ML17069A421

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Limerick Generating Station - Draft Operating Exam (Section a, Section B and Section C) (Folder 2)
ML17069A421
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 01/16/2017
From:
Exelon Generation Co
To:
Operations Branch I
Shared Package
ML16076A445 List:
References
U01940
Download: ML17069A421 (325)
v • d • e


Text

{{#Wiki_filter:j .;:"'!"'f" Exelon Generation Developed By: ,, Validated By: Reviewed By: Reviewed By: Approved By: LOJPM6717 Rev001.doc LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE EVALUATE JET PUMP OPERABILITY JPM Number: LOJPM6717 REVISION NUMBER: 001 DATE: __ _ Instructor ' SME or Instructor Operations Representative EP Representative Training Department SRRS: 30.105 (When used for operator initial or continuing training) Date Date Date Date Date Page 1 of 10 I --* Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is used, the task standard contains criteria for successful completion.
9. Verify the procedure(s) referenced by this JPM reflects thEI current revision:

Procedure ST-6-043-320-1 Rev: 45 -"-""--Procedure Rev: __ _ Procedure

Rev: __ _ Procedure Rev: ---------- ---Procedure---------- Rev: __ _ 10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM6717 Rev001.doc SRRS: 30.105 Page 2 of 10 (When used for operator initial or continuing training)

,, ' I Generation II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: " A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the ' revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision Description of Revision and Affect on Training Content # Date of Number Revision 000 This JPM replaces 2010 RO A 1-2 Revised to new template and to 08/15/14 align with latest procedure revision. 001 Updated template and KA 10/31/16 # Date of Revision -refers to date revision was released for approval LOJPM6717 Rev001.doc SRRS: 30.105 Page 3 of 10 (When used for operator initial or continuing training)

Exelon Generation IV. TASK STANDARD: The candidate should report the test is UNSAT due to failure on "A" loop drive flow high and "A" loop jet pumps flow low. v. INITIAL CONDITIONS: Plant conditions are as follows: 1. Unit 1 is in OPCON 1 2. An unexpected drop in reactor power occurred 3. An unexplained rise in core flow occurred 4. ON-100, Failure Of A Jet Pump, was entered VI. INITIATING CUE: I Perform ST-6-043-320-1, Daily Jet Pump Operability Verification for Two Recirculation Loop Operation, report the results, and (SRO only) any compensatory actions, if required Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. LOJPM6717 Rev001.doc SRRS: 30.105 Page 4 of 10 (When used for operator initial or continuing training) I=-Exelon Generation VII. PERFORMANCE CHECKLIST: JPM Start Time -----I-I-a: ZW ELEMENT STANDARD <( Wal CJ) :a: :a: CJ) z :a: ::> ::::> Oz 0 EVALUATORS NOTE: Provide Candidate with the following:

  • JPM briefing sheet
  • Yellow Copy of ST-6-043-320-1
  • PMS computer screen shots I
  • Calculator
  • Unit 1 Tech Specs (SRO Only) ,, I
  • 1. [ST-6-043-320-1 step 4.3.1.3] Candidate determines that Determine if Loop "A" flow is within Loop "A" is NOT within the 10% of the loop flow values on the limits -UNSAT established pump speed-loop flow characteristic curve 2. [ST-6-043-320-1 step 4.3.2.3] Candidate determines that
  • loop "B" is within the limits -Determine if Loop "B" flow is within 10% of the loop flow values on the SAT established pump speed-loop flow characteristics curve. 3. [ST-6-043-320-1 step 4.3.3.4] Candidate determines that I total core flow is within the
  • Determine if the value of total core flow is within 10% of the established limits-SAT Total Core Flow value derived from Recirc Loop Flow Measurements
4. [ST-6-043-320-1 step 4.3.4.4] Candidate determines that
  • Determine if Loop "A" Jet Pump the jet pumps on Loop "A" are diffuser-to-lower plenum differential NOT within the limits -pressure is within 10% of the UNSAT established patterns LOJPM6717 Rev001.doc SRRS: 30.105 Page 5 of 10 (When used for operator initial or continuing training)

Exelon Generation I-a: I-Zw ELEMENT STANDARD I-<C w Ill <C en :!: :!: en z :!: ::> ::> Oz 0

  • 5. [ST-6-043-320-1 step 4.3.5.4] Candidate determines that all Determine if Loop "B" Jet Pump of the jet pumps on Loop "B" diffuser-to-lower plenum differential are within the limits -SAT pressure is within 10% of the established patterns 6. [ST-6-043-320-1 step 4.4.1] Candidate determines that
  • Verify at least two of the step two of three areas are combinations are satisfactory:

UNSAT and the overall ST results are UNSAT

  • 4.3.1.3 and 4.3.2.3 (Pump speed vs. drive flow) UNSAT Report the unsatisfactory results -The "A" Jet Pumps
  • 4.3.3.4 (Total loop flow vs. total have failed the surveillance core flow) SAT test. ., I
  • 4.3.4.4 and 4.3.5.4 (Individual JP DP vs. Drive Flow) UNSAT ' NOTE: This is the termination point for RO's CUE: (RO's only) -You have met the termination criteria for this JPM The remaining portion of this JPM is "SRO's only' ,,
  • 7. SRO candidate determines Tech Tech Spec LCO 3.4.1.2. With Spec implications of the failed Jet one or more Jet Pumps Pump surveillance test inoperable, be in HOT SHUTDOWN within 12 hours CUE: (SRO) You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM6717 Rev001.doc SRRS: 30.105 Page 6 of 10 (When used for operator initial or continuing training)

I Generation JPM

SUMMARY

Operator's Name: _______________________ _ Job Title: 0 SEO 0 SM 0 SRO 0 RO 0 STA/IA 0 EO D OTHER JPM Title: EVALUATE JET PUMP OPERABILITY JPM Number: LOJPM6717 Revision Number: 001 Task Number and Title: 2000010401 ON-100, Actions For Jet Pump Failure 3410070302 Direct action per T.S. when an LCO is not satisfied Kl A Number and Importance: Generic Generic 2.1.19 2.2.40 3.9/3.8 3.4/4.7 Safety Function (1-9) Admin Category (A1-4} 1/2 (Conduct of Operations I Equipment Control) Level of Difficulty (1-5) i ! Suggested Testing Environment: 1 Classroom Alternate Path:O Yes [8J No SRO;Only: 0 Yes [8J No Time Critical: 0 Yes [8J No I Reference(s}: ST-6-043-320-1, Daily Jet Pump Operability for Two Recirculation Loop Operation, Rev 45 Tech Specs Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate [8J Perform Estimated Time to Complete: _gQ_ minutes Actual Time Used: ____ minutes EVALUATION

SUMMARY

.. ' Were all the Critical Elements performed satisfactorily?

D Yes 0No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name:-----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM6717 Rev001.doc SRRS: 30.105 Page 7 of 10 (When used for operator initial or continuing training)

.* Exelon Generation. INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET Plant conditions are as follows: 1 . Unit 1 is in OPCON 1 2. An unexpected drop in reactor power occurred 3. An unexplained rise in core flow occurred 4. ON-100, Failure Of A Jet Pump, was entered I INITIATING CUE: Perform ST-6-043-320-1, Daily Jet Pump Operability Verification for Two Recirculation Loop Operation, report the results, and (SRO only) any compensatory actions, if required. Document required action(s): ,, ' Page 8 of 10 Exelon Generation RU AA 1 IPMI 47 13 2 [£] 19 i n I EL., e Group Point Display Group Data Display on LG1PA m Change Group Group Number: 33 Gmup Name: Group Definition ST PTS {JET PP Ust Groups Group Status: ACTrVE Point ID :a.o;u 2 1'036 :l R037 4 R034 ,; aoia ti :ti037 7 B039 a El.266 li El.2(;7 iO EOSO H E052 12 E0.51 n l\:05::S 14 15 1fi H 16 .19 20 ll:S4.:S4 current Engineering Low High Oescriptlon Status Value Units Plot Umlt Plot Limit DR¥WSt..r.. EL 330 FT TEMP t'WIL 1J6 DJ:;GF O so DRYWEJ.:.L 260 F'l' '.t'll:.Ml? Nlr<t;L,1 1.24. DEG:E' EL 260 i"I' TE.MP rn:.u. 1.24 PRD'.IEL.L EL 320 FT TEMP ll6 DEGF ( l.S) REACTOR F'U'>W tl14L 13$1. 2 MLB/H {1.9) A RECl'.BC Pm.> A1(0RIVE) FLOW mu, 16.075 WJ3./H {21} :S REC:X:RC PMP JU (DRIVE) 1'"'LOW NHIJ 1.5.1.22 MLB/H A REC:X:R.C PUMP SP'EEP 1,J:tr::L 1Jl4

s rui:crRC PUMP SPEED IiiH::.. nu RPM D11. 4.l.4' KV SFGP nos VOL:'I'AGE Hl!i'.L 4,H ID/AC D:l.3 4.1.6 KV SFGD BOS VOLTAGE: l'l'.WL ... 31 KVAC DJ.:Z 4 .16 KV $l"GP BOS VOLTAali':

Nt".lL ,. .. n. KVAC Pl-4 4 .16 K!.r Sli'QD BOS VOt.TAGE. NH.T, .,;.:n. =I-di.splay MGPPFW -FWD 50 250 .*-.................

      • -***Jii'--

50 "'"jii;'-' 2:50 0

.o o.ooo 0.000 16.()00 18.000 0.00 -o.oo 0.00 o.oo i ewo ... --4.50 4.50 4. .so L.Dl:ERICK 1 1:21SS:l.£1; SrM

[ Generation I :S:119.2FL2 D/W FLl't DRlll $IJMl> FLW 2 .AVGL fu"::IJL O. 245 GPM .00() Group Point Display Group Data Display Change Group Group Number: 2 Group Name: G Group Definition .Jll:T D/P'S (*za SRI.FT ST} Current Low Poli; I JD J:lescrlptlon .. --*-. ***--**-*****

    • -***-**

_ Stat!Jfi' \(;1Jt1e Units Plot Limit El084. JET PUMP l SINGLE TIU' DP 2 :EllOJ .:rnvr !?UMP 2 SINGLE TAP DP 3 Eil05 .n."T PUMP 3 TAP DP 4 J,.;l.247 JET PUMP 4. SINGLE 'l'AP DP S l!:l.249 JET PUMP 5 Sl.NGLE TAJ? DP

me H:U.,

-{:(,._';,..j_,z mnJ 3:5 .S::l9 % J,5 .. 424 % 33.:56 % 3.;,"552 % 44,.305 % 0.000 o.ooo o.ooo. 0.000 o.ooo on LG1PA I§ l.i$l Groups Group Status: ACTIVE High PtotUmit ... .... 100.000 * **-l.00. CHH:> . ., ... 1crn.ooo _____ ...: .... 100. 000 .... I "'"' .... ............ 000 c El255 .n:.T POW? G T.lU? OP 7 El257 JET POMI;' 7 SINGLE TAP DP NZ*1L .::S'J "/Sr/ % % % (I. 000 .... H)0.000 -a IU259 JET PUW? a s::rnGLE TAP DP 9 li:l.263 .ll.'T l>t.Thll' 9 SINGLE TAP DP 10 El265 JET .PUMP 10 SDIGLE TAP DP 11 '.El.03/ JL'T PUM.li' l.l Sl:WI.Jll TAP DP 12 El.097 JET PUMP 12 TAP DP U Ell04. ..JET Pl:JMP 13 SJ:NGli.i: 'l'All Dli' 14 li.:1235 JET PUMJ? 14 Sl:NGl.ll: TAP DP 15 El.254 .n:T J?tJMp 15 Sl:NGU!l 'l'A.P-DP 1fi i 17 111 ;9 21) E124$ EJ.256 £:.l.251:1 l!:l.260 El.264 06;49:0'1 JET l?1;m1:i?

l. ..

':t'Al? .tit> JE'1' POMP .t 7 TAJ! Pl' J£'1' PUMP 18 SINCilJ!.l TAP DP .U."T PtJm? l.9 S:tNQLE TAJ> Di> JET PUMP 2 0 SINGLE TAP DP - h!Jll..L. Nl'1L NJ:"'-L t{LfL 1-.r,:u, r,;t-:t.L Nt<:il .* 1idi.1 N-zu. NML Vi:t1L .. 32.0351 3'01 42. 0:(.):1 27., 54 27 "784 25 ... 119 :,,;,; _ 7;:4 :i?. lb7 ;;s.oss 1$,S1 SI :.7. 021 67. 54:l 21$. !S&C % '\. % % % % % % . ..., o.coo o.ooo 0.000 0. 000 a.ooo J&ll*ful:tMJJMJJL-*-********-***--*--*-**** ... i,.. loo. ooo J._. l.OU.000 .... . .. L. J.00. 000 .JO' ... *L 100.000 ........ J.00.000 ..... 0.000 l.00.000 O.QQO o.ooo o.ooo o.ooo o.ooo 0.000 0.000 o.ooo .... 100.000 ........... -... 1o--100. 000 ..... *-***..,..100.000 ........... .,.. l.00. 000 --... . **-:... 100. 000 .,..., I ..,.100.000 ' .,.. ****'* :UlO. 000 ... ----l.100.000 1 I ffioj***** '******--awo 6: !;;0:45 SIM I ;:;!:; Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE DETERMINE MAXIMUM GENERATOR VARS " I ,, ' Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LOJPM6719 RevOOO.doc JPM Number: LOJPM6719 REVISION NUMBER: 000 DATE: ----Instructor Date SME or Instructor Date Operations Representative Date EP Representative Date Training Department Date SRRS: 30.105 (When used for operator initial or continuing training) Page 1 of 9 .. ' I Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*}. 8. If an alternate path is used, the task standard contains criteria for successful completion.
9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure ON-126 Rev: 14 Procedure E-5 Rev: 22 Procedure

Procedure

10. Verify cues both verbal and visual are free of conflict.
11. Verify performance time is accurate Rev: __ _ Rev: __ _ Rev: __ _ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM6719 RevOOO.doc SRRS: 30.105 Page 2 of 9 (When used for operator initial or continuing training)

.. '

' Exelon Generation.

1-II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date i Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

  • Revision ' # Date of Number Description of Revision and Affect on Training Content Revision 000 This is a new JPM. 07/25/16 # Date of Revision -refers to date revision was released for approval LOJPM6719 RevOOO.doc SRRS: 30.105 Page 3 of 9 (When used for operator initial or continuing training)

I Generation IV. TASK STANDARD: Determine the following: Part 1 -Maximum VARs at 75 psig H2 and 1200 MWe determined to be 400 MVARs Part 2 -A power reduction to 1160 MWe ( :s_ 1163 if linear interpretation is used) is required to maintain VARs at 400 MVARs with Main Generator H2 press at 70 psig. V. SIMULATOR SETUP 1. N/A VI. INITIAL CONDITIONS:

1. Unit 2 is at 100% power when the PJM issued a Voltage Reduction Alertl
  • The TSO has requested the plant maintain maximum VAR support .;
  • U2 Generator Real Power is 1200 MWe
  • Current U2 Generator H2 pressure is 75 psig. VII. INITIATING CUE: 1. Shift supervision directs you, due to Grid conditions, to respond to the TSOs request, and determine the Maximum VAR output that remains within the capability of the U2 Generator for the current plant conditions, and VIII. FOLLOWUP CUE: 2. A leak developed in the generator H2 system that resulted in an unexpected "2 Gen Hydrogen And Seal Oil Sys Trouble" Alarm and uncontrolled Main Generator Hydrogen Pressure drop. The leak has been identified and mitigated, current generator H2 pressure is 70 psig and steady. The load dispatcher informs you that they are prioritizing VAR support over MWe generation; What additional procedure entry is required and what if any U2 maneuvering is required to maintain the maximum VAR output determined in part 1 above while staying within the U2 Generator Capability?

LOJPM6719 RevOOO.doc SRRS: 30.105 Page 4 of 9 (When used for operator initial or continuing training) I ;:.;:"'Exelon Generation Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate the initiating cue. LOJPM6719 RevOOO.doc SRRS: 30.105 ,, I ,, (When used for operator initial or continuing training) Page 5 of 9 = .* Exelon Generation 1-IX. PERFORMANCE CHECKLIST: JPM Start Time -----I-cc I-Zw ELEMENT STANDARD I-<( W III <( (/) :2E :2E (/) z :2E :::> :::> Oz 0 EVALUATORS NOTE: Provide candidate with a copy of the following:

  • E-5, Grid Emergency
  • 1. Candidate determines the Maximum Candidate concludes, using VARS at 1200 MWe with H2 press at E-5 Attachment 2, the 75 psig. maximuni VARs with H2 press at 75 psig and at 1200 MWe determined to be 400 MVARs I EVALUATORS NOTE: Once Initiating Cue is compete provide candidate with Followup Cue and upon request for ON-126 1 Provide candidate with a copy of the following:
  • ON-126. Uncontrolled Main Generator Hydrogen Depressurization .
  • 2. Candidate evaluates conditions Candidate determines that provided in Follow-up Cue and the for ON-126, determines ON procedure entry is Uncontrolled Main Generator required.

Hydrogen Depressurization have been met.

  • 3. Candidate determines the Candidate, using Attachment requirements for Maximum VAR 1 of ON-126 (OR E-5 support when U2 Generator H2 Attachment
2) concludes that pressure is reduced to 70 psig. a power reduction to !5..., 1160 MWe ( 1163 if linear interpretation is used) is required to maintain VARs at 400 MVARs with Main Generator H2 press at 70 psig. CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM6719 RevOOO.doc SAAS: 30.105 Page 6 of 9 (When used for operator initial or continuing training)

I ;;;;-:""Exelon Generation JPM

SUMMARY

Operator's Name: _______________________ _ Job Title: 0 SEO D SM D SRO D RO D STA/IA D EO 0 OTHER JPM Title: DETERMINE MAXIMUM GENERATOR VARS JPM Number: LOJPM6719 Revision Number: 000 Task Number and Title: 2001110501, ON-126 Actions for Uncontrollable Main Generator Hydrogen Depressurization. KIA Number and Importance: Generic 2.1.25 3.9/4.2 Safety Function (1-9) N/A Admin Category (A1-4) 2 (Equipment Control) Level of Difficulty (1-5) 3 Suggested Testing Environment: Simulator Alternate Path:O Yes i:gJ No Only: D Yes i:gJ No Time Critical: D Yes i:gJ No Reference(s): ON-126, Uncontrolled Main Generator Hydrogen Depressurization, Rev 14 E-5, Grid Emergency, Rev 22 Actual Testing Environment: D Simulator LJ Control Room LJ In-Plant 0 Other ' Testing Method: 0 Simulate i:gJ Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements perfprmed satisfactorily?

0 Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: 0 Satisfactory 0 Unsatisfactory Evaluator's Name: -----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM6719 RevOOO.doc SRRS: 30.105 Page 7 of 9 (When used for operator initial or continuing training)

> Exelon Generation. INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Unit 2 is at 100% power when the PJM issued a Voltage Reduction Alert.

  • The TSO has requested the plant maintain maximum VAR support
  • U2 Generator Real Power is 1200 MWe
  • Current U2 Generator H2 pressure is 75 psig. X. INITIATING CUE: 1. Shift supervision directs you, due to Grid conditions, to respond to the TSOs request, and determine the Maximu'm VAR output that remains within the capability of the U2 Generator for the current plant conditions?

' Provide response below: Page 8 of 9

Exelon Generation. XI. FOLLOWUP CUE: 1. A leak developed in the generator H2 system that resulted in an unexpected "2Gen Hydrogen And Seal Oil Sys Trouble" Alarm and uncontrolled Main Generator Hydrogen Pressure drop. The leak has been identified and mitigated, current generator H2 pressure is 70 psig and steady. The load dispatcher informs you that they are prioritizing VAR support over MWe generation; What additional procedure entry is required and what if any U2 maneuvering is required to maintain the maximum VAR output determined in part 1 above while staying within the U2 Generator Capability? Page 9 of 9 ,.:J:!f:f Exelon Generation. Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LOJPM6777 Rev001 LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE PREPARE A PARTIAL PROCEDURE JPM Number: LOJPM6777 REVISION NUMBER: 001 DATE: ___ _ Instructor SME or Instructor Operations Representative EP Representative Training Department Date Date Date Date Date " ' ,, Page 1of9 " I ,, '. ""'iim"<o'" Exelon Generation. Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. 2. 3. 4. 5. 6. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk I (*). 8. 9. If an alternate path is used, the task standard contains criteria for successful completion. Verify the procedure(s) referenced by this JPM reflects the current revision: Procedure ST-6-043-200-1 Rev: 23 Procedure AD-LG-101-1002 Rev: 13 Procedure HU-AA-104-101 Rev: --"'-5 __ Procedure HU-AA-1212 Rev: --=-7 __ Procedure Rev: ---10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate " I *' ' 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM6777 Rev001 Page2of9
w
;::
  • Exelon Generation.

II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Change# Change Approval Tracking I I " I Ill. REVISION HISTORY: Revision Date A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subseque:nt revisions, annotate the changes that were made or incorporated. Revision Description of Revision and Affect on Training Content # Date of Number Revision 000 This JPM replaces LLOJPM0777 Rev. 1. Revised to new template and 5/31/15 aligned with latest procedure revision(s). Rev001 JPM revised to new JPM Template and procedure revisions 11/03/16 # Date of Revision -refers to date revision was released for approval LOJPM6777 Rev001 Page 3 of 9

Exelon Generation IV. TASK STANDARD: Partial procedure, ST-6-043-200-1, Reactor Recirculation System Quarterly Valve Test prepared for PMT of HV-043-1 F020, in accordance with plant procedures, AD-LG-101-1002, Temp Changes to Approved Documents and Partial Procedure Use, and HU-AA-104-101, Procedure Use and Adherence. V. INITIAL CONDITIONS:

1. Maintenance on HV-043-1 F020 is complete per work order C099590301.
2. A PMT is required to determine operability of HV-043-1 F020. VI. INITIATING CUE: " You are directed to prepare a partial on ST-6-043-200-1 to determine operability for valve HV-043-1 F020, following maintenance, and Document actions and notifications, if any, performed Information for Evaluator's Use: Any UNSAT requires written comments on respective step.
  • Denotes critical steps ,, ' Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. LOJPM6777 Rev001 Page 4of9

Exelon Generation. VII. PERFORMANCE CHECKLIST: JPM Start Time -----ELEMENT STANDARD t-a: ZW w al :iE :iE :iE :::> Oz () EVALUATORS NOTE: If copy of C099590301 requested, inform candidate 'Work Order has been evaluated by the WCS". Provide Candidate with the following:

  • JPM briefing sheet
  • Yellow Copy of ST-6-043-200-1 " 1
  • AD-LG-101-1002,Temporary Changes to Approved Documents and Partial Procedure Use
  • HU-AA-104-101, Procedure Use and Adherence.
  • HU-AA-1212; Technical Task Risk/Rigor Assessment, Pre-Job Brief, Independent Third Party Review, and Post-Job Review 1 . Review ST-6-043-200-1 for , determining operability of HV-43-: : 1F020 2. Reference AD-LG-101-1002 section 4.1 "Partial Procedures" and perform the following:

2a. [AD-LG-101-1002 step 4.1.1] IF performing partial ST or RT, then WRITE "PARTIAL" on the first page of ST-6-043-200-1 . 2b. [AD-LG-101-1002 step 4.1.2] COMPLETE partial performance of procedure per HU-AA-104-101, Procedure Use and Adherence. LOJPM6777 Rev001 Candidate reviews ST-6-043-200-1 , Reactor Recirculation System Quarterly Valve Test in preparation of determining operability of HV-43-1 F020 N/A "PARTIAL" written on the first page of ST-6-043-200-1. (duplicate, critical at step #9) Candidate references HU-AA-104-101, Procedure Use and Adherence. Page 5of9

Exelon Generation. I-a: I-Zw ELEMENT STANDARD I-<( w Ill <( en :!E :E en z :E :::> :::> Oz (.) EVALUATOR NOTE: The following steps are directed form HU-AA-104-101, Procedure Use and Adherence, step 4.6.1 , whereas "IF a portion of a procedure is used in lieu of performing the procedure in its entirety, THEN the Work Planner will ... Partial procedure development for equipment operating or test procedures should be evaluated for technical human performance error precursors using HU-AA-1212.

3. [HU-AA-104-101step4.6.1.1]

Candidate determines a Pre-IF required by HU-AA-1212, THEN I job brief is required. conduct a prejob brief. 4. [H U-AA-104-101 step 4.6.1 .2] ,, Candidate determines all I steps of ST-6-043-200-1 DETERMINE the steps that are adequate and appropriate to ' pertaining to HV-043-1 F020 accomplish the desired task. are required.

5. [HU-AA-104-101 step 4.6.1.3] Candidate determines all ENSURE all applicable Prerequisites, Precautions, Prerequisites, Precautions, and and Limitations and Actions ' are met before performing the Limitations and Actions are met ,, ' task. before performing the associated steps. 6. [HU-AA-104-101 step 4.6.1.4] Candidate verifies "AS LEFT" ENSURE the component/system is position of HV-043-1 F020 returned to a condition normal/ determined by plant expected for plant conditions at that conditions as directed by HU-time. AA-1212, prejob brief 7. [HU-AA-104-101 step 4.6.1.5] ENSURE that uncompleted steps will N/A not result in missed acceptance criteria or an incomplete surveillance.

LOJPM6777 Rev001 Page 6of9

/ Exelon Generation. a
ZW ELEMENT STANDARD <t w ttl <t (/)
E :E en z :E ::::> ::::> Oz u EVALUATORS NOTE: Candidate may request to write "PARTIAL" on computer generated "Valve Stroke Timing List" report RO will obtain the "Timing List"
  • 8. [HU-AA-104-101 step 4.6.1.6] "PARTIAL" written on the first WRITE "PARTIAL" on the first page page of the ST-6-043-200-1 of the procedure. (performed in step 3a)
  • 9. [HU-AA-104-101 step 4.6.1.7] "Reason for Partial WRITE for Partial Performance" i.e. "PMT to Performance" on the first page of the determine operability procedure and INSERT the reason following maintenance" or for partial procedure performance.

equivalent, written on the first page of the ST-6-043-200-1 I

  • 10. [HU-AA-104-101 step 4.6.1.8] Steps pertaining to Check ANNOTATE steps that are not Valve Test and HV-043-applicable to HV-043-1 F020 PMT 1 F019 annotated as "N/A" before performing a partial
  • Step 4.5 Check Valve Test procedure with "N/A". I' ,,
  • Step 4.5 Check Valve Test
  • 11 . [HU-AA-104-101 step 4.6.1.9] "Partial Procedure Approval" WRITE "Partial Procedure Approval" written on the first page under on the first page of the procedure. "Additional Action/Comments" of the ST-6-043-200-1 .
  • 12. [HU-AA-104-101step4.6.1.10]

Authorization obtained and AUTHORIZE use of partial use documented on the first page procedure. under "Additional Action/ Comments" of the ST-6-043-200-1. CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM6777 Rev001 Page lot 9 , Exelon Generation. JPM

SUMMARY

Operator's Name: ________________________ ___,:. Job Title: D SED D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: Prepare A Partial Procedure JPM Number: LOJPM6777 Revision Number: 001 Task Number and Title: TC0-2990110301 -Recommend Revisions to Operating Procedures KIA Number and Importance: Generic 2.2.6 Knowledge of the process for making changes to procedures. CFR: 45.13 3.0/3.6 Level of Difficulty (1-5) _L Safety Function (1-9) __ Admin Category (A1-4)--=2-Suggested Testing Simulator/Classroom Alternate Path:D Yes No SRO Only: D Yes IZ! No Time Critical: D Yes 1Z! No Reference(s): ST-6-043-200-1, Reactor Recirculation System Quarterly Valve Test, Rev 23. AD-LG-101-1002, Temp Ch;:mges to Approved Documents and Partial Procedure Use, Rev 13. HU-AA-104-101, Procedure Use and Adherence, Rev 5. HU-AA-1212, Technical Task Risk/Rigor Assessment, Pre-Job Brief, Independent Third Party Review, and Post-Job Review, Rev 7. Actual Testing Environment: D Simulator D Control Room D In-Plant 1Z! Other Testing Method: D Simulate IZ! Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments: Evaluator's Name: -----------------(Print) Evaluator's Signature: _____________ _ Date: LOJPM6777 Rev001 Page 8of9

Exelon Generation. " I ,, INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Maintenance on HV-043-1 F020 is complete per work order C099590301.

2. A PMT is required to determine operability of HV-043-1 F020. INITIATING CUE: You are directed to prepare a partial on ST-6-043-200-1 to determine operability for valve HV-043-1 F020, following maintenance, and Document actions and notifications, if any, performed below: LOJPM6777 Rev001 Page 9of9 I c:i::x Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE ACTIONS REQUIRED FOR SPIKING ARM JPM Number: LOJPM6728 REVISION NUMBER: 000 DATE: __ _ Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Reviewed By: EP Representative Date Approved By: Training Department Date LOJPM6728 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training)

,, I ,, ' Page 1 of 11 I ;;;;:'Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is used, the task standard contains criteria for sucbessful completion.
9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure 827.1.A Rev: 21 _;::;;;..;.....__ Procedure 827.1 O.A Procedure ARC MCR 109 B-4 Procedure

Procedure

10. Verify cues both verbal and visual are free of conflict.

Rev: 9 ---Rev: 2 --=--Rev: ---Rev: ---11. Verify performance time is accurate : : 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM6728 RevOOO.doc SRRS: 3D.105 Page 2 of 11 (When used for operator initial or continuing training) I ;:::ii."': Exelon Generation. II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision Description of Revision and Affect on Training Content # Date of Number Revision 000 This JPM is New 11/01/16 # Date of Revision -refers to date revision was released for approval LOJPM6728 RevOOO.doc SRRS: 30.105 Page 3 of 11 (When used for operator initial or continuing training) J Exelon Generation IV. TASK STANDARD:

1. On the Individual Briefing Sheet the following identified:
a. Location of ARM identified as Unit 1 RHR DIV 2 Rm (Area 16 Elev 201) and b. Section 4.3 of S27.1.A to remove Area ARM from service, documented.

V. SIMULATOR SETUP: None. VI. INITIAL CONDITIONS:

1. Unit 1 is at 100% power. 2. Annunciator 109 B-4 "Reactor Encl Area Hi Radiation", has been received several times this shift ;* 3. Each time it has been determined to be spiking of channel # 9 4. The RP tech has verified that local area readings are normal. VII. INITIATING CUE: ,, ' 1 . Shift Supervision directs you to identify the location in the plant monitored by this ARM 2. Identify any compensatory actions required to address this nuisance alarm. 3. Provide your findings on Individual Briefing Sheet. LOJPM6728 RevOOO.doc SRRS: 30.105 Page 4 of 11 (When used for operator initial or continuing training)

I r Exelon Generation Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts 1 when the candidate acknowledges the initiating cue. LOJPM6728 RevOOO.doc ,, I ,, SRRS: 30.105 (When used for operator initial or continuing training) Page 5 of 11 I-=' ExelonGeneration VIII. PERFORMANCE CHECKLIST: JPM Start Time -----t-I-a: Zw ELEMENT STANDARD I-<( Wal <t (J) :!: :!: en z :!: ::J ::::> Oz (.) EVALUATORS NOTE: Provide Candidate with the following:

  • Individual Briefing Sheet
  • ARC 109 RAD B-4, REACTOR ENCL AREA HI RADIATION
  • 827.10.A, Guidance_

For Area Radiation Monitoring Alarms

  • S27.1.A, Operation of the Area Radiation Monitoring System 1. [ARC MCR 1 ag 8-4] *i Channel # 9 identified per I Reference ARC 109 B-4 to identify Initial Conditions appropriate channel initiating alarm 2. [827.1a.A]

Using 827.10.A, Guidance For Addressing Area Radiation N/A Monitoring Alarm determine the following: ' ,, ' 2a. [827.1 a.A step 4.2] 827.1 O.A Attachment 1 IF a high radiation alarm occurs referenced AND Radiation Protection has determined the alarm to be false, THEN USE Attachment 1 2b. [827.10.A Attachment 1] Area dose rates normal and HP has verified dose rates in area ARM spuriously spiking are normal AND Identified per Initial ARM channel is spuriously spiking Conditions 2c. [827.1 a.A Attachment 1] Candidate determines ARM

  • channel 9 listed and follows T-103 8AMP-2 ARM Channels YES path 1,2,8,9, 10, 11,21,22 For either Unit 1 or2 LOJPM6728 RevOOO.doc 8RR8: 30.1 as Page 6 of 11 (When used for operator initial or continuing training)

I ,::::,'" Exelon Generation I-I-cc ZW ELEMENT STANDARD I-Wal en == :a: en z == :l ::> Oz (..) 2d. [S27.1 O.A Attachment 1] Candidate determines to Place ARM in zero. place ARM in zero using S27.1.A 2e. [527.10.A Attachment 1] Candidate requests HP Tech

  • to install potable ARM DIV 2 Have HP install a potable ARM in the vicinity of the inoperable monitor. RHR room (Area 16, Elev 201') 3. [S27.1.A]

DIV 2 RHR room (Area 16, Using S27 .1.A, Operation of the Elev 201 ') identified I Area Radiation Monitoring System . determine area(s) affected by nuisance alarm.

  • 4.' [S27.1.A step 4.3] ARM #9 placed in ZERO ENSURE mode switch for ARM to ' "ZERO" position at Aux Equipment Room panel 5. [S27.1.A step 4.3] RESET button depressed on
  • PRESS RESET button on ARM ARM TRIP UNIT TRIP UNIT ' ' 6. . [S27 .1.A step 4.3] EST tag hung on channel #9 HANG an EST stating "Removed ARM from Service per S27.1.A 7. [S27.1.A step 4.3] "Area Radiation" alarm reset VERIFY applicable "Area Radiation" in MCR alarm reset in MCR 8. [S27.1.A step 4.3] "ACK Alarm" key on recorder PRESS "ACK Alarm" key on RR-M1-*R600 predded recorder RR-M1-0R601 or RR-M1-*R600 9. [S27.1.A step 4.3] LED for associated ARM on ' VERIFY LED for associated ARM on recorder RR-M1-1 R600 is lit recorder RR-M1-0R601 or RR-M1-*R600 is lit LOJPM6728 RevOOO.doc SRRS: 30.105 Page 7 of 11 (When used for operator initial or continuing training)

Exelon Generation ELEMENT STANDARD 10. [827.1.A step 4.3] "Unit Area Rad Monitor VERIFY "Common Area Rad downscale 1 OC-800/A-5 is Monitor downscale alarm 00-reset. C824/G-5 OR "*Unit Area Rad Monitor downscale

  • OC-800/ A-5 is reset. CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ ,, I ,, LOJPM6728 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training)

I-a: I-ZW I-<( Wm <( en :E :E en z :E :::::> :::::> Oz (.) Page 8 of 11 1-Exelon Generation NRC Answer Summary Page As a minimum the following conditions should be referenced for the spiking ARM" 1. Identify appropriate channel initiating alarm, channel #9 is T-103 I SAMP referenced

2. Area(s) affected by nuisance alarm. -DIV 2 RHR room (Area 16, Elev 201 ') 3. Have HP install a potable ARM in the vicinity of the inoperable monitor DIV 2 RHR room (Area 16, Elev 201 ') 4. Place mode switch for ARM to "ZERO" position at Aux Equipment Room 5. Press RESET button on ARM TRIP UNIT LOJPM6728 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training) " 1 ,, ' Page 9 of 11

" I ,, ' Exelon Generation JPM

SUMMARY

Operator's Name: _______________________ ___ Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: ACTIONS REQUIRED FOR SPIKING ARM JPM Number: LOJPM6728 Revision Number: 000 Task Number and Title: 2990090301 Apply Radiation and Contamination Safety Procedures KIA Number and Importance: Generic 2.3.15 2.9/3.1 Safety Function (1-9) 9 Admin Category (A 1-4) 3 (Radiation Controls) Level of Difficulty (1-5) 3 Suggested Testing Environment: Classroom Alternate Path:D Yes !ZI No SRO Only: D Yes !Z1 No Time Critical: D Yes !ZI Nb Reference(s): ARC 109 RAD B-4, REACTOR ENCL AREA HI RADIATION Rev 2 S27.1 O.A, Guidance For Addressing Area Radiation Monitoring Alarms Rev 9 ,, I S27.1.A, Operation of the Area Radiation Monitoring System Rev 21 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate !Z1 Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes D No ,, ' The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Evaluator's Name:----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM6728 RevOOO.doc SRRS: 3D.105 Page 10 of 11 (When used for operator initial or continuing training) ,::::,,,, Exelon Generation, INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Unit 1 is at 100% power. 2. Annunciator 109 B-4 "Reactor Encl Area Hi Radiation", has been received several times this shift 3. Each time it has been determined to be spiking of channel # 9 4. The RP tech has verified that local area readings are normal. INITIATING CUE: ,, I 1. Shift Supervision directs you to identify what location of the plant that is monitored by this ARM 2. Identify any compensatory actions required to address this nuisance alarm. Provide your results below: ,, ' Page 11 of 11 I Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE DETERMINATION OF ADEQUATE SHIFT STAFFING Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LOJPM6712 RevOOO.doc JPM Number: LOJPM6712 REVISION NUMBER: 000 I DATE: ...,..---,, I Instructor SME or Instructor Operations Representative EP Representative Training Department SRRS: 30.105 (When used for operator initial or continuing training) Date Date Date Date Date Page 1 of 9 J ,.s: , Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is used, thb task standard contains criteria for successful completion.
9. Verify the procedure(s) refere[iced by this JPM reflects the current revision:

Procedure OP-LG-101-111 Rev: 5 ---Procedure Rev: ---Procedure Rev: ---Procedure Rev: ---------------- ---Procedure------------- Rev: __ _ 10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is ac9urate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM6712 RevOOO.doc SRRS: 30.105 Page 2 of 9 (When used for operator initial or continuing training)

I=_,,,,, Exelon Generation II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If a Revision affects a fask Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. ' Revision Description of Revision and Affect on Training Content # Date of Number Revision 000 This JPM replaces LLOJPM0712 Rev. 2. Revised to new template 11/04/16 and to align with latest procedure revision.

  1. Date of Revision -refers to date revision was released for approval LOJPM6712 RevOOO.doc SRRS: 30.105 Page 3 of 9 (When used for operator initial or continuing training)

I ,:!;* * 'Exelon Generali on. IV. TASK STANDARD: Determine that shift is below minimum staffing requirements and take appropriate corrective action to ensure adequate shift staffing. V. SIMULATOR SETUP: None VI. INITIAL CONDITIONS:

1. Unit 1 is in OPCON 1 2. Unit 2 is in OPCON 4 3. Today's date is 12/25 I 4. It is night shift 18:00 -06:00 5. The entire shift has participated in a Christmas meal at @ 0000 I 6. Initial shift staffing consists of the following;
  • 1 Shift Manager
  • 3 Senior Reactor Operators
  • 3 Reactor Operators
  • 11 Equipment Operators (5 Equipment Operators are Fire Brigade Qualified)

,, ' VII. INITIATING CUE: . At 0130, the Unit 2 Reactor Operator and a Fire Brigade Qualified Equipment Operator complain of severe stomach pain/headache and are unable to perform operator duties. Determine if staffing requirements for current operating modes are met.

  • Include any immediate and long term (greater than 2 hours) corrective actions that are required to ensure adequate shift staffing is met. LOJPM6712 RevOOO.doc SRRS: 30.105 Page 4 of 9 (When used for operator initial or continuing training)

I =--:r Exelon Generation Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. Thel JPM Start Time clock starts when the candidate acknowledges the initiating cue . . , I ,, ' LOJPM6712 RevOOO.doc SRRS: 30.105 Page 5 of 9 (When used for operator initial or continuing training)

t;;
.'

Exelon Generation 1-VIII. PERFORMANCE CHECKLIST: JPM Start Time -----ELEMENT STANDARD EVALUATORS NOTE: Provide Candidate with the following:

  • JPM Briefing Sheet
  • OP-LG-101-111, Shift Staffinq Requirements I 1. Candidate reviews OP-LG-101-111, to determine shift staffing NIA " requirements.

I 2. Determine that shift staffing is in ' violation of minimum shift staffing NIA requirements per OP-LG-101-111. 2a. RO position is not adequately filled, Determination made that:

  • additionally Unit 2 must be staffed i RO staffing is not adequately with an RO ' filled per OP-LG-101-111

,, (Minimum required staffing is I 3 ROs) An RO is required at the Unit 2 Controls 2b. Fire Brigade position is not Determination made that Fire

  • adequately filled Brigade position is not adequately filled per OP-LG-101-111 (Minimum required staffing is 5) 3. Determine action necessary IAW current shift manning, as follows: NIA LOJPM6712 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training) t-t-<t <t en en z ::> Page 6 of 9 t-er: ZW w al :E :E :E ::> Oz (.) " I *' '

[ Exelon Generation ELEMENT STANDARD EVALUATORS NOTE: <( CJ) <( en z :::> a: ZW w DJ ::! :a: ::! :::> Oz 0

  • With 1 RO unable to perform duties, the shift is below minimum requirements, and Unit 2 must be staffed with an RO
  • With 1 Fire Brigade qualified EO unable to perform duties the shift is below minimum requirements.
  • 3a. [OP-LG-101-111 Step4.1.1.4]

States except for Shift Manager, shift crew composition may be one less than minimum requirements for up to 2 hours. 3b. [OP-LG-101-111 Step 4.1.2.3] States the fire brigades may be less than the minimum requirements for a period not to exceed 2 hrs. 4. Take action to restore minimum shift staffing as follows: Determination made that action must be taken to restore the crew composition for the RO position within 2 hours Determination made that action must be taken to restore the crew composition for the Fire Brigade within 2 hours N/A ,, ' EVALUATORS NOTE: Action is required to staff the RO position. This action carUnclude ' moving one of the 3 SROs into the RO position.

  • 4a.Take action to restore minimum shift staffing for RO 4b.Take action to restore minimum shift staffing for Fire Brigade Perform operator call-in to get RO position manned within 2 hours or move one of the 3 SROs into the PRO/RO position.

Have PRO replace Unit 2 RO until replacement arrives or SRO fills in for PRO Perform operator call-in to get Fire Brigade qualified EO manned within 2 hours CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM6712 RevOOO.doc SRRS: 30.105 {When used for operator initial or continuing training) Page 7 of 9 Exelon Generation 1-JPM

SUMMARY

Operator's Name: _______________________ --"" Job Title: 0 SEO 0 SM 0 SRO 0 RO 0 ST A/IA 0 EO 0 OTHER JPM Title: DETERMINATION OF ADEQUATE SHIFT STAFFING JPM Number: LOJPM6712 Revision Number: 000 Task Number and Title: 3420140302 Manage the Shift Team 3430160302 Assure Adequate Personnel Coverage For All Plant Conditions In Accordance With Overtime Policy. KIA Number and Importance: Generic 2.1.5 Safety Function (1-9) N/A Admin Category (A1-4) Of Operations) Level of Difficulty (1-5) _L Suggested Testing Environment: Classroom 2.9 I 3.9 Alternate Path:O Yes 1:8J No SRO Only: 1:8J Yes D No Time Critical: D C8J No Reference(s): OP-LG-101-111, Shift Staffing Requirements Rev 5 I Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate 1:8J Perform Estimated Time to Complete: 30 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: 0 Satisfactory D Unsatisfactory Evaluator's Name:----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM6712 RevOOO.doc SRRS: 30.105 Page 8 of 9 (When used for operator initial or continuing training)

,
;/ Exelon Generation.

LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS: 1 . Unit 1 is in OPCON 1 1 . Unit 2 is in OPCON 4 2. Today's date is 12/25 3. It is night shift 18:00 -06:00 4. The entire shift has participated in a Christmas meal at @ 0000 5. Initial shift staffing consists of the following;

  • *
  • 1 Shift Manager 3 Senior Reactor Operators 3 Reactor Operators
  • i I
  • 11 Equipment Operators (5 Equipment Operators are Fire Brigade Qualified)

INITIATING CUE: At 0130, the Unit 2 Reactor Operator and a Fire Brigade qualified Equipment Operator complain of severe stomach pain/headache and are unable to perform operator duties. *' ' Determine if staffing requirements for current operating modes are met.

  • Include any immediate and long term (greater than 2 hours) corrective actions that are required to ensure adequate shift staffing is met. Provide immediate and long term requirements and any corrective actions required below Page 9 of 9

\ LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE DETERMINE ACCEPTABILITY OF INSTALLING FUEL POOL GATES JPM Number: LOJPM6763 REVISION NUMBER: 000 DATE: __ _ ,, I Developed By: Instructor Date ,, Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Reviewed By: EP Representative Date Approved By: Training Department Date LOJPM6763 RevOOO.doc SRRS: 30.105 Page 1 of 9 (When used for operator initial or continuing training) I _:!;;-r Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. 2. 3. 4. 5. 6. 7. 8. 9. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). If an alternate path is usJd, the task standard contains criteria for successful completion. Verify the procedure(s) referenced by this JPM reflects the current revision: Procedure 1 GP-6.1 Rev: 32 _..;;;..;:::;..___ Procedure RT-1-053-850-0 Rev: 7 Procedure Rev: Procedure Rev: Procedure Rev: 1 O. Verify cues both verbal and visual are free of conflict. ' 11. Verify performance time :is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM6763 RevOOO.doc SRRS: 30.105 Page 2 of 9 (When used for operator initial or continuing training) ,::::;'., Exelon Generation 1-11. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the IL Tor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision ' # Date of Number Description of Revision and Affect on Training Content Revision 000 This JPM is new 11/04/16 # Date of Revision -refers to date revision was released for approval LOJPM6763 RevOOO.doc SRRS: 30.105 Page 3 of 9 (When used for operator initial or continuing training) I Exelon Generation IV. TASK STANDARD: Determine the heat transfer capability of the Fuel Pool Cooling System is currently insufficient to dissipate the current Decay Heat Load. V. SIMULATOR SETUP: None VI. INITIAL CONDITIONS:

1. Unit 1 is in a Refueling Outage. 2. The reactor was shutdown 11 days ago 3. Refuel Floor Secondary Containment is established.
4. The only Fuel Pool Cooling available is the '2A' and '2B' FPC Pumps with the '2A' and '2B' FPC Heat Exchangers.
5. Reactor Engineering (Joe Rubinaccio) has determined the total decay heat load contained in the Spent Fuel Pools (SFP) to be the following:

,, VII. INITIATING CUE: Days after Shutdown 9 10 11 12 13 14 15 SFP Heat Load (cross tied) (MW) 4.77 4.66 4.56 4.47 4.40 4.33 4.27 Shift Supervision directs you to perform GP-6.1 step 3.12.10, Install Reactor Cavity/Spent Fuel Pool Gates. LOJPM6763 RevOOO.doc SRRS: 30.105 Page 4 of 9 (When used for operator initial or continuing training) " I ,, ' 1-,::::' ExelonGeneration Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. LOJPM6763 RevOOO.doc SRRS: 30.105 Page 5 of 9 (When used for operator initial or continuing training) ,. I ,, ' " I .. ' I ,::::'7 ExelonGeneration VIII. PERFORMANCE CHECKLIST: JPM Start Time -----I-I-cc ZW ELEMENT STANDARD I-<t w Ill <t CJ) :iE :iE CJ) z :iE ::::> :::> Oz () EVALUATORS NOTE: Provide the following to the Candidate:

  • 1 GP-6.1, Shutdown Operations

-Refueling, Core Alteration and Core Offloading Pages 97, 98, and 135 ..

  • Completed copy of RT;.1-053-850-0, Heat Transfer Capability of Fuel Pool Cooling I Systems performed on Calculator ,f * '
  • Answer Rounding -Students my round answers provided the rounding does not the outcome of the JPM. 1. [1GP6.1step3.12.10.1]

Candidate determines the

  • total heat load for day 11 of OBTAIN the total decay heat load the refueling outage to be contained in the spent fuel pools. 4.56 MW from Initial Conditions.

' *' ' 2. [1GP6.1step3.12.10.2] Candidate records on 1 GP6-1 RECORD the spent fuel pool decay Attachment

  1. 8 Decay Heat heat load on step 1 of Attachment
  2. 8 Load = 4.56 MW 3. [1 GP6.1 step 3.12.10.3]

Candidate determines the 2A DETERMINE the number of Fuel and 28 Fuel Pool Cooling Pool Cooling Water Pumps AND Pumps with the 2A and 28 Heat Exchangers that are available FPC Heat Exchangers are available from Initial Conditions.

  • 4. [1 GP6.1 step 3.12.10.4]

Candidate determines from RECORD the heat transfer capability Attachment

  1. 9 of RT-1-053-shown on Attachment 9 of RT-1-053-850-0 the Heat Transfer 850-0 for available FPC Pumps AND Capability of the Unit 2 'A' Heat Exchangers on Step 2 of and '8' FPC Pumps/HTXCH Attachment
  2. 8. to be 15.1540845 BTU/hr LOJPM6763 RevOOO.doc SRRS: 30.105 Page 6 of 9 (When used for operator initial or continuing training)

Exelon Generation I-I-a: ELEMENT Zw STANDARD I-<( w Ill <( en :E :E en z :E ::::> ::::> Oz 0 5. [1 GP6.1 step 3.12.10.5] Candidate determines the VERIFY that the heat transfer heat transfer capability of the capability of the Fuel Pool Cooling FPC system using 1 GP-6-1, System is greater than the decay Attachment 8 heat load in the spent fuel pools. 15.1540845x10 6 BTUx1 MW Hr 3.413x10 6 BTU HR = 4.44 MW

  • 6. [1GP6.1step3.12.10.6]

Candidate determines that IF the heat transfer capability of the 4.4 MW (heat transfer ; Fuel Pool Cooling System is less capability of the FPC system) than the decay heat load in the spent is< (less than) the 4.56 MW fuel pools, THEN PERFORM one of (decay heat load) " I the following: 4.44 MW < 4.56 MW

  • 6a. [1 GP6.1 step 3.12.10.6a]

Candidate determines to wait WAIT to install Reactor Cavity/Spent until decay heat load in the Fuel Pool Gates until decay heat spent fuel pool is less than or load in the spent fuel pool is less equal to the heat transfer than or equal to the heat transfer capability of the fuel pool capability of the fuel pool cooling cooling system (Day 13.) system. (Candidate may determine to perform 1GP6.1 step 3.12.10.6b which is acceptable) CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM6763 RevOOO.doc SRRS: 30.105 Page 7 of 9 (When used for operator initial or continuing training) I Generation JPM

SUMMARY

Operator's Name: _______________________ _ Job Title: 0 SED 0 SM 0 SRO 0 RO 0 ST A/IA 0 EO D OTHER JPM Title: DETERMINE ACCEPTABILITY OF INSTALLING FUEL POOL GATES JPM Number: LOJPM6763 Revision Number: 000 Task Number and Title: 2035010401 Monitor Fuel Pool Cooling Operation KIA Number and Importance: G2.1.40 2.8/3.9 Safety Function (1-9) N/A Admin Category (A1-4) 1 (Conduct of Operations) Level of Difficulty (1-5) 5 Suggested Testing Environment: Classroom Alternate Path:O Yes [gl No SRO Only: [gl Yes D No Time Critical: ID Yes [gl No Reference(s): RT-1-053-850-0, Heat Transfer Capability of Fuel Pool cooling Systems Rev 7 1 GP6.1, Shutdown Operations, Refueling, Core Alteration and Core Offloading Rev 32 I Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate [gl Perform Estimated Time to Complete: 25 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes , 0 No ,, ' The operator's performance was evaluated against standards contained with.in this JPM and has been determined to be: 0 Satisfactory D Unsatisfactory Evaluator's Name:----------------(Print) Evaluator's Signature: ______________ _ Date:' ------LOJPM6763 RevOOO.doc SRRS: 3D.105 Page 8 of 9 (When used for operator initial or continuing training) ,.:;:r::'"' Exelon Generation INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Unit 1 is in a Refueling Outage. 2. The reactor was shutdown 11 days ago 3. Refuel Floor Secondary Containment is established.

4. The only Fuel Pool Cooling available is the '2A' and '2B' FPC Pumps with the '2A' and '2B' FPC Heat Exchangers.
5. Reactor Engineering (Joe Rubinaccio) has determined the total decay heat load contained in the Spent Fuel Pools (SFP) ttj be the following:

Days after SFF? Heat Load Shutdown (cro'ss tied) (MW) 9 4.77 10 I 4.66 11 4.56 12 4.47 13 4.40 14 4.33 15 ' 4.27 INITIATING CUE: Shift Supervision directs you to perform GP-6.1 step 3.12.10, Install Reactor Cavity/Spent Fuel Pool Gates. Page 9 of 9 J Exelon Generation. LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE CALCULATE THE AVERAGE OFFGAS PRE-TREATMENT RADIOACTIVITY RELEASE RATE Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LOJPM6720 RevOOO.doc " I ,, JPM Number: LOJPM6720 REVISION NUMBER: 000 DATE: __ _ Instructor SME or Instructor Operations Representative EP Representative Training Department SRRS: 30.105 (When used for operator initial or continuing training) Date Date Date Date Date Page 1 of 11 I :_,.,,,Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternatJ path is used, the task standard contains criteria for successful completion.
  • 9. Verify the pracedure(s) referenced by this JPM reflects the current revision:

Procedure GP-5 App 1 EOC Rev: -=5=8 __ Procedure Tech Specs U#1 Rev: __ _ Procedure

Rev: __ _ Procedure---------- Rev: __ _ Procedure Rev: ---------- ---10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM6720 RevOOO.doc SRRS: 30.105 Page 2 of 11 (When used for operator initial or continuing training)

= Exelon Generation 1-II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If :a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision Description of Revision and Affect on Training Content # Date of Number Revision 000 This JPM modifies LLOJPM6760 Rev. 1 to an SRO JPM 10/31/16 #Date of Revision -refers to date revision was released for approval LOJPM6720 RevOOO.doc SRRS: 30.105 Page 3 of 11 (When used for operator initial or continuing training) I =** Exelon Generation IV. TASKSTANDARD: RO: Determines Radioactive off gas release rate is 14,668 to 15,266 µCi/sec and chemistry sampling is required. SRO: Determines Tech Spec 3.4.5 sampling requirements for DOSE EQUIVALENT 1-131: Perform the sampling and analysis requirements of Item 4.a of Table 4.4.5-1 (At least once per 4 hours) until the specific activity of the primary coolant is restored to within its limit. V. SETUP INSTRUCTIONS

1. Provide the following:
  • Calculator
  • GP-5 Appendix 1, End of Steady State Operations I* Placard that is mounted to the 1 OC600 Panel " I VI. INITIAL CONDITIONS:
1. Initial Conditions
a. Unit 1 is in OPCON 1 ':: b. 1 hour ago SUM OF SIX K"A" K"B" Date: 139 0.082 0.080
  • The average Off-gas pretreatment release rate was 341.2 uCi/sec
  • FR-69-115 read 7 4 scfm 2. Current Plant Conditions 1 hour later a. Unit 1 is in OPCON 1 b. There was an increase in SJAE Discharge Rad Monitor readings, the current readings are:
  • RR-26-1 R601 "A" SJAE Discharge Rad Monitor reads 2461 mRem/hr
  • RR-26-1 R601 "B" SJAE Discharge Rad Monitor reads 2534 mRem/hr c. FR-69-115 reads 7 4 scfm LOJPM6720 RevOOO.doc SRRS: 30.105 Page 4 of 11 (When used for operator initial or continuing training)

I ,:::.. ' Exelon Generation. VII. INITIATING CUE: You are directed to calculate the average offgas pre-treatment radioactivity release rate per GP-5 Appendix 1, End of Steady State Operations, and identify any required actions. U/1 OFFGAS SUM OF SIX 139 K"A" K"B" Date: Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps ,, ' Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be 4sed to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. LOJPM6720 RevOOO.doc SRRS: 30.105 Page 5 of 11 (When used for operator initial or continuing training)

x Exelon Generation 1-VIII. PERFORMANCE CHECKLIST

JPM Start Time -----I-a: I-Zw ELEMENT STANDARD I-c::i: Wm c::i: (J) :a: :a: (J) z :a: :::> Oz 0 1. Obtain a copy of current revision of Candidate demonstrates GP-5 Appendix 1, End of Steady ability (actual or discuss) to State Operations locate the correct procedure. CUE: Candidate is given a copy of the I procedure when knowledge of the correct location of procedure is demonstrated. " I 2. CALCULATE Off-gas release rates ' for the A AND B channels using the N/A following equation: RR= RLx F x K ! RR = Release Rate for A(B) ' (µCi/second) ,, RL = Radiation Level of SJAE as indicated on RR-26-1 R601 (mRem/hour) F =Off-gas flow as indicated by FR-69-115 (scfm), Point 2 K = Conversion Factor for A(B) data (posted on panel 1 OC600) 3. Channel A (Point 1) Calculate "A" channel release

  • RR= --mRem/hour X --CFM X _JS 2461 x 74 x 0.082 = RR = __ µCi/second 14 1 933.3 µCi/sec LOJPM6720 RevOOO.doc SRRS: 3D.105 Page 6 of 11 (When used for operator initial or continuing training)

Exelon Generation. ELEMENT STANDARD

  • 4. Channel B (Point 2) Calculate "B" channel release RR =--mRem/hour x __ CFM x K RR = __ µCi/second 2534 x 74 x 0.080 = 15,001.2 µCi/sec
  • 5. CALCULATE the average of the A Calculate the average
  • ANO B channel values to obtain the release rate average Off-gas pretreatment release rate as follows: ARR = (RR "A") + (RR "B") 2 Where: ARR = Average Off-gas Pretreatment Release Rate (µCi/second)

RR 11 A" = Release Rate value for "A" Channel (µCi/second) RR 11 8 11 =Release Rate value for "B" Channel (µCi/second) ARR = ...__( _ __,_)-"'"+__..( __ ),_ 2 ARR = ____ µCi/second

6. IF Off-Gas Release Rate rises by > 10,000 µCi/second in 1 hour during steady state operation at release rates <75,000 µCi/second THEN CONT ACT Chemistry to perform ST-5-041-885-
  • , Dose Equivalent 1-131 Determination I I " I ARR= I (14,933.3

+ 15001.2) 2 ARR=14,967.2 µCi/sec ,, I' Acceptable band is 14,668 to 15,266 (14,967 +/-2%) Chemistry notified to perform ST. Cue: Chemistry acknowledges request to complete the ST and will notify the CRS with the results LOJPM6720 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training) Page 7 of 11 I-c: Zw W ID == == == ::::> Oz () Exelon Generation. ELEMENT 7. IF Off-Gas Release Rate rises by more than 50%, THEN CONT ACT Chemistry to perform ST-5-070-885-

  • , Isotopic Offgas Analysis CUE: Chemistry acknowledges request to complete the ST and notifies the CRS with the results RO ONLY: You have met the termination criteria for this JPM STANDARD Chemistry notified to perform ST. SRO ONLY Portion I I-a: Zw WCC ::=: :ii: ::=: ::::> Oz (.) EVALUATORS NOTE: With time compression, Chemistry has completed ST-5-041-885-1 and notifies the CRS with the results. ;1 Provide candidate with final briefing sheet #2 Fill in date and time 15 minutes after sample requested

' If requested, Chemistry also notifies the CRS that they are still working on ST-5-070-885-1

  • 8. Based on the results of ST-5-041-885-1 the CRS determines Tech Spec action(s)

In OPERATIONAL CONDITION 2, 3, or 4, with the specific adivity of the primary coolant greater than 0.2 microcuries per gram DOSE EQUIVALENT l-131J. perform the sampling and analysis requirements of Item 4.a of Table 4.4.5-1 (at least once per 4 hours) until the specific activity of the primary coolant is restored to within its limit. CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM6720 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training) Page 8 of 11 Exelon Generation JPM

SUMMARY

Operator's Name: _______________________ _ Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: CALCULATE THE AVERAGE OFFGAS PRE-TREATMENT RADIOACTIVITY RELEASE RATE JPM Number: LOJPM6720 Revision Number: 000 Task Number and Title: RO: 2730010101, Monitor Process Rad Monitor Operation SRO: 3420030302, Review results of a completed Surveillance Test KIA Number and Importance: Generic 2.3.11 3.8/4.3 Safety Function (1-9) 9 (Radioactivity Release) Admin Category (A1-4) N/A Level of Difficulty (1-5 3 Suggested Testing Environment: i Classroom Alternate Path:D Yes 1Z1 No SRO Only: D Yes IZI No Time Critical: D Yes 1Z! No Reference(s): GP-5 App 1 EOG Study State' Operations Rev. 058 I ST-5-041-885-1 Dose Equivalent 1-131 Rev. 021 Technical Specification 3.4.5, Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate 1Z! Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes I EVALUATION

SUMMARY

,, ,, Were all the Critical Elements performed satisfactorily?

D Yes 0No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Evaluator's Name:-----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM6720 RevOOO.doc SRRS: 30.105 Page 9 of 11 (When used for operator initial or continuing training)

Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS -Sheet# 1 2. Initial Conditions

a. Unit 1 is in OPCON 1 b. 1 hour ago
  • The average Off-gas pretreatment release rate was 341 .2 uCi/sec
  • FR-69-115 read 74 scfm 3. Plant Conditions 1 hour later a. Unit 1 is in OPCON 1 b. There was an increase in SJAE Discharge Rad Monitor readings, the current readings are:
  • RR-26-1 R601 "A" SJAE Discharge Rad Monitor reads 2461 mRem/hr
  • RR-26-1 R601 "B" SJAE Discharge Rad Monitor reads 2534 mRem/hr c. FR-69-115 reads 7 4 scfm INITIATING CUE ,, I You are directed to calculate the average offgas pre-treatment radioactivity release rate per GP-5 Appendix 1, End of Steady State Operations, and identify any required actions. The following placard is mounted to the 1 OC600 panel: U/1 OFFGAS SUM OF SIX 139 K"A" K"B" Date: -------Page 10 of 11

Exelon Generation, LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET (#2) Final Conditions -Sheet# 2 Chemistry notifies the Control Room Supervisor with the results of ST-5-041-885-1 Dose Equivalent 1-131 Determination

' 1.0.E. Activity (uCi/gm) .3 microcuries per gram ,, Sample Dateffime

______ / ___ _ Page 11 of 11 I; Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE ERP CLASSIFICATION AND REPORTING (TIME CRITICAL) " I ,, ' Developed By: Validated By: Reviewed By: Reviewed By: Approved By: JPM Number: LOJPM3097 REVISION NUMBER: 004 DATE: __ _ Instructor SME or Instructor Operations Representative EP Representative Training Department LOJPM3097 Rev004.doc SRRS: 30.105 (When used for operator initial or continuing training) Date Date Date Date Date Page 1 of 14 I ,i!;!'P' Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. " I Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. 2. 3. 4. 5. 6. 7. 8. 9. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). If an alternate path is used, the task standard contains criteria for successful completion. Verify the procedure(s) referenced by this JPM reflects the current revision: Procedure EP-AA-1008 Addendum 3 Rev: 002 Procedure EP-MA-114-100-F-01 Rev: P Procedure EP-AA-112-1 OO-F-01 Rev: V Procedure EP-AA-111-F-11 Procedure Rev: A ---Rev: ---10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM3097 Rev004.doc SRRS: 3D.105 Page 2 of 14 (When used for operator initial or continuing training) " I ,, I I

Generation II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I 111. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. 1 Revision Description of Revision and Affect on Training Content # Date of Number Revision 000 This JPM replaces LLOJPM0097 Rev. 10. Revised to new template 10/15/13 and to align with latest procedure revision. 001 Added Site Area Emergency declared 10 minutes after initial event 10/6/14 due to the fact that original JPM did not provide an initial declaration within the required 15 minutes. This changes the JPM to an escalation. 002 Revised due to new Limerick PAR Flowchart, EP-AA-111-F-11. 06/19/15 Sectors expanded for evacuation 2-5 miles. 003 Revised to new template 10/13/15 Rev004 Revised JPM to new template and procedural revisions 11/03/16 # Date of Revision -refers to date revision was released for approval LOJPM3097 Rev004.doc SAAS: 30.105 Page 3 of 14 (When used for operator initial or continuing training) I Generation IV. TASK STANDARD:

1. General Emergency (FG1) is declared within 15 minutes of the candidate beginning the classification.
2. Notification form completed and provided to Shift Communicator within 15 minutes of declaring the General Emergency.

V. SIMULATOR SETUP: D Use existing IC Met Data D Insert the following Met Data values: RZZ002 MET Data Wind Direction (0-360) DEG AZIMUTH Target Value= 311° RZZ003 MET Data Wind Speed (0-100) MPH Target Value= 5.0 mph D North Stack WRAM is indicating 2.5E+6 µCi/sec. D Post LOCA Rad Monitors are reading the following: A -96 R/hr. B -89 R/hr. C -103 R/hr. D -97 R/hr. VI. INITIAL CONDITIONS: Unit 1 is initially at 100% power when the following events occur: T=O * 'A' Steam Line ruptures in the Outboard MSIV Room

  • Group 1 Isolation signal is received due to high steam line flow
  • A full scram occurs with all rods inserted ., I ,, ,, * "A" Steam Line Inboard and Outboard MSIVs fail to isolate automatically or manually T = 5 minutes
  • Reactor Coolant Activity starts to rise T = 10 minutes
  • EAL threshold recognized and emergency declaration made T = 15 minutes
  • State and Local notifications complete for emergency declaration
  • Shift Communicator has activated the ERO LOJPM3097 Rev004.doc SRRS: 30.105 Page 4 of 14 (When used for operator initial or continuing training) 15 ExelonGeneration VII. CURRENT PLANT CONDITIONS:
  • RPV pressure is 850 psig and lowering
  • RPV level is + 18" and steady
  • OW pressure is 0.3 psig
  • Reactor Coolant Activity is 370 µCi/gm
  • Outboard MSIV Room temperature is 210 degrees F, up slow
  • Security personnel confirms a steam release outside secondary containment from blowout panels
  • North Stack WRAM is indicating 2.5E+6 µCi/sec.
  • Post LOCA Rad Monitors are reading the following:

A -96 R/hr. B -89 R/hr. c -103 R/hr. D -97 R/hr. " I VIII. INITIATING CUES: This Task is Time Critical This JPM will start when you tell the evaluator that you are aware of task conditions and are ready to begin. You are required to make the highest classification based on the given plant conditions and make subsequent call outs. All communications should indicate a drill. Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps ,, Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. LOJPM3097 Rev004.doc SRRS: 30.105 Page 5 of 14 (When used for operator initial or continuing training) Exelon Generation. IX. PERFORMANCE CHECKLIST: JPM Start Time: ----I-a: I-Zw ELEMENT STANDARD I-<C w cc <C (J) == == (J) z == :::> :::> Oz 0 NOTE TO EVALUATOR//DRIVER: If JPM is NOT conducted in Simulator: Provide a screen shot of "Meteorological 15 Minute Average Point Data". 1. REFER to the appropriate N/A NIA LGS EAL Matrix I 2. Call for Shift Communicator Shift Communicator to report to to report to MCR MCA ' I 3. Identify the operating MODE Matrix obtained: tor the affected Unit(s) prior ' to the abnormal condition, and obtain appropriate 0COLD Matrix. 4. Review the initiating Use EAL Matrix to classify event N/A conditions applicable to the I operating MODE. ' ,,

  • 5. DECLARE the event Event Declared:

0 UNUSUAL EVENT 0 ALERT 0 SITE AREA EMERGENCY EMERGENCY Declared 15 minutes of the JPM START TIME: DECLARATION TIME: 6. Direct Shift Communicator to N/A activate the ERO or make (Shift Communicator has activated management only notifications ERO per Initial Conditions) LOJPM3097 Rev004.doc SRRS: 30.105 Page 6 of 14 (When used for operator initial or continuing training) Exelon Generation I-a: Zw STANDARD I-WED ELEMENT <( (/) :E :? (/) z :E ::::> ::::> Oz 0 7. Complete the Event At the completion of the JPM the N/A Notification form Event Notification Form will be evaluated against the JPM standard located below. 8. Direct Shift Communicator to Shift Communicator notified to make perform state and local notifications within 15 minutes of notifications DECLARATION TIME. Declaration Time: Notification Initiated Time: NOTE: the expectation is notification is initiated within 9 (nine)minutes of declaration time. Notification times between 9-15 minutes constitutes a pass with comment. CUE: When form has been ' completed and Shift Communicator informed to process form: N/A N/A "You have met the termination criteria for this JPM" I ' ,, NOTE: The following steps are performed by the evaluator following the student providing the Notification form to the evaluator. LOJPM3097 Rev004.doc SRRS: 30.105 Page 7 of 14 (When used for operator initial or continuing training) I ,S' Exelon Generation. I-cc I-Zw ELEMENT STANDARD I-<( w ca <( en :E :E en z :E ::::> ::::> Oz 0 EP-MA-114-100-F-01, STATE/LOCAL EVENT NOTIFICATION FORM 9. UTILITY MESSAGE NO. "2" or equivalent entered 10. VERIFIED WITH N/A N/A 11. EMERGENCY DIRECTOR Signature entered APPROVAL

  • 12. CALL STATUS: Call Status marked [8J THIS IS A DRILL
  • 13. AFFECTED STATION: Affected Station marked [8J LIMERICK " I
  • 14. AFFECTED UNIT(S): Unit(s) marked 1:8] ONE DTWO
  • 15. CLASSIFICATION:

Classification marked 0 UNUSUAL EVENT D ALERT CJ SITE AREA EMERGENCY [8JGENERALEMERGENCY

  • 16. DECLARED AT: Time entered Date entered 17. THIS REPRESENTS A/AN: This Represents marked 0 INITIAL DECLARATION

[8J ESCALATION 0 NO CHANGE

  • 18. EMERGENCY ACTION "FG 1" entered LEVEL (EAL) NUMBER: Thresholds:

FC.1 AND (RC.5 OR RC.4.1 OR RC.4.3) AND (CT.6.1 OR CT.6.3.a) LOJPM3097 Rev004.doc SRRS: 30.105 Page 8 of 14 (When used for operator initial or continuing training) Exelon Generation, I-cc I-Zw I-<( w aJ ELEMENT STANDARD <( en en z

> Oz 0
  • 19. A BRIEF NON-TECHNICAL D A-Abnormal Rad Levels/ DESCRIPTION OF THE Radiological Effluent EVENT: 1:8] B-Fission Product Barrier Degradation D C-System Malfunction D D-Hazards and Other Conditions Affecting Plant Safety D E-Independent Spent Fuel Storage Installation Malfunction D F-Cold Shutdown/Refueling I System Malfunctions
  • 20J RADIOLOGICAL RELEASE Release Status marked STATUS: 0 NO RELEASE " I 1:8] AIRBORNE I D LIQUID 0 RELEASE TERMINATED
  • 21. METEOROLOGY DATA: Simulator Values match displayed I Tower 1 175' using 15 minute average values: ' ,, Wind Direction:

311.0 (degrees) ' Provide MET Attachment only if in location other than Wind Speed: 5.0 (MPH) simulator Attachment Values : Wind Direction: 311.0 (degrees) Wind Speed: 5.0 (MPH)

  • 22. PROTECTIVE ACTION PAR Recommendation marked RECOMMENDATION D NOT Applicable (a orb): 1:8] PAR Recommendation LOJPM3097 Rev004.doc SRRS: 30.105 Page 9 of 14 (When used for operator initial or continuing training)
  • Exelon Generation ELEMENT STANDARD CJ) z :::::> NOTE: IF PAR RECOMMENDATION is required the following items should be marked: [ s@360 DEGREES FROM 0 MILES (SITE BOUNDARY)

TO 2 MILES AND THE FOLLOWING SECTORS FROM 2 MILES TO 5 MILES: [S/E]N EIE [S{E)S [ SI E ] NNE [ S ESE [SK) SSW [S/E]NE [S SE [S/E]SW [ SI E ] ENE [ S SSE [ SI E ] WSW AND I THE FOLLOWING SECTORS FROM 5 MILES TO 10 MILES: [S/E]N ! [S/E]E [S/E]S [S/E]NNE [S/E]ESE [S/E]SSW [SI E] NE ;' [SI E] SE [SI E] SW [S/E]ENE [S/E]SSE [S/E]WSW AND [S/E]W [SI E ]WNW [S/E]NW [S/E]NNW [S/E]W [ S/ E] WNW [S/E]NW [S/E]NNW Potassium Iodide (Kl) be administered to the general public in accordance with state procedures and advise the remainder of the EPZ to Monitor and Prepare. AND ' This Recommendation [IS] [l@T] the result of a Rapidly Progressing Severe Accident 23. UTILITY PAR recommendations

24. CONCLUSION Correct PAR Recommendation marked including required sectors Conclusion marked iZ] THIS IS A DRILL (Critical that at least one of the two status blocks on the page is marked correctly and no contradictory info is marked. If contradictory info is marked, then the incorrect step is UNSAT. If one block is blank and the other is correct, then the blank block is N/A) JPM Stop Time: __ _ I-a: ZW w Ill :;,: :E :;,: :::::> Oz 0 LOJPM3097 Rev004.doc SRRS: 30.105 Page 10 of 14 (When used for operator initial or continuing training)

I=' Exelon Generation JPM

SUMMARY

Operator's Name: _________________________ Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: ERP CLASSIFICATION AND REPORTING (TIME CRITICAL) JPM Number: LOJPM3097 Revision Number: 004 Task Number and Title: 3440070302, Classify Emergency Events Requiring Emergency Plan Implementation KIA Number and Importance: Generic 2.4.41 4.6 Safety Function (1-9) N/A Admin Category (A1-4) ___ _ Level of Difficulty (1-5) Suggested Testing Environment: Simulator I Alternate Path:O No SRO Yes D No Time Critical: D No Reference(s): EP-AA-1008, LGS EMERGENCY ACTION LEVEL (EAL) MATRIX, Rev 2 I EP-MA-114-100-F-01, STATE/LOCAL EVENT NOTIFICATION FORM, Rev P EP-AA-112-1 OO-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, Rev V ***** EP-AA-111-F-11, Limerick PAR Flowchart, Rev. A Actual Testing Environment: Simulator D Control Room D In-Plant D Other Testing Method: D Simulate Perform Estimated Time to Complete: 27 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes D No ,, ,, The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Evaluator's Name: ----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM3097 Rev004.doc SRRS: 30.105 Page 11 of 14 (When used for operator initial or continuing training)

  • i I ,, I = j Exelon Generation.

LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS: Unit 1 is initially at 100% power when the following events occur: T=O * 'A' Steam Line ruptures in the Outboard MSIV Room

  • Group 1 Isolation signal is received due to high steam line flow
  • A full scram occurs with all rods inserted * "A" Steam Line Inboard and Outboard MSIVs fail to isolate automatically or manually T = 5 minutes
  • Reactor Coolant Activity starts to rise T = 10 minutes
  • EAL threshold recognized and emergency declaration made T = 15 minutes *
  • State and Local notifications complete for emergency declaration Shift Communicator has activated the ERO Page 12 of 14 *i I ,, I'

Exelon Generation. Current Plant Conditions:

  • RPV pressure is 850 psig and lowering
  • RPV level is + 18" and steady
  • DW pressure is 0.3 psig
  • Reactor Coolant Activity is 370 µCi/gm
  • Outboard MSIV Room temperature is 210 degrees F, up slow
  • Security personnel confirms a steam release outside secondary containment from blowout panels
  • North Stack WRAM is indicating 2.5E+6 µCi/sec.
  • Post LOCA Rad Monitors are reading the following:

A-96 R/hr. B -89 R/hr. C -103 R/hr. D -97 R/hr. INITIATING CUES: This Task is Time Critical *i I This JPM will start when you tell the evaluator that you are aware of task conditions and are ready to begin. You are required to make the highest classification based on the given plant conditions and make subsequent call outs. All communications should indicate a drill. Page 13 of 14 I Generation, I 917METEOROLOGICAL 15 MINUTE AVERAGE POINT DATA PIO SENSOR DESCRIPTION VALUE EU T1DTULFA T1.SP.U TOWER 1 270 FT WIND SPEED 6.7 MPH T1SPIFA T1.SP.I TOWER 1 175 FT WIND SPEED 5.0 MPH T T12SPLFA T1 .SP.L TOWER 1 30 FT WIND SPEED 7.3 MPH 0 T1DRUFA T1.DR.U TOWER 1 270 FT WIND DIRECTION 252.3 DEG AZ w T1DRIFA T1.DR.I TOWER 1 175 FT WIND DIRECTION 311.0 DEG AZ E T1DRLFA T1.DR.L TOWER 1 30 FT WIND DIRECTION 257.2 DEG AZ R T1DTULFA T1.DT.U-L TOWER 1 266 -26 FT DEL TA TEMP -0.3 DEG F T1DTILFA T1.DT.l-L TOWER 1 171 -26 FT DELTA TEMP 0.4 DEG F 1 T1ATLFA T1.AT.L TOWER 1 26 FT AMBIENT TEMP 85.2 DEG F T1DPLFA T1.DP.L TOWER 1 26 FT DEW POINT 45.00 DEG F T1RNFA T1.RN TOWER 1 PRECIPITATION

0.1 INCHES

T2DTULFA T2.SP.U TOWER 2 304 FT WIND SPEED 6.8 MPH T T2SPIFA T2.SP.I TOWER 2 159 FT WIND SPEED 7.3 MPH -------0 T22SPLFA T2.SP.L. -. TOWER 2 30 FT WIND SPEED 7.8 MPH w T2DRUFA T2.DR.U TOWER 2 304 FT WIND DIRECTION 251.7 DEG AZ T2DRIFA T2.DR.I TOWER 2 159 FT WIND DIRECTION 250.5 DEG AZ E T2DRLFA T2.DR.L TOWER 2 30 FT WIND DIRECTION 257.6 DEG AZ R T2DTULFA T2.DT.U-L TOWER 2 304 -26 FT DEL TA TEMP -0.4 DEG F T2DTILFA T2.DT.l-L TOWER 2 155 -26 FT DELTA TEMP 0.6 DEG F 2 T2ATLFA T2.AT.L TOWER 2 26 FT AMBIEWNT TEMP 85.0 DEG F T2DPLFA T2.DP.L TOWER 2 26 FT DEW POINT 44.81 DEG F Page 14 of 14 I ;i:;, Exelon Generation Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE SCRAM RESET JPM Number: LOJPM3001 REVISION NUMBER: 000 " I ,, ,, DATE: ----Instructor SME or Instructor Operations Representative EP Representative Training Department LOJPM 3001 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training) Date Date Date Date Date Page 1 of 10 1-.:" Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path ib used, the task standard contains criteria for successful completion.
  • 9. Verify the procedurE:)(s) referenced by this JPM reflects the current revision:

Procedure GP-11 Rev: 29 -=-=---Procedure _________ _ Rev: ---Procedure Rev: ---Procedure Rev: ---Procedure Rev: __ _ 10. Verify cues both verbal and visual are free of conflict.

11. Verify performance':time is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date ' LOJPM 3001 RevOOO.doc SRRS: 30.105 Page 2 of 10 (When used for operator initial or continuing training)

I Exelon Generation. II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the IL Tor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date i Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the that were made or incorporated. Revision , , Description of Revision and Affect on Training Content # Date of Number Revision 000 This JPM supersedes LLOJPM0001 Rev. 15. Revised to new template 10/31/16 and to align with latest procedure revision.

  1. Date of Revision -refers to date revision was released for approval LOJPM 3001 RevOOO.doc SRRS: 30.105 Page 3 of 10 (When used for operator initial or continuing training)

I ;;7'7 Exelon Generation.. IV. TASK STANDARD: Insert a full reactor scram signal upon recognition that scram will not reset after 2nd attempt. V. SIMULATOR SETUP: 1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC. NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Transfer house loads. I 3. Place fieactor Mode Switch in "SHUTDOWN".
4. EnsurEt Rod Drift Alarms are reset. 5. Insert malfunction MRP028B, RPS Group 1 Reactor Scram. 6. Acknowledge and clear all spurious alarms. VI. INITIAL CONDITIONS:
1. Unit 1 :Reactor was scrammed for a planned shutdown.
2. The SDV has been surveyed by Radiation Protection
3. HEPA Filters and Protective Laundry Bags are not required to be installed on 253' Elevation Floor Drains 4. Flushing of the SDV per RT-6-047-600-1 has been determined not to be required after SCRAM reset 5. No HCUs currently have clearances applied 6. All Prerequisites have been met. VII. INITIATING CUE: Shift supervision directs you to perform a Unit 1 RPS scram reset per GP-11. LOJPM 3001 RevOOO.doc SRRS: 30.105 Page 4 of 10 (When used for operator initial or continuing training)

=*c Exelon Generation. 1-Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. I LOJPM 3001 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training) ,, I Page 5 of 10 " I ,, I I ,g Exelon Generation VIII. PERFORMANCE CHECKLIST: JPM Start Time ____ _ ELEMENT STANDARD 1. Obtain current revision of GP-11, Candidate demonstrates Scram Reset ability (actual or discuss) to locate GP-11, Scram Reset CUE: Candidate is given a copy of GP-11 , Scram Reset when knowledge of the correct location of procedure is demonstrated.

2. REQUEST Radiation Protection to N/A perform the following:

2a. SURVEY SDV prior to release of fluid Radiation Protection requested inventory. to survey SDV 2b. EVALUATE the need for RT-6-047-CRD Scram Discharge Volume 600-*, Flush of CRD Scram Discharge flush not required per Initial Volume (SDV)." Conditions. CUE: Report that RP has surveyed the SDV and that the RT is not required to be done. 2c. IF time permits THEN NOTIFY Rad Pro Protective bags over floor drains to install HEPA filters AND Protective not required per Initial Clothing Bags over the Reactor Conditions. Enclosure 253' elevation floor drains per RP-LG-301-2001 prior to scram reset CUE: Protective bags and HEPA Filters are not required. LOJPM 3001 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training) I-I-cc ZW I-<( w al <( en :::: :::: en z :::: :::> :::> Oz 0 I " I I I ,, I Page 6 of 10 Exelon Generation. I-I-cc ZW ELEMENT STANDARD I-<( W IXI <( en :E :E en z :E :::> :::> Oz 0

  • 3. PLACE Scram Discharge Volume High SDV High Level Bypass Switch Level Bypass Keylock Switch on *OC603 in "BYPASS" position.

to "BYPASS".

  • 4. VERIFY Annunciator Panel *07, Verify by observation that "SDV REACTOR, Window C-2, "SCRAM DISC HI LEVEL SCRAM BYPASSED", VOLUME HI LEVEL SCRAM 107 REACTOR (C-2), is lit. BYPASSED,

is in alarm. 5. ENSURE Annunciator panel *08, Annunciator panel *08, REACTOR, Window E-5, "RPIS REACTOR, Window E-5, "RPIS INOPERATIVE" is clear. INOPERATIVE" is clear 6. IF Annunciator Panel *08, REACTOR, i I Window E-4, "RDCS INOPERATIVE, is in alarm, THEN RESET the Rod Drive N/A Control System (RDCS) in accordance ,, with S73.0.F, "Resetting the Rod Drive I Control System". Otherwise MARK this I 7. IF CRD Full Core Display OR Process Computer indicates not all control rods N/A are fully inserted, THEN PERFORM GP-11 Appendix I using Attachment

1. I Otherwise MARK this step AND ' Appendix 1 Steps 3.1 through 3.2.2 N/A ,, ,. 8. RESET Alternate Rod Insertion (ARI) at N/A panel *OC603 as follows: Ba. DEPRESS ARI RESET pushbuttons ARI Reset pushbuttons 1 A, 1 B, (1A, 18, 2A, 28). 2A, 2B depressed.
9. RESET RPS at panel *OC603 as follows: N/A
  • 9a. PLACE Scram Reset switch to "GP Scram Reset Switch taken to GP 1/4". 1/4 position.
  • 9b. PLACE Scram Reset switch to "GP Scram Reset Switch taken to GP 2/3". 2/3 positions.

Evaluator Note: Alternate Path begins with the next step. The next step is a failure of the scram to reset. LOJPM 3001 RevOOO.doc SRRS: 30.105 Page 7 of 10 (When used for operator initial or continuing training) Exelon Generation I-a: I-ZW ELEMENT STANDARD I-<J: Wal <J: en en z :25 :::> :::> Oz (.)

  • 10. VERIFY the eight (8) scram group white Recognize 1 light for RPS 'A' lights are Lit for Scram System A AND and 1 light for RPS 'B' did not Scram System B on *OC603. light. 11. IF the eight scram group white lights are Verify Mode switch in not lit after initial reset, THEN VERIFY "SHUTDOWN".

proper Reactor Mode Switch position ...

  • 12. AND REPEAT step 3.8 one time (Reset N/A RPS)
  • 13. PLACE Scram Reset switch to "GP Scram Reset Switch taken to GP 1/4". 1/4 position.

I

  • 14. PLACE Scram Reset switch to "GP Scram Reset SwitcH taken to GP 2/3". 2/3 position.

,,

  • 15. VERIFY the eight (8) scram group white Recognize 1 light for RPS 'A' lights are Lit for Scram System A AND and 1 light for RPS 'B' did not Scram System B on *OC603. light. I 16. IF the eight scram group white lights are N/A not Lit after second reset attempt, THEN PERFORM the following:

I 17. VERIFY blue lights on Full Core Display No HCUs have clearances are not Lit, unless determined to be applied per Initial Conditions. expected for clearance application

18. IF blue lights on Full Core Display are N/A Lit THEN PERFORM the following:
  • 18a. INSERT a full scram signal via Manual scram initiated using Manual Scram Pushbuttons Manual Scram Pushbuttons
  • 18b. VERIFY SDV vent AND drain valves SDV vent and drain valves close verified closed. CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM 3001 RevOOO.doc SRRS: 30.105 Page 8 of 10 (When used for operator initial or continuing training)

Exelon Generation. JPM

SUMMARY

Operator's Name: _______________________ ____ Job Title: D SED D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: SCRAM RESET JPM Number: LOJPM3001 Revision Number: 000 Task Number and Title: 2957010401, Reset a Scram KIA Number and Importance: 295006 AA 1.01 4.2/4.2 Safety Function (1-9) 1 (Reactivity Control) Admin Category (A1-4) N/A Level of Difficulty (1-5) -----.;:;3 ____ _ Suggested Testing Environment: Simulator Alternate Path:[8J Yes D No i SRO Only: D Yes [8J No Time Critical: 0Yes [gJ No Reference(s): GP-11 Reactor Protection System -Scram reset Rev 29 Actual Testing Environment: .D Simulator D Control Room D In-Plant D Other I Testing Method: D Simulate [8J Perform Estimated Time to Complete:' 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes 0No I ' The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D* Satisfactory D Unsatisfactory Evaluator's Name:-----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM 3001 RevOOO.doc SRRS: 3D.105 Page 9 of 10 {When used for operator initial or continuing training)

Exelon Generation. INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Unit 1 Reactor was scrammed for a planned shutdown.

2. The SDV has been surveyed by Radiation Protection
3. HEPA Filters and Protective Laundry Bags are not required to be installed on 253' Elevation Floor Drains 4. Flushing of the SDV per RT-6-047-600-1 has been determined not to be required after SCRAM reset 5. No HCUs currently have clearances applied 6. All Prerequisites have been met. INITIATING CUE: " I Shift supervision directs you to perform a Unit 1 RPS scram reset per GP-11. I ,, Page 10 of 10 I

Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE RCIC MANUAL SLOW START USING FIC-49-1 R600 JPM NUMBER: LOJPM3015 REVISION NUMBER: 002 DATE: Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Reviewed By: EP Representative Date Approved By: Training Department Date LOJPM3015 Rev002.doc SRRS: 30.105 (When used for operator initial or continuing training) Page 1 of 11 " 1 ,, I ExelonGeneration 1-Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). i. 8. If an path is used, the task standard contains criteria for successful completion.
9. VerifYithe procedure(s) referenced by this JPM reflects the current revision:

Procedure 849.1.D Rev: _4=2'--- Procedure

Procedure

Procedure----------

10. Verify cues both verbal and visual are free of conflict.
11.

time is accurate Rev: __ _ Rev: ---Rev: ---Rev: __ _ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM3015 Rev002.doc SRRS: 30.105 Page 2 of 11 (When used for operator initial or continuing training) [ = Exelon Generation. II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision I # Date of Number Description of Revision and Affect on Training Cor:itent Revision 000 This JPM replaces LLOJPM0015 Rev. 7. The purpose of this revision 08/30/13 is to reformat in accordance with the new JPM template and to ensure agreement with latest procedure revision. 001 Minor revision for procedural compliance, and remove prerequisite 10/20/15 steps from JPM section VIII. 002 Revised to new JPM standard and added prerequisites satisfied 8/04/16 # Date of Revision -refers to date revision was released for approval LOJPM3015 Rev002.doc SRRS: 30.105 Page 3 of 11 (When used for operator initial or continuing training) " I ,, ,, I ,SJ!' Exelon Generation IV. TASK STANDARD: RCIC in full flow with a discharge pressure at least 70 psig greater than reactor pressure, and a pump flowrate of 600 gpm with the controller in AUTO. V. SIMULATOR SETUP: 1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC. NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Align RCIC for automatic operation.

VI. INITIAL CONDITIONS:

1. LGS Unit 1 is in OPCON 1 2. ST-6-060-390-1 is currently being performed by a second operator 3. S49.9.A, Routine Inspection of RCIC system has been performed
4. Vibration Monitoring System is in service 5. Steam Leak Detection System is not known to be INOP 6. An EO and RP Tech are on station and the Unit 1 RCIC room is posted 7. S49.1.D, RCIC System Full Flow Functional Test prerequisites are satisfied VII. INITIATING CUE STATEMENT (Describe the task clearly): " I ,, ' You are directed by Shift Supervisor to place Unit 1 RCIC in full flow test for a 15 minute PMT using S49.1.D, to obtain discharge pressure at least 70 psig greater than reactor pressure, and a pump flowrate of 600 gpm with the controller in AUTO by the manual slow start method using FIC-49-1 R600. LOJPM3015 Rev002.doc SRRS: 30.105 Page 4 of 11 (When used for operator initial or continuing training)

Exelon Generation Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. I The JPM Start Time clock starts ,hen the candidate acknowledges the initiating cue LOJPM3015 Rev002.doc I " I ,, ' SRRS: 30.105 (When used for operator initial or continuing training) Page 5 of 11 I ,:i::.-Exelon Generation VIII. PERFORMANCE CHECKLIST: JPM Start Time -----t-cc t-Zw ELEMENT STANDARD t-< Wm < (./) :ii: :!!: (./) z :ii: :::::> :::::> Oz (.) 1. OBTAIN current revision of Current revision of S49.1.D S49.1.D. obtained. CUE: Provide M/U copy of S49.1.D to I candidate, with prerequisites signed-off. I 2. VERIFY all prerequisites satisfied. Prerequisites are verified and off as complete.

3. VERIFY procedure being N/A performed on correct unit/train
4. IF Vibration Monitoring System is i available, ' N/A ,, THEN VERIFY in service. ' 5. PERFORM the following:

N/A 5a. ENSURE HV-55-*F071, "HPCl/RCIC Flush Line to HV-55-1 F071 is verified Suppression Pool" (TEST closed. OUTBOARD), closed. 5b. ENSURE HV-55-*FOOS, "Test HV-55-1 FOOS is verified Loop Shutoff" (TEST ISOL), closed. closed. 5c. ENSURE HV-49-*F022, "RCIC Test HV-49-1 F022 is verified Loop Isolation" (TEST ISOL), is closed. closed. LOJPM3015 Rev002.doc SRRS: 30.105 Page 6 of 11 (When used for operator initial or continuing training) 1-= Exelon Generation .. I-er: I-ZW I-<C Wm ELEMENT STANDARD <( CJ) :E :E en z :E :::> :::> Oz (.) 6. PERFORM the following to open HV-055-*F011, "HPCl/RCIC PP. N/A Test Return to C.S.T. (CONDENSATE RETURN)".

  • 6a. PLACE HS-55-*11 in OPEN at HS-55-111 placed in OPEN panel *OC64 7 6b. WHEN HV-55-*F011 is full open When HV-55-1 F011 indicates THEN PLACE HS-55-*11 in STOP. full open (red light on, green ! light off) HS-55-111 placed in STOP. I 7. START *OP219, "Barometric 10P219 Vacuum Pump is Co11denser Vacuum Pump" running. (VACUUM PUMP). 8. OPEN HV-50-*F046, "RCIC Lube Oil HV-50-1F046 is open.
  • Cooling Water Supply" (COOLING WATER). I 9. MONITOR Suppression Pool N/A temperature per ST-6-060-390-*, Per Initial Conditions ST-6-Suppression Pool Temperature 060-390-1 is currently being Check. performed by a second operator.
10. IF required to limit Suppression Pool temperature any time during this procedure, THEN PLACE Suppression Pool Cooling Mode of RHR System in service per S51 .8.A, Suppression N/A Pool Cooling Operation.

CUE: If requested, inform operator Suppression Pool Cooling is not required. LOJPM3015 Rev002.doc SRRS: 30.105 Page 7 of 11 (When used for operator initial or continuing training) I =""':'Exelon Generation I-cc I-ZW ELEMENT STANDARD I-<C w DJ <C en :: :: en z :: ::::> :::::> Oz u 11. INFORM HP of changing HP is informed of Unit 1 RCIC radiological conditions due to RCIC start. system start. 12. PLACE FIC-49-*R600, "RCIC FIC-49-1 R600 M/A selector Pump Discharge Flow Controller" switch repositioned to "M". (FL), in "MANUAL" Depress FIC-49-1 R600 AND SET to 0%. "CLOSE" detent pushbutton until controller output I indicating 0%. 13. OPEN "RCIC Steam HV-50-1F045 is OPEN.

  • Supply" (INLET). I 14. PERFORM the following to start N/A RCIC turbine: I 14a. Slowly RAISE the output of FIC-49-1 R600 OPEN detent
  • FIC-49-*R600 until turbine speed pushbutton is depressed until begins to raise as indicated on speed rises as indicated on Sl-50-*01,-1, "Turbine Speed" (S). Sl-50-101-1.

' 14b. WHEN speed begins to increase, HV-49-1 F022 handswitch is

  • THROTTLE OPEN HV-49-*F022, placed in OPEN and then Pull "RCIC Full Flow Shutoff" (TEST to Stop and repeated until ISOL). valve indicates desired flow. 14c. Slowly INCREASE output of FIC-49-1 R600 OPEN detent
  • FIC-49-*R600, FL, to greater than pushbutton is depressed until 2200 rpm as indicated on Sl-50-speed rises to greater than *01-1, "Turbine Speed" (S). 2200 rpm as indicated on SI-50-101-1.
15. IF HV-49-*F022 will not open, THEN PERFORM the following:

N/A LOWER output of FIC-49-*R600, "RCIC Pump Discharge Flow Controller" (FL), to approximately 2500 rpm. THROTTLE OPEN HV-49-*F022. LOJPM3015 Rev002.doc SRRS: 30.105 Page 8 of 11 (When used for operator initial or continuing training)

/ Exelon Generation.

ELEMENT STANDARD I-a: 1-<C z w w IIl CJ) :E :E z :E ::::> ::::> 0 z u EVALUATORS NOTE: If the candidate is unable to establish 600 GPM due to a partially throttled HV-49-1F022 and the candidate recognizes that the valve needs to be throttled further open and requests permission to do this, it is acceptable to grant permission.

  • 16. Slowly RAISE output of FIC-49-*R600 to approximately 600 gpm AND MATCH setpoint to actual flow, THEN PLACE FIC-49-*R600 in "AUTO". 17. THROTTLE HV-49-*F022, "RCIC Full Flow Test" (TEST ISOL) AND ADJUST FIC-49-*R600, as necessary, to maintain pump discharge pressure at least 70.3 psig over reactor pressure AND pump flow rate of 600 pm. Depress FIC-49-1 R600 "OPEN" detent to achieve 400 to 700 gpm as indicated on Fl-49-1 R600. Flow controller is adjusted such that when the controller is switched to AUTO, flowrate changes less than 100 gpm. I M/A selector switch in AUTO. Maintain pump discharge pressure as indicated on Pl-49-1 R601 at least 70 psig over reactor pressure as indicated on Pl-49-1 R602 by adjusting HV-49-1 F022 as necessary while maintaining pump flow 550 to 650 gpm on R600. ' CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM3015 Rev002.doc SRRS: 30.105 (When used for operator initial or continuing training)

Page 9 of 11 I.=' Exelon Generation. JPM

SUMMARY

Operator's Name: _______________________ Job Title: 0 SEO 0 SM 0 SRO 0 RO 0 STA/IA 0 EO 0 OTHER JPM Title: RCIC MANUAL SLOW START USING FIC-49-1 R600 JPM Number: LOJPM3015 Revision Number: 002 Task Number and Title: TP0-2170070201 Conduct RCIC System Full Flow Functional Test KIA Number and Importance: 217000 A4.01 3.7/3.7 217000 A4.03 3.4/3.3 217000 A4.04 3.6/3.6 Safety Function (1-9) 2 (Reactor Water Inventory Control) Adm in Category (A 1-4) ----;.;.N"""'/ A ____ _ Level of Difficulty (1-5) 3 Suggested Testing Environment: Simulator Alternate Path:O Yes (8J No SRO Only: 0 Yes (8J No Time Critical: 0 Yes (8J No ;* Reference(s): 849.1.D, RCIC System Full Flow Functional Test and Turbine Oil Priming, Rev. 42 ;i Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate 0 Perform ,, I' Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

0 Yes 0 No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: 0 Satisfactory 0 Unsatisfactory ,, Comments: ___________________________ _ Evaluator's Name:----------------(Print) Evaluator's Signature:. ______________ _ Date: _____ _ LOJPM3015 Rev002.doc SRRS: 30.105 Page 10 of 11 (When used for operator initial or continuing training)

.
/ Exelon Generation.

INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. LGS Unit 1 is in OPCON 1 2. ST-6-060-390-1 is currently being performed by a second operator 3. S49.9.A, Routine Inspection of RCIC system has been performed

4. Vibration Monitoring System is in service 5. Steam Leak Detection System is not known to be INOP 6. An EO and RP Tech are on station and the Unit 1 RCIC room is posted 7. S49.1.D, RCIC System Full Flow Functional Test prerequisites are satisfied I I INITIATING CUE: ,/ I You are directed by Shift Supervisor to place Unit 1 RCIC in full flow test for a 15 minute PMT using S49.1.D, to obtain discharge pressure at least 70 psig greater than reactor pressure, and a pump flowrate of 600 gpm with the controller in AUTO by the manual slow start method using FIC-49-1 R600. ,, Page 11 of 11 1,:: 7 ExelonGeneration LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE SHUTDOWN COOLING FLOW ADJUSTMENTS JPM Number: LOJPM3515 REVISION NUMBER: 000 DATE: __ _ Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Reviewed By: EP Representative Date Approved By: Training Department Date LOJPM3515 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training)

,, I ,, Page 1 of 10 I Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is the task standard contains criteria for successful completion.
9. Verify the procedure(s) r¢ferenced by this JPM reflects the current revision:

Procedure 851.8.B Rev: 81 """"'-'--- Procedure Rev: Procedure Rev: Procedure Rev: Procedure Rev: 10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time :is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM3515 RevOOO.doc SRRS: 30.105 Page 2 of 10 (When used for operator initial or continuing training)

I ,:i:; ..

  • ExelonGeneration.
11. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the IL Tor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Peirtormance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision ' # Date of Number Description of Revision and Affect on Training Co11tent Revision 000 This JPM supersedes LLOJPM0515 Rev. 9. Revised to new template 10/31/16 and to align with latest procedure revision.

  1. Date of Revision -refers to date revision was released for approval LOJPM3515 RevOOO.doc SRRS: 30.105 Page 3 of 10 (When used for operator initial or continuing training)

I ;:f:i/:'/ Exelon Generation IV. TASK STANDARD: Additional cooling provided to the '1 A' RHR Heat Exchanger. Following confirmation of the RHRSW High Radiation alarm, '1 A' RHR pump is tripped and '1 A' RHR Heat Exchanger is isolated V. SIMULATOR SETUP: NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

1. Reset the simulator to IC-__ (1A RHR in Shutdown Cooling) and make the manipulations below or reset the simulator to the prepared exam IC and verify the conditions below. 2. Adjust HV-C-51-103A (1A RHR Heat Exchanger Outlet Bypass POS) to 100% 3. Ensure HV-51-1 F015A (Shutdown Cooling Return Valve) is full open 4. Close HV-51-1F003A (Heat Exchang 1 er Outlet) 5. Throttle HV-C-51-1 F048A (Heat Exchanger Bypass) closed to obtain 9000 gpm flow 6. Verify 51-1031A and 51-10181 Transfer valves closed 7. Verify HV-51-1 FOO?A, Min Flow Valve is closed and de-energized
8. Verify DAS Screen set to 1A SOC Lo,op 9. Verify PMS SOC Monitor is active 10. Apply Robust Barriers (mousetraps) to the following:

HV-43-1F023A, RECIRC SUCTION HV-51-1 F027A, SUPP POOL HV-51-1F040, LETDOWN TO RW, HV-51-1F024A, SUPP POOL CLNG HV-51-1F008, SHUTDOWN COOLING SUCTION (OUTBOARD) HV-51-1F-15A, SHUTDOWN COOLING INJECTION (OUTBOARD) 1AP202, '1A' RHR Pump Handswitch HV-51-1F014A, RHRSW INLET HV-51-1F006, SUCTION B HV-43-1 F023B, RECIRC SUCTION HV-51-1 F027B, SUPP POOL SPRAY HV-51-1F049, LETDOWN TO RW HV-51-1F006B, SUCTION A HV-51-1 F009, SHUTDOWN COOLING SUCTION (INBOARD) HV-51-1F048A. HEAT EXCH BYPASS OAP506, 'OA' RHRSW Pump Handswitch HV-51-1F068A, RHRSW OUTLET 11. Prepare a copy of S51.8.B marked up completed to step 4.4.30 12. Establish the Malfunction MRM019A, U1 RHR SW Return Hdr Rad Mon fails to 500 cpm on Automatic Trigger #1 or other available trigger if performing this JPM in an exam set of JPMs. This Trigger will be activated when HIC51-103A Controller Output meter reads less than or equal to 15%. LOJPM3515 RevOOO.doc SRRS: 30.105 Page 4 of 10 (When used for operator initial or continuing training) I *S' Exelon Generation VI. INITIAL CONDITIONS:

1. '1 A' RHR has been placed in service for Shutdown Cooling with Reactor Coolant temperature at 125°F as read on Xl-36-101 TE-51-1N004A
2. 'OA' RHRSW pump is in service providing flow to '1 A' RHR Heat Exchanger
3. Reactor level is being maintained at 83" as read on Ll-42-1 R605 4. HV-C-51-103A, RHR Heat Exchanger Outlet Bypass (POS), is full open and additional cooling is required to maintain reactor coolant temperature within the 110°F to 130°F band 5. The Unit 1 Reactor Operator is performing ST-6-107-640-1, Rx Vessel Temperature and Pressure Monitoring VII. INITIATING CUE: The CRS has directed you to continue performing 851.8.B at step number 4.4.30 to provide additional cooling to reactor coolant LOJPM3515 RevOOO.doc

,, I ,, ,, SRRS: 30.105 (When used for operator initial or continuing training) Page 5 of 10

c,* Exelon Generation 1-Information for Evaluator's Use
Any UNSAT requires written comments on respective step.
  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when candidate acknowledges the initiating cue. LOJPM3515 RevOOO.doc ,, I ,, ' SRRS: 30.105 (When used for operator initial or continuing training) Page 6 of 10 j ,:i'! Exelon Generation VIII. PERFORMANCE CHECKLIST: JPM Start Time ____ _ I-a: ZW ELEMENT STANDARD I-w Ill <C en :E :E en z :E ::> ::> Oz 0 1. Candidate obtains copy of S51.8.B Candidate obtains marked up completed up to and including step copy of S51.8.B and 4.4.30 determines additional cooling is required. CUE: Candidate is given a copy of S51.8.B, Shutddwn Cooling/Reactor Coolant Circulation Operation Start-Up And Shutdown marked up completed to and including step 4.4.30. 2. [4.4.23.6] ' IF additional cooling is required, N/A THEN PERFORM the following: 2a. [4.4.23.6.a] OPEN HV-C-51-1 F048A, red

  • OPEN HV-C-51-1 F048A, HEAT light lit EXCH BYPASS. ,, 2b. [4.4.23.6.b]

.. OPEN HV-51-1 F003A, red

  • OPEN HV-51-1 F003A, OUTLET. light lit 2c. [4.4.23.6.c]

CLOSE HV-C-51-103A,

  • CLOSE HV-C-51-103A, POS. green light lit EVALUATORS NOTE: THE ALTERNATE PATH PORTION OF THE JPM BEGINS IN THE NEXT STEP WITH THE FOLLOWING INDICATIONS:
  • Insert MRM019A, U 1 RHR SW Return Hdr Rad Mon fails to 500 cpm
  • The following steps include actions from the ARC-MCR 011-B-4 Annunciator (RHRSW Hi Radiation)
3. Respond to alarm 011 B-4, SERV ARC MCR 011 B-4, SERV WTR B (RHRSW HI RADIATION)

WTR B (RHRSW HI RADIATION) referenced. LOJPM3515 RevOOO.doc SRRS: 30.105 Page 7 of 10 (When used for operator initial or continuing training) Exelon Generation. I-cc I-ZW ELEMENT STANDARD I-w Ill <t CJ) :e :e en z :e ::J ::::> Oz (.) 4. Verify the high radiation condition ObseNe RHRSW rad on RR-OR615A panel C667 recorder RR-OR615A and determine increasing trend 5. IF an actual high radiation condition Determine recorder response is suspected, THEN: is due to an actual increasing radiation condition CUE: If asked, report Chemistry has confirmed that a hi rad condition exist.

  • 5a. Trip assoc!ated RHR pump '1A' RHR Pump handswitch taken to STOP (Green Flag) "
  • 5b. AND Isolate the shell side of HX by HV-51-1 F04 7 A keylock switch closing HV-51-1F047A or HV-51-taken to CLOSE, (Green light 182A with HS-51-182A (309/238' on, Red light off). U/1)
  • 5c. AND HV-51-1F003A or HV-C-51-HV-51-1 F003A keylock switch 103A taken to CLOSE, (Green light on, Red light off). *' ' CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM3515 RevOOO.doc SRRS: 30.105 Page 8 of 10 (When used for operator initial or continuing training)

I;/ Exelon Generation. JPM

SUMMARY

Operator's Name: _______________________ __..;;. Job Title: 0 SEO 0 SM 0 SRO 0 RO 0 STA/IA 0 EO 0 OTHER JPM Title: SHUTDOWN COOLING FLOW ADJUSTMENTS JPM Number: LOJPM3515 Revision Number: 000 Task Number and Title: 2031010101 Place RHR in Shutdown Cooling Operation, Monitor and Secure KIA Number and Importance: 205000 K1 .15 Safety Function (1-9) 4 (Heat Removal From the Core) Admin Category (A1-4) N/A Level of Difficulty (1-5) 3 Suggested Testing Environment: Simulator 3.5/3.6 Path:i::g] Yes 0 No SRO Only: 0 Yes i::g] No Time Critical: 0 Yes i::g] No Reference(s): S51.8.8, Shutdown Cooling I Reactor Coolant Circulation Operation Start-up ana Shutdown, Rev 081 ARC-MCR-011-84, RHRSW Hi Radiation, Rev 004 Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate 0 Periorm Estimated Time to Complete: 15 minutes Actual Time Used: minutes I ,, EVALUATION

SUMMARY

We're all the Critical Elements periormed satisfactorily?

0 Yes 0 No The operator's periormance was evaluated against standards contained within this JPM and has been determined to be: 0 Satisfactory 0 Unsatisfactory Evaluator's Name:----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM3515 RevOOO.doc SRRS: 30.105 Page 9 of 10 (When used for operator initial or continuing training)

Exelon Generation. LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET IX. INITIAL CONDITIONS: ,, I x. ,, ,. 1. '1 A' RHR has been placed in service for Shutdown Cooling with Reactor Coolant temperature at 125°F as read on Xl-36-101 TE-51-1N004A

2. 'OA' RHRSW pump is in service providing flow to '1 A' RHR Heat Exchanger
3. Reactor level is being maintained at 83" as read on Ll-42-1 R605 4. HV-C-51-103A, RHR Heat Exchanger Outlet Bypass (POS), is full open and additional cooling is required to maintain reactor coolant temperature within the 110°F to 130°F band 5. The Unit 1 Reactor Operator is performing ST-6-107-640-1, Rx Vessel Temperature and Pressure Monitoring INITIATING CUE: The CRS has directed you to continue performing 851.8.B at step number 4.4.30 to provide additional cooling to reactor coolant Page 10 of 10 " I ,, '

i .:=* Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE MAIN TURBINE BYPASS VALVE EXERCISING JPM Number: LOJPM3083 REVISION NUMBER: 000 DATE: __ _ Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Reviewed By: EP Representative Date Approved By: Training Department Date LOJPM3083 RevOOO.doc SRRS: 30.105 {When used for operator initial or continuing training) " I ,, Page 1 of 9 I Generation. Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is used, the task standard contains criteria for sucbessful completion.
9. Verify the procedure(s) referenced by this JPM reflects the current re\/ision:

Procedure ST-6-001-761-1 Rev: 28 -=.;:;.....___ Procedure _________ _ Rev: __ _ Procedure Rev: ---Procedure Rev: ---Procedure Rev: ---10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate : : 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM3083 RevOOO.doc SRRS: 30.105 Page 2 of 9 (When used for operator initial or continuing training)

J Generation II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the IL Tor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Perfornfance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision ' # Date of Number Description of Revision and Affect on Training Content. Revision 000 This JPM supersedes LLOJPM0083 Rev. 3. Revised to new template and to 10/31/16 align with latest procedure revision.

  1. Date of Revision -refers to date revision was released for approval ' LOJPM3083 RevOOO.doc SRRS: 30.105 Page 3 of 9 (When used for operator initial or continuing training)

,:::;:;' Exelon Generation 1-IV. TASK STANDARD: Bypass Valve #1 tested successfully as directed by ST-6-001-761-1, Main Turbine Bypass Valve Exercising V. SIMULATOR SETUP: 1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC. NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. VI. INITIAL CONDITIONS:

1. Unit 1 is at 99% power. 2. No other testing is in progress on Unit 1. " I ' 3. ST-6-001-761-1, Main Turbine Bypass Valve Exercising is complete up to section 4.3. VII. INITIATING CUE: You have been directed by the CRS to continue of ST-6-001-761-1, Main Turbine Bypass Valve Exercising.

'* LOJPM3083 RevOOO.doc SRRS: 30.105 Page 4 of 9 (When used for operator initial or continuing training) 1-=, Exelon Generation Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. LOJPM3083 RevOOO.doc " I ,, ,. SRRS: 30.105 (When used for operator initial or continuing training) Page 5 of 9 I .:Ii:' Exelon Generation VIII. PERFORMANCE CHECKLIST: JPM Start Time -----I-a: I-Zw ELEMENT STANDARD I-<( w Dl <( en :s :s en z :s :::::> :::::> Oz 0 1. Obtain M/U copy of ST-6-001-761-Candidate obtains M/U copy Main Turbine Bypass Valve of ST-6-001-761-Main Exercising Turbine Bypass Valve Exercising Test I CUE: Candidate is given M/U copy of ST-6-001-761-Main Turbine Bypass ;1 Valve Exercising

2. RECORD "AS FOUND" positions'of Positions of all valves listed in all valves listed in Attachment 1, Attachment 1 Independent Verification Of Restoration (IVOR). 3. VERIFY all 9 BPV's are closed. i All 9 BPV's are closed ' ,, 4. PERFORM the following for Bypass N/A Valve #1 4a. SELECT TESTS TESTS selected 4b. SELECT VALVE TESTS VAL VE TESTS selected 4c. SELECT BPV TESTS BPV TESTS selected
  • 4d. SELECT #1 BPV for test at the #1 BPV selected for test at VALVE TEST SELECTION window. the VAL VE TEST SELECTION window.
  • 4e. VERIFY the correct BPV selected #1 BPV selected for test is indicated on the test window LOJPM3083 RevOOO.doc SAAS: 30.105 Page 6 of 9 (When used for operator initial or continuing training)

Exelon Generation I-a: I-ZW ELEMENT STANDARD I-<( w cc <( U) :E :E en z :E ::> ::> Oz (J

  • 4f. DEPRESS OPEN TREND button, OPEN TREND button OR TREND all 9 BPVs. depressed
  • 4g. DEPRESS START button to initiate ST ART button depressed opening test 4h. DEPRESS PAUSE button if N/A necessary, AND THEN DEPRESS CONTINUE button to resume test
  • 4i. VERIFY #1 Bypass Valve opens Candidate verifies #1 Bypass AND recloses I Valve opens and recloses 4j. IF #1 BPV opened and fails Candidate verifies #1 Bypass to reclose, THEN SELECT CANCEL Valve opens and recloses AND VERIFY Bypass Valve Closes 4k. VERIFY BYPASS 1 VALVE OPEN 106 D-4, BYPASS VALVE annunciator on 106 MAIN STEAM OPEN, annunciator cleared. clears. 41. SAVE the Trend file, if required i N/A I ,, ' CUE: Saving the Trend file is not req'd 4m. IF trend file saved, THEN ENTER a comment in the Additional Action/Test Comments section N/A noting the file name AND location.

4n. WHEN plant conditions are stable, THEN PROCEED to next BYPASS N/A VALVE. CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM3083 RevOOO.doc SRRS: 30.105 Page 7 of 9 (When used for operator initial or continuing training) Exelon Generation JPM

SUMMARY

Operator's Name: _______________________ __.;;, Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: MAIN TURBINE BYPASS VALVE EXERCISING JPM Number: LOJPM3083 Revision Number: 000 Task Number and Title: 2480090201 Perform Bypass Valve Exercise Test KIA Number and Importance: 241000 A4.06 3.9/3.9 Safety Function (1-9) 3 (Reactor Pressure Control) Admin Category (A1-4) N/A Level of Difficulty (1-5) Suggested Testing Environment: Simulator Alternate Path:O Yes C8],No SRO Only: D Yes C8J No Time Critical: D Yes [8J No I Reference(s): ST-6-001-761-Main Turbine Bypass Valve Exercising, Rev28 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other I Testing Method: D Simulate [2J Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes 0 No I The operator's performance was evaluated against standards contained within this JPM and has been determined to be:. D Satisfactory D Unsatisfactory Evaluator's Name:-----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM3083 RevOOO.doc SRRS: 30.105 Page 8 of 9 (When used for operator initial or continuing training) ......,, ;..-;:?'" Exelon Generation. INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Unit 1 is at 99% power. 2. No other testing is in progress on Unit 1. 3. ST-6-001-761-1, Main Turbine Bypass Valve Exercising is complete up to section 4.3. INITIATING CUE: you have been directed by the CRS to continue performance of ST-6-001-761-1, Main Turbine Bypass Valve Exercising. " I ,, ,, Page 9 of 9 Exelon Generation. LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE SUPPLY RECW TO THE DRYWELL COOLERS JPM Number: LOJPM3028 REVISION NUMBER: 001 DATE: ___ _ Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Reviewed By: EP Representative Date Approved By: Training Department Date LOJPM3028 Rev001.doc SRRS: 30.105 (When used for operator initial or continuing training) ,, I ,, ' Page 1 of 9

  1. Exelon Generation 1-Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is used, the task standard contains criteria for completion.
9. Verify the procedure(s) referenced by this JPM reflects the current Procedure 813.6.D Rev: 15 """""""'"--

Procedure Rev: ---------- ---Procedure---------- Rev: __ _ Procedure

Rev: __ _ Procedure Rev: ---------- ---10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate : , 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. . 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM3028 Rev001.doc SAAS: 30.105 Page 2 of 9 (When used for operator initial or continuing training)

I ,:::; Exelon Generation II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change Change# Change Ill. REVISION HISTORY: ILT/LORT Approval ' i ! ,, I Action Revision Tracking Date A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all revisions, annotate the changes that were made or incorporated.

: Revision Description of Revision and Affect on Training Content # Date of Number Revision 000 This JPM replaces LLOJPM0028 Rev. 0. Revised to new template and to 10/15/13 align with latest procedure revision.

001 This SEG is revised to new 3/16 SEG format template, including any 08/05/16 procedure revisions.

  1. Date of Revision -refers to date revision was released for approval LOJPM3028 Rev001.doc SAAS: 30.105 Page 3 of 9 (When used for operator initial or continuing training)

Exelon Generation IV. TASK STANDARD: RECW aligned to Drywall Chilled Water. V. SIMULATOR SETUP INSTRUCTIONS: 1 . Reset simulator to IC-3 2. Trip '1 B' Drywall Chiller 3. Place HS-87-115 and HS-87-116 in BYPASS 4. Trip '1 A' RWCU Pump and close the HV-44-1 F001 and HV-44-1 F004 valves. 5. Build a trigger to toggle Remote Function RPC306 to CLOSE. VI. INITIAL CONDITIONS:

1. A manual scram was inserted due to rising Drywall
2. The CRS has entered OT-101, and T-102. 3. Drywall pressure is 4 psig and steady. 4. Drywall temperature is 160°F and steady. 5. The Drywell Chilled Water isolation has been bypassed and Chilled Water inlet and outlet valves have been re-opened.
6. '1 B' Drywell Chiller has tripped and '1A' Drywall unable to be started. ,, 7. Service Water is aligned to the RECW Heat Exchangers.
8. RWCU has been shutdown per S44.2.A, Reactor Water Cleanup Shutdown.
9. Administrative Clearances have been applied for valves in S13.6.D, section 4.2.4. 10. An EO is briefed and in the field with a copy of S13.6.D. VII. INITIATING CUE: Shift Supervision has directed you to supply RECW to the 'A' Drywall Chilled Water Loop per S13.6.D beginning at step 4.2.2.
  • Locked Valve Log entries have been authorized for required beaker closures LOJPM3028 Rev001.doc SRRS: 30.105 Page 4 of 9 (When used for operator initial or continuing training)

I $'Exelon Generation Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when thF candidate acknowledges the initiating cue. LOJPM3028 Rev001.doc ,, I ,, I' SRRS: 30.105 (When used for operator initial or continuing training) Page 5 of 9 j Generation VIII. PERFORMANCE CHECKLIST: JPM Start Time -----I-I-a: Zw ELEMENT STANDARD I-ct WIJJ ct en en z ::::> :J Oz (.) 1. Obtain a current revision of S13.6.D, RECW Candidate Operation With Loss of Drywell Chilled demonstrates ability Water. (actual or discuss) to locate the correct procedure. CUE: Candidate is given a copy of S13.6.D, RECW Operation With Loss of Dryrell Chilled Water. 1 2. SHUTDOWN RWCU system per S44.2.A, RWCU shutdown per I initial conditions Reactor Water Cleanup Shutdown. ' 3. CLOSE HV-13-*02, Cooling Water to Handswitch for HV-13-* Reactor Building Isolation (SUPPLY ISOL). 102 taken to close and valve verified to close I 4. IF loss of instrument air prohibits closure of HV-13-*02, SUPPLY ISOL, in step 4.2.2, THEN CLOSE 13-*039, "RECW Header Valve to RWCU Non-Regen Heat N/A Exchanger." 5. Block CLOSE the following sample point Candidate verifies isolation valves Information tags on:

  • HV 51 *FOBOA
  • HV 51 1F080A
  • HV 51 *FOBOB
  • HV 511F080B
  • HV 41 *F085
  • HV 41 1F085
  • HV 43 *F020
  • HV 431F020
  • 023-1246 CUE: After 1 minute And directs EO to report: EO reports 023-1246 is closed and info close and Info tag: tagged.
  • 023-1246 LOJPM3028 Rev001.doc SRRS: 30.105 Page 6 of 9 (When used for operator initial or continuing training)

Exelon Generation I-a: I-ZW ELEMENT STANDARD <C w al en :!:: :!:: en z :!:: ::::> ::::> Oz (.) EVALUATORS NOTE: When operator requests the breakers in the following step to be closed, activate trigger associated with remote function RPC306 to close the breakers.

6. UNLOCK AND CLOSE the following Candidate directs EO breakers:

to close following

  • breakers:
  • 0*14-R-C-15 (124A) 0114-R-C-15
  • 0*14-R-C-19 (1248) 0114-R-C-19
  • 0*14-R-C-16 (125A) 0114-R-C-16
  • 0*14-R-C-20 (1258) 0114-R-C-20
  • CUE: After confirmation of 124A(8) and 125A(8) c1dsed (Trigger 1 activated) report the following breakers closed:
  • 0114-R-C-15
  • 0114-R-C-19
  • 0114-R-C-16
  • 0114-R-C-20
7. ENSURE indication for the valves is Indication (Green received in MCR Lights) received for I 124A(8) and 125A(8) ' ,, 8. IF requil-ed THEN BYPASS isolations per N/A GP-8.5 ..
  • 9. PLACE HSS-87-*21A(8), Loop Drywall HSS-87-121A in RE Water Source Mode Switch (LOOP), in "RE CLG WTR placed CLG WTR" for loop to be supplied by position for LOOP A. RECW AND VERIFY the following:

9a. Red indicating lights RECW IN RECW IN and OUT AND RECW OUT lit. red lights verified lit 9b. Green indicating lights CHLO WTR IN CHLO WTR IN and AND CHLO WTR OUT lit. OUT green lights verified lit CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM3028 Rev001.doc SRRS: 30.105 Page 7 of 9 (When used for operator initial or continuing training) 1-,:::;!/ Exelon Generation JPM

SUMMARY

Operator's Name: _______________________ __... Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: SUPPLY RECW TO THE DRYWELL COOLERS JPM Number: LOJPM3028 Revision Number: 001 Task Number and Title: 2080040401, Line Up RECW System to Supply Drywell Chilled Water System KIA Number and Importance: 400000 A2.01 3.3/3.4 Safety Function (1-9) 5 (Containment Control) Admin Category (A1-4) N/A Level of Difficulty (1-5) _L Suggested Testing Environment: Simulator Alternate Path:D 1Z! No SRO Only: D Yes 1Z! No Time Critical: D Yes IZ! No Reference(s): S13.6.D, RECW Operation With Loss Of Drywell Chilled Water, Rev. 15 ,, I Actual Testing Environment: D Simulator D Control Room D In-Plant D Other ' Testing Method: D Simulate D Pertorm Estimated Time to Complete: 15 minutes Actual Time Used: minutes I EVALUATION

SUMMARY

Were all the Critical':Elements performed satisfactorily?

D Yes D No The operator's pertormance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Evaluator's Name:-----------------(Print) Evaluator's Signature: ______________ _ Date: ___ _ LOJPM3028 Rev001.doc SRRS: 30.105 Page 8 of 9 (When used for operator initial or continuing training) " I ,, =;;/ Exelon Generation, LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. 2. 3. 4. 5. 6. 7. 8. A manual scram was inserted due to rising Drywell pressure.

The CRS has entered OT-101, and T-102. Drywell pressure is 4 psig and steady. Drywell temperature is 160°F and steady. The Drywell Chilled Water isolation has been bypassed and Chilled Water inlet and outlet valves have been re-opened. '1 B' Drywell Chiller has tripped and '1A' Drywell Chiller is unable to be started. Service Water is aligned to the RECW Heat Exchangers. RWCU has been shutdown per 844.2.A, Reactor Water Cleanup Shutdown.

9. Administrative Clearances have been applied for valves in S13.6.D, section 4.2.4. 10.An EO is briefed and in the field with a copy of 813.6.D. INITIATING CUE: Shift Supervision has directed you to supply RECW to the 'A' Drywell Chilled Water Loop per 813.6.D beginning at step 4.2.2.
  • Locked Valve Log entries have been authorized for required beaker closures Page 9 of 9 " I ,, '

Exelon Generation. LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE DIESEL GENERATOR FAST START FROM THE MCR JPM Number: LOJPM3130 REVISION NUMBER: 003 DATE: __ _ Developed By: Instructor Validated By: SME or Instructor Reviewed By: Operations Representative Reviewed By: N/A EP Representative Approved By: Training Department LOJPM3130 Rev003.doc SRRS: 30.105 (When used for operator initial or continuing training) " I Date Date N/A Date Date Page 1 of 11 I*,::**":' Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is used, the task standard contains criteria successful completion.
  • 9. Verify the procedure(s) referenced by this JPM reflects the current revision:

I Procedure ST-6-092-318-1 Rev: 55 Procedure 892.2.N Rev: 34 ..=.....;.. __ Procedure ARC MCA 123 014 D-1 Procedure ARC BOP 1DC514 D-1 Procedure----------

10. Verify cues both verbal and visual are free of conflict.

Rev: O ------Rev: 2 -=---Rev: __ _ 11. Verify performance time is accurate : : 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM3130 Rev003.doc SRRS: 30.105 Page 2 of 11 (When used for operator initial or continuing training) I; Exelon Generation II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately Indicate how the training content of the Revision has changed. C. The description of the Revision should also include; 'previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisio,ns, annotate the changes that were made or incorporated. Revision Description of Revision and Affect on Training Content # Date of Number Revision This JPM replaces LLOJPM0130 Rev. 2. Revised to new template and 10/17/13 000 to align with latest procedure revision. C.hanged from D11 D/G to D14 DIG. ,, , , 001 Revised to align with latest procedure re'visions. Deleted Low Jacket 1/17/13 Water Pressure indication from EO field report. Previous revision included both High Jacket Water Temperature indication as well as Low Jacket Water Pressure but did not include any indication of a leak. High Jacket Water Temperature alone is an appropriate reason to secure the Diesel Generator with actual temperature greater than the auto trip setpoint of 195 degrees F. 002 Revised to align with the latest procedure revisions. 10/11/15 003 Aligned to new JPM format and verified procedure revisions and 10/24/16 changed alarm condition to Lube Oil Filter dP High. #Date of Revision -refers to date revision was released for approval LOJPM3130 Rev003.doc SRRS: 30.105 Page 3 of 11 (When used for operator initial or continuing training)

Exelon Generation. IV. TASK STANDARD: 014 DG is synchronized to the bus and secured from service following high Lube Oil Filter Differential Pressure. V. SIMULATOR SETUP INSTRUCTIONS:

1. This JPM can be run from any Simulator IC. 2. Build trigger to activate 30 seconds after 014 DG 200 KVAR to toggle Annunciator 123 D-1, 014 D-G TROUBLE, to ON. NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
3. Start 014 EOG 4. Insert Remote RSW397, "ESW Loop 8 Service;Water Isolated?" 5. Change Service Water Placards for 11-1013 arid 11-2013 to indicate closed VI. INITIAL CONDITIONS:
1. ST-6-092-318-1, 014 Diesel Generator Fast Operability Test Run, is complete up to and including Step 4.5.14. '* 2. An Equipment Operator is standing by at 014 DIG to support Diesel Generator operation.

VII. INITIATING CUES: You are directed by the CRS to continue with ST-6-092-318-1, 014 Diesel Generator Fast Start Operability Test Run. LOJPM3130 Rev003.doc SRRS: 30.105 Page 4 of 11 (When used for operator initial or continuing training)

Generation. Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examines had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock when the candidate acknowledges the initiating cue. LOJPM3130 Rev003.doc ,, 1 ,, SRRS: 3D.105 (When used for operator initial or continuing training) Page 5 of 11 ,:::' Exelon Generation 1-VIII. PERFORMANCE CHECKLIST: JPM Start Time -----I-a: I-ZW ELEMENT STANDARD I-<C w Ill <C tn :e :e en z :e ::> ::> Oz 0 1. Provide the candidate with a marked up N/A copy of ST-6-092-318-1 completed up to and including Step 4.5.14

  • 2. PLACE DIESEL GEN 14, 125-11807

/SS, SYNC, to "ON, 11 using Sync Switch handle, DIESEL GEN 14, at Panel 1 DC661 ' SYNC, placed to "ON, 11 using Sync Switch " handle, at Panel I 1 DC661 3. VERIFY Synchroscope is rotating with Synch roscope S/EAS-both lights Lit fully bright at 180° 4 verified rotating with AND not Lit at 0° both lights Lit fully bright at 180° I AND not Lit at 0° 4. OBSERVE change iri' DIG frequency by 165-DG501 /CS rotated placing 165-DG501/CS, SPEED to "RAISE," F/DG501-2 GOVERNOR, to "RAISE" (HERTZ) rises. AND to "LOWER 165-DG501/CS rotated to "LOWER," F/DG501-2 (HERTZ) lowers 5. OBSERVE change in D/G voltage by 170-DG502/CS rotated placing to "RAISE," V/1-EAS-4 170-DG502/CS, VOLTAGE REGULATOR, (INCOMING) rises. to "RAISE," 170-DG502/CS rotated AND to "LOWER." to "LOWER," V/1-EAS-4 (INCOMING) lowers LOJPM3130 Rev003.doc SRRS: 30.105 Page 6 of 11 (When used for operator initial or continuing training) I =* Exelon Generation. I-a: I-ZW ELEMENT STANDARD I-<( w a::i <( en :E :E en z :E :l :l Oz (..)

  • 6. ADJUST 165-DG501/CS, SPEED 165-DG501

/CS, GOVERNOR, so Synchroscope is rotating SPEED GOVERNOR slowly in FAST (CW) direction adjusted so that Synchroscope S/EAS-4 is rotating slowly in FAST direction

  • 7. ADJUST 170-DG502/CS, VOLTAGE 170-DG502/CS, REGULATOR, so INCOMING Voltage is VOLTAGE slightly higher than RUNNING Voltage REGULATOR, I adjusted so that V /1-EAS-4 (INCOMING) indicates between 0 to " 5 volts greater than I V/R-EAS-4 I
  • 8. WHEN Synchroscope is within 3° before 12 D14 DG Output o'clock position rotating slowly in FAST Breaker closed (CW) direction, THEN CLOSE 152-11807/CS I GENERATOR Breaker, at Panel 1 DC661 ,, '9. Immediately RAISE load to 200 to 300 KW 165-DG501/CS, by placing 165-DG501/CS, SPEED SPEED GOVERNOR, GOVERNOR, to "RAISE." rotated to "RAISE until W/DG501-2 (AC KILOWATTS) indicates between 200 to 300 KW 10. RAISE reactive load to 100 to 150 KVAR 170-DG502/CS, by placing VOLTAGE 170-DG502/CS, VOLTAGE REGULATOR, REGULATOR, rotated to "RAISE." to "RAISE" until VAR/DG5012 (AC KILOVARS) indicates between 100 to 150 KVAR LOJPM3130 Rev003.doc SRRS: 30.105 Page 7 of 11 (When used for operator initial or continuing training)

=' Exelon Generation. 1-I-I-a: ZW ELEMENT STANDARD I-ct WIII ct en == :as en z :as ::> ::> Oz 0 11. PLACE 125-11807/SS, DIESEL GEN 14, 125-11807 /SS, SYNC, to "OFF" DIESEL GEN 14, SYNC, placed in "OFF." EVALUATORS NOTE: 30 seconds after D14 DIG Reactive Load exceeds 200 KVAR, "014 D-G TROUBLE" will alarm and the alternate path will begin. 12. RESPOND to ARC-MCR-123 D14 D1, Annunciator reported "D14 D-G TROUBLE" to CRS 12a. REFER to ARC-MCR-123 D14 D-1, D14 ARC-MCR-123 D14 '1 D-G TROUBLE D-1, "D14 D-G TROUBLE" referenced "

  • 12b. DISPATCH Equipment Operator to DISPATCH Equipment I investigate Trouble Alarm Operator to investigate Trouble Alarm CUE: Equipment Operator reports local alarm is Lube Oil Filter Differential Pressure Hi, ARC-BOP-1DC514 D1. Current FilterdP Is 16 psid ,UP SLOW I 1.3. DETERMINE D14 DG should be shutdown Review ARC and with the given filter dP condition.

execute Operator Action #2, "IF engine is under test, THEN shutdown engine AND investigate cause of high filter dP ." EVALUATORS NOTE: The following steps may be performed from memory or by performing S92.2.N, Shutdown of Diesel Generators, Section 4.2, Rapid Shutdown Due To Alarm Or Abnormal Condition. 13a. PLACE Diesel Generator Breaker to Diesel Generator "TRIP" Breaker placed to AND "PULL-TO-LOCK" "TRIP" AND "PULL-TO-LOCK" LOJPM3130 Rev003.doc SRRS: 30.105 Page 8 of 11 (When used for operator initial or continuing training) I ,:;;;' Exelon Generation. ELEMENT STANDARD

  • 13b. PLACE Diesel Generator Control Switch Diesel Generator 101-DG501/CS to "STOP" Control Switch 101-AND "PULL-TO-LOCK" DG501/CS placed to "STOP" AND "PULL-TO-LOCK" CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM3130 Rev003.doc SRRS: 30.105 (When used for operator initial or continuing training)

I-<( en " I ,, ' I-<( en z :::> Page 9 of 11 I-c: ZW w Ol == == == :::> Oz 0 I ;;:f:!:""':r Exelon Generation JPM

SUMMARY

Operator's Name: _______________________ __;. Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: DIESEL GENERATOR FAST START FROM THE MCR JPM Number: LOJPM3130 Revision Number: 003 Task Number and Title: TP0-2640020101 Manually Startup, Load and monitor a Diesel Generator KIA Number and Importance: 264000 A4.04 3.7/3.7 Safety Function (1-9) 6 (Electrical) Admin Category (A1-4) N/A Level of Difficulty (1-5) _L Suggested Testing Environment: Simulator Alternate Path:[8J Yes D No SRO Only: D Yes [8J No Time Critical: D Yes l:EJ No Reference(s): ST-6-092-318-1 D14 Diesel Generator Fast Start Operability Test Run, Rev. SS S92.2.N, Shutdown of Diesel Generators Rev. 34 ., ARC MCR 123 D14 D-1, D14 D-G Trouble, Rev 0 I ARC BOP 1DC514 D-1, Lube Oil Filter Differential Pressure High, Rev 2 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate [8J Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes ,, D No.' The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Evaluator's Name:----------------(Print) Evaluator's Signature: ______________ _ Date: ---LOJPM3130 Rev003.doc SRRS: 30.105 Page 10 of 11 (When used for operator initial or continuing training)

  • =t" Exelon Generation, INITIAL CONDITIONS:

LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. ST-6-092-318-1, 014 Diesel Generator Fast Start Operability Test Run, is complete up to and including Step 4.5.14. 2. An Equipment Operator is standing by at 014 DG to support Diesel Generator operation. INITIATING CUE STATEMENT: I You are directed by the CRS to continue with ST , D 14 Diesel Generator Fast Start Operability Test Run. " ' ,, I' Page 11 of 11 I= Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE PLACING SAFEGUARD PIPING FILL SYSTEM IN SERVICE Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LOJPM3118 RevOOO.doc JPM Number: LOJPM3118 REVISION NUMBER: 000 " I ,, DATE: __ _ Instructor SME or Instructor Operations Representative EP Representative Training Department SRRS: 30. 105 (When used for operator initial or continuing training) Date Date Date Date Date Page 1 of 9 I .=:. Exelon Generation. Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is uded, the task standard contains criteria for successful completion.
9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure 852.1.C Rev: 11 Procedure Rev: ---Procedure Rev: ---Procedure Rev: ---Procedure Rev: __ _ 1 O. Verify cues both verbal and visual are free of conflict.

11. Verify performance is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date I LOJPM3118 RevOOO.doc SRRS: 30.105 Page 2 of 9 (When used for operator initial or continuing training)

Exelon Generation. II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision* Description of Revision and Affect on Training Content # Date of Number** Revision 000 This is a New JPM 08/15/16 # Date of Revision -refers to date revision was released for approval LOJPM3118 RevOOO.doc SRRS: 30.105 Page 3 of 9 (When used for operator initial or continuing training) -=w Exelon Generation 1-IV. TASK STANDARD: Safeguard Piping Fill System in service with both Fill Pumps and feedwater lines filled V. SIMULATOR SETUP 1. Reset the simulator to an IC that does not require feedwater in service, or an IC if JPM was validated in the respective IC. NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Initiate Loss Of Offsite Power MED261 3. Ensure all Diesels are running I i VI.

CONDITIONS: I 1. A LOCA/LOOP condition occurred 30 minutes ago. 2. SE-10, LOCA is in progress 3. S52.1.C prerequisites have been performed ,, I VII. INITIATING CUE: Shift Supervision directs you to place the Safeguard Piping Fill System in service per S52.1.C, "Operation of Safeguard Piping Fill System" to fill the Feedwater Lines. LOJPM3118 RevOOO.doc SAAS: 30.105 Page 4 of 9 (When used for operator initial or continuing training) Exelon Generation Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cui. LOJPM3118 RevOOO.doc SAAS: 3D.105 (When used for operator initial or continuing training)

  • i I ,, I' Page 5 of 9

,, ' Exelon Generation VIII. PERFORMANCE CHECKLIST: JPM Start Time -----ELEMENT STANDARD 1. Obtain current revision of M/U Candidate reviews M/U copy S52.1.C, Operation of Safeguard of S52.1 .C, Operation of Piping Fill System. Safeguard Piping Fill System. CUE: Candidate is given a copy of S52.1.C, Operation of Safeguard Piping Fill System with prerequisites completed.

2. VERIFY all prerequisites satisfied Prerequisites verified complete.
3. VERIFY procedure being performed Candidate verifies procedure on correct unit/train being performed on correct unit/train
4. IF required PERFORM S52.1.C (COL), Equipment Alignment For N/A Safeguard Fill System For Operation.

CUE: S52.1.C(COL) is not required

  • 5. ENSURE the following Core Spray Core Spray Pump Supp Pool Pump Supp Pool Suet valves are Suction valves HV-52-open: 1 F001A thru 1 F001 Dare opened. (Red Light)
  • HV-52-1 F001A
  • HV-52-1 F001 B
  • HV-52-1 F001C
  • HV-52-1 F001 D LOJPM3118 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training)

I-a: .... ZW I-<( w al <( (J) (J) z :::> :::::> Oz (.) I I ' ' : Page 6 of 9 Exelon Generation ELEMENT STANDARD 6. ST ART the following pumps. N/A

  • 6a. 1 AP256, "Fill Pump A" Fill Pump A started (Red Light)
  • 6b. 18P256, "Fill Pump 8" Fill Pump 8 started (Red Light)
  • 7. IF system is required to fill the Safeguard Piping PCIVs open feedwater lines, THEN OPEN the
  • HV-41-130A following valves; as appropriate:

HV-41-130A

  • HV-41-1308
  • HV-41-1308
  • HV-41-133A
  • HV-41-133A
  • HV-41-1338
  • " I
  • HV-41-1338 CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM3118 RevOOO.doc SRRS: 30.105 (When used for operator initial or continuing training)

,, I-I-<C <C en en z :::> Page 7 of 9 --I-a: ZW w Dl :E :E :E ::J Oz 0

Exelon Generation. 1-JPM

SUMMARY

Operator's Name: _______________________ _ Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: PLACING SAFEGUARD PIPING FILL SYSTEM IN SERVICE JPM Number: LOJPM3118 Revision Number: 000 Task Number and Title: 2000950501 (SE-10) Actions After a LOCA Signal KIA Number and Importance: 290001 K3.01 4.0/4.1 Safety Function (1-9) 5 (Containment Integrity) Admin Category (A1-4) N/A Level of Difficulty (1-5) 3 Suggested Testing Environment: Simulator Alternate Path:D Yes C8J No SRO Only: D Yes C8J No Time Critical: D Yes C8J No Reference(s): S52.1.C, Operation of Safeguard Piping Fill System 1 Rev011 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other I Testing Method: D Simulate D Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes I D No ' The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory

  • . Evaluator's Name:----------------(Print) Evaluator's Signature:

______________ _ Date: ------LOJPM3118 RevOOO.doc SRRS: 30.105 Page 8 of 9 (When used for operator initial or continuing training)

,,y ExelonGeneration, INITIAL CONDITIONS:

LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. A LOCA/LOOP condition occurred 30 minutes ago. 2. SE-10, LOCA is in progress 3. S52.1.C prerequisites have been performed INITIATING CUE: " I Shift Supervision directs you to place the Safeguard Piping Fill System in service per S52.1.C, "Operation of Safeguard Piping Fill System" to fill the Feedwater Lines. ,, 1 Page 9 of 9 1,$ ExelonGeneration LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE T-239 DEFEATING HIGH RPV LEVEL INTERLOCKS Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LOJPM2273 RevOOO.doc ,, I .. ' JPM Number: LOJPM2273 REVISION NUMBER: 000 DATE: __ _ Instructor SME or Instructor Operations Representative EP Representative Training Department SRRS: 30.105 (When used for operator initial or continuing training) Date Date Date Date Date Page 1 of 10 I .=:' Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an path is used, the task standard contains criteria for successful completion.
9. Verify the;procedure(s) referenced by this JPM reflects the current revision:

Procedure T-239 U/1 Rev: 0 ---Procedure T-239 U/2 Rev: 0 Procedure Rev: Procedure Rev: Procedure Rev: 1 O. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate 12. If the JPM.cannot be performed as written with proper responses, then revise the JPM. . 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date I LOJPM2273 RevOOO.doc SRRS: 30.105 Page 2 of 10 (When used for operator initial or continuing training)

I ,::::;c Exelon Generation. II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: ,; 1 A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the ;* ,, revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision Description of Revision and Affect on Training Content # Date of* Number Revision** 000 This is a New JPM 11/01/16 # Date of Revision -refers to date revision was released for approval LOJPM2273 RevOOO.doc SRRS: 30.105 Page 3 of 10 (When used for operator initial or continuing training) I S" Exelon Generation IV. TASK STANDARD: The high RPV level interlocks defeated for the Unit __ 'B' RFPT, and the HPCI system per T-239, Defeating RFPT, HPCI and RCIC High RPV Level Interlocks, completed sat. V. SIMULATOR SETUP 1. None VI. INITIAL CONDITIONS:

1. Unit RPV level cannot be determined 2! RPV flooding is required I ,, I VII. INITIATING CUE: Shift Supervision directs you to defeat the high RPV level interlocks on Unit_ for the '_B' RFPT, and the HPCI system per T-239, "Defeating RFPT, HPCI and RCIC High RPV Level Interlocks." ,, LOJPM2273 RevOOO.doc SAAS: 30.105 Page 4 of 10 (When used for operator initial or continuing training) 1.= ExelonGeneration.

Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examines had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowlidges the initiating cue. LOJPM2273 RevOOO.doc SRRS: 30.105 ,j I ,, (When used for operator initial or continuing training) Page 5 of 10 Exelon Generation VIII. PERFORMANCE CHECKLIST: JPM Start Time ____ _ ELEMENT STANDARD Forln-Plant T-200 JPMs, include the following: NOTE: IF this JPM is the first of multiple T-200 series JPMs being performed by a single candidate THEN steps #1 and #2 apply., OTHERWISE mark steps #1 and #2 as NIA AND provide the folfowirig to the candidate

a. INITIATING CUE(S) b. CUE: "You are now in possession of the T-239 equipment container.

It contains all tools and equipment required by the procedure. You are to simulate their use during performance of the procedure." PROCEDURE COPY 1. Obtain current revision of T-239, Defeating RFPT, HPCI and RCIC High RPV Level Interlocks for Unit# __ .* CUE: Candidate is given a copy of T-239, Defeating RFPT, HPCI and RCIC High RPV Level Interlocks, when knowledge of the correct location of procedure is demonstrated. Candidate demonstrates ability (actual or discuss) to locate T-239, Defeating RFPT, HPCI and RCIC High RPV Level Interlocks.

2. Obtain required tools. Tools obtained.
  • Insulated screwdriver
  • Holding screwdriver
  • Flashlight
  • Roll of electrical tape CUE: You have tools identified.

LOJPM2273 RevOOO.doc SRRS: 3D.105 (When used for operator initial or continuing training) ,, ,. Page 6 of 10 I =, Exelon Generation. I-a: I-ZW ELEMENT STANDARD I-<( w Dl <( en :ii: :ii: en z :ii: :::> ::::> Oz 0

  • 3. PERFORM the following at panel Lead from FFF5-3 lifted and *C612, Bay A (AER) to defeat high tapped. RPV level trip of "*B" RFPT (ATTACHMENT 1).
  • LIFT
  • AND TAPE lead connected to FFF5-3 CUE: Lead from FFF5-3 lifted and tapped. I I 4. WHEN the respective RFPT high MCR notified the '*B' RFPT RPV level trip(s) defeated is high level trip defeated per T-complete, THEN NOTIFY Main' 239. Control Room. '
  • 5. PERFORM the following at panel Lead from FFF5-2 lifted and *C620, (AER) (ATTACHMENT 2). tapped.
  • LIFT
  • AND TAPE lead connected to FFF5-2 ' ,, ,, CUE: Lead from FFF5-2 lifted and tapped. 6. At Panel *OC647, PRESS E41A-E41 A-S25, "RPV High Water S25, "RPV High Water Level" (Rx Level" Reset Pushbutton LEVEL HIGH RESET) Reset depressed and white Rx Pushbutton AND VERIFY white Rx LEVEL HIGH RESET light LEVEL HIGH RESET light not Lit. not Lit. CUE: PRO reports "E41 A-S25, RPV High Water Level" reset pushbutton and white Rx LEVEL HIGH RESET light not Lit. I LOJPM2273 RevOOO.doc SRRS: 30.105 Page 7 of 10 {When used for operator initial or continuing training)

I ..:::i::f Exelon Generation. ELEMENT STANDARD 7. At Panel *OC647, VERIFY HPCI D837 status light not lit at TURB TRIP 180L ENERGIZED panel *OC64 7 D837 status light not lit CUE: PRO reports "HPCI TURB TRIP 180L ENERGIZED D837 status light not lit" 8. WHEN the HPCI high RPV level trip MCR notified HPCI high level is defeat is complete, THEN NOTIFY trip defeated per T-239 Main Control Room. *,, CUE: You have met the termination criteria forthis, 1 JPM JPM Completion Time ____ _ LOJPM2273 RevOOO.doc ,, ,, SRRS: 30.105 {When used for operator initial or continuing training) I-a: I-ZW I-<( Wal <( en :s :s en z :s ::::> ::::> Oz 0 Page 8 of 10 1.= ExelonGeneration .. JPM

SUMMARY

Operator's Name: _______________________ _ Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: T-239 DEFEATING HIGH RPV LEVEL INTERLOCKS JPM Number: LOJPM2273 Revision Number: 000 Task Number and Title: 2001340401 (T-239) Defeat the RFP, HPCI, RCIC high level trips KIA Number and Importance: 259002 A4.11 3.5/3.3 Safety Function (1-9) 2 (Reactor Water Inventory Control) Admin Category (A1-4) N/A Level of Difficulty (1-5) Suggested Testing Environment: In-Plant Alternate Pfth:D Yes 0No SRO Only:D Yes [gl No Time Critical: D Yes [gl No Reference(s): T-239 U/1, Defeating RFPT, HPCI and RCIC High RPV Level Interlocks Rev 0 .: T-239 U/2, Defeating RFPT, HPCI and RCIC High RPV Level Interlocks Rev 0 ' Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate D Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all Elements performed satisfactorily?

D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Evaluator's Name:----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM2273 RevOOO.doc SRRS: 30.105 Page 9 of 10 (When used for operator initial or continuing training) Exelon Generation, INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Unit RPV level cannot be determined

2. RPV flooding is required INITIATING CUE: Shift Supervision directs you to defeat the high RPV level interlocks on Unit _for the '_B' RFPT, andl the HPCI system per T-239, "Defeating RFPT, HPCI and RCIC High RPV Level Interlocks." " I ,, I Page 10 of 10 1-,::::/ Exelon Generation Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LOJPM2119 RevOOO.doc LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE RESET RDCS JPM Number: LOJPM2119 REVISION NUMBER: 000 DATE: __ _ Instructor SME or Instructor Operations Representative EP Representative Training Department SRRS: 30.105 (When used for operator initial or continuing training)

Date Date Date Date Date " I ,, Page 1 of 11

Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate path is used, the task standard contains criteria for successful completion.

,, 9. Verify the procedure(s) referenced by this JPM reflects the current revision: " I I Procedure 873.0.F Rev: 17 Procedure 873.0.E Rev: 18 Procedure Rev: Procedure Rev: Procedure Rev: 10. Verify cues both verbal and visual are free of conflict. ,, 11. Verify performance time is accurate ,, 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM2119 RevOOO.doc SRRS: 30.105 Page 2 of 11 (When used for operator initial or continuing training)

Generation. II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If a Revision affects a Task Performande from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should, adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision # Date of Number Description of Revision and Affect on Training Content Revision 000 This is a New LOJPM 08/10/16 # Date of Revision -refers to date revis,ion was released for approval LOJPM2119 RevOOO.doc SRRS: 30.105 Page 3 of 11 (When used for operator initial or continuing training) I Generation, IV. TASK STANDARD: Unit _Control Rod 18-31 bypassed from RMCS, and RDCS is reset V. SIMULATOR SETUP 1. None VI. INITIAL CONDITIONS: 1 . Unit _Control Rod 18-31 has drifted out 2. Unit _Control Rod 18-31 was fully inserted, and isolated.

3. Tech Spec 3.1.3.1 has been referenced
4. Unit _Control Rod 18-31 was declared INOP 5. 'RDCS INOP' alarm on ARC MCR *08 E-4 has annunciated

,; I 6. The LED for Unit _HCU 18-31 on The Rod Drive Control System Analyzer -Fault Location Map is lit VII. INITIATING CUE: I Shift supervision directs you to reset Unit _RDCS in accordan,ce with S73.0.F, Operation of the Rod Drive Control System. : : LOJPM2119 RevOOO.doc SRRS: 30.105 Page 4 of 11 (When used for operator initial or continuing training) \ ,:}::.':/Exelon Generation Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item tq be performed. ' The JPM Start Time clock starts when the candidate acknowledges the initiating cue. I ., I ,, LOJPM2119 RevOOO.doc SRRS: 30.105 Page 5 of 11 (When used for operator initial or continuing training) 1-,:;;.:c Exelon Generation VIII. PERFORMANCE CHECKLIST: JPM Start Time -----I-cc I-ZW ELEMENT STANDARD I-<( Wm <( (/'J ::!!: ::!!: (/'J z ::!!: :::> :::> Oz 0 1. Obtain current revision of S73.0.F, Candidate demonstrates Operation Of The Rod Drive Control ability (actual or discuss) to System. locate S73.0.F I CUE: Candidate is given a !1 copy of S73.0.F, Operation Of The Rod Drive Control System when of the correct location of procedure is demonstrated. ' 2. Reference section 4.3 'RDCS Section 4.3 'RDCS RESET' of RESET' of S73.0.F, Operation Of The S73.0.F referenced Rod Drive Control System. 3. [S73.0.F 4.3. 1] IF immediate reset of RDCS is required as determined by Shift Supervision THEN;MARK NIA for steps 4.3.2 and 4.3.1 NIA CUE: Immediate reset of RDCS is required 4. {S73.0.F 4.3.3} ENSURE RO has logged RDCS I NOP NIA CUE: RO has logged RDCS INOP 5. {S73.0.F 4.3.4] OBTAIN CRS permission to reset RDCS NIA (given in Initiating Cue) CUE: Permission given in Initiating Cue. LOJPM2119 RevOOO.doc SRRS: 30.105 Page 6 of 11 (When used for operator initial or continuing training) ,, I ,, Exelon Generation. ELEMENT STANDARD

  • 6. {S73.0.F 4.3.5] DEPRESS RESET for RESET depressed for at least at least two seconds two seconds Evaluator Note: Alternate Path begins with the next step. 7. {S73.0.F 4.3.6] IF RDCS Candidate verifies RDCS INOPERATIVE will not clear THEN inoperative LED remains lit PERFORM the following:

CUE: RDC8 Inoperative LED remains lit and the LED for HCU 18-31 on The Fault Location Map remains lit 7a. {S73.0.F 4.3.6.1] CONTACT l&C for l&C contacted troubleshooting 7b. {S73.0.F 4.3.6.2]CONSIDER Candidate recommends performing 873.0.E, Bypassing/ Un-bypassing Control Rod 18-31 bypassing a Control Rod from the from the Reactor Manual Reactor Manual Control System. Control System. CUE: As 88VN, request candidates recommendation on how to proceed, then agree with their recommendation.

8. Candidate obtains 73.0.E, Candidate obtains copy of Bypassing/Unbypassing a Control 873.0.E. Rod from the Reactor Manual Control System CUE: Candidate is given a copy of S73.0.E, Bypassing/Unbypassing a Control Rod from the Reactor Manual Control System. LOJPM2119 RevOOO.doc SRRS: 3D.105 (When used for operator initial or continuing training)

I-0: I-Zw I-<C w cc <C en :E :E CJ) z :E :::> :::> Oz 0 I ,, ' i ' ,, ' Page 7 of 11 I Exelon Generation " I ,, ,, I-I-er: ZW ELEMENT STANDARD I-<C W CD <C en := := en z := ::::> ::::> Oz 0 EVALUATORS NOTE: Per S73.0.E, Bypassing/Unbypassing a Control Rod from the Reactor Manual Control System, Bypassed Rod Identity switches are labeled X4, X3, X2, X1, XO and Y 4, Y3, Y2, Y1, YO. A switch in UP position corresponds to '1 ', and DOWN position corresponds to 'O' 9. [S73.0.E 4.2.1] REFER TO S73.0.E, Binary coordinates for control

  • Attachment 1 AND PLACE BYPASSED rod 18-31 identified as: ROD INENTITY switches in position x = 00110 y = 01001 corresponding to binary coordinates for Switches aligned: Control Rod 18-31 at *OC616. X4, down Y4, down X3, down Y3,up CUE: Switches X2, X1, Y3, YO are in X2,up Y2, down UP position, and remaining switches are X1, up Y1, down in the down position.

XO, down YO, up 10. [S73.0.E 4.2.2] OBTAIN SSV SSV permission requested to Permission to bypass the Rod bypass Control Rod 18-31 . CUE: SSV has granted permission for Control Rod Bypass. 11. [S73.0.E 4.2.3] PLACE BYPASSED BYPASSED Switch in UP

  • Switch in UP in position at *OC616 position panel. CUE: Switch is in the Up Position
  • 12.[S73.0.E 4.2.4JIF RDCS is INOP, as "RESET" pushbutton in indicated by "INOPERABLE" LED Lit RDCS STATUS section of on RDCS Status section at *OC616 analyzer card for several THEN DEPRESS "RESET" seconds AND RELEASE. pushbutton in RDCS STATUS section of analyzer card for several seconds AND RELEASE. CUE: RDCS INOP LED and HCU 18-31 LED light both extinguish LOJPM2119 RevOOO.doc SRRS: 30.105 Page 8 of 11 (When used for operator initial or continuing training)

' : Exelon Generation. ELEMENT STANDARD 13. [S73.0.E 4.2.5] VERIFY ROD Request from MGR status of BYPASS light Lit on the RDCS ROD BYPASS light Lit on the STATUS section of the ROD RDCS STATUS section of the SELECT MODULE at *OC603 panel ROD SELECT MODULE at *OC603 panel CUE: The RO reports, "The ROD BYPASS light is lit on the *OC603 "Reactor Control Console." 14. [S73.0.E 4.2.5] VERIFY RDCS Candidate calls MGR to verify INOPERATIVE annunciator clear on RDCS INOPERATIVE

  • 08 REACTOR (E-4) , annunciator clear on *08 REACTOR (E-4) f'\ CUE: You have'met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM2119 RevOOO.doc

,, I' SRRS: 30.105 (When used for operator initial or continuing training) I-c: I-ZW I-<C w co <( en :iE :iE en z :iE ::::> ::> Oz u Page 9 of 11 I$ Exelon Generation. JPM

SUMMARY

Operator's Name: _______________________ _ Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: RESET RDCS JPM Number: LOJPM2119 Revision Number: 000 Task Number and Title: 2140050401, Bypass A ROD From RMCS KIA Number and Importance: 201002 K3.01 3.4/3.4 Safety Function (1-9) 1 (Reactivity Control) Admin Category (A1-4) N/A Level of Difficulty (1-5) 3 Suggested Testing Environment: In-Plant Alternate Path:IZI Yes D No SRO Only: D Yes IZI No Time D Yes IZI No Reference(s): S73.0.F, Operation Of The Rod Drive Control System, 17 S73.0.E, Bypassing/Unbypassing a Control Rod from Reactor Manual Control System. Rev 18

  • ARC-MCR-*08 E-4, RDCS INOPERATIVE I Actual Testing Environment:

D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate D Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes ,, D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Evaluator's Name:----------------(Print) Date: ] Evaluator's Signature: ______________ _ ------LOJPM2119 RevOOO.doc SRRS: 30.105 Page 10 of 11 (When used for operator initial or continuing training) ,=:, Exelon Generation. INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Unit _Control Rod 18-31 has drifted out 2. Unit _Control Rod 18-31 was fully inserted, and isolated.

3. Tech Spec 3.1.3.1 has been referenced
4. Unit _Control Rod 18-31 was declared INOP 5. 'RDCS INOP' alarm on ARC MCR *08 E-4 has annunciated
6. The LED for Unit _HCU 18-31 on The Rod Drive Control System Analyzer -Fault Location Map is lit INITIATING CUE: " I Shift supervision directs you to reset Unit _RDCS !n accordance with S73.0.F, Operation of the Rod Drive Control System. ,, ,. Page 11 of 11 I :c:" Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE MANUALLY INITIATE A CONTROL ROOM CHLORINE I TOXIC CHEMICAL ISOLATION JPM Number: LOJPM3023 REVISION NUMBER: 001 DATE: ----Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Reviewed By: EP Representative Date Approved By: Training Department Date LOJPM3023 Rev001.doc SRRS: 3D.105 (When used for operator initial or continuing training)

,, I ,, Page 1of10

Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.
3. Performance location specified. (in-plant, control room, simulator, or other) 4. Initial setup conditions are identified.
5. Initiating cues (and terminating cues if required) are properly identified.
6. Task standards identified and verified by SME review. 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 8. If an alternate is used, the task standard contains criteria for successful completion.
9. Verify the proced1.1re(s) referenced by this JPM reflects the current revision:

Procedure 878.8.A Rev: Procedure Rev: __ _ Procedure Rev: ---------- ---Procedure Rev: ---------- ---Procedure---------- Rev: ---10. Verify cues both verbal and visual are free of conflict.

11. Verify performanc;e time is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM3023 Rev001.doc SRRS: 30.105 Page 2 of 10 (When used for operator initial or continuing training)

J Generation II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the IL Tor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision ,, # Date of Number Description of Revision and Affect on Training Content Revision 000 This JPM replaces LLOJPM0023 Rev. 10. Revised to new template 11/04/14 and to align with latest procedure revision. 001 This JPM revised to new JPM template and procedure changes 10/28/16 #Date of Revision -refers to date revision was released for approval LOJPM3023 Rev001.doc SRRS: 30.105 Page 3 of 10 (When used for operator initial or continuing training) I Generation .. IV. SIMULATOR SETUP INSTRUCTIONS:

1. Reset the Simulator to IC-3 2. Ensure the "B" CREFAS fan switch is in "AUTO" and the "A" CREFAS fan switch is in "STBY" 3. Ensure the "A" Control Room Supply and Return fans are in "RUN," and the "B" Control Room Supply and Return fans are in "AUTO." V. TASK STANDARD:

The Main Control Room HVAC System is operating in the Chlorineffoxic Chemical Isolation mode with a chlorine/toxic chemical isolation signal present on "B" and "D" isolation channels and no radiation isolation signals present. VI. INITIAL CONDITIONS: ., I 1 . Main Control Room HVAC System is in the normal operating mode per Section 4.2 of S78.1.A. 2. The Main Control Room Emergency Fresh Air Supply System is lined up for automatic operation per S78.1.B. 3. All prerequisites of S78.8.A are met. VII. INITIATING CUE: ,, ' You are directed by Shift Supervision to manually initiate a Main Control Room HVAC Chlorineffoxic Chemical Isolation for maintenance using the "B" subsystem only per S78.8.A, Section 4.5. LOJPM3023 Rev001.doc SRRS: 30.105 Page 4 of 10 (When used for operator initial or continuing training)

.*** Exelon Generation.

1-Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individu'*I item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. " I ,, ' LOJPM3023 Rev001.doc SRRS: 30.105 Page 5 of 10 (When used for operator initial or continuing training) ..:::C*' Exelon Generation 1-VIII. PERFORMANCE CHECKLIST: JPM Start Time -----I-a: I-ZW *ELEMENT STANDARD I-<( Wal <( en :E :E en z :E :::> :::> Oz ", () 1. Obtain copy of S78.8.A, Manual N/A Initiation of Control Room Radiation or Chlorine/Toxic Chemical Isolation.

2. IF no chemical isolation haf. been N/A initiated, THEN ENSURE alignment as follows: I 2a. HS-78-010B, ""B" CONT RM HS-78-01 OB, verified in EMERG FRESH AIR FAN AUTO OBV127" in AUTO 2b. HS-78-010A, ""A" CONT RM HS-78-01 OA, verified in EMERG FRESH AIR FAN OAV127" STANDBY in STANDBY ' 3. PLACE Control Room Isolation Reset Keylock switch
  • Valve Reset Keylock switch HS-78-017B (RESET B) is HS-78-017B (RESET B) to RESET. placed in RESET at Panel OOC681. 4. PLACE Control Room Isolation Reset Keylock switch
  • Valve Reset Keylock switch HS-78-017D (RESET D) is HS-78-017D (RESET D) to RESET. placed in RESET at Panel OOC681. 5. PLACE Control Room Isolation Switch HSS-78-017B (TRIP
  • Valve Trip Switch HSS-78-017B B) arming collar is rotated to (TRIP B) to CL2. CL2 at Panel OOC681. 6. PLACE Control Room Isolation Switch HSS-78-017D (TRIP
  • Valve Trip Switch HSS-78-017D D) arming collar is rotated to (TRIP D) to CL2. CL2 at Panel OOC681 . LOJPM3023 Rev001.doc SRRS: 3D.105 Page 6 of 10 (When used for operator initial or continuing training)

I ;f::;:' Exelon Generation. t-cc I-ZW *ELEMENT STANDARD t-<( w al <( (J) :E "' z :E :::> :::> Oz 0 7. PLACE Control Room Isolation Reset Keylock switch

  • Valve Reset Keylock switch HS-78-0178 (RESET 8) is HS-78-0178 (RESET 8) to AUTO. placed in AUTO at Panel OOC681. 8. PLACE Control Room Isolation Reset Keylock switch
  • Valve Reset Keylock switch HS-78-017D (RESET D) is HS-78-017D (RESET D) to AUTO. placed in AUTO at Panel OOC681.
  • 9. DEPRESS AND RELEASE Trip Switch HSS-78-0178 pushbutton portion of Trip Switch (TRIP 8) pushbutton is I HSS-78-0178 (TRIP 8). depressed and released at Panel OOC681 . ,, 10. DEPRESS AND RELEASE Trip Switch HSS-78-017D
  • pushbutton portion of Trip Switch (TRIP D) pushbutton is I HSS-78-017D (TRIP D). depressed and released at Panel OOC681 . EVALUATORS NOTE: [4.5.6] CREFAS run time data will be logged by another operator ' ' 11. RECORD CREFAS run time in appropriate log. NIA CUE: Another Operator will log the CREFAS Run time data 12. ENSURE "CHLOR ISLN CHAN 8" "CHLOR ISLN CHAN 8" AND "CHLOR ISLN CHAN D" amber AND "CHLOR ISLN CHAN D" lights are lit. amber lights are lit on OOC681. 13. VERIFY "CONTROL ROOM Annunciator window A-2, CHLORINE ISOLATION INITIATED" "CONTROL ROOM annunciator alarmed at 002 VENT CHLORINE ISOLATION A-2. INITIATED," on 002 VENT, is in alarm. LOJPM3023 Rev001.doc SRRS: 30.105 Page 7 of 10 (When used for operator initial or continuing training)

Exelon Generation I-I-a: ZW *ELEMENT STANDARD I-<t WCO <t (J) == == (J) z == :> :::::> Oz () 14. VERIFY "CONTROL ROOM Annunciator window A-3, ISOLATION NOT COMPLETE" "CONTROL ROOM annunciator is not alarmed at 002 ISOLATION NOT VENT A-3, after 25 seconds. COMPLETE," on 002 VENT, is not alarmed 25 seconds after the isolation is initiated.

15. ENSURE OB(A)V127, OBV127, EMERGENCY AIR EMERGENCY AIR FAN B(A), is FAN B, is running. running. 16. ENSURE OA(B)V116, CONTROL OAV116, SUPPLY FAN A, is ROOM AIR SUPPLY FAN A(B), running. running. 17. ENSURE OA(B)V121, CONTROL OAV121, RETURN FAN A, is ROOM AIR RETURN FAN A(B), running. running. ,, CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM3023 Rev001.doc SRRS: 30.105 Page 8 of 10 (When used for operator initial or continuing training)

I =-;*Exelon Generation JPM

SUMMARY

Operator's Name: _______________________ __. Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: MANUALLY INITIATE A CONTROL ROOM CHLORINE!TOXIC CHEMICAL ISOLATION JPM Number: LOJPM3023 Revision Number: 001 Task Number and Title: TP0-2881030401 Manually Initiate Control Room Radiation or Chlorine!T oxic Chemical Isolation KIA Number and Importance: 290003 A3.01 3.3/3.5 Safety Function {1-9) 9 {Radioactivity Release) Admin Category {A1-4) N/A Level of Difficulty {1-5) i Suggested Testing Environment: Simulator ' Alternate Path:O No SRO Only: D Yes No Time Critical: D Yes No ,, Reference{s): S78.8.A, "Manual Initiation of Control Room Radiation or Chlorine I Toxic Chemical Isolation", Rev. 17 Actual Testing Environment: Simulator D Control Room tJ In-Plant D Other Testing Method: D Simulate Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes ----EVALUATION

SUMMARY

,, Were all the Critical Elements performed satisfactorily?

D 'ves D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Evaluator's Name:----------------(Print) Evaluator's Signature: ______________ _ Date: ------LOJPM3023 Rev001.doc SRRS: 30.105 Page 9 of 10 (When used for operator initial or continuing training)

,
, Exelon Generation, INITIAL CONDITIONS

LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. Main Control Room HVAC System is in the normal operating mode per Section 4.2 of S78.1.A. 2. The Main Control Room Emergency Fresh Air Supply System is lined up for automatic operation per S78.1 .B. 3. All prerequisites of S78.8.A are met. INITIATING CUE: " I You are directed by Shift Supervision to manually initiate a Main Control Room HVAC Chlorine!Toxic Chemical Isolation for maintenance using the "B" subsystem only per S78.8.A, Section 4.5. maintenance using the "B" subsystem only per S78.8.A, Section 4 .5. ,, Page 10 of 10 Ir Exelon Generation Developed By: Validated By: Reviewed By: Reviewed By: Approved By: LOJPM2258 Rev002.doc LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE START ESW PUMP PER SE-1 JPM Number: LOJPM2258 REVISION NUMBER: 002 DATE:_! __ _ " I Instructor ,, I' SME or Instructor Operations Representative EP Representative Training Department SRRS: 30.105 (When used for operator initial or continuing training) Date Date Date Date Date Page 1 of 8 1-,:::f!!;' Exelon Generation. Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 through 13 below. 1. 2. 3. 4. 5. 6. 7. 8. 9. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and ,verified by SME review. I steps meet the criteriaifor critical steps and are identified with an asterisk ( ). i If an alternate path is used, task standard contains criteria for successful completion. Verify the procedure(s) by this JPM reflects the current revision: Procedure SE-1 Rev: 73 Procedure Rev: ---Procedure Rev: __ _ Procedure Rev: __ _ Procedure Rev: ---10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate 12. If the JPM cannot be performed as written with proper responses, then revise the JPM. 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date LOJPM2258 Rev002.doc SRRS: 30.105 Page 2 of 8 (When used for operator initial or continuing training) j #":!f Exelon Generation II. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date I Ill. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description, of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format). D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated. Revision ' # Date of Number Description of Revision and Affect on Training Content Revision 000 This JPM replaces LLOJPM0258 Rev. 4. Revised to new template and to 10/7/13 align with latest procedure revision. This revision changes this JPM to an Alternate Path. 001 Revised to new template and aligned for Equipment Operator use 10/01/15 002 This SEG is revised to new 3/16 SEG format template, including any 10/24/16 procedure revisions

  1. Date of Revision -refers to date revision was released for approval LOJPM2258 Rev002.doc SRRS: 30.105 Page 3 of 8 (When used for operator initial or continuing training) 1-,:::;;.:'

Exelon Generation IV. TASK STANDARD: 'OC' ESW Pump Breaker closed from controls at 023 Switchgear. V. INITIAL CONDITIONS:

1. The Main Control Room has been evacuated.
2. SE-1 has been entered and Remote Shutdown Panel transfer switches have been positioned to Emergency
3. 012, 013, 021, 022, and 023 Safeguard Buses are energized from their normal sources. 4. 011 Safeguard Bus is being powered from the 011 Diesel Generator.

i 5. An Equipmen' Operator performing running checks for 011 D/G reports that there is no indication of ESW flow through the 011 D/G Heat Exchangers. " I VI. INITIATING CUE: Shift Supervision has directed you to start 'OA' ESW Pump per section 4.5 of SE-1 beginning at step 4.5.3. *' Information for Evaluator's Use: Any UNSAT requires written comments on respective step.

  • Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document:

the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system. Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue. LOJPM2258 Rev002.doc SAAS: 30.105 Page 4 of 8 (When used for operator initial or continuing training) \ ,:"""f Exelon Generation VII. PERFORMANCE CHECKLIST: JPM Start Time ____ _ I-ELEMENT STANDARD I-<C CJ) en z :::> 1. Obtain current revision of SE-1. Current revision of SE-1 obtained. CUE: When candidate demonstrates the ability to obtain current revision of procedure, provide a copy of SE-1. 2. IF 'A' ESW Pump is not running, N/A ., THEN perform the following I EVALUATOR NOTE: Alternate path starts here. 'A' ESW Pump will fail to start from RSP handswitch. ,, ' 2a. START OAP548, "A" ESW Pump" Candidate simulates placing (PUMP A). 'A' ESW Pump switch in START. 2b. VERIFY OAP548, PUMP A, running. Candidate recognizes pump is not running. CUE: When 'A' ESW Pump control switch is placed in ST ART, inform the Note: Candidate may place candidate: "The green light above the handswitch back in Normal switch is on 1 red light is off." after Stop. This is not critical.

3. IF 'A' ESW will not function from the N/A RSP, THEN PERFORM the following to start 'C' ESW Pump from 023 Switchgear:

3a. PLACE 152-11708/CST, "Test Candidate simulates placing Switch" ESW C Pump OCP548 to 152-11708/CST in PULL TO "PULL TO LOCK" LOCK LOJPM2258 Rev002.doc SRRS: 3D.105 (When used for operator initial or continuing training) Page 5 of 8 I-c: Zw w Ill :E :E :E ::> Oz (..) I I I I ; .=* Exelon Generation, 1-I-a: I-Zw ELEMENT STANDARD I-c::r: wee c::r: CJ) :E :E (/) z :E ::> :::> Oz 0 EVALUATOR NOTE: The GE-75 key required for transfer switch HSS-11-095 is an alternate I I " I I ,, remote shutdown key on remote shutdown key ring obtained in SE-1.

  • 3b. PLACE HSS-11-095, "Handswitch Candidate simulates placing For MCR or Local Control of 'OC' HSS-11-095, "Transfer ESW Pump, to "EMERGENCY" Switch" to "EMERGENCY"
  • 3c. PLACE 152-11708/CST, to Candidate simulates placing "CLOSE" 152-11708/CST, to "CLOSE" CUE: "Breaker closing sound can be Candidate recognizes that heard, the red light is lit, the green light 'OC' ESW Pump feeder is out and ammeter indicates starting breaker is closed. current value decaying to running value." CUE: You have met the termination criteria for this JPM JPM Completion Time ____ _ LOJPM2258 Rev002.doc SRRS: 3D.105 (When used for operator initial or continuing training)

Page 6 of 8 " I ,, I

.** Exelon Generation.

1-JPM

SUMMARY

Operator's Name: _______________________ ___ Job Title: D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM Title: START ESW PUMP PER SE-1 JPM Number: LOJPM2258 Revision Number: 002 Task Number and Title: 2000410501, (SE-1) Control Room Abandonment (RO) 2000160404, Manual S/U of Pumps from Emergency Switchgear Room (EO) KIA Number and Importance: 295016 AA 1.04 3.1/3.2 Safety Function (1-9) 8 (Plant Service Systems) Admin Category (A1-4) __ Level of Difficulty (1-5) .d_ Suggested Testing Environment: In-Plant Alternate Path:[gj Yes D No SRO Only: D Yes [gj No Time Critical: 1 o Yes L8J No Reference(s}: SE-1, Remote Shutdown, Rev. 73 " 1 Actual Testing Environment: D Simulator D Control Room D ln-Pla11t D Other Testing Method: [gj Simulate D Perform Estimated Time to Complete: 15 minutes Actual Time Used: ___ minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

D Yes :'. 0No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: ------------------------(Print), Evaluator's Signature: __________________ _ Date: --------LOJPM2258 Rev002.doc SRRS: 30.105 Page 7 of 8 (When used for operator initial or continuing training)

.
:,,* Exelon Generation.

INITIAL CONDITIONS: LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET 1. The Main Control Room has been evacuated.

2. SE-1 has been entered and Remote Shutdown Panel transfer switches have been positioned to Emergency.
3. 012, 013, 021, 022, and 023 Safeguard Buses are energized from their normal sources. 4. 011 Safeguard Bus is being powered from the 011 Diesel Generato'r.

I 5. An Equipment Operator performing running checks for 011 O/G reports that there is no indication of ESW flow through the 011 O/G Heat Exchangers. " I INITIATING CUE: Shift Supervision has directed you to start 'OA' ESW Pump per section 4.5 of SE-1 beginning at step 4.5.3. ,, ,, Page 8 of 8 LIMERICK GENERATING STATION Exelon Gener*ation

  • . SIMULATOR EXERCISE GUIDE CODE NO: SEG-5006E REV NO: AUTHOR: T.A.BYERS APPROXIMATE RUN TIME: TYPE: SIMULATOR EVALUATION EFFECTIVE DATE: GUIDE PROGRAM: LICENSED OPERATOR TRAINING 000 70 minutes COURSE: LICENSED OPERATOR TRAINING TITLE: Simulator Evaluation Guide for Individual and Crew Performance Prepared By: Reviewed By: Reviewed By: Reviewed By: Approval:

Approved For Use: Training Instructor -Signature Program (IL Tor LOR) Lead -Signature EP (as appropriate) -Signature RE (as appropriate) -Signature OPS Manager -Signature Training Manager -Signature ,, I ,, SEG-5006E RevOOO.doc SRRS: 30.126 Date: Date: Date: Date: Date: Date: Page 1 of 49 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EXERCISE GUIDE Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-5006E Rev _o_ Op-Test No.:_1_. Examiners: Operators: Initial Conditions: Unit 1 is at j.QQ_% power. Unit 2 is at 100 % power. Turnover: Maintain 100% Reactor 12ower Place '1 C' SBLC Pumg in Automatic Injection Mode 12er S48.1.A 1 Standby Liguid Control I System Set-Ug For Normal 012eration 1 steQ 4.7 in 12re12aration of a 1 B SLC System Outage Window. ,, I Event Malfunction Event ' Event No. Number Type* Description MSL 1988 N-PRO Align '1 C' SLC Pump for automatic operation

1. TS-SRO C41-S1C I 2. MPR020C C-RO #3 APRM fails upscale (Malfunction)

' R-RO MRR430A 3. C-PRO '1 A' Reactor Hecirc Pump shaft seizure resulting in MRD024 TS-SRO Recirc Pump trip (Abnormal)

4. MFH563C C-PRO Low Pressure FWH Level Transient (Abnormal)

MFH116C '6C' FWH Isolation (Abnormal)

5. MFH016C C-RO MPR003A Core Power Oscillations MFW252A M-ALL LOCA Inside Containment (T-111) 6. MRR440A 7. MRC457B C-PRO RCIC controller in AUTO failure (Malfunction)

' 8. MAD148D C-PRO '1 M' SRV fails to open (Malfunction)

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-5006E RevOOO.doc SRRS: 30.126 Page 2 of 49 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EXERCISE GUIDE I. QUANTITATIVE ATTRIBUTES A. ILT Target Quantitative Attributes (Per Scenario; See ES-301 Section D.5.d) 1. Malfunctions after EOP entry (1-2) 2. Abnormal events (2-4) 3. Major transients (1-2) ! 4. EOPs entered/rfquiring substantive actions (1-2) 5. EOP contingencies requiring substantive actions (0-2) *i 6. EOP based Critical tasks (2-3) ACTUAL NUMBER 2 2 1 2 2 4 Review TQ-AA-151 attachment 5 and ES-301-5 for individual position requirements for scenario and scenario set SEG-5006E RevOOO.doc

,, SAAS: 30.126 Page 3 of 49 LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EXERCISE GUIDE II. PURPOSE: Systematically evaluate individual and team performance to identify areas for improvement. Critical Tasks and Assessment Items from this evaluation guide are to be used to assess crew and individual performance and as input into a 4.0 Crew Critique Process. Ill. SIMULATOR EVALUATION GUIDE OBJECTIVES: A. The following evaluation objectives apply to the Crew (C), Shift Manager (SM), Control Room Supervisor (S), Unit Reactor Operator I Plant Reactor Operator (R), or Incident Assessor I Shift Technical Advisor (A). 1. The general condition for each of the evaluation objectives will be "Given the plant conditions and sequence of events in the Simulator Evaluation Guide (SEG)". 2. The general acceptable evaluation objective criteria for each of the evaluation objectives will be "To perform effectively as an individual and contribute to successful crew performance in accordance with appropriate reference plant procedures and Operations Expectations, Fundamentals and Strategies".

3. Specific UNSAT evaluation objective criteria will be consistent with TQ-AA-155, Conduct of Simulator Training and with applicable forms and job aids. 4. During performance of this Simulator Evaluation Guide, the individuals and crew should satisfactorily demonstrate}he following overall procedure and plant control objectives:
  • Direct and perform actions per OT-104, Unexpected, Unexplained Positive or Negative Reactivity Insertion
  • Direct and perform actions per OT-112, Unexplained/Unexpected Change in Core Flow
  • Direct and perform actions per T-101, RPV Control
  • Direct and perform actions per OT-101, Drywell High Pressure
  • Direct and perform actions per T-102, Primary Containment Control I
  • Direct and perform per T-111, Level Restoration/Steam Cooling
  • Direct and perform actions per T-112, Emergency Slowdown SEG-5006E RevOOO.doc SRRS: 30.126 Page 4 of 49 LIMERICK GENERATING STATION Exelon Generation.

SIMULATOR EXERCISE GUIDE RECORD OF TEMPORARY CHANGES: B. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence C. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision D. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change LORT Action Revision Change# Change Approval Tracking Date I IV. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The ,description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (e.g for conversion of LSTS to LLORSEG format). Revision Description of Revision and Affect on Training Content #Date of Number:. Revision ,. RevOOO. Initial Issue of Simulator Evaluation Guide Template to revised LSES 5006 07/15/16 #Date of Revision -refers to date revision was released for approval SEG-5006E RevOOO. doc SRRS: 30.126 Page 5 of 49 LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

Event One: Shortly after the crew has assumed responsibility, they will be required to align the '1 C' SLC Pump for automatic operation, using S48.1.A, Standby Liquid Control System Up For Normal Operation, and remove the '1 B' SLC Pump from service. Evaluation:

Evaluate the crew's ability to perform the procedure and place equipment in service and to evaluate the CRSs ability to apply Tech Spec 3.1.5. for the SLC Pump being removed from service. Event Two: Shortly after the evolution of placing the '1 C' SLC Pump in standby service, APRM #3 will fail upscale. " I Event Three: I Evaluate the crew's response to the plant for the failed APRM, reference Tech Spec 3.3.1 and place the inoperable APRM in the BYPASS position. After the failed APRM issue is resolved, the '1 A' Recirc Pump shaft will seize resulting in a Recirc Pump trip and reduction in core flow and reactor power. Evaluation: To evaluate the crew's ability to address the sudden change in reactor power by entering and executing OT-104, Unexpected/ Unexplained Positive or Negative Reactivity Insertion, and OT-112, Unexpected/ Unexplained Change In Core Flow, for the tripped Recirc Pump. The crew will isolate the failed Recirc Pump and insert Control Rods to exit the Restricted Region of the Power/Flow Map. The crew will also execute GP-5 to stabilize the plant. ,, ' Event Four: and Five: As the crew is recovering from the tripped Recirc Pump and attempting to exit the Restricted Region of the Power/flow Map a low pressure FWH level transient will occur requiring re-entry into OT-104. As the crew addresses the transient another FWH level control problem will result in a 6 1 h FWH isolation causing a larger positive reactivity addition and subsequent Thermal Hydraulic Instabilities (THI). Evaluation: To evaluate the crew's ability to diagnose the positive reactivity addition from the loss of FWH while in the Restricted Region of the Power/Flow Map and to detect/suppress core THI, by monitoring LPRM, APRM and period meters to detect indications for signs of core THI. The crew will shutdown the plant due to the Thermal Hydraulic Instabilities. SEG-5006E RevOOO. doc SRRS: 30.126 Page 6 of 49 LIMERICK GENERATING STATION Exelon Generation.. SIMULATOR EXERCISE GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

cont'd Event Six: After the reactor is shutdown, a Feedwater line break will occur resulting in a loss of all feedwater to the RPV. Evaluation: To evaluate the crew's ability to take appropriate actions to control RPV level using T-101, RPV Control, and eventually T-111, Level Restoration/Steam Cooling. The crew will start ECCS Pumps in preparation to maintain RPV level following an RPV Emergency Slowdown. Also to maintain Containment parameters, enter T-102, Primary Containment Control and, as RPV level drops due to the loss of high pressure feed, enter T-112, Emergency Slowdown to assure adequate core cooling with the low pressure injection systems. Event Seven: During reactor RPV level restoration the RCIC flow controller will fail in automajic. Evaluation: To evaluate the PROs response to the RCIC system failure and diagnose RCIC is available only when manual control is taken. Event Eight: As RPV level decreases to -161" the crew performs the T-112, Emergency Slowdown allowing low pressure ECCS systems to maintain RPV level. To accomplish the blowdown, five ADS valves are selected to be opened, however the '1 M' SRV will fail to open from the handswitch, and require an alternate SRV be opened to ensure 5 SRVs are opened. ,, ' Evaluation: Evaluate the crew's ability to identify failure of the '1 M' SRV to open, and open a non-ADS valve to ensure 5 SRV's are open. Termination Point: The scenario may be terminated when the Emergency Slowdown is complete, RPV level is restored to normal band with ECCS systems and Containment Spray is in service. SEG-5006E Revooo. doc SRRS: 30.126 Page 7 of 49 LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EXERCISE GUIDE V. REFERENCES A. Training Procedures

1. TQ-LG-150, Limerick Operator Training Programs 2. TQ-AA-151, ILT Certification and NRC Examination Development and Administration
3. TQ-AA-155, Conduct of Simulator Training and Evaluation B. Annunciator Response Cards (ARC) 1. 102 F-1, 1C FEEDWATER HEATER HI LEVEL 2. 102 F-2, 2C FEEDWATER HEATER HI LEVEL 3. 102 G-4, FM/ HTRS 1&2 HI-HI LEVEL LP HTR STRING ISOLATION
4. 102 G-3, 6C FEEDWATER HEATER HI LEVEL 5. 102 G-5, FEEDWATER HEATER 3/4/5/6 HI HI LEVEL ISOLATION
6. 107 A-3, SLCS PUMP AUTO-START STATUS TROUBLE 7. 107 H-2, REACTOR HI/LO LEVEL 8. 1071-2, VIBRATION ALARM ALERT 9. 108 A-4, OPRM TRIPS ENABLED 10. 108 B-3, APRM UPSCALE TRIP/I NOP 11 . 108 F-3, ROD OUT BLOCK 12. 108 B-4, APRM UPSCALE 13. 108 A-3, OPRM PRE-TRIP *i I 14. 1081-1, 1A/1B/1C STANDBY LIQUID PUMP MOTOR OVERLOAD/LOSS OF POWER 15. 111 B-1, 1A RECIRC ASD TRIPPED 16. 111 B-2, 1A RECIRC ASD MAJOR FAILURE 17. 111 D-2, 1A RECIRC PUMP MOTOR HI VIBRATION
18. 111 E-2, 1A RECIRC ASD 13 KV BKR TRIP C. System Procedures (S) 1. S48.1.A, Standby Liquid Control System Set-up For Normal Operation.
2. S12.1.A, RHR Service Water System Startup. D. General Procedures (GP) E. Off Normal Procedures (ON) F. Operating Transient Procedures (OT) 1. OT-104, Unexpected, Unexplained Positive or Negative Reactivity Insertion
2. OT-112, Unexpected/Unexplained Change in Core Flow 3. OT-101, Drywell High Pressure G. Event Procedures (E) H. Special Event Procedures (SE) 1. SE-10, LOCA I. Surveillance Test and Routine Test Procedures (ST and RT) SEG-5006E RevOOO.doc SRRS: 3D.126 ,, ,, Page 8 of 49 LIMERICK GENERATING STATION Exelon Generation*.

SIMULATOR EXERCISE GUIDE REFERENCES cont'd J. Technical Specifications and TRM (TS) 1. 3.4.1.1.a.

2. 3.1.5 3. 3.3.1 4. 3.3.6 5. 3.5.1.c. 6. 3.3.2.1 7. 3.7.3.a, K. Transient Response Implementation Procedures (T-100 series)/SAMPs
1. T-101, RPV Control 2. T-102, Primary Containment Control 3. T-111, Level Restoration/Steam Cooling 4. T-112, Emergency Slowdown L. TRIP 200 Series Procedures I 1. T-240, Maximizing CRD Flow After Shutdown During Emergency Conditions
2. T-225, Startup And Shutdown Of Suppression Pool And DryweU, Spray Operation M. EP-AA-1008, Limerick, Radiological Emergency Plan Annex for Limerick Generating Station N. Administrative Procedures
1. OP-AA Procedures
a. OP-AA-1, Conduct of Operations
b. OP-AA-20, Conduct of Operations Process Description
c. OP-AA-101-111-1003, Operations Department Standards and Expectations I d. OP-AA-101-113, Operations Fundamentals
e. OP-AA-101-113-1006, 4.0 Crew Critique Guidelines

,, f. OP-AA-106-101-1006, Operational Decision Making Process * . 2. OP-LG Procedures

a. OP-LG-101-111-1000, Licensed Operator Duties b. OP-LG-102-106, Operator Response Time Program at Limerick c. OP-LG-103-102-1000, Human Performance Continuing Good Practices
d. OP-LG-103-102-1002, Strategies for Successful Transient Mitigation
e. OP-LG-108-101-1001, Simple Quick Acts I Transient Acts 0. Current Shift Night Orders Forced Outage Plan P. INPO Significant Operating Experience Reports (SOER), Significant Event Reports (SER) and INPO Event Reports (IER) 1. IER-L 1 11-3, Weaknesses in Operator Fundamentals
2. SER 3-05, Weakness in Operator Fundamentals
3. SOER 10-02, Engaged Thinking Organizations
4. INPO 15-004, Operator Fundamentals SEG-5006E RevOOO.doc SRRS: 30.126 Page 9 of 49 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EXERCISE GUIDE VI. PREBRIEF INSTRUCTIONS Unit 2 is in OPCON 1 at 100 % power Unit 1 is in OPCON 1 at 100 % power Specific Plant Conditions are as Follows:
  • None Inoperable/Out of Service Equipment and Estimated Time of Return {ETR):
  • None Restrictions on Plant Operations:
  • None Planned Evolutions:

,,

  • Place '1 C' SBLC Pump in Automatic Injection Mode per S48.1.'A, Standby Liquid Control System Set-Up For Normal Operation, step 4.7 in preparation of a '1 B' SLC System Outage Window Documents Provided:
  • S48.1.A, Standby Liquid Control System Set-Up For Normal Operation I SEG-5006E RevOOO. doc SRRS: 30.126 ,, Page 10 of 49 LIMERICK GENERATING STATION Exelon Generation*.

SIMULATOR EXERCISE GUIDE VII. DIRECTIONS FOR EVALUATION PREPARATION A. INITIAL PREPARATION ., ITEM I MALFUNCTION I REMOTE FUNCTIONS Complete TQ-AA-155, Operator Training Programs Attachment 02, Evaluated Scenario Administration Checklist. Complete TQ-LG-201-0113, Limerick Training Department Simulator Examination Security Actions Checklist B. SIMULATOR SETUP ., ITEM I MALFUNCTION I REMOTE FUNCTIONS I Complete Limerick Simulator Pre-Evaluation Checklist ' Reset Simulator to the Pre-loaded Cycle IC developed for the Evaluation OR Reset the simulator to designatec;:f base load IC-3 AND Load scenario file SEG5006E RevOOO.scn

  • Verify that all Malfunctions, Remotes, Overrides, Annunciators and Triggers are properly loaded OR
  • Manually enter the Malfunctions, Remotes, Overrides, Annunciators and Triggers per the Scenario Generator Screen Shots: I Simulator Operator (Driver) perform ,the following:

,,

  • Momentarily place simulator in RUN
  • Acknowledge and clear all spurious alarms
  • Place the simulator back into FREEZE
  • Place appropriate tags and equipment in required condition I status . SEG-5006E RevOOO.doc SRRS: 30.126 Page 11 of 49 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EXERCISE GUIDE C. MALFUNCTION/REMOTE/OVERRIDE/ANNUNCIATORS FUNCTION TIME TABLE j
  • Malfunction Summary**
  • -**** 1
    • *. 13LC Pµmp 18 Los* of Control Powei l . APRM Channel 3 Fails to Selected Value MRR430A R*eactor Recirculation Pu111> 1A Seizure l MPR003A. In-Phase Core Power Oscillations l Mall ID I Mult ID I Description

! MFH116C Feedwater Healer 16C Dump Valve Fails MFH016C Feedwater Heater 16C DrainVatve Fails MRD024 Ro_d _Drive _Control System F_ai_l_u_re MRR44iJA Recirculation Loop A Rupture MFw252A Fw Line A Break Inside Primary Containment*

  • ** MR(;.q78j,{:r>

& ... Fli11,_ C&W; . ::>,' Feedwater Heater 11 Show Malfunctions

  • 100.1036 False 0.00 0.00 0.00 True 23.00000 0.00 ci.oo 00:00:10 00:00:15 00:00:15 00:04:00 . 00:01 :00 2 3 5 5 5 I i

\ -C 1C Standby Liquid Control Pump Ind Lamps CONTINUITY OFF 1 I **1 llR'iiMl&1lihl\\liiD:'f'M\M&M&& iM14MMr£!1%iliMM!i1iffiii!Mfiliiiii&*Hil\11AAM

  • '"hMW.W!1%filifili!il\11111iW Jii1Mlill)ll1IJ-lflll-\Mm&m j 1*1 1 i-Timer Pause

---*****-.. -* * --****J I Vv'indow I Description I Tagname I ! I 14 Standby Liquid Squib Valve Loss of Continuity 108REACTOR14 ON ON OFF 1 ! ' I J ' " . *i

  • Active ; Pending I r Timer Pause Delete A// ----****-"--*:c_.c,-",.:

.. :. c:.c.:: .. :,:.:.c::cc:".:.:J SEG-5006E RevOOO.doc SRRS: 30.126 Page 12 of 49 . ....-.&llli!\\c:*

  1. Wf"w Exelon Generation

.. LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE D. EVENT TRIGGERS ASSIGNMENT 1 . Timers should be used on event triggers where possible for time validation

2. Timing of event triggers may be altered by the Lead Evaluator (or designee)
3. Verify triggers are actuated automatically as designed or manually initiate the trigger when the initiating action has occurred.
4. Inform Lead Evaluator (or designee) of expected plant response prior to actuation of each trigger. 5. Trigger #1 is manually initiated at Lead Evaluator (or designee) direction after the crew assumes responsibility for operation.

co . TRIGGER I MALFUNCTION I EVENT 2 7 8 9 10 11 12 13 14 15 16 17 18 19 TIME 1 Manual 2 Manual 3 Manual 4 Auto I ZDIB1 (3864) II ZDIB1 (3858) " 5 Auto I FWZR607R<=20852 6 " ' ' . *-' -ZDIB1(3864) llZDIB1(3858) FWZR607R <= 20852 ZRPS1SDN Auto I ZRPS1 SON Irigger Now I !;;lear CJearAll SEG-5006E RevOOO.doc SRRS: 30.126 DESCRIPTION Remove power from XV-48-1 F004C Initiates APRM #3 Upscale Initiates '1A' Recirc Pump trip HV-043-1 F031 A or 1 F023A to Close Initiates Low Pressure FWH Level Transient Total Steam Flow reduced to 10 Mlbm/hr Initiates 5th FWH high level and THI RMS to SHUTDOWN Initiates Feedwater Line rupture I DW leak 8ccept Operators: Arithmetic:

  • Multiplication I Division + Addition
  • Subtraction Relational:

> Greater than >= Greater than or equal < Less than < = Less than or equal == Equal to != Not equal to Logical: && And II Or ! Not Other: Open Paren ) Close P aren Page 13 of 49 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE E. EQUIPMENT REPORTS AND LEAD EVALUATOR (OR DESIGNEE) OPERATIONS

1. Scripted Activity Reports should be followed with adherence to Operations Communication standards of performance.
2. The T-200 procedure reference book should be used for familiarity of reports to aid in operator prompting and expected communications.
3. The Lead Evaluator (or designee) should be informed if any event is not reported as scripted due to lack of Operator request. 4. The Standard Equipment Operator Response Times are per Attachment 1 5. A record of communications from the MCR and to the MCR will be maintained by the Simulator Operator using Attachment
2. 6. The OCOEE Simulator Operator Station P&IDs, Floor Plans and Panels should be used by the Simulator Operator as reference information when making reports to the MCR for plant parameters which are not driven by a communications script. Examples include: ARMs, Blowout Panel status, Reactor Building Area Temperatures and Pressures, RMMS, Turbine Enclosure parameters etc. SEG-5006E RevOOO.doc I " I ,, I SRRS: 30.126 Page 14 of 49

,; I ,, ' LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE X. CREW CRITICAL TASKS A. Critical Tasks are based on the current Crew Critical Task List revision, NU REG 1021 and AA-150 requirements.

1. T-111.4 Standard:

2.a T-112.1 Standard: OR 2.b T-102.2 Standard:

3. T-111.3 Standard:

SEG-5006E RevOOO. doc Inhibit Automatic ADS KIA 218000 A2.06 4.2/4.3 Prevent automatic initiation of ADS prior to exceeding -129" reactor level and ADS logic being completed. SAT/UNSAT Perform emergency blowdown per T-112. KIA 295031 EA1.07 3.713.7 KIA 295031 EA2.04 4.6/4.8 When RPV level drops below TAF, open 5 SRV's. SAT/UNSAT Perform emergency blowdown per T-112. KIA 295024 EA1.08 3.9/3.9 KIA 295024 EA2.04 3.9/3.9 When Suppression Pool Pressure cannot be maintained below the Pressure Suppression Pressure (PC/P-3) curve and before Drywell pressure exceeds 55 psig, open 5 SRVs. SAT/UNSAT Maintain RPV level greater than the TAF. KIA 295031 EA1.01 4.4/4.5 KIA 295031 EA1 .02 4.5/4.5 KIA 295031 EA 1.05 4.3/4.3 KIA 295031 EA 1.11 4.1/4.1 KIA 295031 EA1.12 3.9/4.1 Operate injection systems to maintain reactor level greater than the T AF or enter T-112, perform an emergency blowdown, and when pressure permits, inject wit low pressure ECCS to restore RPV level above TAF. SAT/UNSAT SRRS: 30.126 Page 15 of 49 " I ,, ' ,, I ,, I LIMERICK GENERATING STATION Exelon Generation SIMULATOR EXERCISE GUIDE CREW CRITICAL TASKS cont'd 4. T-102.1 Standard: Spray the Drywell per T-225. KIA 295024 EA1 .11 KIA 295028 EA1 .01 KIA 295028 EA1 .04 4.2/4.2 3.8/3.9 3.9/4.0 When Drywall temperature and pressure are on the SAFE side of curve PC/P-2, spray the Drywell before exceeding 340°F or 55 psig. SAT/UNSAT SEG-5006E RevOOO.doc SRRS: 30.126 Page 16 of 49 ,, I ,, I LIMERICK GENERATING STATION Exelon Generation" SIMULATOR EXERCISE GUIDE XI. ASSESSMENT OF CREW PERFORMANCE DURING CONDUCT OF THE DYNAMIC SIMULATOR EVALUATIONS: A. B. c. D. E. F. G. H. I. Conduct the Simulator Evaluation Session per TQ-AA-155, Conduct of Simulator Training and Evaluation, Attachment 02, Evaluated Scenario Administration Checklist Assessment of Crew and Individual performance shall be consistent with OP-AA-20, Conduct of Operations Process Description Where possible record the time and position responsible for performance of each task or assessment item Items not performed as expected SHALL be discussed in the post performance crew critique During the performance of the evaluation, the Simulator Evaluators shall MAINTAIN notes of observations and information consistent with the timeline Assessment items with the CD symbol indicate a time critical standard for performance Assessment items with the symbol indicate a Probabilistic Risk Assessment (PRA) association with the task The Simulator Operator will respond with scripted or proceduralized responses when requested by the MCR operators with Procedure completion times requested per 1 The Simulator Operator will also maintain a timeline and record of all reports and requests issued by the MCR personnel with response provided by the simulator operator using Attachment 2 " I ,, I SEG-5006E RevOOO.doc SRRS: 30.126 Page 17 of 49 LIMERICK GENERATING STATION Exelon Gene1-ation

  • . SIMULATOR EXERCISE GUIDE 1. EVENT-1 PLACE '1C' SLC PUMP IN AUTOMATIC INJECTION MODE Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger At time 1 min when requested to power down the '1 B' SLC Pump insert malfunction MSL198B and report: Feed breaker for '1 B' SLC Pump, 0124-R-C-34 is opened. When requested by RO to remove fuse 2 and fuse 3 from C640 panel per S48.1.A step 4.7.2 and 4. 7 .3, manually actuate Trigger # .J._ to remove power to C41-S 1 C XV-048-1 F004C Squib Valve, and alarm 108 1-4, Standby Liquid Squib Valve Loss Of Continuity. ! Ensure annunciator 108 1-4, Standby Liquid Squib Valve Loss Of Continuity d1eared when fuses re-installed, per step 4. 7 .1 O and 4. 7 .11 of S48.1 .A .; I When requested by RO to install fuse 2 and fuse 3 from C640 panel per S48.1.A step 4.7.1 O and 4.7.11, DELETE-C41-S1C '1C' SBLC Pump Indicating Lamps AND DELETE -Annunciator Override 108 Reactor 14 (Standby Liquid Squib Valve Loss of Continuity). SEG-5006E RevOOO.doc SRRS: 30.126 ,, ,, Page 18 of 49 TIME 1. LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-1 PLACE '1C' SLC PUMP IN AUTOMATIC INJECTION MODE POSITION Lead Evaluator {or designee) Notes: The crew will be directed to align the '1C' SBLC Pump for automatic injection per 848.1.A, Standby Liquid Control System Set-up For Normal Operation, section 4. 7. When the 1 B SLC Pump is de-energized, annunciator 108 1-1, 1 A/1 B/1 C ST AND BY LIQUID PUMP MOTOR OVERLOAD/LOSS OF POWER will be received. [S48.1.A 4.7.1] PRO Direct EO to open '1 B' SLC Pump Feed (0124-R-C-34) SRO references Tech Spec 3.1.5 action a for only one pump and SRO corresponding explosive valve OPERABLE [S48.1.A 4.7.2/3] PRO REMOVE fuse F2 and F3 in panel C640 to disarm;XV-48-1 F004C [S48.1.A 4.7.4/5] I PRO OBTAIN key for 1CP208 SLC Injection Pump and PLACE 1 CP208 control switch to "NORM" position [S48.1.A 4.7.6] PRO VERIFY annunciator 107 A-3 SLCS PUMP AUTOTSTART STATUS TROUBLE alarmed [S48.1.A 4.7.7] RO VERIFY "OVERRIDE (amber) light not Lit [S48.1.A 4.7.8] I RO PLACE SS-48-104C-1 switch to "ENABLE" positi9n [S48.1.A 4.7.9] RO/PRO VERIFY annunciator 107 A-3 SLCS PUMP STATUS TROUBLE clears [S48.1.A 4.7.10/11] RO INSTALL fuse F2 and F3 in panel C640 to arm XV-48-1F004C The CRS References Tech Spec 3.1.5 and determines with 2 pumps and SRO corresponding explosive valves are operable. SEG-5006E RevOOO.doc SRRS: 30.126 Page 19 of 49

2. LIMERICK GENERATING STATION . Exelon Generation..

SIMULATOR EXERCISE GUIDE EVENT-2 APRM # 3 FAILS UPSCALE (Malfunction) Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger Manually actuate Trigger #i when requested by Lead Evaluator, to initiate APRM #3 Upscale At time 5 min after FSSV or EO action requested to investigate

  1. 3 APRM failure, report: "Unit 1, APRM #3 shows an internal failure on the ODA." Manually actuate Trigger .1LL when requested by Lyad Evaluator, to initiate '1A' Recirc Pump trip. I I " I ,, ' SEG-5006E RevOOO.doc SRRS: 30.126 Page 20 of 49 TIME 2. LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-2 APRM # 3 FAILS UPSCALE (Malfunction)

POSITION Lead Evaluator (or designee) Notes: The RO will identify APRM #3 fails upscale as the annunciator alarms. THE ODA on 1 OC603 panel will show APRM #3 upscale with all other APRMs reading normal. Reference appropriate ARC:

  • 108 B-3, APRM UPSCALE TRIP/I NOP
  • 108 F-3, ROD OUT BLOCK
  • 108 B-4, APRM UPSCALE [ARC MCR 108 B-3] Determine APRM #3 ODA has upscale trip with 'TRIP' message on display header CRS directs bypassing APRr'A #3 [ARC MCR 108 B-3] I RO places #3 APRM in Reference Tech Spec 3.3.1 and 3.3.6 and determines the requirement of 3 is met I Reset annunciators on panel 108 SEG-5006E RevOOO.doc

,, I SRRS: 3D.126 RO/PRO RO SRO RO SRO RO Page 21 of 49

3. LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EXERCISE GUIDE EVENT-3 '1A' REACTOR RECIRC PUMP SHAFT SIEZURE (Abnormal)

Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger At time 5 min when FSSV or EO directed to respond to investigate '1 A' Recirc Pump trip report: The '1 A' ASD feed breaker is tripped. There is nothing that is obvious wrong with it. " I ,, ,, SEG-5006E RevOOO.doc SAAS: 30.126 Page 22 of 49 TIME 3. LIMERICK GENERATING STATION Exelon Generation SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-3 '1A' REACTOR RECIRC PUMP SHAFT SIEZURE (Abnormal) POSITION Lead Evaluator (or designee) Notes: The 1 A Reactor Recirc Pump will experience a shaft seizure resulting in a trip of the 1A ASD. OT-104, Unexpected/Unexplained Positive or Negative Reactivity Insertion is normally entered during a reactivity addition event, and directs entry into OT-112, Unexpected/Unexplained Change in Core Flow, due to Recirc Pump trip. Reference ARCs as appropriate:

  • 111 B-1, 1A RECIRC ASD TRIPPED
  • 111 B-2, 1A RECIRC ASD MAJOR FAILURE
  • 111 D-2, 1A RECIRC PUMP MOTOR HI VIBRATION
  • 111 E-2, 1A RECIRC ASD 13 KV BKR TRIP
  • 107 H-2, REACTOR HI/LO LEVEL I 1* 1071-2, VIBRATION ALARM ALERT
  • 108 A-4, OPRM TRIPS ENABLED 3.1] SRO I Enter OT-104 Unexpected/Unexplained Positive or Negative, Reactivity Insertion and directs entering OT-112 [ARC-MCA 111 B-2/D-2] SRO Enter OT-112, Unexpected/Unexplained Change in Core Flow [OT-112, 2.0] Immediate Operator Action RO M()NITOR RPV level AND manually CONTROL RPV level, as required [Ot-112, 3.1] SRO I DIRECT RO to monitor for core THI indications
  • APRM flux level oscillations
  • APRM and LPRM signal changes from random to periodic variations
  • Period meter display strong positive to negative swings [OT-112, 3.2] SRO Direct OT-112, Att. 1 [OT-112, Att.1 step 5.0] PRO CLOSE HV-043-1 F031A, "A Recirc Pump Disch Viv" (DISCHARGE A) OR HV-043-1 F023A, "A Recirc Pump Suction Viv" (SUCTION A) for tripped Recirc Pump. [OT-112, Att.1step6.0]

PRO IF Recirc Pump discharge isolation valve is not required to be closed AND approximately 5 minutes have elapsed, THEN OPEN HV-043-1 F031A, "A Recirc Pump Disch Viv" (DISCHARGE A) OR HV-043-1 F023A, "A Recirc Pump Suction Viv" (SUCTION A) for tripped Recirc Pump SEG-5006£ RevOOO.doc SRRS: 3D.126 Page 23 of 49

3. LIMERICK GENERATING STATION Exelon Generation.

SIMULATOR EXERCISE GUIDE EVENT-3 '1 A' REACTOR RECIRC PUMP SHAFT SIEZURE (Abnormal) Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger " I ,, ,. SEG-5006E RevOOO.doc SRRS: 30.126 Page 24 of 49 TIME 3. 3. LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-3 '1 A' REACTOR RECIRC PUMP SHAFT SIEZURE (Abnormal) [OT-112, Att.1 step 7.0] Limit speed of operating Recirc Pump to <1510 rpm [OT-112, Att.1 step 8.0] IF possible, THEN Maintain flow in operating loop such that total core flow is >40 Mlb/hr [OT-112, Att.1 step 9.0] PERFORM S43.2.A, Shutdown of a Recirculation Pump, to ensure tripped Recirc pump is properly shutdown [OT-112, Att.1 step 10.0 GP-5 step 3.1.6] (If time permits) SELECT the new MCPR limit for SLO using S38.1.L I ENSURE Reactor Engineering enters new MCPR limit inti PMS Computer. [OT-112, Att.1step11.0] NOTIFY Chemistry that power change of greater than 15% occurred in less than one hour (Tech Spec 3.4.5) [OT-112, Att.1 step 12] (If time permits) REQUEST APRM channels calibrated for SLO [OT-112, Att.1 step 15] (If time permits) ENSURE ST-6-043-321-1, Daily Jet Pump Operability Verification For Single Recirc Loop Operation, performed [OT-112, Att.1 step 16] ENTER GP-5, Appendix 3, Unintentional Drop in Power [OT-112, 3.2 GP-5 App#3 step 3.1.1.2] PERFORM OT-112, Att. 3 to confirm operation in the authorized region of the Power/Flow Map [OT-112, 3.3] DEMAND a P-1 edit AND determine whether a Thermal Limit violation exists [OT-112, 3.4] IF any Thermal Limit violations exist, THEN ENTER GP-14 [OT-112, 3.5] CONSIDER reportability of Rx power excursion AND REFER to Discussion Step 6.17 [OT-112,Att.3, GP-5App#3 step3.1.1.5] Direct RO to insert control rods to exit restricted region of power/flow map (-45%) EVENT-3 '1A' REACTOR RECIRC PUMP SHAFT SIEZURE (Abnormal) SEG-5006E RevOOO.doc SRRS: 30.126 POSITION RO RO RO RO I ! I I RO I " I CRS I PRO I CRS ' ,, I SRO RO/SRO SRO SRO SRO I Page 25 of 49 " I *' ' LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EXERCISE GUIDE Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger Ensure Trigger#__!__ automatically actuates when either HV-043-1 F031A or HV-043-1 F023A is closed to initiate a low pressure FWH level transient ,; I ,, ' SEG-5006E RevOOO.doc SRRS: 30.126 Page 26 of 49 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 3. EVENT-3 '1A' REACTOR RECIRC PUMP SHAFT SIEZURE (Abnormal) Insert control rods IAW RMSI to reduce power to exit restricted region RO [GP-5 App#3 step 3.1.6.2] (time permitting) SRO ENSURE, within 4 hrs. ST-6-107-889-1, Thermal Limits Determination For Single Recirc Loop Operation, has been performed. [GP-5 App#3 step 3.1.6.3/4] (time permitting) SRO ENSURE ST-6-043-321-1, Daily Jet Pump Operability Verification For Single Recirc Loop Operation, and shiftly check sections of ST-6-107-590-*, Daily Surveillance Log/OPCONS 1, 2, 3, performed. Reference Tech Spec 3.4.1.1.a.1 for Single Loop Operations (time permitting) SRO With one reactor coolant system recirculation loop not in operation:

1. Within 4 hours: I a. Place the recirculation flow control system in the Local Manual mode, and, b. Reduce THERMAL POWER to:::; 74.9% of RATED THERMAL POWER, and, c. Limit the speed of the operating recirculation pump to less than or equal to 90% of rated pump speed, and d. Verify that the differential temperature requirements of Surveillance Requirement 4.4.1.1.5 are met if THERMAL POWER is :::; 30% of RATED THERMAL POWER or the recirculation loop flow in the operating loop is:::; 50% of rated loop flow, or suspend the THERMAL POWER or recirculation loop flow increase.

' ,, 2. Within 6 hours, change APRM and Rod Block setpoints for Sirigle Loop Ops SEG-5006E RevOOO.doc SRRS: 30.126 Page 27 of 49

4. LIMERICK GENERATING STATION Exelon Generation SIMULATOR EXERCISE GUIDE EVENT-4 Low Pressure FWH Level Transient Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger At time 5 min when FSSV or EO directed to respond to investigate 1 C and 2C Feedwater Heater High Level report: The 1 C Low Pressure FWH Levels have returned to normal. Ensure Trigger # __§___ automatically actuates when reactor power decreased to -65% as designated by Main Steam Total Flow, to initiate FWH high level, RDCS failure and In-Phase Core Power Oscillations " I ,, SEG-5006E RevOOO.doc SRRS: 30.126 Page 28 of 49 TIME 4. LIMERICK GENERATING STATION Exelon Generation*. SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-4 Low Pressure FWH Level Transient POSITION Lead Evaluator (or designee) Notes: During the power reduction the 1 C Low Pressure Feedwater heater (FWH) String will experience a level transient that will cause a temporary high high level condition of the string. This condition will initiate an automatic isolation of the FWH String. The condition will clear and the crew is expected to identify that the isolation is no longer required to go to completion and take actions to stop the closure and re-open the isolation valves. Reference ARCs as appropriate: PRO

  • 102 F-1, 1C FEEDWATER HEATER HI LEVEL
  • 102 F-2, 2C FEEDWATER HEATER HI LEVEL
  • 102 G-4, F/W HTRS 1&2 HI-HI LEVEL LP HTR STRING ISOLATION

[ARC MGR 102 G-4] '1 PRO Verify L.P. F/W HTR string inlet AND out1 1 et valve HV-06-101C AND HV-06-102C close , [ARC MGR 102 G-4] SRO/RO " IF low pressure heater string isolation is bccurring THEN Enter OT-104, (positive reactivity insertion) and maintain power below pre-transient value. [ARC MGR 102 G-4] ' PRO Attempt to reset alarm on MGR panel 102. [ARC MGR 102 G-4] PRO IF alarm clears, AND the MOV's are still in mid position, THEN: I a. Pull to stop HS-006-101C AND

b. Re-open HV-006-101C AND HV-006-102C.

SEG-5006E RevOOO.doc SRRS: 30.126 Page 29 of 49

5. LIMERICK GENERATING STATION Exelon
  • . SIMULATOR EXERCISE GUIDE EVENT-5 '6C' FWH ISOLATION WITH THI {Abnormal)

Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger Ensure Trigger # _5_ automatically actuates when reactor power decreased to -65% as designated by Total Steam Flow, to initiate FWH high level, RDCS failure and In-Phase Core Power Oscillations Ensure Trigger#__§_ automatically actuates when RMS is taken to SHUTDOWN, to initiate Feedwater Line break and drywell leak. At time 3 min after FSSV or EO action to verify 6C FWH level locally report: FWH level indicates high -30" Double Red Dots. IMPORTANT NOTE: " I DELETE malfunction MPR003A, In-Phase Qore Power Oscillations, on reactor scram. ,, ,, SEG-5006E RevOOO.doc SRRS: 30.126 Page 30 of 49 TIME 5. LIMERICK GENERATING STATION Exelon Generation*. SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-5 '6C' FWH ISOLATION WITH THI (Abnormal) POSITION Lead Evaluator (or designee) Notes: A high level in the '6C' FWH will result due to a malfunction of the FWH level controller. As a result of the high level in the FWH the Feedwater will isolate causing a rise in core reactivity, and a shift in the core power shape. The core is already operating in the RESTRICTED REGION of the Power/Flow Map due to the Recirc Pump trip where there is an increased potential for core THI. The RO will identify indications of THI using LPRM, APRM and SRM period meter indications. Reference ARCs RO

  • 102 G-3, 6C FEEDWATER HEATER HI LEVEL
  • 102 G-5, FEEDWATER HEATER 3/4/5/6 HI HI LEVEL ISOLATION

[ARC MGR 102 G-3] RO Dispatch operato,r to verify high level locally [ARC MGR 102 G-5] RO Verify extraction steam valve to 6C FWH closed '* [ARC MGR 102 G-5] RO/PRO Monitor Feedwater temperature decreasing [ARC MGR 102 G-5] SRO Re-Enter OT-104, Unexpected/Unexplained Positive or Negative Reactivity Insertion, and perform Attachment 3 [OT-104 Attach 1# 3] SRO/RO DETERMINE of FW inlet temperature reduction by comparing pre-transient and post-transient FW temperature from Core Power And Flow Log OR P-1. [OT-104 Attach# 3] SRO IF transient is due to Feedwater Heating isolation, THEN MAINTAIN power level in accordance with Attachment

  1. 8 guidelines

[OT-104 Attach# 3] SRO IF FW inlet temperature is not in the "Normal Operating Region" of Attachment 2 "Feedwater Inlet Temperature vs Core Thermal Power" in GP-5 Appendix 2,

  • REDUCE Rx power to in accordance with GP-5 Appendix 2, Planned Rx Maneuvering Without Shutdown, Section 3.1, Reducing Rx Power,
  • AND Reactor Maneuvering Shutdown Instructions until FW inlet temperature returns to the "Normal Operating Region". SEG-5006E RevOOO.doc SRRS: 30.126 Page 31 of 49
5. LIMERICK GENERATING STATION Exelon Generation.

SIMULATOR EXERCISE GUIDE EVENT-5 '6C' FWH ISOLATION WITH THI (Abnormal) Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger Ensure Trigger # _§_ automatically actuates when RMS is taken to SHUTDOWN, to initiate Feedwater Line break and drywell leak. " I ,, SEG-5006E RevOOO. doc SRRS: 30.126 Page 32 of 49 ----------*----- LIMERICK GENERATING STATION ,::::'"' Exelon Generation*. SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 5. EVENT-5 '6C' FWH ISOLATION WITH THI (Abnormal) Lead Evaluator (or designee) Notes: The OPRM System enabled region is APR Simulated Thermal Power (STP).2: 29.5% AND Recirc Drive Flow <60%. The RO will identify indications of THI using LPRM, APRM and/or period meter indications. Reference ARCs RO

  • 108 A-4, OPRM TRIPS ENABLED
  • 108 A-3, OPRM PRE-TRIP
  • 108 F-3, ROD OUT BLOCK [OT-104 Attach# 8] RO RO identifies abnormal swings on APRMs indications due to signal growth by two or more times than initial levels, and with APRM flux level oscillations I exceeding 10% peak-to-peak.

I I Notify CRS THI identified RO *i Direct manual scram SRO PLACE Reactor Mode Switch in "SHUTDOWN" RO I Recognize/report indications for scram; RO

  • Scram annunciators for auto RPS actuation
  • White scram lights extinguished Enter T-101 SRO ' [T-101 RC-6] RO ,, Insert SAM and IRM detectors

' [T-101 RC/Q-1] RO Verify all control rods inserted [T-101 RC/Q-2] PRO Ensure turbine trip and gen lockout [T-101 RC/L-7] RO Restore and maintain RPV level between + 12.5" AND +54" [T-101 RC/L-7] PRO Ensure RCIC start and injection on RPV Level <-38" [T-101 RC/P-13] RO Stabilize RPV press below 1096 psig. SEG-5006E RevOOO.doc SRRS: 30.126 Page 33 of 49 LIMERICK GENERATING STATION Exelon Generation,, SIMULATOR EXERCISE GUIDE sn. EVENTS 6-7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE " I ,, Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger SEG-5006E RevOOO.doc SRRS: 30.126 Page 34 of 49 " I ,, ' TIME LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION sn. EVENTS 6-7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE Lead Evaluator (or designee) Notes: After the plant is scrammed a rupture of the 'A' Feedwater line occurs. The operator will identify the Feedwater line break as RPV level decreases and Primary Containment pressure rises. Recognize RPV level decreasing and Drywell pressure increasing RO/PRO Recognize 'A' FW Line Break RO Attempt to isolate 'A' Feedwater Line RO Report rising drywell pressure RO/PRO Enter and execute OT-101, Drywell High Pressure, as drywell pressure rises SRO [OT-101 3.1] PRO ESTABLISH Drywell pressure as a Critical Parameter I I Enter T-102, Primary Containment Control, and SRO Re-enter T-101, Reactor Control, on 1.68# Drywell Pressure ,; I Verify Isolations complete for> 1.68 psig drywell press. and RPV level <12.5" RO/PRO Secure from depressurization l?RO Evaluate closing MSIV's to conserve RPV inventory SRO [T-101 RC/L-12] SRO Enter T-111 on lowering RPV level I ' [T-111 LR-5] pRO Manually inhibit auto ADS {Critical Task) ,, [T-111 LR-6] RO Maximize RPV Injection with CRD per T-240 [T-111 LR-6] PRO Maximize RPV Injection using RCIC Identify RCIC flow controller in AUTO failed PRO Direct to operate RCIC in Manual mode SRO [T-111 LR-7] RO Start SLC Pumps [T-111 LR-8] PRO Start 2 or more subsystems (ie. C & D RHR Pumps) Identify RPV level decreasing -approaching LOCA -129" Crew SEG-5006E RevOOO.doc SRRS: 30.126 Page 35 of 49 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE sn. EVENTS 6 -7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger At time 8 min after FSSV or EO action requested for T-240 field actions (Insert RCR019 to open 'B' CRD Pump discharge valve) and report: Field actions for T-240 are complete and standby pump ready for start. SEG-5006E RevOOO.doc SRRS: 30.126 " I ,, ,, Page 36 of 49 TIME LIMERICK GENERATING STATION Exelon Generation.. SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION sn. EVENTS 6

  • 7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE Enter SE-10, LOCA when RPV level <-129" Crew [SE-10 3.1] RO PLACE the following to "CLOSE"
  • 52-20224/CS, "D*24 Safeguard L.C. D*24-G-D MCC Bkr" (SAFEGUARDS B), on *BC661
  • 52-20124/CS, "D*14 Safeguard L.C. D*14-G-D MCC Bkr" (SAFEGUARDS A), on *AC661. [SE-10 3.2] RO PLACE to "RESET":
  • 43-22322/CS, "Div. 111 Non SFGD Instr. Panel" (INST AC 201 CONTROL PNL), on *CC661 I
  • 43-22422/CS, "Div. IV Non SFGD Instr. Panel" (INST AC 202 CONTROL PNL), on *DC661. *i Dispatch Equipment Operator to perform SE-10-1 field actions PRO [SE-10 4.3] I SRO Maintain ECCS for injection IF Low Pressure ECCS is not required to restore RPV level, THEN ALIGN per SSV direction.

Re-start of '1A' CRD Pump following LOCA and maximize: using T-240 RO Restart '1A' and '1 C' SLC Pumps following LOCA I RO ,, , , [T-240 4.2] RO Fully OPEN HV-46-1 F003, "Drive Water Pressure Control" (DRIVE WATER PRESSURE), at 1 OC603 (Main Control Room). [no power available] [T-240 4.3] RO OPEN FV-C-46-1 F002A(B), "Flow Control," at 10C603 (Main Control Room) using FC-46-1 R600, "Rod Drive Flow Controller" (FL), in "MANUAL" to maximize CRD flow, while maintaining greater than 1,200 psig as indicated on Pl-46-108A(B), "CRD Pump Discharge" (252-T6-200). [T-240 4.4] RO OPEN 46-1 F045, "CRD Pumps Suction Filter Bypass Valve" (EO) [T-240 4.5] RO If additional CRD flow required place second CRD Pump in Service Trend RPV Level to T AF RO/PRO SEG-5006E RevOOO.doc SRRS: 30.126 Page 37 of 49 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EXERCISE GUIDE sn. EVENTS 6-7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger SEG-5006E RevOOO.doc SRRS: 30.126 " I ,, ,, Page 38 of 49 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE TIME II ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION sn. EVENTS 6-7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE EVALUATORS NOTE: The following steps are directed from T-102 to address the rise in Containment pressure. T-225, Startup and Shutdown of Suppression Pool (Section 4.2) and Drywell Spray Operation (Section 4.5) is used to control containment pressure. [T-102 PC/P-7] SRO DIRECT before Supp Pool pressure reaches 7.5 psig Spray the Suppression Pool per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation [T-225 4.2.1] PRO ENSURE HV-51-1F004A(B), "1A{B) RHR Pump Suction PCIV" (SUCTION A(B)), open [T-225 4.2.2] i PRO ENSURE the following valves closed: I

  • HV-51-1F006A(B), "1A(B) RHR Pp S/D Clg Suet lntertie Viv
  • HV-51-1F015A(B), "1A(B) Shutdown Clg Injection PCIV"
  • HV-51-1 F016A(B), "1 A(B) RHR Cntmt Spray Line Outboard PCIV
  • HV-51-1F017A(B), "1A(B) RHR LPCI lnj PCIV" [T-225 4.2.3] PRO IF RHR pump not running THEN start 1A(B)P202 "RHR Pump" [T-225 4.2.4] i PRO ENSURE the following valves oper:i: ,,
  • HV-51-1 F047A(B), "1A RHR Htx Shell Side Inlet Viv" (INLET)
  • HV-51-1 F003A(B), "1A RHR Htx Shell Side Outlet Viv" (OUTLET)
  • HV-C-51-1 F048A(B), "1A RHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS) [T-225 4.2.5] PRO OPEN HV-51-1 F024A(B), "1A RHR Pp Full Flow Test Return Viv" (SUPP POOL CLG A AND OBTAIN flow of 8,000 to 8,500 gpm as indicated on Fl-51-1R603A, FL. [T-225 4.2.6] PRO OPEN HV-51-1F027A(B), "1A RHR Supp Pool Spray Line PCIV" (SUPP POOL SPRAY). [T-225 4.2.8] PRO PLACE RHR Service Water Pump for RHR Heat Exchanger to be used in service per S12.1.A, RHR Service Water System Startup. SEG-5006E RevOOO.doc SRRS: 30.126 Page 39 of 49 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EXERCISE GUIDE sn. EVENTS 6-7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger SEG-5006E RevOOO. doc ., I ,, ,. SRRS: 30.126 Page 40 of 49 TIME LIMERICK GENERATING STATION Exelon Generation*. SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION sn. EVENTS 6-7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE [T-225 4.2.9] PRO CLOSE HV-C-51-1F048A(B), "1A AHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS). [T-225 4.2.1 OJ PRO IF more spray flow is required, THEN REDUCE flow through Full Flow Test line by throttling closed HV-51-1F024A(B), "1A AHR Pp Full Flow Test Return Viv" (SUPP POOL CLG A. EVALUATORS NOTE: The following steps are performed as directed by S12.1.A, AHR Service Water System Startup. [S 4.1.4/5 or App1 1.3] PRO

  • OPEN HV-51-1 F014A(B), HEAT EXCHANGER INLET . I
  • Throttle OPEN HV-51-1 F068A(B) for 18 to 20 seconds . 4.1.6(7) orApp1 1.4] PRO VERIFY' Pl-51-105A-1 (B), HX DISCH, indicates system static pressure greater than or equal to 15 psig. ' [S12.1.A 4.1.8 or App1 1.4] PRO IF the HI RAD AND/OR HI Pump Discharge pressure trips need to be bypassed AND the required actions of ODCM Part 1 Control 3.1.1 have been met for the INOPERABLE RHRSW Radiation Monitor, THEN PLACE HSS-12-002A(B), PUMP TRIP BYPASS, in "BYPASS." [S12.1.1:\

4.2.1.1 or App1 1.6] PRO IF 'A' Loop pump (OA(C)-P506) is to be placed in service, THEN ENSURE OA-V543 OR OC-V543, Spray Pond Pump Room Fans, in "RUN" at OOC681. [S12.1.A 4.2.1.2 or App1 1.7] PRO IF 'B' Loop pump (OB(D)-P506) is to be placed in service, THEN ENSURE OB-V543 OR OD-V543, Spray Pond Pump Room Fans, in "RUN" at OOC681. [S12.1.A 4.2.2 or App1 1.8] PRO START OA(B),(C,D)P506, RHRSW PUMP. [S12.1.A 4.2.3 or App1 1.9] PRO THROTTLE HV-51-1F068A(B) to the maximum obtainable position without exceeding 11,000 gpm on Fl-51-*R602A(B) while maintaining pump disch pressure (Pl-12-001A-1(8) between 75 psig to 85 psig. SEG-5006E RevOOO.doc SRRS: 30.126 Page 41 of 49 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE sn. EVENTS 6 -7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger ., I " ,, SEG-5006E RevOOO.doc SRRS: 30.126 Page 42 of 49 " ' ,, LIMERICK GENERATING STATION =ii Exelon Generation, SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION sn. EVENTS 6-7 '1A' FEEDWATER LINE RUPTURE I RCIC CONTROLLER FAILURE EVALUATORS NOTE: The following steps are performed as directed by T-225 section 4.5 to spray the Drywell. ' [T-225 4.5.3] PRO IF RHR pump not running THEN START 1A(B)P202 "RHR Pump." [T-225 4.5.4] PRO ENSURE the following valves open:

  • HV-51-1 F047A(B), "1A(B) RHR Htx Shell Side Inlet Viv" (INLET)
  • HV-51-1F003A(B), "1A(B) RHR Htx Shell Side Outlet Viv" (OUTLET)
  • HV-C-51-1F048A(B), "1A(B) RHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS) [T-225 4.5.5] TRIP Reactor Recirc Pumps. PRO/RO [T-225 4.5.6] PRO/RO REMOVE Drywell Cooling Fans from service by placing all 16 Drywell Cooler Fan switches to "OFF." [T-225 4.5.7] PRO IF Drywell High Pressure AND LOCA signals are present, THEN GO TO T-225 step 4.5.11. [T-225 4.5.11] PRO OPEN HV-51-1 F024A(B), "1A(B) AHR Pp Full Flow Test Return Viv" (SUPP POOL CLG A(B)), AND OBTAIN flow of 9,250 to 10,500 gpm as indicated on Ff-51-1 R603A(B), FL. [T-225 4.5.12] OPEN only one loop HV-51-1 F021A(B), "1A(B) AHR Cntmt PRO Spray Line Inboard PCIV" (INBOARD).

[T-225 4.5.13] PRO/SRO REQUEST SSV verify drywell temperature AND drywell pressure are on SAFE side of Drywell Spray Initiation Limit Curve per T-102, Primary Containment Control OR SAMP-1, RPV and Primary Containment Flooding Control. [T-102 PC/P-9] SRO DIRECT to Spray the Drywell per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation (Critical Task) [T-225 4.5.14] PRO Throttle OPEN only one loop HV-51-1 F016A(B), "1A(B) AHR Cntmt Spray Line Outboard PCIV" (OUTBOARD) to initiate spray AND OBSERVE raising flowrate as indicated on Fl-51-1 R603A(B), FL. SEG-5006E RevOOO.doc SRRS: 30.126 Page 43 of 49 I ! ,, I ', " I ,, 8. LIMERICK GENERATING STATION Exelon Generation SIMULATOR EXERCISE GUIDE EVENT-8 '1M' SRV FAILS TO OPEN (Malfunction) Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger SEG-5006E RevOOO. doc SRRS: 30.126 Page 44 of 49 " I ,, ' TIME 8. LIMERICK GENERATING STATION Exelon Generation SIMULATOR EXERCISE GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-8 '1 M' SRV FAILS TO OPEN (Malfunction) POSITION Lead Evaluator (or designee) Notes: As RPV level drops to -161" the crew will enter and execute T-112, Emergency Slowdown to rapidly depressurize the RPV. SRVs are the preferred mechanism to discharge steam. As the operator opens 5 SRVs the '1 M' SRV will fail to open. As the crew identifies the failed SRV, another SRV will be opened until a total of 5 SRVs are open. [T-111 LR-1 OJ SRO When RPV level drops to -161 inches, or when the safe side of the PSP curve cannot be maintained enter T-112 (Critical Task) Enter T-112, Emergency Slowdown SRO [T-112 EB-12] SRO DIRECT Open all 5 ADS valves I [T-112 EB-12] I PRO PERFORM Open all 5 ADS valves (Critical Task) I Recognize that the '1 M' SRV failed to open (Malfunction) " PRO The CRS directs to open additional non ADS SRVs until a total of 5 SRO ADS/SRVs are open I [T-111 LR-20] Crew Maximize RPV injection using all available systems subsystems and alt subsystems EXCEEDING pump NPSH and vortex limits if necessary. Restore RPV Level restored above TAF (Critical Task) I Crew [T-111 LR-2] ' SRO ,, When RPV level above -161" exit T-111 and re-enter T-101 at RC/L-1 Restore RPV Level to +12.5" to 54" with ECCS RO/PRO EVALUATORS NOTE: The scenario may be terminated when the Emergency Slowdown is complete, RPV level is restored to normal band with ECCS systems and Containment Spray is in service. After the scenario is terminated, direct the SRO to make the highest EAL classification for the scenario. EAL: declaration due to: (RC.3.1 and RC.3.2)

  • Drywell pressure > 1.68 psig AND
  • Drywell pressure rise is due to RCS leakage SEG-5006E RevOOO.doc SAAS: 30.126 Page 45 of 49 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EXERCISE GUIDE Attachment 1 Simulator Operator Response Times Procedure Performance T-209 Injection from the Standby Liquid Control Storage Tank with the RCIC System T-212 Bypassing SQUIB Valves for SLC Injection T-215 De-energization of Scram Solenoids T-216 Manual Isolation and Vent of Scram Air Header T-217 RPS/ARI Reset and Backup Method of Draining Scram Discharge Volume I T-219 Maximizing CRD Cooling Water Header Flow during ATWS T-221 MSIV Isolation Bypass Procedure T-225 Startup and Shutdown of Suppression Pool and Drywell Spray ,, I Operations T-240 Maximizing CRD flow after Shutdown During Emergency Conditions T-245 RPV Injection from AHR S/D Cooling T-248 Injection from SLC Test Tank to RPV T-251 Establish a HPCI Injection flow Path VIA Feedwater Only '1 T-270 Terminate and Prevent Injection into the RPV ,, ,, T-290 Instrumentation Available for T-103 SAMP-2 S46.7.A Control Rod Drive Hydraulic System Operation Following Reactor (4.2.1) Scram (Securing CAD flow to the Reactor -Close 46-1 F060, CAD Water Pressure Control Station Inlet Valve) SE-10-1 Breaker Reset Following LOCA (Also reset ARMs, RHRSW Rad Resets and Monitor and RDCS) Floor action SEG-5006£ RevOOO.doc SRRS: 30.126 Response Time (Minutes) 45 19 7 7 17 23 11 8 8 12 15 6 7 5 7 10 Page 46 of 49 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EXERCISE GUIDE CREW: ___ _ DATE: ___ _ START SM: -----CRS: ____ _ PERSON PERSON TIME BEING CALLING CALLED SEG-5006E RevOOO. doc Attachment 2 Communications Log LSEG: ----STOP TIME:----RO: WCS: -----------PRO: -----FSSV: ____ _ CALL COMMUNICATION I REQUEST BACK TIME i I I I I ' ,, I SRRS: 30.126 Page 47 of 49

LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE This Page Intentionally ,, Blaiik ,, ' Page 48 of 49 LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EXERCISE GUIDE XII. CREW PREBRIEF INSTRUCTIONS Unit 2 is in OPCON 1 at 100 % power Unit 1 is in OPCON 1 at 100 % power Specific Plant Conditions are as Follows:

  • None Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):
  • None Restrictions on Plant <;>perations:
  • None I Planned Evolutions:
: I
  • Place '1 C' SBLC Pump in Automatic Injection Mode per S48.1.A, Standby Liquid Control System Set-Up For Normal Operation, step 4.7 in preparation of a '1 B' SLC System Outage Window Documents Provided:

I

  • S48.1 .A, Standby qquid Control System Set-Up For Normal Operation

,, ' Page 49 of 49 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE CODE NO: SEG-2007E REV NO: AUTHOR: T.A.BYERS APPROXIMATE RUN TIME: TYPE: SIMULATOR EVALUATION EFFECTIVE DATE: GUIDE PROGRAM: LICENSED OPERATOR TRAINING 002 65 minutes COURSE: LICENSED OPERATOR (REQUALIFICATION/INITIAL) TRAINING TITLE: Simulator Evaluation Guide for Individual and Crew Performance .; I Prepared By: Reviewed By: ,, Reviewed By: Reviewed By: Approval: Approved For Use: SEG-2007E Rev002.doc Date: Training Instructor -Signature Date: LORT Lead Instructor -Signature Date: EP (as appropriate) -Signature N/A Date: N/A RE (as appropriate) -Signature Date: OPS Manager -Signature Date: Training Manager -Signature SAAS: 30.126 Page 1 of 47 LIMERICK GENERATING STATION Exelon Generation.* SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-2007E Rev_2_ Op-Test No.: 1 Examiners: Operators: Initial Conditions: Unit 1 is at 90% power. Unit 2 is at 100% power. Turnover: I Withdraw Control Rods per ReMA and raise Recirc flow to return to 100% Reactor power '1 BJ EHC Pump is blocked for pump replacement. Repairs are scheduled to be.complete in two (2) Maintain 100% power and support PMT of '1 B' EHC pump when it is returned to operations. I Event Malfunction Event Event No. I Number Type* Description

1. None R-RO Raise Power with Control Rods 2. I MRD016E C-RO Control Rod ( 46-15) uncoupled (Abnormal)

{46-15) TS-SRO ' : 3. MAD149E C-RO '1 N' SRV fails open I closes when Rx power lowered to <90 % C-PRO (Abnormal) C-RO 4. MCS183C C-PRO Inadvertent Div 4 LOCA Signal (Abnormal) TS-SRO 5. MRH172D C-PRO '1 D' RHR Pump fails to auto start (Malfunction) TS-SRO 6. MRR441 C-PRO Small leak in Drywell (Abnormal)

7. MMS067 M-ALL Large Steam Leak in Drywell 8. MRH600B C-PRO '1 B' RHR Pump Trips (Malfunction)
9. MRH573A C-PRO HV-51-1 F024A Thermal Overload condition (Malfunction)
  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-2007E Rev002.doc SRRS: 30.126 Page 2 of 47 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE I. QUANTITATIVE ATTRIBUTES A. ILT Target Quantitative Attributes (Per Scenario; See ES-301 Section 0.5.d) 1. Malfunctions after EOP entry (1-2) 2. Abnormal events (2-4) 3. Major transients (1-2) 4. EOPs entered/requiring substantive actions (1-2) 5. EOP contingencies requiring substantive actions (0-2) 6. EOP based Critical tasks (2-3) ACTUAL NUMBER 2 4 1 2 1 2 ,; I Review TQ-AA-151 attachment 5 and ES-301-5 for individual position requirements for scenario and scenario set ' SEG-2007E Rev002.doc SRRS: 30.126 ,, 1' Page 3 of 47 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE II. PURPOSE: Systematically evaluate individual and team performance to identify areas for improvement.

Critical Tasks and Assessment Items from this evaluation guide are to be used to assess crew and individual performance and as input into a 4.0 Crew Critique Process. Ill. SIMULATOR EVALUATION GUIDE OBJECTIVES: A. The following evaluation objectives apply to the Crew (C), Shift Manager (SM), Control Room Supervisor (S), Unit Reactor Operator I Plant Reactor Operator (R), or Incident Assessor I Shift Technical Advisor (A) as indicated in the following categories.

1. The general condition for each of the evaluation objectives will be "Given the plant conditions and sequence of events in the Simulator Evaluation Guide (SEG)". 2. The general acceptable evaluation objective criteria for each of the evaluation objectives will be "To perform effectively as an individual and contribute to successful crew performance in accordance with appropriate reference plant procedures and Operations Expectations, Fundamentals and Strategies".
3. Specific UNSAT evaluation objective criteria will be consistent with TQ-AA-155, Conduct of Simulator Training and Evaluation with applicable forms and job aids. I 4. During performance of this Simulator Evaluation Guide, the individuals and crew should satisfactorily demonstrate the following overall procedure and plant control
  • Direct and perform actions per ON-104, Control Rod Problems . I
  • Direct and perform actions per OT-101, Drywell High Pressure I
  • Direct and perform actions per OT-104, Unexpected/Unexplained Positive or Negative Reactivity Insertion.
  • Direct and perform actions per OT-114, Inadvertent Opening of a Relief Valve
  • Direct and perform actions per SE-10, LOCA
  • Direct and perform actions per OT-101, High Drywell Pressure
  • Direct and perform actions per OT-102, Reactor High Pressure
  • Direct and perform actions per T-112, Emergency Slowdown SEG-2007E Rev002.doc SRRS: 30.126 ,, I' Page 4 of 47

. LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE IV. RECORD OF TEMPORARY CHANGES: A. B. c. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change LORT Action Revision Change# Change Approval Tracking Date REVISION HISTORY: V. A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

  • i B. The description of the Revision should adequately indicate how' the training content of the Revision has changed. c. The description of the Revision should also include previous for'mat reference and number and previous template used (e.g for conversion of LSTS to LLORSEG format). Revision Description of Revision and Affect on Training Content # Date of Number Revision I This is a reformat to the new SEG Evaluation template.'Jhis replaces RevOOO LSES2007 Rev 9. Deleted '1N' SRV failing open and added HV-51-1 F024A 10/28/13 Thermal Overload.

Rev001 Revised to new template, and control rod drift 9/2/15 Rev002 Revised to new template, changed to control rod uncoupled, and open SRV 7/22/16 response I # Date of Revision -refers to date revision was released for approval SEG-2007E Rev002.doc SRRS: 30.126 Page 5 of 47 . LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

Events One and Two: Evaluation:

Event Three: Evaluation: Event Four: Evaluation: Event Five: Evaluation: As the crew assumes responsibility for the shift, they are directed to withdraw Control Rods and adjust Recirc flow per the ReMA and return the reactor to 100% power. During the power ascension and as Control Rod 46-15 is being withdrawn, a "Rod Overtravel" alarm will annunciate, and Control Rod 46-15 will become uncoupled. To evaluate the crews ability to raise Recirc flow and withdraw Control Rods per a ReMA, and when the 'Rod Overtravel' alarms, identify an uncouple Control Rod, implement ON-104, Control Rod Problems, and OT-104, Unexpected/ Unexplained Positive or Negative Reactivity Insertion, isolate the Control Rod ( 46-15) and evaluate Tech Specs for the INOP Control Rod. When the Control Rod has been fully inserted as by the ON procedure, and Tech Specs are evaluated for the Control Rod being INOP, the '1 N' SRV will inadvertently open. The SRV will close when react9r power is lowered to -90%. I To evaluate the crews' response to an open The crew will enter and execute OT-114, Inadvertent Opening Of A Relief Valve. The crew will identify that when reducing reactor power to -90%, per the OT procedure, the SRV closes. The crew will then evaluate the plants response to the now closed SRV. After the SRV is closed, an inadvertent Division 4 (OCA signal will occur. To evaluate the crews response to use MCR instrumentation and determine the Division 4 LOCA signal is inadvertent. The crew will identify the cause of the Division 4 LOCA signal to be an excess flow check valve actuation. The crew will recognize a reactor power increase and that HPCI is running and injecting into the RPV, and isolate the HPCI system. The crew will also identify the 014 EOG running unloaded, and a Core Spray Pump running. The CRS will determine the required Tech Spec Actions for systems that are unavailable due to the LOCA signal. During the inadvertent Division 4 LOCA signal, the '1 D' RHR Pump will fail to auto start. To evaluate the crews response to the failure to auto start of the '1 D' RHR Pump. Identify the Tech Spec requirements for an RHR system that failed to auto start. SEG-2007E Rev002.doc SRRS: 30.126 Page 6 of 47 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

cont'd: Events Six and Seven: Evaluation: Event Eight and Nine: Evaluation: Termination Point: When actions for the inadvertent LOCA signal are complete, a gradually increasing coolant leak in the drywell will develop requiring the plant to shutdown. Following Plant shutdown a large steam leak into the Drywell will occur which will eventually require a T-112, Emergency Slowdown be performed. To evaluate the crews response to increasing drywell pressure and temperature, including the initial execution of OT-101, Drywell High Pressure, and eventually a plant shutdown and execution of T-101, RPV Control, and T-102, Primary Containment Control. The '1 B' RHR Pump, which was placed in service when the SRV opened, trips on a time delay after the plant is shutdown, and when the crew transitions to the 'A' Loop of RHR for containment cooling, the HV-51-1 F024A, 'A' Loop RHR Test Return Valve, will trip on a Thermal Overload conditif n. To evaluate the crew's respcinse to the tripped '1 B' RHR Pump and to transition the '1 A' RHR Pump when directed to re-direct from Suppression Pool Spray to Drywell Spray. As the crew re-direc,ts to 'A' RHR for Drywell Spray they will manually open the HV-51-1 F024A valve when a thermal overload trip is identified. The scenario may be terminated when an Emergency Depressurization has been performed, Drywell Spray is in 1 service, control rods inserted and reactor level is restored. ':: SEG-2007E Rev002.doc SRRS: 30.126 Page 7 of 47 LIMERICK GENERATING STATION Exelon Gener*ation. SIMULATOR EVALUATION GUIDE VI. REFERENCES A. Training Procedures

1. TQ-LG-150, Limerick Operator Training Programs 2. TQ-AA-151, ILT Certification and NRC Examination Development and Administration
3. TQ-AA-155, Conduct of Simulator Training and Evaluation B. Annunciator Response Cards (ARC) 1. 002 0-4, B CONTROL STRUCTURE CHILLER OUT OF SERVICE 2. 002 A-1, CONTROL ROOM RADIATION ISOLATION
3. 004 B-1, B DRYWELL CHILLER TRIP/FAILED TO START 4. 004 B-4, DIV I/II ARCS CHANNEL ACTIVATED
5. 103 B-3 DRYWELL FLOOR DRAIN HI LEVEL 6. 107 H-2, REACTOR HI/LO LEVEL 7. 107 F-2, DRYWELL HI I LO PRESS 8. 108 F-5, ROD OVERTRAVEL 1 9. 110 B-1, SRV/HEAD VENTVALYE LEAKING 10. 110 B-2, SAFETY RELIEF VALVE OPEN 11. 112 H-1, RWCU PUMP SUCTION LO FLOW 12. 112 C-5, DRYWELL EQUIP ORN TK/FLR ORN SUMP LEAKAGE HI FLOW 13. 112 E-5, EXCESS FLOW CHECK VALVE OPERATED 10C218 14. 113 B-5, CORE SPRAY LINE INTERNAL BREAK 15. 114 C-2, REACTOR LO-LO LEVEL 16. 114 0-1, DIV 4 NSSSS MSIV INITIATED
17. 114 C-2, REACTRO LO-LO LEVEL 18. 114 0-1, DIV 4 NSSSS MSIV INl,TIATED
19. 115 H-3, REACTOR LO-LO-LO 'LEVEL I 20. 115 1-1, DIV 4 AHR AUTO START 21. 115 0-1, DIV 4 CORE SPRAY AUTO START 22. 115 B-5, DRYWELL COOLER DRAIN FLOW HIGH 23. 118 C-2, 1B INSTRUMENT AIR HOR LO PRESS C. System Procedures (S) 1. S73.1.A, Normal Operation of the Reactor Manual Control system 2. S51.8.A App. 1, Placing AHR SP Cooling in Service During a Plant Event 3. S12.1.A App. 2, RHR Service Water System Dual Loop Startup Hard Card 4. S78.7.A, Control Room HVAC System Restoration from an Isolation
5. S87.1.A App. 1, Startup of Standby/Tripped Drywell Chiller Hard Card 6. S91.6.B App. 1, Transferring House Loads to S/U Buses Hard Card D. General Procedures (GP) 1. GP-3, Normal Plant Shutdown 2. GP-4, Rapid Plant Shutdown to Hot Shutdown E. Off Normal Procedures (ON) 1. ON-104, Control Rod Problems F. Operating Transient Procedures (OT) 1. OT-101, High Drywell Pressure SEG-2007E Rev002.doc SRRS: 3D.126 Page 8 of 47

. LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE REFERENCES cont'd 2. OT-104, Unexpected/Unexplained Positive or Negative Reactivity Addition 3. OT-114, Inadvertent Opening of a Relief Valve G. Event Procedures (E) H. Special Event Procedures (SE) 1. SE-10, LOCA I. Surveillance Test and Routine Test Procedures (ST and RT) J. Technical Specifications and TRM (TS) 1. 3.1.3.1, Control Rod Operability

2. 3.1.3.6, Control Rod Drive Coupling 3. 3.3.3, Emergency Core Cooling System Actuation Instrumentation 3.5.1, ECCS -Operating
4. TAM 3.4.4, Reactor Coolant System -Chemistry
5. 3.4.3, Reactor Coolant System -Leakage Detection Systems 6. 3.5.1, Emergency Core Cooling Systems K. Transient Response, Implementation Procedures (T-100 series)/SAMPs
1. T-101, RPV Control 2. T-102, Primary! Containment Control 3. T-112, Emergency Blowdown L. TRIP 200 Series Procedures
1. T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation M. EP-AA-1008, Limerick, Radiological Emergency Plan Annex for Limerick Generating Station N. Administrative Procedures
1. OP-AA Procedures
a. OP-AA-1, Conduct of Operations
b. OP-AA-20, Conduct of Operations Process Description
c.

Operations Department Standards and Expectations

d. OP-AA-101-'113, Operations Fundamentals
e. OP-AA-101-i 13-1006, 4.0 Crew Critique Guidelines
f. OP-AA-103-102-1001, Strategies For Successful Transient Mitigation
g. OP-AA-106-101-1006, Operational Decision Making Process 2. OP-LG Procedures
a. OP-LG-101-111-1000, Licensed Operator Duties b. OP-LG-102-106, Operator Response Time Program at Limerick c. OP-LG-103-102-1000, Human Performance Continuing Good Practices
d. OP-LG-103-102-1002, Strategies for Successful Transient Mitigation
e. OP-LG-108-101-1001, Simple Quick Acts I Transient Acts 0. Current Shift Night Orders Forced Outage Plan P. INPO Significant Operating Experience Reports (SOER), Significant Event Reports (SER) and INPO Event Report9 (IER) 1. I ER-L 1 11-3, Weaknesses in Operator Fundamentals
2. SER 3-05, Weakness in Operator Fundamentals
3. SOER 10-02, Engaged Thinking Organizations
4. INPO 15-004, Operator Fundamentals SEG-2007E Rev002.doc SRRS: 30.126 Page 9 of 47 LIMERICK GENERATING STATION Exelon Generation

.. SIMULATOR EVALUATION GUIDE VII. PREBRIEF INSTRUCTIONS Unit 2 is in OPCON 1 at 100% power Unit 1 is in OPCON 1 at 90% power Specific Plant Conditions are as Follows:

  • Reactor power reduced to 90% due to Control Rod pattern adjustment Inoperable/Out of Service Equipment and Estimated Time of Return (ETR): * '1 B' EHC pump is blocked for replacement
  • Repairs are scheduled to be complete in 2 hours I Restrictions Jn Plant Operations:
  • None " I Planned Evolutions:
  • Raise Reactor power to 100%
  • Continue replacement of '1 B' EHC pump and perform PMT when complete I " Documents Provided:
  • ReMA and Control Rod Move Sheet (with control rod steps 1-16 signed off )
  • GP-5 Attachment 1 (signed off to step 2.6)
  • S73.1 .A, Normal Operation of the Reactor Manual Control System SEG-2007E Rev002.doc SRRS: 30.126 Page 10 of 47

. LIMERICK GENERATING STATION Exelon Gener*at1on, SIMULATOR EVALUATION GUIDE VIII. DIRECTIONS FOR EVALUATION PREPARATION A. INITIAL PREPARATION ., ITEM I MALFUNCTION I REMOTE FUNCTIONS Complete TQ-AA-155, Operator Training Programs Attachment 02, Evaluated Scenario Administration Checklist. Complete TQ-LG-201-0113, Limerick Training Department Simulator Examination Security Actions Checklist B. SIMULATOR SETUP ., ITEM I MALFUNCTION I REMOTE FUNCTIONS Complete Limerick Simulator Pre-Evaluation Checklist I I Reset Simulator to the Pre-loaded Cycle IC developed for the Evaluation ' OR Reset the simulator to designated base load IC-3 ,f AND Load scenario file SEG2007E Rev002.scn I

  • Verify that all Malfunctions, Remotes, Overrides, Annunciators and Triggers are properly loaded ' OR
  • Manually enter the Malfunctions, Remotes, Overrides, Annunciators and Triggers per the Scenario Generator Screen Shots: I Simulator Operator (Driver) perform the following:
  • Momentarily place simulator in RUN ' ,, Ensure reactor power is at 90% ,. *
  • Acknowledge and clear all spurious alarms
  • Place the simulator back into FREEZE
  • Place INFO tag on '1 B' EHC Pump with handswitch in PTL SEG-2007E Rev002.doc SRRS: 30.126 Page 11 of 47

" I ,, ,, . LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE C. MALFUNCTION/REMOTE/OVERRIDE/ANNUNCIATORS FUNCTION TIME TABLE Ma/function Summary * *** **** f Mall ID -J Mull ID J Desc1ipt!on l MR0016E js.15 . .Coot!Q(flod Failu!.e, Uncoopjed fP> . . :;, )MRH1720 ***** . */1 RHAP\ai1pJOfaMoAutoStatt IMAD149E . .. RelielValve IF013N) Fah Open: Mechanicaij , ! .. Line B1eak Downstream dX\142*1F045D '! ' .. j MRR441 Smal Coolant Leak in Drywell [0*100%)

  • MMS067 Steam Leak in 01ywelt I0-5000 gpm) MRHGOOB AHR Pump 1BP202 Elect Fault MRH57ll\ HV51*1F024AFailsdueto TheimalOVLD I Ti mer Pause SEG-2007E Rev002.doc False False 000 0.00 FALSE SRRS: 30.126 True ,_True 15.00000 2000.000 TRUE 00:00:15 . . 00:00:15 00:05:00 00:00:15 00:0000 '00:0200 00:05:00 Active
  • Pending Page 12 of 47 ,,

LIMERICK GENERATING STATION s Exelon Generation SIMULATOR EVALUATION GUIDE 0. EVENT TRIGGERS ASSIGNMENT 1 . Timers should be used on event triggers where possible for time validation

2. Timing of event triggers may be altered by the Lead Evaluator (or designee)
3. Verify triggers are actuated automatically as designed or manually initiate the trigger when the initiating action has occurred.
4. Inform Lead Evaluator (or designee) of expected plant response prior to actuation of each trigger. 5. Trigger #1 is manually initiated at Lead Evaluator (or designee) direction after the crew assumes responsibility for operation.

co TRIGGER I . TIME 1 2 3 4 5 6 favorites. Iriggers Trigger ti 2 3 4 ZRPS1SDN 5 G 7 8 9 10 11 12 13 , 14 15 16 17 18 19 Irigger Now SEG-2007E Rev002.doc b;lear MALFUNCTION I DESCRIPTION EVENT Manual Initiates '1 N' Safety Relief Valve fails open Manual XV-42-1 F045D Instrument Line breai I '1 D' RHR Pump failure to Auto Start , Manual Small coolant leak in Drywell ' I Auto I ZRPS1 SON RMS to SHUTDOWN Initiates Drywell Steam Leak I '1 B' pp trip N/A N/A Manual '1 N' Safety Relief Valve Fuse removed Operators: Arithmetic: Trigger Text . Multiplication I Division + Addition Subtraction Relational: > Greater than >= Greater than or equal < Less than <= Less than or equal ;{ == Equal to != Not equal to t Logical: && And II Or I Not ,_.::'.'..l Other: 2J Open Paren CloseParen CjearAll 8ccept SRRS: 30.126 Page 13 of 47 LIMERICK GENERATING STATION Exelon Gener*ation. SIMULATOR EVALUATION GUIDE E. EQUIPMENT REPORTS AND LEAD EVALUATOR (OR DESIGNEE) OPERATIONS 1 . This table section is moved and now integrated with Assessment of Crew Performance to facilitate simulator Operator and Instructor observation of crew activities related to simulator operation and instructor intervention.

2. Scripted Activity Reports should be followed with adherence to Operations Communication standards of performance.
3. The T-200 procedure reference book should be used for familiarity of reports to aid in operator prompting and expected communications.
4. The Lead Evaluator (or designee) should be informed if any event is not reported as scripted due to lack of Operator request. 5. The Standard Equipment Operator Response Times are per Attachment 1 6. A record of communications from the MCR and to the MCR will be maintained by the Simulator Operator using Attachment
2. 7. The OCOEE Simulator Operator Station P&IDs, Floor Plans and Panels must be used by the Simulator Operator as reference information when making reports to the MCR for plant parameters which are not driven by a communications script. Examples include: ARMs, Blowout Panel status, Reactor Building Area Temperatures and Pressures, Turbine Enclosure parameters etc. ' SEG-2007E Rev002.doc SRRS: 30.126 " I ,, '. Page 14 of 47 LIMERICK GENERATING STATION Exelon Generation.

SIMULATOR EVALUATION GUIDE IX. CREW CRITICAL TASKS A. Critical Tasks are based on the current Crew Critical Task List revision, NUREG 1021 and TQ-AA-150 requirements.

1. 2. 3. T-102.1 Spray the Drywell per T-225. KIA 295024 KIA 295028 KIA 295028 EA1.11 EA1 .01 EA1.04 4.2/4.2 3.8/3.9 3.9/4.0 Standard:

When Drywell temperature and pressure are on the SAFE side of curve PC/P-2, spray the Drywell before exceeding 340°F or 55 psig. SAT/UNSAT T-102.2 Perform emergency blowdown per 12. KIA 295024 EA1.08 EA2.04 3.9/3.9 " 3.9/3.9 I KIA 295024 Standard: When suppression Pool Pressure cannot be maintained below the Pressure Suppression Pressure (PC/P-3) curve and before Drywell pressure exceeds 55 psig, open 5 SRVs. SAT/UNSAT OT-114.1 Close the stuck open relief valve. *' I' KIA 239002 A2.03 4.1/4.2 Standard: Direct closure of the stuck open SRV by removing fuses or reducing turbine inlet pressure per OT-114. SAT/UNSAT SEG-2007E Rev002.doc SRRS: 30.126 Page 15 of 47 . LIMERICK GENERATING STATION Exelon Generation,, SIMULATOR EVALUATION GUIDE X. ASSESSMENT OF CREW PERFORMANCE DURING CONDUCT OF THE DYNAMIC SIMULATOR EVALUATIONS: A. Conduct the Simulator Evaluation Session per TQ-AA-155, Conduct of Simulator Training and Evaluation, Attachment 02, Evaluated Scenario Administration Checklist B. Assessment of Crew and Individual performance shall be consistent with OP-AA-20, Conduct of Operations Process Description C. Where possible record the time and position responsible for performance of each task or assessment item D. Items not performed as expected SHALL be discussed in the post performance crew critique E. During the performance of the evaluation, the Simulator Evaluators shall MAINTAIN notes of observations and information consistent with the timeline F. Assessment items with the CO symbol indicate a time critical standard for performance G. Assessment items with symbol indicate a Probabilistic Risk Assessment (PRA) association with the task H. The Simulator Operator will respond with scripted or proceduralized responses when requested by the MCR operators with Procedure completion times requested per Attachment 1 I. The Simulator Operator will also maintain a timeline and of all reports and requests issued by the MCR personnel with response provided by the simulator operator using Attachment 2 J. Shaded items do not require assessment for ILT Evaluations;;The CRS may be requested to complete the Shift ED forms and determine the EAL classification at the completion of the scenario. SEG-2007E Rev002.doc SRRS: 30.126 ,, Page 16 of 47 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE SEG-2007E Rev002.doc This Page Intentionally Blank 1i I ,, ,, SRRS: 30.126 ---------*-- '-----Page 17 of 47 LIMERICK GENERATING STATION Exelon Gener-at ion. SIMULATOR EVALUATION GUIDE 1/2. EVENTS 1 -2 RAISE POWER I CONTROL ROD UNCOUPLED (Abnormal) Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger. Respond to request for assistance as appropriate. SEG-2007E Rev002.doc " I ,, ' SRRS: 30.126 Page 18 of 47 TIME LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 112. EVENTS 1-2 RAISE POWER I CONTROL ROD UNCOUPLED (Abnormal) Lead Evaluator (or designee) Notes: As the RO withdraws control rods per the ReMA "Rod Overtravel" will alarm indicating a control rod has failed its coupling check. ON-104 will be referenced and the operator will perform a second attempt to verify the coupling check. When the second attempt fails the control rod will be declared Inoperable, fully inserted and isolated. Note: [ST-6-107-730-1 4.3.4] If a coupling check is signed off in ReMA/Control Rod Move Sheets, THEN copy of ReMA is normally attached to ST-6-107-730-1 Withdraw control rods IAW ReMA and S73.1.A RO [S73.1.A 4.3.3] RO SELECT the control rod to be withdrawn [S73.1.A 4.3.4] RO VERIFY correct rod position on four rod display [S73.1.A 4.3. fl RO Simultaneously, DEPRESS Withdraw and Continuous Withdraw pushbuttons to withdraw control rod [S73.1.A 4.3.8] RO I VERIFY proper RDCS light sequence for control rod withdraw [S73.1.A 4.3.1 O] RO WHEN control rod is located two notches before target position RELEASE Withdraw and Continuous Withdraw pushbuttons I (Note: Student may hold continuous withdraw to notch position 48 as permitted by Note 4 on Page 8 of S73.1.A) [S73.1.A 4.3.1'1] RO VERIFY the SETILE light Lit AND THEN extinguishes after -6.1.sec. [S73.1.A 4.3.12] RO IF control rod settles short of target position, THEN PLACE the control rod in target position using single notch withdraw per Section 4.2 [S73.1.A 4.3.13] RO VERIFY control rod has been withdrawn to target position at Four Rod Display [S73.1.A 4.3.14] RO IF control rod is positioned to notch position 48, THEN PERFORM an overtravel check per ST-6-107-730-1 , Control Rod Coupling Check Select next rod in sequence, repeat previous steps RO SEG-2007E Rev002.doc SRRS: 30.126 Page 19 of 47 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 1/2. EVENTS 1 -2 RAISE POWER I CONTROL ROD UNCOUPLED (Abnormal) Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger. Respond to request for assistance as appropriate. If RE's contacted for support for uncoupled control rod: report: "A Reactor Engineer is on the way to assist with a Recovery ReMA". At time 5 min after floor personnel are dispatched to isolate HCU (46-15), DELETE malfunction MRD016E for (46-15) and report: Valves 047-1-03-46-15 and 047-1-05-46-15 valves are closed for HCU (46-15). OR ! report: ON-1104 step 2.5.6.5 is complete for Unit 1 HCU 46-15. Manually actL1ate Trigger # when directed by Lead Evaluator, to initiate '1 N'SRV to fail open. ,, ' SEG-2007E Rev002.doc SRRS: 30.126 Page 20 of 47 . LIMERICK GENERATING STATION Exelon Gener*at1on., SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 1/2. EVENTS 1 -2 RAISE POWER I CONTROL ROD UNCOUPLED (Abnormal) Respond to RO

  • 108 F-5, ROD OVERTRAVEL Report alarm and notify SRO that control rod ( 46-15) may be uncoupled RO Enter ON-104, Control Rod Problems (Abnormal)

SRO [ON-104 2.5.6] RO IF reactor power is greater than 25%, then perform the following: -Insert the rod to position 46 -Withdraw the control rod to 48 and attempt a coupling check [ON-104 2.5.6.3] RO I IF coupling check unsuccessful DECLARE control rod INOP and continue I I I [ON-104 2.5.6.4] RO Fully continuously INSERT the control rod and MAINTAIN insert signal for 10 " seconds I [ON-104 2.5.6.5] RO I DISARM directional control valves by closing 047-1-03-46-15 and 047-1-05-46-15 vlvs Demand P-1 Edit (after rod settles at 00) RO i Contact RE for assistance SRO I Enter T.S. 3.1.3.6 -Control Rod Drive Coupling SRO ,, I' and T. S. 3.1.3.1 -Control Rod Operability for Control Rod (46-15) SEG-2007E Rev002.doc SRRS: 30.126 Page 21 of 47 ., I . LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE 1/2. EVENTS 1 -2 RAISE POWER I CONTROL ROD UNCOUPLED (Abnormal) ,, Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. Manually actuate Trigger #__!_when directed by Lead Evaluator, to initiate '1 N'SRV to fail open. IMPORTANT DRIVER NOTE: When Reactor power reduction initiated Manually DELETE MAD149E at <90% APRM power, to simulate closure of the '1N' SRV. *** OT-114 directs a GP-4 Shutdown if SRV remains open at 85% power*** SEG-2007E Rev002.doc SRRS: 30.126 Page 22 of 47 " I ,, ,, . LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 3. EVENT-3 1 1N 1 SRV INADVERTENTLY OPEN (Abnormal) Lead Evaluator (or designee) Notes: The '1 N' SRV will inadvertently open. The crew will enter and execute OT-114 for the open SRV. Two loops of Suppression Pool Cooling will be placed in service (Six minute requirement per OP-LG-102-108) and reactor power will be reduced to 85%. Since the SRV closes prior to reaching 85% reactor power, a GP-3 Shutdown will be performed. Reference AR Cs RO/PRO

  • 110 B-1, SRV/HEAD VENT VALVE LEAKING
  • 110 B-2, SAFETY RELIEF VALVE OPEN Recognize

'1 N' SRV open (confirming indications) PRO Enter OT-114, Inadvertent Opening Of A Relief Valve, and perform Immediate SRO Operator Actions (Abnormal) co [OT-114 IOA] !PRO . Place both loops Suppression Pool Cooling in service [S51.8.A App. 1 1.1] PRO START selected RHRSW loop per S12.1.A " I [S12.1.A App.2 1.3] PRO

  • OPEN HV-51-1F014A, HEAT EXCHANGER INLET '
  • Throttle OPEN HV-51-1 F068A for 18 to 20 seconds [S12.1.A App.2 1.4] PRO
  • OPEN HV-51-1F014B, HEAT EXCHANGER INLET I
  • Throttle OPEN HV-51-1 F068B for 18 to 20 seconds [S12.1.A App.2 1.5] PRO VERIFY Pl-51-105A-1, HX DISCH, indicates system static pressure greater than or equal to 15 psig [S12.1.A App.2 1.6] PRO VERIFY Pl-51-1058, HX DISCH, indicates system static pressure greater than or equal to 15 psig [S 12.1.A App.2 1.8] PRO ENSURE OA-V543 OR OC-V543, Spray Pond Pump Room Fans, in "RUN" at OOC681. [S 12.1.A App.2 1.9] PRO ENSURE OB-V543 OR OD-V543, Spray Pond Pump Room Fans, in "RUN" at OOC681. [S12.1.AApp.2 1.10] :PRO START OA(C)P506, RHRSW PUMP SEG-2007E Rev002.doc SRRS: 30.126 Page 23 of 47 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE 3. EVENT -3 '1 N' SRV INADVERTENTLY OPEN (Abnormal)

Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 min if requested to pull fuses per OT-114, Attachment 1: Manually actuate Trigger #6 to remove fuses for '1 N' SRV SEG-2007E Rev002.doc SRRS: 30.126 " I ,, Page 24 of 47 TIME 3. LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENTS-3 1 1 N' SRV INADVERTENTLY OPEN (Abnormal) [S12.1.A App.2 1.11] THROTTLE HV-51-1 F068A to the maximum obtainable position without exceeding 11,000 gpm on Fl-51-*R602A(B) while maintaining pump disch pressure (Pl-12-001A-1) between 75 psig to 85 psig [S12.1.AApp.2 1.12] START OB(D)P506, RHRSW PUMP [S12.1.AApp.2 1.13] THROTTLE HV-51-1 F068B to the maximum obtainable position without exceeding 11,000 gpm on Fl-51-*R602A(B) while maintaining pump disch pressure (Pl-12-001 B) between 75 psig to 85 psig [S51.8.A App.1 1.4] (Repeated for A Loop and B Loop) START 1 A(B) P202 RHR Pump I [S51.8.A App.1 1.5] (Repeated for A Loop and B Lodp) Throttle OPEN HV-51-1F024A(B) "RHR Pump Full Fl9wTest Return" AND MAINTAIN flow indicated on Fl-51-1 R603A(B) between 8000 to 8500 gpm [S51.8.A App.1 1.6] (Repeated for A Loop and B Loop) I CLOSE HV-C-51-1F048A(B) HEAT EXCH BYPASS [OT-114 3.1] DISPATCH EO to attempt SRV closure by pulling fuses using OT-114 Attachment 1 for PSV-41-1 FO 13N I [OT-114 3.2] ' ,, I' REDUCE Reactor power to 85% per RMSI [OT-114 3.3] Establish Suppression Pool Temperature as Critical Parameter CRS briefs stuck open SRV and contingency plans Crew trends Suppression Pool temperatures Crew identifies '1 N' SRV closed during power reduction CRS directs to perform a GP-3 Plant shutdown SEG-2007E Rev002.doc SRRS: 30.126

POSITION PRO PRO PRO PRO PRO PRO PRO RO SRO SRO PRO PRO/RO SRO Page 25 of 47 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE 4/5. EVENTS 4 -5 INADVERTANT DIV 4 LOCA SIGNAL/ '1 D' RHR PUMP FAILS Simulator Operator Instructions Respond to request for assistance as appropriate.

Inform Floor Instructor prior to each event trigger. At time 1 O min after FSSV or EO action requested for SE-1 O Floor Actions Load All SE* 1 O Floor Actions with Time Delays Scenario and report: "SE-1 O Floor Actions for Div 4 are complete" SEG-2007E Rev002.doc SRRS: 30.126 i " ' ,, Page 26 of 47 TIME LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 415. EVENTS 4-5 INADVERTANT DIV 4 LOCA SIGNAL/ '1 D' RHR PUMP FAILS Lead Evaluator (or designee) Notes: An instrument line downstream of excess flow check valve XV-42-1 F045D breaks resulting in a DIV 4 LOCA signal. As a result DIV 4 ECCS will start on reactor level low signal. HPCI will also start and inject into the vessel, and 014 EOG will start, but the output breaker will not close. Also, all DIV 4 shunt trips will result in trips of various BOP systems. Reference appropriate ARC: PRO/RO

  • 002 A-1, CONTROL ROOM RADIATION ISOLATION
  • 002 D-4, B CONTROL STRUCTURE CHILLER OUT OF SERVICE
  • 004 B-1, B DRYWELL CHILLER TRIP/FAILED TO START
  • 004 B-4, DIV 1/11 RRCS CHANNEL ACTIVATED
  • 107 H-2, REACTOR HI/LO LEVEL
  • 112 H-1, RWCU PUMP SUCTION LO FLOW
  • 112 E-5, EXCESS FLOW CHECK VALVE OPERATED 10C218
  • 113 B-5, CORE LINE INTERNAL BREAK
  • 114 C-2, REACTOR LO-LO LEVEL
  • 114 D-1, DIV 4 NSSS$ MSIV INITIATED
  • 1151-1, DIV 4 RHR AUTO START
  • 115 D-1 , DIV 4 CORE 1 SPRA Y AUTO START
  • 115 H-3, REACTOR LO-LO-LO LEVEL
  • 118 C-2, 1B INSTRUMENT AIR HOR LO PRESSURE Recognize Div 4 LOCA signal 1 PRO ' Enter SE-10, LOCA (Abnormal)

SRO ' [SE-10 3.2] PRO PLACE to "RESET":

  • 43-22422/CS, "Div. IV Non SFGD Instr. Panel" (INST AC 202 CONTROL PNL), on *DC661. Dispatch Equipment Operator to perform SE-10-1 field actions PRO Recognize/report HPCI running and injecting PRO Enter OT-104, Unexpected/Unexplained Positive or Negative Reactivity SRO Insertion. (Abnormal)

[OT-104 IOA] RO Reduce power to pre-transient power levels or below per OT-104 [OT-104 Attach #2] PRO Recognize power rise due to HPCI injection and is NOT required [OT-104 Attach #2] PRO TRIP HPCI per S55.2.A SEG-2007E Rev002.doc SRRS: 3D.126 Page 27 of 47 LIMERICK GENERATING STATION Exelon Gener-at Ion SIMULATOR EVALUATION GUIDE 4/5. EVENTS 4-5 INADVERTANT DIV 4 LOCA SIGNAL/ 1 10 1 RHR PUMP FAILS Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 min after requested to respond to Excess Flow Check Valve Panel 1 OC218, and report: At panel 1 OC218, Excess Flow Check Valve XV-42-1 F045D is indicating CLOSED. All other Excess Flow Valves indicate open. SEG-2007E Rev002. doc " I ,, SRRS: 30.126 -Page 28 of 47 . LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 4/5. EVENTS 4-5 INADVERTANT DIV 4 LOCA SIGNAL/ '1 D' RHR PUMP FAILS [ARC MCR 112 E-5] PRO/RO Recognize excess flow check valve actuated and send an operator to investigate 1 OC218 panel [ARC MCR 002 A-1] PRO Recognize partial CR HVAC RAD isolation and reset the isolation per S78.7.A [S78.7.A 4.3.1] PRO PLACE the desired following Control Room Isolation Valve Reset Keylock Switches to "RESET"

  • HS-78-0170, RESET D [S78.7.A 4.3.2] PRO ENSURE the desired following Control Room Isolation Valve Trip Switches to "NOR")
  • HSS-78-0170, TRIP D [S78. 7 ;A 4.3.3] PRO PLACE the desired Control Room Isolation Valve Reset Keylock Switches to "AUTO"
  • HS-78-0170, RESET D Recognize 014 DIG is running and send an EO to perform running checks PRO [ARC MCR 004 B-1] PRO I Recognize loss of '1 B' Drywell Chiller I' Enter OT-101 on rising Drywell Pressure SRO [OT-101, 3.1] Crew ESTABLISH Drywell pressure as a Critical Parameter

[OT-101 Att 3 2] PRO IF the Drywell Chiller is tripped PLACE a Drywell Chiller in-service using S87.1.A Appendix 1. [S87.1.A App1 2.1] PRO PLACE 1 BK111 Drywell Chiller (CHILLER) to STOP (Green Flagged). [S87.1.A App1 2.2 and 2.3] PRO PLACE OW Chilled water pumps 1A-P161and1B-P161 to OFF. [S87.1.A App1 4.0] PRO PLACE 1 BK111, "D/W Chiller" (CHILLER) for oncoming Drywell Chiller in "START." SEG-2007E Rev002.doc SRRS: 30.126 Page 29 of 47 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 415. EVENTS 4 -5 INADVERTANT DIV 4 LOCA SIGNAL/ 11 D' RHR PUMP FAILS Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. Manually actuate Trigger # --1--when directed by Lead Evaluator, to initiate Small Coolant Leak in the Drywell. ,, I ,, ,, SEG-2007E Rev002.doc SRRS: 30.126 Page 30 of 47 .; I ,, ' . LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 4/5. EVENTS 4-5 INADVERTANT DIV 4 LOCA SIGNAL/ '1 D' RHR PUMP FAILS [S87.1.A App1 4.0] PRO ENSURE 1A-P161and1B-P161 in RUN. [ARC MGR 115 1-1] PRO Recognize '1 D' RHR Pump failed to Auto start on LOCA signal Manually start of '1 D' RHR Pump (Malfunction) PRO Recognize RWCU is Out of Service and contact Chemistry to perform PRO conductivity sampling per TRM 3.4.4 Direct Chemistry to perform sampling for Containment Leak Detector INOP PRO Determine Tech Spec LCO's: SRO 3.5.1.c.2 HPCI and '1 D' LPCI (8 hours) 3.4.3.1.a Cont. Leak Detector (12 hours sampling/restore within 30 days) TRM 4.4.4.c RWCU (4 hour sampling) 3.3.3 for Div 4 EGGS instrumentation SEG-2007E Rev002.doc SRRS: 30.126 Page 31 of 47 " I ,, ' " I ,, LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE sn. EVENTS 6 -7 STEAM LEAK IN THE DRYWELL Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. Manually actuate Trigger tl__ when directed by Lead Evaluator, to initiate Small Coolant Leak in the Drywell. Ensure Trigger...!..!._ automatically actuates when RMS taken to SHUTDOWN, to initiate Steam Leak in the Drywell " I ,, ,, SEG-2007E Rev002.doc SRRS: 3D.126 Page 32 of 47 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE TIME II ASSESSMENT ITEMS AND TASK PERFORMANCE sn. EVENTS 6-7 STEAM LEAK IN THE DRYWELL II POSITION EVALUATORS NOTE: A coolant leak will develop in the Drywell. The coolant leak will result in a plant shutdown. Once the reactor is shutdown the operators will continue to address the containment parameters. Reference ARCs: RO/PRO

  • 112 C-5, DRYWELL EQUIP ORN TK/FLR ORN SUMP LEAKAGE HI FLOW
  • 115 B-5, DRYWELL COOLER DRAIN FLOW HIGH
  • 107 F-2, DRYWELL HI I LO PRESS Re-enter and execute OT-101 on rising Drywell pressure RO [OT-101 3.1] SRO ESTABLISH Drywell pressure as a Critical Parameter I I [OT-101 3.3] I PRO Perform OT-101 Attach #4 *i [OT-101, Att. 4] PRO ENSURE Main Steam Line sample valves closed HV-041-(1 F084 and ,1 F085) [OT-101, Att. 4] PRO ENSURE Recirc sample valves closed HV-043-(1 F019 and 1 F020) [OT-101, Att. 4] PRO PRO secures and isolates RWCU (time permitting)

! '

  • SECURE operating RWCU pump(s) (Already secured) ,, ,,
  • ENSURE the following valves closed:
  • HV-C-044-1 F003
  • HV-44-1F001, INBD
  • HV-44-1 F004, OUTBD
  • HV-44-1F100, BOTIOM HEAD DRAIN
  • HV-44-1F105, INLET FLOW Direct GP-4 rapid plant shutdown (time permitting)

SRO Transfer House Loads per 891.6.B (time permitting) PRO Reduce Recirc Flow to Minimum (time permitting) RO Manually scram reactor before OW pressure reaches 1.68 psig RO Place Mode Switch to Shutdown RO [T-101 RC-6] RO Insert SRMs AND IRMs SEG-2007E Rev002.doc SRRS: 30.126 Page 33 of 47 LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE sn. EVENTS 6 -7 STEAM LEAK IN THE DRYWELL Simulator Operator Instructions Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. Ensure Trigger__u_ automatically actuates when RMS taken to SHUTDOWN, to initiate Steam Leak in the Drywell SEG-2007E Rev002.doc SRRS: 30.126 ,; I ,, ,, Page 34 of 47 LIMERICK GENERATING STATION ; Exelon Generation .. SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE 617. EVENTS 6-7 STEAM LEAK IN THE DRYWELL POSITION EVALUATORS NOTE: When the plant is shutdown a steam leak into the drywell occurrs. The crew will enter and execute T-102, Primary Containment Control and utilize RHR system to spray the Suppression Pool and Drywell. Enter/Re-enter T-102 and T-101 when Drywall pressure exceeds 1.68 psig SRO [OT-101 3.5] RO Trip both Recirc pumps when Drywall pressure exceeds 1.68 psig [T-101 RC/Q-2] PRO Ensure Turbine trip and Gen lockout [T-101 RC/L-7] I PRO Restore and maintain RPV level between + 12.1 5" and +54" I [T-101 RC/P-1] i PRO Stabilize RPV pressure below 1096 psig ,, [T-101 RC-5] PRO/RO Verify isolations for RPV level <+ 12.5" and > 1,59 psig Drywell pressure Verify HPCI System initiation on 1.68 psig Drywall pressure (already running PRO from DIV 4 LOCA signal) Establish Suppression Pool Temperature as a Critical Parameter CRS I CRS directs depressurizing reactor to 600 psiQ to reduce leak input SRO ,, [OT-200 Att. 11] RO Depressurizes to 600 psig using EHC [T-102 DW/T-5] PRO When Drywall temperature exceeds 145 °F, verify DWCW Head Tank level, then bypass isolations and maximize Drywall cooling (time permitting) SEG-2007E Rev002. doc SRRS: 30.126 Page 35 of 47 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 8/9. EVENTS 8 -9 '1 B' RHR PUMP TRIP I HV-51-1 F024A THERMAL OVERLOAD Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 min after requested to investigate the trip of the '1 B' RHR Pump report: "The '1 B' RHR Pump breaker has tripped on 'B' Phase Overcurrent." SEG-2007E Rev002.doc

I *' ' SRRS
30.126 Page 36 of 47

. LIMERICK GENERATING STATION Exelon Generation" SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 8/9. EVENTS 8-9 '1 B' RHR PUMP TRIP I HV-51-1 F024A THERMAL OVERLOAD EVALUATOR NOTE: The following steps are performed as directed by T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation. [T-102 PC/P-5] PRO BEFORE Supp Pool pressure reaches 7.5 psig Spray the Suppression Pool per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation Recognize '1 B' RHR pump trips (Malfunction) PRO Investigate trip of '1 B' RHR pump PRO [T-225 4.2.4] PRO ENSURE the following valves open: I * "1A(B) RHR Htx Shell Side Inlet Viv" (INLET)

  • HV-51-1 F003A(B), "1A(B) RHR Htx Shell Side Outlet Viv" (OUTLET)
  • HV-C-51-1 F048A{B), "1A(B) RHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS) [T-225 4.2.5] I PRO OPEN HV-51-1F024A(B), "1A(B) RHR Pp Full Flow Test Return Viv" (SUPP POOL CLG A(B)) AND OBTAIN flow of 8,000 to 8,500 gpm as indicated on Fl-51-1 R603A(B), FL f PRO Recognize HV-51-1 F024A, "1A RHR Pp Full Flow Test Return Viv" tripped on thermals and requires td be manually opened Override HV-51-1 F024A thermals by holding handswitch in OPEN PRO (Malfunction)

[T-225 4.2.6] PRO OPEN HV-51-1F027A(B), "1A(B) RHR Supp Pool Spray Line PCIV" (SUPP POOL SPRAY) EVALUATOR NOTE: The following steps are normally performed as directed by S12.1.A, RHR Service Water System Startup as directed from T-225. For this scenario RHRSW should have been placed in service for the open SRV (Event 2). If required reference page 23 of this SEG for RHRSW being placed in service. SEG-2007E Rev002.doc SAAS: 30.126 Page 37 of 47 LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE 8/9. EVENTS 8 -9 '1 B' AHR PUMP TRIP I HV-51-1 F024A THERMAL OVERLOAD Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger . SEG-2007E Rev002.doc . ; I ,, I SRRS: 30.126 Page 38 of 47 TIME LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE ASSESSMENTITEMSANDTASKPERFORMANCE POSITION 8/9. EVENTS 8-9 '1 B' RHR PUMP TRIP I HV-51-1 F024A THERMAL OVERLOAD EVALUATOR NOTE: The following steps are normally performed as directed by S12.1.A, RHR Service Water System Startup as directed from T-225. For this scenario RHRSW should have been placed in service for the open SRV (Event 2). If required reference page 23 of this SEG tor RHRSW being placed in service. [T-225 4.2.8] PRO PLACE AHR Service Water Pump for AHR Heat Exchanger to be used in service per S12.1.A, AHR Service Water System Startup [T-225 4.2.9] PRO CLOSE HV-C-51-1 F048A(B), "1A(B) AHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS) I [T-102 PC/P-12] CRS WHEN SAFE side of the Pressure Suppression Pressure (PSP) curve (Curve ;PC/P-3) cannot be maintained, enter T-112 [T-112 EB-12] CRS , DIRECT Open all 5 ADS valves [T-112 EB-12] RO/PRO PERFORM Open all 5 ADS valves (Critical Task) [T-102 PC/P-1 O] -or-[T-102 OW /T-8] PRO 1 Spray the Drywell per T-225, Startup and Shutdown of Suppression Pool and : Drywell Spray Operation .[T-225 4.5.1] PRO ENSURE HV-51-1 F004A(B), "1A(B) AHR Pump Suction PCIV" (SUCTION A(B)), open [T-225 4.5.2] RO/PRO ENSURE the following valves closed:

  • HV-51-1 F006A(B), "1A{B) AHR Pp S/D Clg Suet lntertie Viv" (SUCTION A(B))
  • HV-51-1 F015A(B), "1A(B) Shutdown Clg Injection PCIV" (OUTBOARD A(B))
  • HV-51-1F016A(B), "1A(B) RHR Cntmt Spray Line Outboard PCIV" (OUTBOARD A(B))
  • HV-51-1F017A(B), "1A(B) AHR LPCI lnj PCIV" (OUTBOARD A(B)) SEG-2007E Rev002.doc SRRS: 30.126 Page 39 of 47 LIMERICK GENERATING STATION Exelon Gener-ation, SIMULATOR EVALUATION GUIDE 8/9. EVENTS 8 -9 '1 B' RHR PUMP TRIP I HV-51-1 F024A THERMAL OVERLOAD Simulator Operator Instructions Respond to request for assistance as appropriate.

Inform Floor Instructor prior to each event trigger. ' ; I ,, ,, SEG-2007E Rev002.doc SRRS: 30.126 Page 40 of 47 TIME LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 8/9. EVENTS 8-9 '1 B' RHR PUMP TRIP I HV-51-1 F024A THERMAL OVERLOAD [T-225 4.5.4] PRO ENSURE the following valves open:

  • HV-51-1 F047A(B), "1A(B) RHR Htx Shell Side Inlet Viv" (INLET)
  • HV-51-1 F003A(B), "1A(B) RHR Htx Shell Side Outlet Viv" (OUTLET)
  • HV-C-51-1 F048A(B), "1A(B) RHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS) [T-225 4.5.5] PRO TRIP Reactor Recirc Pumps [T-225 4.5.6] PRO REMOVE Drywell Cooling Fans from service by placing all 16 Drywell Cooler Fan switches to "OFF" i i [T-225 4.5.7] PROI IF Drywell High Pressure AND LOCA signals are present, THEN GO TO step 4.5.11 " I [T-225 4.5.11] PRO OPEN HV-51-1 F024A(B), "1A(B) RHR Pp Full Flow Test Return Viv" (SUPP 1 POOL CLG A(B)), AND OBTAIN flow of 9,250 to 10,500 gpm as indicated on Fl-51-1 R603A(B), FL [T-225 4.5.12] PRO OPEN only one loop HV-51-1 F021A(B), "1A(B) RHR Cntmt Spray Line I Inboard PCIV" (INBOARD)

' [T-225 4.5.13] ,, PRO, REQUEST SSV verify drywell temperature AND drywell pressure are on SAFE side of Drywell Spray Initiation Limit Curve per T-102, Primary Containment Control OR SAMP-1, RPV and Primary Containment Flooding Control [T-225 4.5.14] PRO Throttle OPEN only one loop HV-51-1F016A(B), "1A(B) RHR Cntmt Spray Line Outboard PCIV" (OUTBOARD) to initiate spray AND OBSERVE raising flowrate as indicated on Fl-51-1 R603A(B), FL. [T-225 4.5.15] PRO MONITOR Drywell pressure. [T-225 4.5.16] (Critical Task) PRO Throttle OPEN HV-51-1 F016A(B), "1A(B) RHR Cntmt Spray Line Outboard PCIV" (OUTBOARD) AND Fully CLOSE HV-51-1F024A(B),"1A(B) RHR Pp Full Flow Test Return Viv", (SUPP POOL CLG A(B)) AND OBTAIN flow of 9,250 to 10,500 gpm as indicated on Fl-51-1 R603A(B), FL SEG-2007E Rev002.doc SAAS: 30.126 Page 41 of 47 . LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE 8/9. EVENTS 8 -9 '1 B' RHR PUMP TRIP I HV-51-1 F024A THERMAL OVERLOAD Simulator Operator Instructions Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 1 O min after FSSV or EO action requested for SE-1 O Floor Actions Load All SE-10 Floor Actions with Time Delays Scenario and report: The status of individual resets as requested OR when all resets are timed out report: All SE-1 O Floor Actions are complete " I ,, ' SEG-2007E Rev002.doc SRRS: 30.126 Page 42 of 47 TIME LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 8/9. EVENTS 8-9 '1 B' AHR PUMP TRIP I HV-51-1 F024A THERMAL OVERLOAD [T-225 4.5.18] PRO CLOSE HV-C-1F048A(B), "1A(B) RHR Htx Shell Side Bypass Valve" (HEAT EXCHANGER BYPASS). EVALUATORS NOTE: The following steps are from SE-10, LOCA. Recognize LOCA signal when RPV pressure drops below 455 psig Crew Enter SE-10, LOCA Crew [SE-10 3.1] RO PLACE the following to "CLOSE"

  • 52-20224/CS, "D*24 Safeguard LC. D*24-G-D MCC Bkr" (SAFEGUARDS B), on *BC661 I
  • 52-20124/CS, "D*14 Safeguard LC. D*14-G-D MCC Bkr" 1 (SAFEGUARDS A), on *AC661. ' [SE-10 3.2] I RO PLACE to "RESET": '
  • 43-22322/CS, "Div. Ill Non SFGD Instr. Panel" (INST AC 201 CONTROL PNL), on *CC661 Dispatch Equipment Operator to perform SE-10-1 field actions PRO Restore RPV Level to +12.5" to 54" with Condensate and/or Loi.y Pressure RO/PRO ECCS ' EVALUATORS NOTE: The scenario may be terminated when an Emergency Depressurization has been performed, Drywell Spray is in service, control rods inserted and reactor level is restored.

After the scenario is terminated, direct the SRO to make the highest EAL classification for the scenario. EAL: FA-1 declaration due to: (RC.3.1 and RC.3.2)

  • Drywel/ pressure>

1.68 psig AND

  • Drywell pressure rise is due to RCS leakage SEG-2007E Rev002.doc SRRS: 3D.126 Page 43 of 47 TIME LIMERICK GENERATING STATION Exelon Generation.

SIMULATOR EVALUATION GUIDE ASSESSMENTITEMSANDTASKPERFORMANCE Rough Log(s) Maintained by the crew with the following items noted:

  • Rod { 46-15) uncoupled
  • '1N' SRV
  • DIV 4 LOCA * '1 D' AHR Pump failed to auto start
  • Reactor Scram
  • ATWS
  • 1.68 Drywall Pressure
  • RPV Level < + 12.5" and Drywall Pressure > 1.68 psig Isolations verified
  • HV-51-1 F024A thermal overload * '1 B' RHR Pump Trip
  • FA-1 declaration due to: {RC.3.1 and RC.3.2) l
  • Drywall pressure > 1.68 psig : AND .f Drywall pressure rise is due to RCS leakage I
  • Critique any instances where fundamentals were not properly adhered to, and whether in-the-moment coaching was provided by Supervision.

Provide examples of effective Leadership and areas for improvement. ,, ,. SEG-2007E Rev002.doc SRRS: 30.126 POSITION Crew SM Page 44 of 47 Procedure T-209 T-212 T-215 T-216 T-217 T-219 T-221 T-225 T-240 T-245 T-248 T-251 T-270 T-290 S46.7.A (4.2.1) SE-10-1 Resets and Floor action Performance LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE Attachment 1 Simulator Operator Response Times Injection from the Standby Liquid Control Storage Tank with the RCIC System Bypassing SQUIB Valves for SLC Injection De-energization of Scram Solenoids Manual Isolation and Vent of Scram Air Header RPS/ARI Reset and Backup Method of Draining Scram Discharge Volume ' ' I Maximizing CRD Cooling Water Flow during ATWS Conditions MSIV Isolation Bypass Procedurs Startup and Shutdown of Suppression Pool and Drywell Spray ' Operations Maximizing CRD flow after Shutdown During Emergency Conditions RPV Injection from RHR S/D Coqling ' Injection from SLC Test Tank to RPV Establish a HPCI Injection flow Path VIA Feedwater Only Terminate and Prevent Injection into the RPV Instrumentation Available for T-103 SAMP-2 Control Rod Drive Hydraulic System Operation Following Reactor Scram (Securing CRD flow to the Reactor -Close 46-1 F060, CRD Water Pressure Control Station Inlet Valve) Breaker Reset Following LOCA (Also reset ARMs, RHRSW Rad Monitor and RDCS) SEG-2007E Rev002.doc SRRS: 30.126 Nuclear Response Time (Minutes) 45 19 7 7 17 23 11 8 8 12 15 6 7 5 7 10 Page 45 of 47 CREW: ___ _ DATE: ___ _ START TIME: LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE Attachment 2 Communications Log LSEG: ___ _ STOP TIME: Exelonw Nuclear ---------SM: _____ _ RO: ------WCS: ____ _ CRS: ____ _ PRO: ____ _ FSSV: _____ _ PERSON PERSON CALL TIME CALLING BEING COMMUNICATION I REQUEST BACK CALLED TIME I I *i I I ' ,, ' SEG-2007E Rev002.doc SRRS: 30.126 Page 46 of 47 ......------------*

  • -**.

XI. CREW PREBRIEF INSTRUCTIONS Unit 2 is in OPCON 1 at 100% power Unit 1 is in OPCON 1 at 90% power Specific Plant Conditions are as Follows:

  • Reactor power reduced to 90% due to Control Rod pattern adjustment Inoperable/Out of Service Equipment and Estimated Time of Return (ETR): * '1 B' EHC pump is blocked for replacement
  • Repairs are scheduled to be complete in 2 hours Restrictions op Plant Operations:
  • None I Ji I Planned Evolutions:
  • Raise Reactor power to 100%
  • Continue replacement of '1 B' EHC pump and perform PMT when complete I Documents P(ovided:
  • ReMA and Control Rod Move Sheet
  • GP-5 Attachment 1
  • S73.1.A, Normal Operation of the Reactor Manual Control System Page 47 of 47

" I ,, '. LIMERICK GENERATING STATION ;;;;x Exelon Generation. SIMULATOR EVALUATION GUIDE CODE NO: SEG-7016E REV NO: 002 AUTHOR: T. A. BYERS APPROXIMATE 75 minutes RUN TIME: TYPE: SIMULATOR EVALUATION EFFECTIVE DATE: GUIDE PROGRAM: LICENSED OPERATOR TRAINING COURSE: LICENSED OPERATOR (REQUALIFICATION/INITIAL) TRAINING TITLE: Simulator Evaluation Guide for Individual and Crew Performance Prepared By: Date: Training Instructor -Signature Reviewed By: Date: LORT Lead Instructor -Signature Reviewed By: Date: EP (as appropriate) -Signature Reviewed By: Date: RE (as appropriate) -Signature Approval: Date: OPS Manager -Signature Approved For Use: Date: Training Manager -Signature SEG-7016E Rev002.doc SRRS: 30.126 Page 1 of 39 " I ,, ' ' LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-7016E Rev 002 Op-Test No.:_ 1 Examiners: Operators: Initial Conditions: Unit 1 is at 100% power. Unit 2 is at 100% power. Turnover: I None i ;Event Malfunction Event Event No. Number Type* Description I R-RO 1. MFW001 C-PRO HWC System Failure (Abnormal) TS-SRO VIC104C8 C-RO I 2. MFW250A C-PRO '1 C' RFP Min Flow Valve fails open (Abnormal) MFW246A ,, ,. MCW481A 3. C-PRO '1 A' TECW Pump trip MCW486B '1 B' TECW fails to auto start (Abnormal)

4. MVl234C C-RO Reactor High Pressure Transmitter Failure (Abnormal)

TS-SRO 5. MRP029D ATWS MSL559 M-ALL The ATWS is mitigated by the insertion of control rods via MRP407C T-215. (Major) 6. MRD024 C-RO RDCS Inoperative after reactor shutdown (Malfunction)

7. MMT002 C-PRO Turbine Trip I Bypass Valves Fail Closed (Malfunction)

MEH108 C-RO 8. MRSW600A C-PRO 'OA' or 'OC' RHRSW Pump Trips (Malfunction) I MRSW600C (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-7016E Rev002.doc SRRS: 30.126 Page 2 of 39 *i I ,, LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE I. QUANTITATIVE ATTRIBUTES A. ILT Target Quantitative Attributes (Per Scenario; See ES-301 Section 0.5.d) 1. Malfunctions after EOP entry (1-2) 2. Abnormal events (2-4) 3. Major transients (1-2) 4. EOPs entered/requiring substantive actions (1-2) 5. EOP contingencies requiring substantive actions (0-2) 6. EOP based Critical tasks (2-3) ACTUAL NUMBER 2 4 1 2 1 f I 4 :; I Review TQ-AA-151 attachment 5 and ES-301-5 for individual position requirements for scenario and scenario set SEG-7016E Rev002.doc SRRS: 30.126 ,, I' Page 3 of 39 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE II. PURPOSE: Systematically evaluate individual and team performance to identify areas for improvement. Critical Tasks and Assessment Items from this evaluation guide are to be used to assess crew and individual performance and as input into a 4.0 Crew Critique Process. Ill. SIMULATOR EVALUATION GUIDE OBJECTIVES: A. The following evaluation objectives apply to the Crew (C), Shift Manager (SM), Control Room Supervisor (S), Unit Reactor Operator I Plant Reactor Operator (R), or Incident Assessor I Shift Technical Advisor (A) as indicated in the following categories.

1. The general condition for each of the evaluation objectives will be "Given the plant conditions and sequence of events in the Simulator Evaluation Guide (SEG)". 2. The general acceptable evaluation objective criteria for each of the evaluation objectives will be "To perform effectively as an individual and contribute to successful crew performance in accordance with appropriate reference plant procedures and Operations Expectations, Fundamentals and Strategies".

[ 3. Specific UNSAT evaluation objective criteria will be consistent with TQ-AA-1,55, Conduct of Simulator Training and Evaluation with applicable forms and job aids. 4. During performance of this Simulator Evaluation Guide, the individuals and drew should satisfactorily demonstrate the following overall procedure and plant control objectives:

  • * * * * * * * *
  • Direct and perform actions per ON-102, Air Ejector Discharge or Main Steam Line High Radiation.

Direct and perform actions per ON-117, Loss of TECW Direct and perform actions per OT-100, Reactor Low Level Direct and perform actions per OT-104, Unexpected-Unexplained Positive or Negative Reactivity Insertion. Direct and perform actions per OT-117, RPS Failures ,, ,, Direct and perform actions per GP-5, App. 2, Planned Rx Maneuvering Without Shutdown. Direct and perform actions per T-270, Terminate And Prevent Injection Into The RPV Direct and perform actions per T-101, RPV Control Direct and perform actions per T-102, Primary Containment Control Direct and perform actions per T-117, Level/Power Control SEG-7016E Rev002.doc SRRS: 30.126 Page 4 of 39 LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE IV. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the IL Tor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in IL Tor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change Lead Action Change# Change Approval Tracking I I I " I V. REVISION HISTORY: Revision Date A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. I C. The description of the Revision should also include pr¢vious format reference and number and previous template used (e.g for conversion of LSTS tq.LLORSEG format). Revision Description of Revision and Affect on Training Content # Date of Number Revision This was originally used as 2012 ILT Cert Scenario #3 (This scenario was RevOOO designated as the spare and was not used). 8/12/13 Rev001 Revised to template with changes including RPS Pressure transmitter failure 8/15/15 and RHRSW Pumps trip Rev002 Revised to new template, removed APRM failure, added TECW Pump 10/08/16 failure(s), reordered first 4 events, and changed initial power from 80% to 100%. # Date of Revision -refers to date revision was released for approval SEG-7016E Rev002.doc SRRS: 30.126 Page 5 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

Event One: Shortly after the crew has taken responsibility of the shift, the HWC system will fail such that the Hydrogen Flow Controller output will rise and the PLC will lock up. The MSL Rad Monitor alarms will be received due to excess Hydrogen injection.

Evaluation: Evaluate the crews' response to the HWC malfunction including actions taken per ON-102, Air Ejector Discharge Or Main Steam Line High Radiation and T-103, Secondary Containment Control. The crew will reduce power and will trip the HWC System as well as reference Tech Specs due to excessive H2 injection. Event Two: After the crew has taken Tech Spec actions for HWC, the '1 C' RFP Min Flow Valve will fail open causing '1C' RFP injection rate to lower and the '1A' and '18' RFPs to increase injection to the vessel. I Evaluation: Evaluate the crew's response to '1 C' RFP Min Flow Valve failing open and to secure the '1C' RFP, and isolate the minimum flow valve. The crew will execute OT-104, Unexpected/ Unexplained Positive or Negative Reactivity Insertion and reduce total Feedwater less than 13 Mlb/hr per GP-5. Event Three: After the '1C' RFP is secured and reactor power lowered, the in-service '1A' TECW Pump will inadvertently trip, with the '18' TEWC Pump failing to auto start. I Evaluation: Evaluate the crew's response to i{jentify the TECW Pump failure, enter and execute ON-117, Loss of TECW, manually start the '18' TECW Pump, and monitor Condensate Pump and Air' Compressor temperatures. Event Four: After the crew has started the '18' TECW Pump a RPS reactor pressure transmitter and Five: fails upscale. The failed RPS instrument will result in a failed RPS channel (Will fail to de-energize. As a result of the RPS channel failure a manual full scram is required. On the scram the Control Rods will fail to insert, resulting in an ATWS. Evaluation: Evaluate the crews' ability to address the failed pressure transmitter and implement OT-117, RPS Failures, and respond to a failure of the reactor to manually scram, and subsequent ATWS. The crew will be evaluated on their ability to implement T-101, RPV Control and T-117, Level/Power Control, and the initial level lowering per T-270, 1 Terminate And Prevent Injection Into The RPV. Complicating the event, the SLC discharge line will rupture in the DW. SEG-7016E Rev002.doc SRRS: 30.126 Page 6 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

cont'd Event Six: After the Mode Switch is taken to shutdown, RDCS will become inoperative and prevent manual insertion of control rods. Evaluation:

Evaluate the crew's ability to recognize the failure of RDCS and call out for floor assistance in resetting RDCS in the AER. Once RDCS is reset, the crew is expected to manually insert control rods to help mitigate the ATWS condition. Event Seven: After level is lowered and pressure has been stabilized, the Main Turbine will begin to experience vibration caused by bearing failure. The excess vibration will eventually cause a MT trip. Along with the Turbine trip, the Bypass Valves will fail to maintain RPV pressure, resulting in a rise in Suppression Pool temperature. I I Evaluation: Evaluate the crews' ability to respond to a Main Turbine trip while maintaining reactor control by manual operation of SRVs. The crew will perform a second lowering of reactor level per T-270, to less than -161" and maintain level between -186" to -161" as Suppression Pool temperature exceeds 110 deg F. Event Eight: Also, after the Main Turbine Trip, the first started 'OA' Loop RHRSW Pump will fail to start from the MGR. Evaluation: To identify the trip of the lead RHRSW Pump and place the alternate pump in service in the 'OA' RHRSW loop. Termination Criteria: The scenario is terminated when RPV level has been maintained -186" to -161", followed by Control Rods inserted per T-215, De-energizing Of Scram Solenoids. SEG-7016E Rev002.doc SRRS: 30.126 Page 7 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE VI. REFERENCES A. Training Procedures

1. TQ-LG-150, Limerick Operator Training Program 2. TQ-AA-151, IL T Certification and NRC Examination Development and Administration
3. TQ-AA-155, Conduct of Simulator Training and Evaluation B. Annunciator Response Cards (ARC) c. 1. 101 E-5, CONDENSATE FILTERDEMIN TROUBLE 2. 104 D-4, CONDENSATE PUMPS DISCHARGE HEADER LO PRESS 3. 104 D-5, CONDENSATE PUMPS DISC SAMPLE STATION TRB 4. 1071-1, MAIN STEAM LINE HIGH-HIGH RADIATION
5. 107 D-5, FWLCS Trouble 6. 107 G-1, REACTOR HIGH PRESSURE TRIP 7. 1071-2, VIBRATION ALARM ALERT 8. 1071-3, VIBRATION ALARM DANGER I 9. 108 E-4, RDCS INOPEfATIVE
10. 109 F-1, 1 MAIN STEAM LINE DIV 1 RAD MONITOR Hl/DNSC 11. 109 F-2, 1 MAIN STEAry-1 LINE DIV II RAD MONITOR Hl/DNSC 12. 109 B-5, TURBINE ENCL AREA HI RADIATION
13. 118 G-3, TURB BLDG COOLING WATER HTX OUT LO PRESS I 14. 118 A-1, SERVICE Al R COMPRESSOR TROUBLE 15. 118 B-1, 1A INST AIR COMPRESSOR TROUBLE 16. 118 C-1, 1B INST AIR COMPRESSOR TROUBLE 17. 1271-1, 1 UNIT HWC TROUBLE System Procedures (S) , . 1. S12.1.A, RHR Service Water System Startup 2. S51.8.A, Placing RHA*Suppression Pool Cooling in service D. General Procedures (GP) 1. GP-5, Steady State Operations
2. GP-5 Appendix 2, Planned Reactor Maneuvering Without Shutdown E. Off Normal Procedures (ON) 1. ON-102, Air Ejector or Main Steam Line High Radiation
2. ON-117 Loss Of TECW F. Operating Transient Procedures (OT) 1. OT-104, Unexpected-Unexplained Positive or Negative Reactivity Insertion
2. OT-117, RPS Failures 3. OT-100, Reactor Low Level G. Event Procedures (E) I H. Special Event Procedures (SE) 1. SE-10, LOCA I. Surveillance Test and Routine Test Procedures (ST and RT) SEG-7016E Rev002.doc SRRS: 30.126 Page 8 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE REFERENCES cont'd J. Technical Specifications and TRM (TS) 1. TS 3.11.2.6 K. Transient Response Implementation Procedures (T-100 series) 1. T-101, RPV Control 2. T-102, Primary Containment Control 3. T-103, Secondary Containment Control 4. T-117, ATWS Level Control L. TRIP 200 Series Procedures
1. T-215, De-energization of Scram Solenoids
2. T-221, MSIV Isolation Bypass Procedure
3. T-251, Establish a HPCI Injection Path Via Feedwater Only i 4. T-270, Terminate and Prevent Injection into the RPV 5. T-290, Instrumentation Available For T-103/SAMP-2 M.1 EP-AA-1008, Limerick, Radiological Emergency Plan Annex for Limerick Generating Station N. :: Administrative Procedures I 1 . OP-AA Procedures
a. OP-AA-1, Conduct of Operations
b. OP-AA-20, Conduct of Operations Process Description
c. OP-AA-101-111-1003, Operations Department Standards and Expectations
d. OP-AA-101-113, Operations Fundamentals
e. OP-AA-101-113-1006, 4.0 Crew Critique Guidelines

,, f. OP-AA-106-101-1006, Operational Decision Making Process '* 2. OP-LG Procedures

a. OP-LG-101-111-1000, Licensed Operator Duties b. OP-LG-101-111-1002, Time Critical Operator Actions c. OP-LG-103-102-1000, Human Performance Continuing Good Practices
d. OP-LG-103-102-1002, Strategies for Successful Transient Mitigation
e. OP-LG-108-101-1001, Simple Quick Acts I Transient Acts 0. Current Shift Night Orders Forced Outage Plan P. INPO Significant Operating Experience Reports (SOER), Significant Event Reports (SER) and INPO Event Reports (IER) 1. IER-L 1 11-3, Weaknesses in Operator Fundamentals
2. SER 3-05, Weakness in Operator Fundamentals
3. SOER 10-02, Engaged Thinking Organizations
4. INPO 15-004, Operator Fundamentals SEG-7016E Rev002.doc SRRS: 30.126 Page 9 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE VII. PREBRIEF INSTRUCTIONS Unit 2 is in OPCON 1 at 100% power Unit 1 is in OPCON 1 at 100% power Specific Plant Conditions are as Follows:
  • Operation per GP-5, Steady State Operations Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):
  • None Restrictions on Plant Operations:

I

  • Npne " Planned Evolutions:
  • Maintain 100%. Documents Provided:

I

  • None ' ' SEG-7016E Rev002.doc SRRS: 30.126

---Page 10 of 39 LIMERICK GENERATING STATION ,,t:':"/ Exelon Generation. SIMULATOR EVALUATION GUIDE VIII. DIRECTIONS FOR EVALUATION PREPARATION A. INITIAL PREPARATION ., ITEM I MALFUNCTION I REMOTE FUNCTIONS Complete TQ-AA-155, Operator Training Programs Attachment 02, Evaluated Scenario Administration Checklist. Complete TQ-LG-201-0113, Limerick Training Department Simulator Examination Security Actions Checklist B. SIMULATOR SETUP ., ITEM I MALFUNCTION I REMOTE FUNCTIONS Complete Limerick Simulator Pre-Evaluation Checklist i Reset Simulator to the Pre-loaded Cycle IC developed for the Evaluation i OR Reset the simulator to designated base load IC-3 " ' AND Load scenario file SEG7016E Rev002.scn

  • Verify that all Malfunctions, Remotes, Overrides, Annunciators and Triggers are properly loaded OR
  • Manually enter the Malfunctions, Remotes, Overrides, Annunciators and Triggers per the Scenario Generator Screen Shots: I ' Simulator Operator (Driver) perform the following:

,, ,.

  • Momentarily place simulator in RUN
  • Acknowledge and clear all spurious alarms
  • Place the simulator back into FREEZE
  • Place appropriate tags and equipment in required condition I status . SEG-7016E Rev002.doc SRRS: 30.126 Page 11 of 39 LIMERICK GENERATING STATION Exelon Generation.

SIMULATOR EVALUATION GUIDE C. MALFUNCTION/REMOTE/OVERRIDE/ANNUNCIATORS FUNCTION TIME TABLE Description HWC System Excess H2 lnjeclion and PLC Lockup . Reactor Feedpump C Min Fans Open Reactor Feedpump CT rip . T_EDN Pump AT rips (Magnetic Overload) Current Value False False False Fant .** False MF\.11001 MF\.1125(]/\ MF\.\1246A MDN481A MV1234C ' ReaclorVesselfressure Transmitter (RPS) N078B Fails High False r Timer Pause Rod Drive Control System Failure TBWD Turbine Thrust Failure

  • MILS
  • . SLCJriectiorilineRup!ure lmide .

.. Turbine Bypass Valves lo Selected Value (0*100%) RHR Service Water Pump (J/\P506 Elect Fault RHR Service Water Pump OCP506 Elect Fault 1 C RFPT Pump Imbalance at Probe 104C08 SEG-7016E Rev002.doc Nllt'l *5.00000 FALSE FALSE 2.900000 SRRS: 30.126 J Target \f alue True True True True True 10.00000 00:08:00 00:00:15 Active Pending Page 12 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE D. EVENT TRIGGERS ASSIGNMENT

  • 1. Timers should be used on event triggers where possible for time validation
2. Timing of event triggers may be altered by the Lead Evaluator (or designee)
3. Verify triggers are actuated automatically as designed or manually initiate the trigger when the initiating action has occurred.
4. Inform Lead Evaluator (or designee) of expected plant response prior to actuation of each trigger. 5. Trigger #1 is manually initiated at Lead Evaluator (or designee) direction after the crew assumes responsibility for operation.

© TRIGGER I TIME MALFUNCTION

1. Manual 2. Manual 3. Manual 4. Manual 5. Auto I ZRPS1 SON 6. Auto I ZSWRPCC 7. Auto I ZSWRPAC favorites Irrg g ers 3 4 5 ZRPS1SDN G ZSWRPCC 7 ZSWRPAC 8 9 10 11 12 13 14 15 16 17 18 19 ?Ii .. CJearAll DESCRIPTION Initiates HWC system lockup Initiates

'1 C' RFP Min Flow Valve opens I TECW Pump trip \ Initiates Rx Pressure Transmitter Failure RMS TO SHUTDOWN Initiates TBWD failure and RDCS failure 'C' RHRSW Pump CS to START Deactivates 'A' RHRSW failure 'A' RHRSW Pump CS to START Deactivates 'C' RHRSW failure 8ccept Operators: Arithmetic:

  • Multiplication I Division + Addition
  • Subtraction Relational:

> Greater than >= Greater than or equal < Less than < = Less than or equal =m Equal to != Not equal to Logical: && And 11 Or I Not Other: OpenParen Close Paren Eis it SEG-7016E Rev002.doc SRRS: 30.126 Page 13 of 39 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE E. EQUIPMENT REPORTS AND SIMULATOR INSTRUCTOR OPERATIONS

1. Scripted Activity Reports should be followed with adherence to Operations Communication standards of performance.
2. The T-200 procedure reference book should be used for familiarity of reports to aid in operator prompting and expected communications.
3. The Lead Evaluator (or designee) should be informed if any event is not reported as scripted due to lack of Operator request. 4. The Standard Equipment Operator Response Times are per Attachment 1 5. A record of communications from the MCR and to the MCR will be maintained by the Simulator Operator using Attachment
2. 6. The OCOEE Simulator Operator Station P&IDs, Floor Plans and Panels should be used by the Simulator Operator as reference information when reports to the MCR for plant parameters which are not driven by a communications sbript. Examples include: ARMs, Blowout Panel status, Reactor Building Area Temperatu 1 res and Pressures, RMMS, Turbine Enclosure parameters etc. ,, SEG-7016E Rev002.doc SRRS: 30.126 I ,, I' Page 14 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE IX. CREW CRITICAL TASKS A. Critical Tasks are based on the current Crew Critical Task List revision, NUREG 1021 and AA-150 requirements.
1. T-117.1 Inhibit automatic ADS KIA 295037 KIA 218000 EA2.06 EA4.04 4.04.1 4.1/4.1 Standard:

Prevent automatic initiation of ADS SAT/UNSAT

2. T-117.12 Terminate and prevent injection into the RPV. KIA KIA KIA 295037 295037 I EK1.02 EK3.03 EA2.02 4.1/4.3 4.1/4.5 4.1/4.2 Standard:

RPV.level deliberately lowered by Terminating and Preventing injection into the RPV per LQ-11 when conditions of step LQ-14 are met. 3. T-101.5 SAT/UNSAT Implement T-215 to insert control rods. KIA 295037 KIA 295Q;37 , , EA1.05 EA2.05 3.9/4.0 4.2/4.3 Standard: Direct the performance of T-215 to operations personnel located outside the control room. 4. T-117.8 SAT/UNSAT Maintain RPV level between -186 inches and the level to which it was intentionally lowered. KIA 295037 KIA 295037 EA2.01 EA2.02 4.2/4.3 4.1/4.2 Standard: RPV level maintained between -186 inches and -161 inches after initially raising RPV level into the required band. Any deviations from the RPV level band DO NOT require an Emergency Slowdown per T-117. SAT/UNSAT SEG-7016E Rev002.doc SRRS: 30.126 Page 15 of 39

x. A. B. c. D. E. F. G. H. I. J. LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE ASSESSMENT OF CREW PERFORMANCE DURING CONDUCT OF THE SIMULATOR EVALUATION GUIDE TRAINING:

Conduct the Simulator Evaluation Session per TQ-AA-155, Conduct of Simulator Training and Evaluation, Attachment 02, Evaluated Scenario Administration Checklist Assessment of Crew and Individual performance shall be consistent with OP-AA-20, Conduct of Operations Process Description Where possible record the time and position responsible for performance of each task or assessment item Items not performed as expected SHALL be discussed in the post performance crew critique During the performance of the evaluation, the Simulator Evaluators shall MAINTAIN notes of observations and information consistent with the timeline Assessment items with the CD symbol indicate a time critical standard for performance Assessment items with the symbol indicate a Probabilistic Risk Assessment (PRA) association with the task [ The Simulator Operator will respond with scripted or proceduralized responses when requested by the MCR operators with Procedure completion times requested per Attachment 1 :; The Simulator Operator will also maintain a timeline and record of all reports and requests issued by the MCR personnel with response provided by the simulator operator using Attachment 2 Shaded items do not require assessment for IL T Evaluations. The CRS may be requested to complete the Shift ED forms and determine the EAL classification at the completion of the scenario ,, ,, SEG-7016E Rev002.doc SRRS: 30.126 Page 16 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE .; I ,, I' SEG-7016E Rev002.doc This Page Intentionally Blank SRRS: 30.126 Page 17 of 39

1. LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE EVENT-1 HYDROGEN WATER CHEMISTRY FAILURE (Abnormal)

Simulator Operator Instructions: Respond to request for assistance as appropriate Inform Floor Instructor prior to each event trigger Manually actuate Trigger#_!_ when directed by Lead Evaluator to initiate HWC PLC Lockup At time 5 min after FSSV or EO action requested to investigate HWC Panel 10C177, report: local alarm is HYDROGEN FLOW TO SETPOINT ERROR. ' " I Manually actuate Trigger#_£_ when directed by Lead Evaluator to initiate '1 C' RFP Min Flow Valve to fai'I open ,, ,, SEG-7016E Rev002.doc SRRS: 30.126 Page 18 of 39 TIME 1. LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-1 HYDROGEN WATER CHEMISTRY FAILURE (Abnormal) POSITION Lead Evaluator (or designee) Notes: A HWC flow control valve failure causes H2 flow to increase into the suction of the RFPs and result in a lockup of the HWC system. The crew will identify the increased H2 flow and isolate the system by depressing HS-06-154 on the C673 panel. Reference appropriate ARCs RO/PRO

  • 109 F-1, 1 MAIN STEAM LINE DIV 1 RAD MONITOR Hl/DNSC
  • 109 F-2, 1 MAIN STEAM LINE DIV 11 RAD MONITOR Hl/DNSC
  • 109 B-5, TURBINE ENCL AREA HI RADIATION
  • 127 1-1, 1 UNIT HWC SYSTEM TROUBLE
  • 107 1-1, MAIN STEAM LINE HIGH-HIGH RADIATION I Dispatch EO to 1OC177 panel to investigate H2 system 1 PRO [ARC MCR 109 F-2/107 1-1] 1 SRO I Enter and execute ON-102, Air Ejector Discharge Or Main Steam Line High :i I Radiation

[ARC MCR 109 F-2/107 1-1] HO/PRO Enter T-103, Secondary Containment Control [T-1 03 SCC-6] SRO Direct performance of T-290 for available instrumentation i I [ON-102 2.2] '.SRO ,, ,. Direct power reduction IAW GP-5, App.2 and RMSI to maintain air ejector discharge rad below HI HI Alarm setpoint and Main Steam Line Rad less than 1.5 X NFPB Perform power reduction IAW GP-5, App.2 and RMSI to maintain air ejector RO discharge rad below HI HI Alarm setpoint and Main Steam Line Rad less than 1.5 X NFPB (Reactivity) Verify proper H2 and 02 flows and Offgas indications PRO [ON-102 2.2] PRO Trip HWC by depressing HS-06-154 on the C673 panel. Contact WWM for assistance SRO [ON-102 2.2] PRO Notify Chemistry for samplinq I Verify Rad Levels Dropping in Offgas and MS Lines after HWC Trip RO Reference TS 3.11.2.6 when Offgas H2 is >4% SRO SEG-7016E Rev002.doc SRRS: 30.126 Page 19 of 39

2. LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE EVENT-2 '1C' RFP MIN FLOW VALVE FAILS OPEN (Abnormal)

Simulator Operator Instructions: Respond to request for assistance as appropriate Inform Floor Instructor prior to each event trigger At time 3 min after FSSV or EO action requested to close 006-1007C report: We can't get the '1 C' RFP Min Flow Recirc Isolation valve closed. We have four operators attempting to close it now and it will not move even with wrenches. Manually actuate Trigger directed by Lead Evaluator to initiate TECW Pump DELETE malfunction VIC104C8 '1 C' RFPT vibration when '1 C' RFP is tripped. " I ,, I' SEG-7016E Rev002.doc SRRS: 30.126 Page 20 of 39 TIME 2. LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE EVENT-2 '1C' RFP MIN FLOW VALVE FAILS OPEN (Abnormal) POSITION Lead Evaluator (or designee) Notes: As the '1 A' RFP Min Flow Recirc Viv fails open, the DFWLCS will respond to a reduction in FW flow to the RPV and lower RPV level which raises speed of the RFPTs to control RPV level. The RO will identify '1 A' RFP flow is lower than the other RFPs and identify the Min Flow Recirc Valve opened. Reference appropriate ARCs: RO/PRO

  • 107 D-5, FWLCS Trouble
  • 101 E-5, CONDENSATE FILTERDEMIN TROUBLE
  • 104 D-4, CONDENSATE PUMPS DISCHARGE HEADER LO PRESS
  • 104 D-5, CONDENSATE PUMPS DISC SAMPLE STATION TRB Identify '1 C' feedflow lowering on Fl-06-1 R604C i RO Recognize unexpected/unexplained drop in RPV

-enter OT-100, SRO Reactor Low Level ii Recognize and report '1C' RFP Min Flow Valve is Open RO [OT-100 step 2.2 IOA] ' RO Reduce Rx power per GP-5, App. 2, section 3.1 and RMSI until Reactor Level is restored Direct EO to close 06-1007C, '1 C' RFP min flow manual isolation valve RO Direct '1 C' RFP be secured when the manual isolatidn valve cannot be closed SRO (Malfunction) ' ,, Recognize vibration on '1C' RFP rising RO Trip '1C' RFP RO Close the '1 C' RFP Suction Valve (Malfunction) RO Direct Rx power reduction per RMSI until Total FW flow is <13Mlbm/hr RO (Reactivity) [OT-100 ATT 1] RO Reduce Total FW flow <13Mlbm/hr per RMSI, if> 13Mlbm/hr Contact Work Week Manager to investigate RFP Min Flow Valve going open SRO Perform S06.2.A to Shutdown the '1 C' RFP RO Notify TSO and Power Team of power changes SRO Notify Chemistry that GEZIP is OOS and surveillance required for power PRO reduction SEG-7016E Rev002.doc SRRS: 30.126 Page 21 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 3. EVENT -3 '1 A' TECW PUMP TRIP/ '1 B' TECW PUMP FAILS IN AUTO (Abnormal) Simulator Operator Instructions: Respond to request for assistance as appropriate Inform Floor Instructor prior to each event trigger Manually actuate Trigger #i when directed by Lead Evaluator to initiate TECW Pump trip. SEG-7016E Rev002.doc SRRS: 30.126 ,, I ,, ' Page 22 of 39 TIME LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 3. EVENT-3 '1A' TECW PUMP TRIP/ '18' TECW PUMP FAILS IN AUTO (Abnormal) Lead Evaluator (or designee) Notes: The PRO will respond to alarm and identify the '1 A' TECW Pump has tripped and the '1 B' TECW Pump has failed to start in AUTO. If the PRO immediately manually starts the '1 B' TECW Pump the air compressor Hi temperature alarms will not occur. Reference appropriate ARC: RO/PRO

  • 118 G-3, TURB BLDG COOLING WATER HTX OUT LO PRESS
  • 118 A-1, SERVICE Al R COMPRESSOR TROUBLE
  • 118 B-1, 1A INST AIR COMPRESSOR TROUBLE
  • 118 C-1, 18 INST AIR COMPRESSOR TROUBLE [ARC MGR 118 G-3] PRO Verify low TECW header using Pl-14-106 at C655 panel [ARC MCA 118 G-3] I PRO i Verify standby TECW Pump to auto start on lo header pressure [ARC MCA 118 G-3] I SRO Enter ON-117, Loss Of TEcvy [ON-117 2.1] PRO Place alternate TECW Pump in service [ON-117 2.6] PRO DISPATCH an operator to mo'nitor Instrument and Service Air Compressor temperatures

' ,, [ON-117 2.8] PRO MONITOR Condensate Pump bearing temperatures on PMS points SEG-7016E Rev002.doc SRRS: 30.126 Page 23 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 4 / 5 EVENTS 4 -5 RPS HIGH PRESSURE TRANSMITTER FAILURE I ATWS (Major) Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger Manually actuate at Lead Evaluators discretion to initiate RPS instrument failure. At time 5 min after FSSV or EO action requested to investigate RPS Pressure Trip units inAER, I report: PIS-042-1 N678B is indic,ting upscale. SEG-7016E Rev002.doc " I ,, I SRRS: 30.126 Page 24 of 39 TIME LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GU1DE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 4/5 EVENTS 4-5 RPS HIGH PRESSURE TRANSMITTER FAILURE I ATWS (Major) Reference appropriate ARC: RO

  • 107 G-1, REACTOR HIGH PRESSURE TRIP Verify Rx pressure normal with high RPS pressure transmitter alarm RO Recognize failure to Y2 scram on B RPS and inform CRS RO Dispatch an EO to investigate the Rx pressure transmitter PRO/RO Enter OT-117, RPS Failures, for failure to Y2 scram on B RPS SRO [OT-117 3.2.1] SRO Direct inserting manual Y2 scram on 'B' Side Perform Arm and depress 'B1' RPS RO failure to Y2 SCRAM on 'B' RPS RO [OT-117 3.2.1] SRO ,, Direct Arm and depress 'B2' Perform Arm and depress 'B2' RPS RO [OT-117 3.2.1] SRO Direct manual scram lnsert 1'A' Side RPS Manual SCRAM signals RO Place .the Reactor Mode Switch in SHUTDOWN RO ,, Recog.nize failure to scram RO Enter T-101 on SCRAM condition with power above 4% SRO [T-101 RC-6] RO Insert SRMs/IRMs

[T-101 RC/Q-5] RO Initiate ARCS (Malfunction) Verify after 118 seconds after ARCS initiation SLC pumps start and inject RO Manually attempt SLC injection including '1 C' SLC Pump RO Recognize/report SLC low discharge pressure RO Direct securing SLC SRO Secure SLC pumps RO SEG-7016E Rev002.doc SRRS: 30.126 Page 25 of 39 LIMERICK GENERATING STATION

  • V Exelon Generation SIMULATOR EVALUATION GUIDE 41 5 EVENTS 4
  • 5 RPS HIGH PRESSURE TRANSMITTER FAILURE I ATWS (Major) Simulator Operator Instructions:

Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger At time 11 min after FSSV or EO action requested for T-221, perform the following: Toggle Remote Function RTR051 to "BYPASS" and report (via phone): T-221 is complete on Unit 1. \ At tim$ 7 min OR immediately if pre-staged for at least 7 minutes after FSSV or EO action !requested for T-270, manually perform T-270 as follows: Toggle Remote Functions RTR220 through RTR227 to "TEST' OR the 7-minute T-270 file from the Ops Training Scenarios\Remotes folder and report (via phone): Section 4.6 of T-270 is complete At time 6 min after FSSV or EO action requested for implementation of T-251; contact MCR: and have Operators verify that HV-055-1 F006 indicates closed in the MCR AND perform the following: Toggle Remote Function RTR309 to "OPEN" and report: T-251 is complete in the field SEG-7016E Rev002.doc SRRS: 30.126 Page 26 of 39 " I ,, ' LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 4/5 EVENTS 4-5 RPS HIGH PRESSURE TRANSMITTER FAILURE I ATWS (Major) [T-101 RC/Q-8] RO Runback Recirc pumps to minimum with 28% runback pushbutton [T-101 RC/Q-10] RO Trip both Recirc pumps at least 1 O seconds apart [T-101 RC/Q-12] RO Insert control rods manually with RWM bypassed [T-101 RC/Q-13] SRO Direct performance of T-213 to personnel outside Main Control Room (MCR) [T-101 RC/Q-5] SRO I Direct performance of T-214 to personnel outside Main Control Room (MCR) [T-101 RC/Q-13] (Critical Task) SRO J Direct performance of T-215 to personnel outside Main Control Room (MCR) ,; [T-101 RC/Q-13] SRO Direct performance of T-216 to personnel outside Main Control Room (MCR) I \=b-[T-101 RC/Q-19] (Critical Task) PRO Inhibit Auto ADS [T-101 RC/Q-20] SRO I Direct performance of T-209 ' PRO Stabilize RPV pressure Enter and execute T-117 SRO [T-101 RC/P-11] SRO Direct performance of T-221 w/MSIVs open [T-117 LQ/7] SRO Direct establish RPV level< -50 inches performing T-270 Direct performance of Section 4.6 of T-270 to personnel outside Main PRO Control Room (MCR) (Critical Task) [T-270 4.2.1] PRO IF HPCI initiation signal is present, AND CANNOT be reset, THEN SHUTDOWN 1 OS211, "HPCI Turbine" as follows: I DEPRESS AND RELEASE "Pushbutton For Manual Isolation", and ENSURE HV-55-1 F003 closed SEG-7016E Rev002.doc SRRS: 30.126 Page 27 of 39

I ,, LIMERICK GENERATING STATION ;:::::;';/

Exelon Generation SIMULATOR EVALUATION GUIDE 41 5 EVENTS 4 -5 RPS HIGH PRESSURE TRANSMITTER FAILURE I ATWS (Major) Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger When requested to perform T-221, toggle remote function RTR051 to BYPASS on an 11 minute delay. When time has expired, call and report as complete. At time 7 min OR immediately if pre-staged for at least 7 minutes after FSSV or EO action requested for T-270, manually perform T-270 as follows: Toggle Remote Functions RTR220 through RTR227 to "TEST' OR load the 7-minute T-270 file from the Ops Training Scenarios\Remotes folder and report (via phone): Section 4.6 of T-270 is complete At time 6 min after FSSV or EO action requested for implementation of T-251; contact MCR: and have Operators verify that HV-055-1 F006 indicates closed in the MCR AND perform the following: Toggle Remote Function RTR309 to "OPEN" and report: T-251 is complete in the field ,1 I ,, ' SEG-7016E Rev002.doc SRRS: 30.126 Page 28 of 39 TIME LIMERICK GENERATING STATION Exelon Generation. SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 4/5 EVENTS 4-5 RPS HIGH PRESSURE TRANSMITTER FAILURE I ATWS (Major) [T-270 4.2.2] PRO IF HPCI initiation signal is not present, THEN SHUTDOWN 1 OS211, "HPCI Turbine" as follows: Simultaneously DEPRESS AND HOLD HS-056-161, "Pushbutton for HPCI Turbine Trip (E41A-S19) (TURBINE TRIP) AND CLOSE HV-55-1 F003, "HPCI Main Steam Supply Outbd PCIV (OUTBOARD) [T-270 4.4.1] RO ENSURE HV-06-138A, (BYPASS) is closed [T-270 4.4.2] J RO ENSURE LIC-06-138, (STARTUP BYPASS) in Manual and set to 0°/c [T-270 4.4.3] RO ' ENSURE LIC-06-120, (PUMP BYPASS) in Manual and set to 0% at' [T-270 4.4.4] RO ' ENSURE FIC-M1-1R601A, B, C "A,B,C RFPT Speed Controller in Manual for all three RFPTs [T-270 4.4.5] RO DEPRESS EMERGENCY STOP pushbutton for ALL AVAILABLE RFPTs at panel 1 OC603 ' ,, [T-270 4.4.6] RO WHEN the emergency stop light goes out, THEN DEPRESS AUTO START pushbutton for ALL AVAILABLE RFPTs [T-270 4.4.7] RO CLOSE HV-06-108A, "1A RFP Discharge" [T-270 4.4.8] RO CLOSE HV-06-1088, "18 RFP Discharge" [T-270 4.4.9] RO CLOSE HV-06-108C, "1C RFP Discharge" Stabilize RPV level between -60" and -100" RO [T-101 RC-5] I PRO Isolations verified for + 12.5" and -38" [T-117 LQ/18] SRO Direct performance of T-251 SEG-7016E Rev002.doc SRRS: 30.126 Page 29 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 415 EVENTS 4 -5 RPS HIGH PRESSURE TRANSMIITER FAILURE I ATWS (Major) Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger SEG-7016E Rev002.doc SRRS: 30.126 " I ,, t' Page 30 of 39 TIME LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 4/5 EVENTS 4-5 RPS HIGH PRESSURE TRANSMITTER FAILURE I ATWS (Major) EVALUATORS NOTE: The crew, if permitted, during a high power ATWS, is expected to place RHRSW in service. The following steps are directed by S12.1.A, AHR Service Water System Startup followed by, S51.8.A, Suppression Pool Cooling Operation (Startup and Shutdown) and Level Control. START selected AHR Service Water Pump loop per S12.1.A, AHR Service PRO Water System Startup [812.1.A 4.1.4 or App #1 1.3] PRO OPEN HV-51-1F014A(B), HEAT EXCHANGER INLET [812.1.A 4.1.5 or App #1 1.3] PRO Throttle OPEN HV-51-1F068A(B) for 18 to 2.0 seconds [812.1.A 4.1.6(7) or App #1 1.4] I PRO I VERIFY Pl-51-105A-1(B), HX DISCH, indicates system static pressure greater than or equal to 15 psig *i I [812.1.A 4.1.8 or App #1 1.5] PRO I IF the HI RAD AND/OR HI Pump Discharge pressure trips need to be bypassed AND the required actions of ODCM Part 1 Control 3.1.1 have been met for the INOPERABLE RHRSW Radiation Monitor, THEN PLACE HS8-12-002A(B), PUMP TRIP BYPASS, in "BYPASS" [812.1.A 4.1.10 orApp#1 1.6/1.7] I PRO START OA(B,C,D)V543 Spray Pond Room 'fan [812.1.A 4.2.2 or App #1 1.8] PRO START OA(B,C,D)P506, RHRSW PUMP [812.1.A 4.2.3 or App #1 1.9] PRO THROTTLE HV-51-1F068A(B) to the maximum obtainable position without exceeding 11,000 gpm on Fl-51-1 R602A(B) while maintaining pump disch pressure (Pl-12-001A-1(B)) between 75 psig to 85 psig SEG-7016E Rev002.doc SRRS: 30.126 Page 31 of 39 LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 6/8 EVENTS 6 -8 RDCS !NOP/TURBINE TRIP/A LOOP RHRSW INOP (Malfunction) Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger At time 5 min after FSSV or EO action requested to reset RDCS DELETE MRD024 and toggle RRD001 to RESET and report: RDCS has been reset in the AER" " I ,, SEG-7016E Rev002.doc SRRS: 30.126 Page 32 of 39 TIME LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 6/8 EVENTS 6 -8 RDCS INOP/TURBINE TRIP/A LOOP RHRSW INOP (Malfunction) EVALUATORS NOTE: When reactor power is lowered a RDCS failure will prevent control rod insertion. Reference appropriate ARC: PRO

  • 1071-2, VIBRATION ALARM ALERT
  • 1071-3, VIBRATION ALARM DANGER
  • 108 E-4, RDCS INOPERATIVE Respond to High (Main Turbine)Vibration alarms PRO Recognize/report Main Turbine Hi Vibration PRO Trip the Main Turbine due to high vibration PRO [T-101 RC/P-1] i PRO Stabilize Rx pres ure with SRVs, 990-1096 psiq (Malfunction)

I SRO If RPV pressure rises above 1096 psig, re-enter T-101 [T-101 RC/P-13] ;: RO RFPTs are used to consume additional Steam. (108 valve closed with elevated Feedpump RPM) (Malfunction) Recognize and report RDCS INOP alarm RO Direct RDCS Reset in AER (Malfunction) RO When RDCS in the MCR manually inset control rods RO I Enter T-102, Prirriary Containment Control on Suppression Pool Temp> 95°F SRO Establish Suppre'ssion Pool Temperature as a Critical Parameter SRO [T-102 SP/T-2] PRO Place Two Loops of Suppression Pool Cooling in service per S51.8.A [S51.8.A App #1 step 1.4] PRO START 1A(B)P202, RHR Pump (PUMP) [S51.8.A App #1 step 1.5] PRO OPEN HV-51-1 F024A(B) "RHR Pump Full Flow Test Return" (SUPP POOL CLG), AND MAINTAIN flow indicated on Fl-51-1R603A(B), "RHR Loop Flow" between 8000 to 8500 qpm [S51.8.A App #1 step 1.6] PRO CLOSE HV-C-51-1 F048A(B), HEAT EXCH BYPASS Recognize failure of either 'OA' or 'OC' RHRSW pump to Start (Malfunction) PRO Start other RHRSW pump in 'A' loop PRO When SP temperature reaches 110 deg F DIRECT perform T-270 to lower SRO level until -161, SRV closed or <4% power Perform T-270 to lower level until -161, SRV closed or <4% power PRO/RO (Critical Task) SEG-7016E Rev002.doc SAAS: 30.126 Page 33 of 39 LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE 6/8 EVENTS 6 -8 RDCS !NOP/TURBINE TRIP/A LOOP RHRSW INOP (Malfunction) Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger At time 1 O min after FSSV or EO action requested to perform SE-1 O Floor Actions Load All SE-1 O Floor Actions with Time Delays Scenario and, report: status of individual resets as requested or when all resets are timed out OR report: "All SE-1 O Floor Actions are complete." Perform T-215 folloVI ina T-270 second lowerina with RPV level -161" to -186" Control Rods to be inserted by T-215 as follows: When directed by Lead Evaluator Call MCR and notify MCA control rod movement should occur and DELETE MRP029D I The PURPOSE of this 1 SEG is to get to the T-270 second lowering. With Lead Evaluators permission, vary Bypass Valve malfunction MEH108 so the crew achieves their objective. SEG-7016E Rev002.doc ,, SRRS: 30.126 Page 34 of 39 TIME LIMERICK GENERATING STATION Exelon Generation' SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 6/8 EVENTS 6 -8 RDCS INOP/TURBINE TRIP/A LOOP RHRSW INOP (Malfunction) Re-perform T-270 steps to Emergency Stop Reactor Feed Pumps RO Re-inject with Feedwater when RPV level is< -161" (TAF) and stabilize level RO between -186" and -161" [SE-10 3.1] RO PLACE the following to "CLOSE"

  • 52-20224/CS, "D*24 Safeguard LC. D*24-G-D MCC Bkr" (SAFEGUARDS B), on *BC661
  • 52-20124/CS, "D*14 Safeguard LC. D*14-G-D MCC Bkr" (SAFEGUARDS A), on *AC661. [SE-10 3.2] RO PLACE to "RESET":
  • 43-22322/CS, "Div. 111 Non SFGD Instr. Panel" (INST AC 201 CONTROL PNL), on *CC661
  • 43-22422/CS, "Div. IV Non SFGD Instr. Panel" (INST AC 202 ,, CONTROL PNL), on *DC661. Dispatch Equipment Operator to perform SE-10-1 field actions PRO I Ensure ECCS Pumps other than '1 A' and '1 B' RHR remain shutdown PRO RPV level restored and stabilized between -186 and -161 inches RO (Critical Task) MCR notified of expected control rod movement and recognize all rods in due RO l to T-215, De-energization Of Scram Solenoids (Critical Task) ' ,, I' Secure SLC Pumps that restart on LOCA Signal RO Exit T-117 when all Control Rod in SRO Isolations verifed for -129" RPV level PRO Stabilize level with the core covered after rod insertion to maintain the RO cooldown rate Slowly raise Reactor Level Band 12.5" to 54" RO EVALUATORS NOTE: The scenario is terminated when RPV level has been maintained

-186" to -161 ", followed by Control Rods inserted per T-215, De-energizing Of Scram Solenoids. After the scenario is terminated, direct the SRO to make the highest EAL classification for the scenario. EAL: Alert (MA3) due to: 1. Automatic or manual scram did not shutdown the reactor as I indicated by Reactor Power > 4%. AND 2. Manual I ARI actions taken at the Reactor Console are not successful in shutting down the reactor as indicated by Reactor Power> 4%. SEG-7016E Rev002.doc SRRS: 30.126 Page 35 of 39 TIME ! I I ' i I I f ' ,, I' LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE ASSESSMENT ITEMS AND TASK PERFORMANCE

  • Rough Log(s) Maintained by the crew with the following items noted: * '1 C' RFP Min Flow Valve fails open * '1 C' RFP manually tripped
  • ON-102 entry
  • HWC tripped
  • RPV High Pressure Trip with failure to scram
  • OT-117 entry
  • ATWS
  • T-101 entry
  • T-200 Callouts:
  • T-209
  • T-213
  • T-214
  • T-215
  • T-216
  • T-221
  • T-251
  • T-270
  • T-117 entry
  • Main Turbine Vibration/Trip
  • BPV failure
  • A or C RHRSW Pump Trip
  • LOCA signal
  • SE-1 O entry/floor actions
  • Isolations verified for + 12.5", -38", -129"
  • All rods in
  • Level restored above T AF
  • Alert (MA3) declaration due to ATWS with failure of auto and manual RPS and RRCS SEG-7016E Rev002.doc SRRS: 30.126 POSITION Crew Page 36 of 39 LIMERICK GENERATING STATION Exelon Generation, SIMULATOR EXERCISE GUIDE Attachment 1 Simulator Operator Response Times Procedure Performance T-209 Injection from the Standby Liquid Control Storage Tank with the RCIC System T-212 Bypassing SQUIB Valves for SLC Injection T-215 De-energization of Scram Solenoids T-216 Manual Isolation and Vent of Scram Air Header T-217 RPS/ARI Reset and Backup Method of Draining Scram Discharge Volume T-219 Maximizing CRD Cooling Water Flow during ATWS Conditions T-221 MSIV Isolation Bypass Procedure I T-225 Startup and Shutdown of Pool and Drywell Spray Operations I T-240 Maximizing CRD flow after Shutdown During Emergency Conditions I T-245 RPV Injection from RHR S/D Cooling T-248 Injection from SLC Test Tank to RPV T-251 Establish a HPCI Injection flow Path VIA Feedwater Only T-270 Terminate and Prevent Injection the RPV T-290 Instrumentation Available for T-103 SAMP-2 846.7.A Control Rod Drive Hydraulic System Operation Following Reactor (4.2.1) Scram (Securing CRD flow to the Reactor -Close 46-1 F060, CRD Water Pressure Control Station Inlet Valve) SE-10-1 Breaker Reset Following LOCA (Also reset ARMs, RHRSW Rad Resets and Monitor and RDCS) Floor action SEG-7016E Rev002.doc SRRS: 30.126 Response Time (Minutes) 45 19 7 7 17 23 11 8 8 12 15 6 7 5 7 10 Page 37 of 39 LIMERICK GENERATING STATION ' Exelon Generation SIMULATOR EXERCISE GUIDE CREW: ----DATE: ----START TIME: -----SM: ------CRS: ____ _ PERSON PERSON TIME CALLING BEING CALLED SEG-7016E Rev002.doc Attachment 2 Communications Log LSEG: ----STOPTIME:

RO: ____ _ WCS: _____ _ PRO: ____ _ FSSV: _________

_ CALL COMMUNICATION I REQUEST BACK ' TIME f :; I I ' SRRS: 30.126 Page 38 of 39 LIMERICK GENERATING STATION Exelon Generation.. SIMULATOR EXERCISE GUIDE XI. CREW PREBRIEF INSTRUCTIONS Unit 2 is in OPCON 1 at 100% power Unit 1 is in OPCON 1 at 100% power Specific Plant Conditions are as Follows:

  • Operation per GP-5, Steady State Operations Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):
  • None Restrictions on Plant Operations:
  • None Planned Evolutions:
  • Maintain 100%. Documents Provided:
  • None :; I ,, I' Page 39 of 39}}
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