL CONDITIONS: IC-7 (BOL) . Present Previousresent power ours PMR TEE

571 Tav 586875 BoNn 839174 D Rod Hgt 208 0

INSTRUCTOR GUIDE:Ilppp.. I 2„0 1002. I'I-122A I llcharging flow to increase. CSIP failure requires placing "C" pump in service.External load breakers opening with no auto dumps should cause reactor first out(Lo-Lo S/G Lvl). ATWS causes RCS pressure to increase. When spray valves open,fail PCY-444B open. (Note: Do not trip R remotely until PORV opened). RCS

will become saturated and remain saturated until block valve closed. Allowblock valve to close after ISC and maintenance investigates. (Upon completionof exercise, reset for shift turnover per CLC-7-2-1).SHIFT TURNOVER

INFORMATION'crease

power to or feed pump maintenance. Feed pump tested and running.

MALFUNCTIONST-O All Auto Reactor Tr p

Functions (Disabled)T-0 Auto Steam Dump Con-

troller ( Inhibited)T-0 Manual Reactor Trips

(Disabled)T-120 External Load Breakers

52-8 5 52-9 (Open)

OVERRIDEST- PZR PORV Iso Vlv

8000C (Open)T-50 FI-122 A Charging

'eader Flow (Low)T-90 Charging Pump "A"

(Stop)T-VAR PCV-444B Pressurizer

Relief Valve (Open—Fail when sprays open)

REMOTE OPS

L AC arg ng F ow - Transmitter failureChar ging Pump "A" .- Motor bearing seizedExternal Load Breakers - Phase differential relayPCV-4448 - Controller failure/valve jammed on backseatBlock Valve - Breaker tripped (overcur rent relay failed)ATWS - Trip breaker binding/improper lubricationEXPECTED RESPONSE: AS PER SERIAL RELATED CHECKOFF

REQUIREMENTS: 5B, SD, 17, 18, 19, 8, 10, 16, 20, 21, 23, 24

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (80)

Course

SINJLATOR EXERCISE PERFORNHCE/OBSERVATION RECORD

Group Oata

Instructors

Gradings: S = Satisfactory U Unsatisfactory

I. Exercise

A.

B.

Initial Conditions/Scenario - exercise guide

Shift Assignments R S/U p ManipulationsPer. Su Per. Su .

SF

2. SRO

3. RO

BOP

5. STA

II. Evaluation SRO RO BOP STA

A.1.

2.

3.

4.

5.

6.

7.

B.1.

'2.3 ~

4 ~

GeneralSupervisory ability--a. Effective supervision of othersb. Effective direction of otherOperator communications —passesalong information accurately andpromptlyAnnunciator response —immediatelyresponds —uses alarm procedureUse of procedures —pullsprocedure and utilizesSystematic and logical approachto pr obl emsa. Attentive to instrumentation

and controlsb. Compares redundant channelsc. Compares meter to recorderAlertness —aware of plant statusat all timesShift TurnoverOral turnoverHourly logsReview control. boardTest annunciator lights

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (81)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (82)

FILE NO: CLC-7-2-2

Rev. 1

11/10/83

C. Exercise Performance

1. Power Escalation 50% to 100%

SF SRO RO BOP

a.b.C ~

d.e.f.goh.

a ntains avg refTurbine Load LimitsGenerator Loading (MVARs)S/G Level ControlMSR OperationMaintains CAOC

Anticipates Xenon TransientsUses CurvesSecondary Calorimetric at 90%

2. Char in Flow Indicator Failure(low)Imme ate Act ons(1) Identifies Charging

Flow Low(2) Identifies Charging

Pump Running(3) Verifies PZR Level Increasing(4) Takes Manual Control of FCV-122Subsequent Actions(1) Stabilizes Plant(2) Maintains RZR Programmed Level(3) Investigates Cause

3. Char in Pum "A'rimme >a e c ons

(1) Acknowledge Annunciators(2) Starts "B" PumpSubsequent Actions(1) Stabilizes Plant With

PZR Level In Band(2) Refers to Tech Specs(3 ) Investigates Cause(4) Initiates Request to Place "C"

Pump in Service4. Generator Breakers 0 n

a ~

b.

c ~

ent cat on(1) Generator Output

OCBs Open(2) Rapid Load Decrease to

Unit Auxiliary Loads(3) Increased S/G Pressure(4) Inward Rod MotionImmediate Actions(1) Verifies Automatic Actions(2) Observes Failure of Steam Dumps(3) Verifies S/G PORVs Open(4) Refers to AOP-15(5) Places Steam Dumps in Pressure

ControlSubsequent Actions(1) Stablilizes Plant(2) Investigates Cause '

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (83)

File No. CLC-7-2-

C. Exercise Performance (continued)

(3) Transfers Aux Loads(4) Identifies ATNS

5. ATMSa. Immediate Actions

(1) Attempts To manually Trip Rx(2) Drives Rods In(3) Sends Personnel To

(a) Trip MG Sets(b) Trip R Trip Breakers

.(c) Trip M3 Set SupplyBreakers

(4) Emergency Borate(5) Refers to FPP-1, FPP-2, or

FRP-S.1b. Subsequent Actions

(1) Investigate Cause(2) Initiates PEP (Alert)

'I

6. Reactor Tri

Rev. 1

11/10/83

SRD RD BOP ST

a ~

b.

mme ate Actions(1) Verifies R Trip(2) Verifies Turbine Trip(3) Checks Power to AC

Emergency Buses(4) Checks SI Actuated(5) Refers to FPP-1 or FPP-2Subsequent Actions(1) Verifies Plant Parameters

Stablilizing at No-load Values(a) T(b) S/PLevel(c) PZR Pressure and Level

(2) Conducts "Dead-Bus" Transferto S/U Transformers

(3) Verifies Source Range Energized(4) Secures Unnecessary Equipment(5) Stabilizes Plant at No-load

Conditions

7. PZR PORV Failurea ~

b ~

(1) PZR Pressure Decreasing(2) Relief Line Temp

Increase/Alarm'3)

PORV Indicates Open(4) PRT Parameters Increasing(5) PZR Sprays Indicate OpenImmediate Actions(1) Attemps To Close Block PORV(2) Energizes Heaters(3) Refers to AOP-19(4) Observes SI Initiates

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (84)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (85)

File No. CLC-7-2-2

C. Exercise Performance (continued)

c. Subsequent Actions(1) Investigates Failure of Block

Val ve(2) C1oses after IAC Repair

8. Safet Injectiona. e ers to -1 or FPP-2b. Performs Imaediate Actionsc. Stops RCPs (1400 psig)d. Verifies Plant Recoverye. Identifies Causef. Terminates SI Mhen Criteria Met

9. Natural Circulationa. ent cat on

(1) No RCPs Running(2) Heat Sink Available

b. Subsequent Actions(1) Refer To EPP-5(2) S/G Press < 1110 psig(3) ,RCS 40'F(4) RCS h T < 60'F

10. Added Malfunctionsa.b.

c ~

d.

Rev. 1

11/10/83

SRD RD BOP STA

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (86)

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (87)

FILE NO. CLC-7-5-2

Rev. 04/12/84

C. Exercise Performance (continued)

5. S/G Tube Leak

( 1) Increased Charging Flow(2) Leak Rate OST Performed(3) RMS increase R-19(4) Performs Leak Isolation or

Identifies Source(5) Checks all Instrumentation

b. Immediate Actions( 1) Determines Appropriate S/G(2) Checks Tech Specs(3) Commences Rx S/D(4) Shifts Condenser Exhaust

-(5) Refers to AOP-16(6) Observes Blowdown Isolated

6 ATWSa. Immediate Actions

(1) Attempts to Manually Trip Rx(2) Drives Rods In(3) Sends Personnel to Trip Rx

Breakers(4) Emergency Borate(5) Refers to FRP-S.1

b. Subsequent Actions(1) Investi gates Cause(2) Initiates PEP (Alert)

7. ~|ia. Immed>ate Actions

(1) Verifies Rx Trip(2) Verifi es Turbine Trip(3) Checks Power to AC

Emergency Buses(4) Checks SI actuated(5) Refers to FPP-1 or FPP-2

b. Subsequent Actions( 1) Verifies Plant Parameters

Stabilizing at No-load values(a)(b) S/G level(c) PZR Pressure and Level

(2) Verifies Transfer to SUTransformers

(3) Verifies Source RangeEnergized

(4) Secures. Unnecessary Equipment(5) Stabilizes Plant at No-load

Conditions

SF SRO RO BOP

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (88)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (89)

F ILE NO. CLC-7-5-2

Rev. 04/12/84

C. Exerci se. Performance (continued)

c. Initiates PEP (unusual event)

8. Safety Injection/S/G PORV Failed ena. Comp etes Immediate Actions o

FPP-1 or FPP-2(1) Identifies RHR Pump A Tripped(2) Restarts RHR Pump A

b. Identifies SGTR as Causec. Identifies Ruptured S/Gd. Isolates Ruptured S/Ge. Identifies S/G PORV Failed Openf. Begins RCS Depressurization and .

Cooldowng. Maintains Ruptured S/G Level

Between 10% and 50%h. Implements FPP-17

(1) Resets SI/Phase A

(2) Cooldowns to 200'F at< 100'F/hour

(3) Depressurizes to MinimizeRCS Subcooling at 40'F

(4) Maintains PZR Level(5) Terminates SI(6) Restores LP and Charging(7) Isolates Accumulator

9. Intermediate Range Undercom ensateda. Ident> ies Undercompensat>onb. Manually Energizes Sources Ranges

10. Added Nalfunctions

SF SRO RO BOP

a 0

b.

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (90)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (91)

0. iaalator Exercise Comments:

NTS/AI-26

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (92)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (93)

E. . xerc3se Critique:SRO - S/U

RO - S/U

Eval. - S/U

. ~SF - S/U BOP - S/U

STA - S/U

Overall Group

F. Student Comnents/Sfaalator Improvement:

Instructor' Signature

HTS/AI-26 14 Rev. I

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (94)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (95)

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SHNPP SIMULATOR EXERCIS UIDE

EXERCISE: Inadvertent SI/SW MalfunctionsLOCA W/0 CSIPs

LESSON CODE: SS7421H

OBJECTIVES: Upon completion of this exercise, the student will be able to:

1. Perform the immediate actions required of operators following a Rx trip andSI.

'.

Use the EOP network inclusive of the Flow Paths, End Path Procedures andFoldouts to direct operator actions.

3. Complete the appropriate attachments of OMM-004 following an activation ofthe ESFAS.

4. Identify a need to and make notifications required by the PEP.

5. Identify a stuck control rod and make required adjustments in shutdownmargin.

6. Use AOP-001 to correct for a stuck control rod.I

7. Use available MCB indications plus requested information to identify a lealC.from the CCW to ESW system.

8. Use OWPs to place the protective cabinets in the correct alignment asrequired by Tech Specs following an instrument failure.

9. Detect and take corrective action for a failure of the steam dumps tocontrol temperature.

10. Use EPP-001 to mitigate the consequences of a loss of both CSIPs inconjunction with a small break LOCA.

INITIALCONDITIONS: IC 43 ( )Present conditions for: )100 Hrs

Present~100

588'F,527ppm

"D" at 192 steps

PWR

TavBar30Rod Hgt.

Previous

same

SHIFT TURNOVER INFORMATION: Presently on line within one day of exceedingCPELs Nuclear on-line record. No surveillances scheduled. No testingallowed. Anticipate no changes CSIP under clearance for bearing replacement."C" CSIP will be available in six hours, two hours into action statement.

INSTRUCTOR GUIDE: Reset to IC 43, reboot RMS, ERF IS and conduct shiftturnover. With lamp test complete override the Vacuum pump trip alarms to offand the operating vacuum pump red light to "on". Fail the operating vacuum

'pump. When requested, report the motor operating but' drastic drop in noiselevel (coupling sheared). With stability restored insert the inadvertent SI.After restoration have the SF complete an OMM-004. With this report ongoinginsert the CCW-ESW leak. With trouble shooting ongoing and temperaturerestored to 557 fail P-12. Allow both conditions to run their course and becorrected. With all systems restored to normal fail the operating CSIP. Givetime for immediate action and fail the seal stack on any RCP (insert ~ 100 gpmleak to provide the leakage of the seal failure). If EPP-001 not addressed theinstructor should prod in that direction before the situation degrades too far.

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (96)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (97)

MALFUNCTIONST-0 CRF3A untripable for P-8T-0 CRF3A untripable for K-14T-15 CND4A(B) to activeT-30 SIS 1 to activateT-75 CCW 3 to 30 gpmT-90 MSS9 to fail .

T-120 CVC 5 for operating unitTVAR RCS14A(B)(C) to 60 gpmTVAR RCS15A(B) (C)TVAR RCS16A(B) (C)

OVERRIDES REMOTE OPS.

T-O CND 94 (99) to low T-0 CSIP rackingT-0 CND 104 to low statusT-0 CNE 28 (29) D to "hi"

SUPPLEMENTAL INFORMATION:Inadvertent SI to ensure completion of OMM-004 prior to Exam.

2. Vacuum Pump coupling break occurred at HBR.3. Loss of both CSIPs to use EPP-001 for this condition.

EXPECTED RESPONSE: AS PER SERIAL RELATED CHECKOFF

SUCCESSFUL COMPLETION OF THIS EXERCISE FULFILLS THE FOLLOWING NRC AND INPOREQUIREMENTS: 5C, 11, 17, 19, 24

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (98)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (99)

~ 4 ~

. ~SIMULATOR EXERCISE PERFORMANCE/OBSERVATION RECORG

Cour se

Instructors

Group Oate

Gradfngs: S Satisfactory O'nsatisfactory

I. Exercf se

A. Initial Condftfons/Scenario - exercise guide

B. Shfft AssignmentsPer.

1. SF

2. SRO

3. RO

4. BOP

5. STA

x S U

U ~ Per. S~

II. Evaluation

A. General1. Supervisory ability-

a. Effective supervision of othersb. Effective direction of others

2. Operator coamunfcatfons —passesalong information accurately andpromptly

3. Annunciator response-fmmedfatelyresponds —uses alarm procedure

4. Use of procedures —pullsprocedure and utilizes

5. Sytematfc and logical approachto problems

6. a. Attentive to fnstrumentatfonand controls

b. Compares'redundant channelsc. Compares meter to recorder

7. Alertness —aware of plant statusat all times

B. Shift Turnover1. Oral turnover2. Hour ly logs3. Review control board4. Test annunciator lights

SF SRQ RO BOP ST

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (100)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (101)

~ \~ ~ +

Rev. 0

LESSON COOE: SS7421H

C. Exercise Performance SF SRO RO BOP

2.

3.

Loss of Condenser Vacuuma. Notes change in efficiency,'reports

same and'nvestigatesb. Notes change in condenser vacuum and

performs immediate actions-of AOP-012c. Refers to AOP-012 for auto and

immediate action verificationd. Performs follow-up action of AOP-012e. Request sufficient information of

A.O. to diagnose problemf. Initiates corrective maintenanceg. Makes notifications required

Inadvertent SIa. Recognizes condition and takes

appropriate immediate actionsb. Uses EOP path 1 for action

verificationc. Recognizes SI termination criteriad. Address foldout A and B of EOP networke. Terminates SI IAW EPP-004f. Initiates investigationg. Performs required administrative

dutiesh. Address PEP and make notificationsi. Performs required portions of OMM-004

Stuck Rodsa. Recognizes mispositioned control rodsb. Recognizes SI flow sufficient to meet

emergency boration requirementsc. Following SI realignment verifies

sufficient SOM'.

Address AOP-001 for corrective actionfollowing SI termination

e Initiates corrective action

4,

5.

Steam Ou Failurea. Notes SG-PORVs operating with

condenser availableb. Investigates and finds steam dump

mal functionc. Investigates cause and correctsd. Initiates corrective action,

CCW Leaka. Interprets indications and recognizes

a loss of CCW

b. Perform immediate action of AOP-014c. Refers to AOP-014 for auto and

immediate action verificationd. Performs follow-up action of AOP-014

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (102)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (103)

~ I~

Rev. 0

LESSON CODE: SS7421H

C. Exercise Performance (continued)

e. Trouble shoots and isolates leakto source

f. Performs system realignment toisolate leak

g. Address potential environmentalconcerns

SF SRO RO BOP

6. Loss of second CSIPa. Recognizes severity of failureb. Immediately takes action to reduce

RCS inventory lossc. Takes action to recover any CSIPd. Addresses EPP-001 as the only

procedure that remotely covers thesituation

P

7. RCP seal failure LOCAa. Perform immediate action of AOP-016b. Addresses AOP-016 for verificationc. Recognizes impact of excessive

leakage W/0 CSIPsd. Initiates rapid cooldowns to allow

depressurization to reduce leakagee. Classifies event and makes notifi-

cations as required by the PEPf. Properly injects accumulatorsg. Request assistance from plant staffh. Places RHR in service when allowable

8. Added Malfunctions

'a ~

b.

c ~

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (104)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (105)

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0. Siaolator Exercise Coaments:

NTS/AI-26

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (106)

ee,

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (107)

E ~ Exercise Critique:

SRO - S/U

RO - S/U

SF-S/U

STA-S/UW

Overall Group Evan -S/U

BOP-S/U

F ~ Student Cosiients/SiauI ator I aproveaent:

Instructor 's Signatur e

S IMPE RFORM Page 3 of 3 Rev. 1

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (108)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (109)

SHNPP SIMULATOR EXERCIS IDE

Rev. 04/12/84

EXERCISE: S/G Tube Leak/Rupture/ATNS/ FILE RQ. CLC-7-5-2 TINE: A braS/G PORV Failed Open

OBJECTIVES: Upon completion of this exercise, the student will be able to:P /P k k, k / i /«P/

open to stabi1 ize the pl ant, and minimize radioactive rel eases to theenvironment per FPP-17.

2. Take proper actions to put the reactor in a safe shutdown conditionfollowing an ATWS event.

RELATED LER's, UER's, POER's, etc: Ginna - January 25, 1982--S/G tube rupture;tu e ea ; - LER-81-026 tube leak; HBR - LER-81-022 tube

leak.

IC-11 (MOL) Present Previous5% PWR 75%5579'F Tav 578'F380 ppm Boron 450 ppm103 on "D" Rod Hgt. 194 on "D"

INSTRUCTOR GUIDE:~p. P P //P« . p /PP . k

eower, fail CCW pump. Fail N-42 after 90% calorimetric, and insert S/G tube

eak during subsequent pwr increase. Increase tube leak severity to cause SIactuation. An ATWS event will occur.

INITIAL CONDITIONSPresent Power 3 1/2 hrs.

SHIFT TURNOVER INFORMATION:sve p ant condst1ons. ant at 5% power following trip of "B" condensate pump ..

(BKR malfunction). Repairs are completed. Synchronize to grid and increasepower to 100%.

MALFUNCTIONS OVERRIDES REMOTE OPS

T-0

T-0

T-0

T-90

T-130

T-130

T-VAR

All Auto R TripFunctions (Disabled)Manual R Trips(Disable5)IR Channel 35(Undercompensated)PR Channel 42 (Instr.Power Fuses Blown)Rather Than C-Loop,Leak in (A-Loop)Generator Tube Leak(24 GPM Increase to600 GPM)Power Oper. Rel. Valve(Failed Open)

T-0 PZR heaters Gr-A offT-0 "A" RHR pump (stop)T-30 "A" CCW pump (stop)

SUPPLEMEN AL IN ORMATION:pump - se>ze motor bearing

PZR heaters Gr-A breaker tripped at control cabinet - due to overcurrent(heater grounds)

ATWS - BKR failureTR-412 bT pen - stuck pen"A" RHR pump - electrical circuit breaker closing mechanism failureN-42 - Instrument power fuses blown

EXPECTED RESPONSE: AS PER SERIAL RELATED CHECKOFF

RE(}UIREMENTS: 2, 3, 5A, 7, 8, 14, 16, 19, 21, 23, 24, 25, 26, 31

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (110)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (111)

Course

Instructors

SINLATOR EXERCISE PERFORMANCE/OBSERVATION RECORD

Group Date

Gradings: S = Satisfactory U = Unsatisfactory

I. Exercise

A.

B.

Initial Conditions/Scenario - exercise guide

Shift AssignmentsPer.

R S/USu Per.

p ManipulationsSu

SF

2. SRO

3. RO

4 ~ BOP

5. STA

II. Evaluation SRO RO BOP STA

A.1.

2.

3.

4,

5.

6.

7.

B.1.2.3.4,

GeneralSupervisory ability--a. Effective supervision of othersb. Effective direction of otherOperator communications —passesalong information accurately andpromptlyAnnunciator response--immediatelyresponds —uses alarm procedureUse of procedures —pullsprocedure and utilizesSystematic and logical approachto problemsa. Attentive to instrumentation

and controlsb. Compares redundant channelsc. Compares meter to recorderAlertness —aware of plant statusat all timesShift TurnoverOral turnoverHourly logsReview control boardTest annunciat'or lights

Rev. 0

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (112)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (113)

FILE NO. CLC-7-5-2

Rev. 04/12/84

C. Exercise Performance SF SRO RO BOP

1. Reactor Critical with Reactor Power < 3'X

a ~

b.

c ~

eri ies, nitia on itionsMaintains Primary and Secondary(1) S/G Level.(2) R„ Power <

3'3)

T ve/T efGenerator Start-up(1) Voltage Control(2) Synchronizing

2. Power EscalationCl 0

b.c ~

d.e.f.goh.1 ~

J ~

,/T„pTurbine Load LimitsGenerator Loading (MVARs)S/G Level ControlMSR OperationMaintains CAOC

Anticipates Xenon TransientsSecondary Calorimetric at 90'XUses CurvesIdentifies bT pen failure

3. Com onent Coolin Water Pum Failurea ~

b.'

~

dent»cation(1) Acknowledges Annuciators(2) Checks Flow IndicatorsImmediate Actions(1) Starts Backup Pump(2) Verifies flow(3) Refers to AOP-14Subsequent Actions(1) Investigates Cause(2) Checks Tech Specs(3) Informs ISC(4) Fills Out Work Request(5) Aligns C Pump as Backup

4. Power Range NI Failurea e

b.

Immediate Actions(1) Stabilizes Plant(2) Refers to Tech SpecsSubsequent Actions(1) Rod Stop Bypassed(2) Comparator Channels Oefeated(3) Fuses Removed(4) OP-OT aT Bistables Tripped(5) Mrites Clearance(6) Refers to AOP 8 OWP

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (114)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (115)

NTS(Al-Z6 13 Rev.

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (116)

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· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (117)

E. xercfse Crftfque:*

SRO - S/U

RO - S/U

Eval. - S/U

SF - S/U BOP - S/U

STA - S/U

Overall Group

F. Student Comnents/Sfaalator Improvement:

Instructor's Signature

NTS/AI-26 14 Rev.

· ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (118)

C- C.R

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 · ~ ' REGULA, Y INFORNATION DIBTRIBUTI YSTEN (RIDS) ACCESS/ON NBR: Sb10090482 DQC. DATE: Sb/10/01 NOTARIZED: NQ, DOCKET 0 FACIL;50-400 Shearon Harris Nuclear Power Planti Unit ii - [PDF Document] (2024)

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