Text

J.A. Fitzpatrick - Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML101740486
Person / Time
Site:	FitzPatrick
Issue date:	04/09/2010
From:	Caruso J G; Operations Branch I
To:	; Entergy Nuclear Northeast
	HANSELL S L
Shared Package
ML092470037	List: IR 05000333/2010301; ML092520570; ML101740426; ML101740446; ML101740465; ML101740486; ML101750110; ML101750130; ML101750137; ML101750146; ML102710031;
References
	50-333/10-301, TAC U01786 50-333/10-301
	Download: ML101740486 (310)
	v • d • e

{{#Wiki_filter:NRC JAMES A. FITZPATRICK INITIAL EXAMINATION JAMES A. Job Performance Core Thermal Power Calculated Manually ..IPM Number: RO A-1-1 Revision Number: 2 Date: 04/08/20'10 Developed T. Hedigan 04/08/10 Author Date Validated By: Facility Technical Representative Date Review By: Examiner Date Approved By: Chief Examiner Date RO ADMIN JPM A-1-1rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA JOB PERFORMANCE MEASURE VALIDATION All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, ..IPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date _______ Pilot test the JPM: a. verify cues both verbal and visual ape free of conflict, and b. ensure performance time is accurate. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Technical changes and modifications: Not Applicable RO ADMIN JPM A-1-1rev2.doc 2 NRC JAMES A. FITZPA TRICK INiTIAL EXAMINA TlON REVISION RECORD (Summary):

1. This JPM is the original revision O. JPM Setup Instructions:

ITEM: 1.502 6.0.85 12.3.95 2.420 7.47 13.4.00 3. 159 8. 1026 14.392/392 4.155 9.59 15. 391.9/391.9 5.0.85 11.625 Provide applicant with the following:

JPM handout sheet
RAP*7.3.03 , CORE THERMAL POWER EVALUATION, Rev 13
Calculator
ASME Steam Tables
Attachment 1 partially filled out. TASK CONDITIONS:

Plant data has been recorded for steps 1 through 15 of attachment

1. INITIATING CUE: Calculate Core Thermal Power manually per section 9.2 of RAP*7.3.03 , CORE THERMAL POWER EVALUATION.

EPIC computer points are not available. Items 14 and 15 were obtained from 02TT*168A1C and BID on attachment

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

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of 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 caning for each individual item to be performed. RO ADMIN JPM A-1-1rev2.doc 3 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON The time clock starts when the candidate acknowledges the initiating cue. RO ADMIN JPM A-1-1rev2.doc 4 ____ _ NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON Operator's Name: ________________________ _ Job Title: RO JPM Title: Core Thermal Power Calculated Manually JPM Number: RO A-1-1 Revision Number: 0 KIA Number and Importance: KIA 2.1.18 IR: 3.6 Suggested Testing Environment: Classroom/Simulator Actual Testing Environment: Testing Method: Table-Top Alternate Path: No Time Critical: No Estimated Time to Complete: 75 minutes Actual Time Used: __minutes

References:

RAP*7.3.03 , CORE THERMAL POWER EVALUATION, Rev 13 RAP*7.3.16 , PLANT POWER CHANGES, Rev. 46 ST*50, APRM CALIBRATION, REV. 3 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes DNa 2. Was the task standard The operator's performance was evaluated against the standards contained in this JPM, and has determined to be: 0 Satisfactory Comments:___________________________Note: Any grade of UNSAT requires a comment. Evaluator's Name: ______________(Print) Evaluator's Signature: Date: RO ADMIN JPM A-1-1rev2.doc 5 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE JPM Start Time _____ ELEMENT Applicant calculates feedwater temperature compensated feed flow. data on Attachment 1 items through Applicant uses the ASME steam tables to calculate Items 24 through 30 on attachment

1. Note: Steam tables will not be able to be used to determine the enthalpy of compressed water. Items number 26, 27,28, 29, 30. Applicant calculates items through 34 on attachment STANDARD SAT UNSAT Comment Number Correctly calculates feedwater compensated flow. 16. 392 391.9 18. 28.1 20. 1.01031 21. 1.01034 22. A=3.99 (3.96-4.02)

23. B=4.04 (4.01-4.07)

Correctly determines enthalpy from steam tables. 24.1191.9 (1191.2-1192.6)

25. 645.5 (639.9-651.1)

26. 367.4 (363.9-370.9)

27. 367.3 (363.8-370.8)

28. 490.1 (486.1-494.2)

29. 397.6 (393.6-401.6)

30. 65.8 (61.8-69.8)

Correctly calculaltes Q to feedwater. 31.8.03 (7.97-8.09) 32.367.4 (363.9-370.9) 33.1191.9 (1191.2-1192.6) 1940.4 (1935.4-1945.4) RO ADMIN JPM A-1-1rev2.doc 6 NRC JAMES A. FITZPATRICK INITIAL EXAMINA ELEMENT Applicant calculates items through 36 on attachment Applicant calculates items through 39 on attachment Applicant calculates items 41 on attachment

1. 7. (*) Applicant calculates items 42 through 43 on attachment

1. Task is complete.

JPM Stop Time _____ STANDARD SAT UNSAT Comment Number Correctly calculates Q to CRD flow. 35..037 (.036-.0:38)

36. 12.2 (11.9-12.5)

Correctly calculates Q to Cleanup system. 37. . 1 56 (. 1 54-. 158) 38. 92.5 (90.5-94.5) 39.4.24 (4.04-4.44) Correctly calculates QPUMP 41. 1.58 (1.38-1.78) Correctly determines core thermal power. 42.1956.3 (1841.1-2069.4)

43. 77.1 (72.6-81.6)

RO ADMIN JPM A-1-1rev2.doc 7 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON HEAT BALANCE CALCULATION SHEET Page 1 of 1 PERFORMED BV: ______________, DATErrlME: ________ PURPOSE' ITEM PARAMEnR PANEL INSTRUMENT VALUE UNITS 1. Cleanup Inlet 9-4 12TS5-142 POS 1 ,)6;L. of 2. Cleanup Outlet 9-4 12TS5-142,POS 4 .., L. 0 of 3. Cleanup Row 9-4 12FI-126A J s-'l, GPM 4. Cleanup Row 9*4 12FI-1268 ,<;", GPM 5. POwer to Reclrc. Pum..,2,A 9*4 RWR MG A GEN PWR l'>. Sl{, MW 6. Power to Reclrc. Pump B 9-4 RWR MG B GEN PWR 0 _(" MW 7. Total Core 9-6 02-3DPRIFR*95 <./7 Mlblhr 8. Reactor Pressure (psiQ+14.71 9-5 'O.:l,(" PSlA 9. CRD Flow to Reactor 9-5 03FI-3l0 GPM 9a RWR & RWCU Pump Seal Rows Constallt 15 GPM 10. CRD Svstem Temp 95 OF 11. Groas MW 8ectric 9-7 MAIN (lEN MW c.')"S" GMWE *12. Feedwater Flow Loop A 9-5 06FI-SSA . q<; MLB/HR *13. FeedwaterFlowLoop_B 9-5 WI-8SB LI_QO ML8/HR 14. TFWA.uaePTID407I4100r 9-21 'H;)./3Q;l.°F TFWB. use PTIO 408/411 or 9-21 02TI-I6BBJO 291. '1 FEEDWA TER now CALCULA *16. AVBrlKle TFWA (407+410)/2 or (16BA+168C)/2 '17. AVBraoeTFW8(408+411)J2or(168B+168DII2 '18. Delta T loaD A (DTA)

TFWA -420 -2 '19. Delta T Loop B lOTS) TFWB* 420 -7_\'1. I *20. C.F." 1.0 + {OTA*(-3.8064E-4

+ (DTA*-4.4310E-7JJ) 1.0-.103

21. C.F... 1.0 + {DTB*[-3.8064E-4

+ I 0 I (13 <I *22. 'Compensated Flow (#12 * #20) _,,/<1 (J."i{ -\(o.).)MLB/HR

Compensated Row B (#13 * #21) 't,o 'f ( </, (J J -Yo 07) MLB/HR PARAMETFR "EM DATA USED UNITS 24. 18. ASME Table 1\ q I. '1 (If QI.2AM'lJ.13TU/LB

....'25.' HFG '26. HFWA *27. HFWB #8 #17. ASME Table 3r...... ' 3.B -)"Xl. BTu/LB 28. #8 #1 ASMETable BTU/LB 29. #8. #2 ASME Table '3 -</61_(, STUILS HCR #B. #1 O.ASME Table G;>. 'il 'Col.'A -I.'? III BTUILB PARAMETER EOUA TlON (ITEM #-81 VALUE UNITS 31. Total (622 + #231 tOo (:7-'11 .Il") MLBIHR 32. Feedwater EnthelDv 1(626'622) + 1627,*623)]1#31 3(..:1. ..,-no.ql BTU/LB 33.* Steam Enthalpy ('24 -(0.000'#25)] u'IJL9( II "1'1. 7AI9H,)BTU/LS 34. Q to. feedwater [#31 *(633 -#3211/3.413 ltiJL'I{r!tJ.r.:'f-nYr.vjMWt

35. CRD flow (WCRI ((69 " 0.498E-31

+ (Ige

0.498E-3lJ ( OJ!. -8\ MLBlHR 36. Q to

[#35 *(133 -#30)]/3.413 \1." -IJ .S). MWt' 37. Total CU flow (#3 + 141 "'0.498E-31

I,Co .,..-.1 -

MLS/HR 38. HCUI (#28 -#291 ()02. d .11l.<: *jlYor: STUILB 39. 0 to Cleanup 1#38

637113.413

'f. 7.<1 ( /.{.o" -My MWt 40. Vellsel ambient loss 1.t MWt 41, QPUMP 1#5 + #6) *0.93 IS'll (t.}?. *1.)9) MWt 42. Core Thermal Power (#34+ #36 + #39 + #4<)*'411 1'):'\(0, . 43 CTP/2536 (642/25361*100 '/,.1 .. Not Applicable when Attachment 5 is used. Contact Operations to determine if this is performed to satisfy Tech. Specs: DVES DNO

If Ves, Second Verifier:

____________ _ DstefTlme:,__________ Reviewed By: ___-::---:--:::--::---:--=-_-:-----: _____ Datemme: ____....;.._____ Reactor Engineering Superintendent 1§. a Quality Record RAP-7.3.03 CORE THERMAL POWER EVALUATION ATTACHMENT Rev. No. 13 Page 11 of E' ><J A IV'. \<"'6" '( NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON HANDOUT PAGE TASK CONDITIONS: Plant data has been recorded for steps 1 through 15 of attachment

1. INITIATING CUE: Calculate Core Thermal Power manually per section 9.2 of RAP-7.3.03, CORE THERMAL POWER EVALUATION.

EPIC computer points are not available. Items 14 and 15 were obtained from 02TT-168A1C and BID on attachment

3. RO ADMIN JPM A-1-1rev2.doc NRC JAMES A. FITZPATRICK INITIAL HEAT BALANCE CALCULATION SHEET Page 1 of 1 PERFORMEDBY:

________________________DATEfTlME: _________ PURPOSE' ITEM PARAMETER PANEL INnRUMENT VALUE UNITS 1. Cleanup fnlet Temp 9-4 12156-142 POS 1 S"'D :J. of 2. Cleanup Outlet Temo. 9-4 12TSS*142POS 4 _'1'::L 0 of 3. Cleanup Flow A 9*4 12FI*126A IS" ., GPM 4. Cleanup Row B 9*4 GPM I"6. Power to Recire. Pump A 9-4 GEN PWR 0.'9:<::" MW 6. Power to Recire. Pump S 9-4 GENPWR (} go(' MW i=im 7. T etal Core Flow 9*6 02-30f>RIFR*95 Mlblhr 8. 9*5 06PR/FR-98 {O.J. c., PSIA

9. e Reactor 9-6 03FI*310 GPM ge PumP Seal Flows Constant 15 GPM 10. 'CRO System Temp Constant 95 "F 11. Gross MW Bactrlc 9-7 MAINGENMW

(,;,. .... GMWE *'2. Feedwater Flow loOP A 9*5 OSFI-89A <" MLBlHR*'3. Faedwater Flow Loop B 9-5 06FI-898 MLBlHR 4.0 14. TFWA use pnO 4071410 or 9*21 02TI-168AlC ':? q.l.. (3<ii OF 16. TFW8, use PTID 408/411 or 9-21 02TI-168BIO hq/qoF FEEDWA TER FLOW CALCfJLA TTONS *16. Alier8lle TFWA (407+4101/2 or 116BA+16BC1/2 OF "11. Average TFWS 1408+411112 or (1688+1660)12 OF "18. Dllltil T Loop A IOTAl .. TFWA

420 OF *'9. Delta T Loop BIDTBI "" TFWB* 420 OF "20. C.F. '" 1.0 + fDTA*[-3.8064E-4

'" (DTA".....4310e-7ll) "21. C.f... 1.0 T {DTB*[-3.B064E-4 + (OTB*-4.43101:*7/1} '22. ComD6I1$ated Flow A 1#12 * '2Q) MLBIHR *23. CompenSjltlld Flow B' (113 * '211 PARAMETER ITEM DATA USED

24. HS 118, ASMETllble BlUM ,.,'25. tiFG . -" *,8*' ASr.4tT iible BrullS "26. HFWA lIS #16, BTU/1.B *27. HFWB 1t8 #17 Table BTVlLB mTable 28. HCUI #8." ASME.TabI&

BlUIlB 29. HCUO #8 #2. ASME Table BTu/LS 30. HCR 18 #10. ASMETabie BTU/LS PARAMEnR EQUATION (ITEM r8I VALUE UNITS 31. T 0181 Feedflow (122 + #231 MLS/Hfi 32. ((i/26*'221 '+ STU/LS 33. Steam EnthalPY 1#24 -lO.OOO"'2,@ BTU/1.B 34. 1321113.413 MWt CRO .35. O.49&E*3) + 119a

O.49aE*31l MI.BtHR 36. Q to COO flow IOCR) [136 +(133-8301113.413 MWt 37. Totlll CU flow ('NeUJ (#3 + #4) *(O.498e-31 MLBIHR 38. HCUI (126, '291 STU/LS 39. Q to Cleanup Svs I#S8 * #37113.413 IW. Veallel ambient 1.1 MWt 41. OPUMP (#5 + #61 .. 0.93 MWt I 42. Core Thermal Power #39 + #40*1411 MWt I 43 CTP/2536 (I 1° 100 % .. Not Applicable when Attachment 5 is used. Contact Operations to determine if this is performed to satisfy Tech. Specs: DYES DNO .. If Yes, Second Verifier:

__________ Oatemme:.__________ Datemme: ____ __Reviewed By: Reactor Engineering liiuperi(ltendent -IS a Quality Record " . , RAP-7.3.03 CORE THERMAL POWER EVALUATION ATTACHMENT Rev. No. 13 page J.1 of 16 ROAf.. NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON Heat Balance Calculation Sheet (RO Candidate Worksheet) VALUE UNITS of 502 420 of 159 GPM 155 GPM 0.85 MW 0.85 MW 47 Mlb/hr 1026 PSIA 59 GPM 15 GPM of 95 625 GMWE 3.95 Mlb/hr 4.00 Mlb/hr of 392/392 of 391.9/391.9 of of OF of Mlb/hr Mlb/hr VALUE UNITS BTU/lb BTU/lb BTU/lb BTU/lb BTUllb BTU/lb BTUllb VALUE Mlb/hr BTU/lb BTU/lb MWt Mlb/hr MWt Mlb/hr BTU/lb MWt MWt MWt MWt % PARAMETER

1. Cleanup Inlet Temp. 2. Cleanup Outlet Temp. 3.

Flow A 4. Cleanup Flow B 5. Power to Recirc. Pump A 6. Power to Recirc. Pump B 7. Total Core Flow 8. Reactor Pressure (psig + 14.7) 9. CRD Flow to Reactor 9a. RWR & RWCU Pump Seal Flows 10. CRD System Temp 11. Gross MW Electric *12. Feedwater Flow Loop A *13. Feedwater Flow Loop B 14. TFWA, use PTID 407/410 or 15. TFWB, use PTID 408/411 or *22. Compensated Flow A *23. Compensated Flow B PARAMETER

24. HS 25. HFG *26. HFWA *27. HFWB 28. HCUI 29. HCUO 30. HCR PARAMETER UNITS 31. Total Feedflow 32. Feedwater Enthalpy 33. Steam Enthalpy 34. o to Feedwater (OFW) 35. CRD flow (WCR) 36. o to CRD Flow OCR) 37. Total CU flow (WCU) 38. HCUI-HCUO 39. o to Cleanup Sys 40. Vessel Ambient Loss 41. OPUMP 42. Core Thermal Power 43. CTP 12536 PANEL 09-4 09-4 09-4 09-4 09-4 09-4 09-5 09-5 09-5 09-7 09-5 09-5 09-21 09-21 FEEDWATER FLOW CALCULATIONS

16. AveraQe TFWA 407+410) 12 or (168A+168C) 12 *17. Average TFWB 408+411) 12 or (1689+168D) 12 *18. Delta T Loop A ( DTA);; TFWA -420 *19. Delta T Loop B ( DTB) ::: TFWB -420 *20. C.F. ::: 1.0 + {DTA x [-3.8064E-4

+ (DTA x -4.4310E-7)]}

21. C.F. ::: 1.0 + {DTB x [-3.8064E-4

+ (DTB x -4.4310E-7)]} (#12 x #20) (#13 x #21) DATA USED ASME Table ASMETable ASMETable ASME Table ASME Table ASMETable ASME Table ITEM #8 #8 #8,#16 #8,#17 #8,#1 #8,#2 #8,#10 INSTRUMENT 12TSS-142 1 12TSS-142, 4 12FI-126A 12FI-126B RWR MG A GEN PWR RWR MG B GEN PWR 02-3DPRlFR-95 06PRlFR-98 03FI-310 Constant Constant MAINGENMW 06FI-89A 06FI-89B 02TI-168A1C 02TI-168B/D EQUATION (ITEM #'5) (#22 + {(#26 x #22) + (#27 x #23)} 1#24 -(0.000 x {#31 x (#33 -#32)} {(#9 x 0.498E-3) + (#9a x 0.498E-3)} {#35 x (#33 -#30)} 13.413 #3 + #4) x (0.498E-3)

28 -#29) #38 x #37) 13.413 #5 + #6) x 0.93 #34 + #36 + #39 + #40 -#41 ) (#42/2536) x 100

Not applicable when Attachment 5 is used. RO ADMIN JPM A-1-1rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON RO ADMIN JPM A-1-1rev2.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINATION JAMES A. FITZPATRICK Job Performance Measure
Work Hour Restrictions JPM Number: RO A-1-2 Revision Number: 1 Date: 03/11/2010 Developed By: B. Litkett Author 410812010 Date Validated By: Facility Technical Representative Date Review By: Examiner Date Approved By: Chief Examiner Date RO ADMIN JPM A-1-2rev1.doc NRC JAMES A. FITZPA TRICK INITIAL ADMIN RO JPM #A-1-2 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 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date ______ Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Technical changes and modifications: Not Applicable RO ADMIN JPM A-1-2rev1.doc 2 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION ADMIN RO JPM #A-1-2 REVISION RECORD (Summary):

1. This JPM is the original revision 1. JPM Setup Instructions:

Provide applicant with the following:

JPM handout sheet TASK Determine any work hour RO ADMIN JPM A-1-2rev1.doc 3

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 TASK CONDITIONS: A Reactor Operator has called in sick for Thursday, May 6th Day Shift. The following is the recent work hour history of 3 Reactor Operators. Their hours worked were and are in the Main Control Room during Mode 1, except for the training week. Dayshift Nightshift Training 7:00 am -7:00 pm 7:00 pm -7:00 am 7:00 am -3:30 pm The schedules show the day that each work shift begins. RO -John Smith Week of April 12 Week of April 19 Week of April 26 Week of May 3 Week of May 10 M T D N T T D N W T N T T N F T D N S D N D S D N D RO -Bill Waters Week of April 5 Week of April 12 Week of April 19 Week of April 26 Week of May 3 M T D D N T T D N VV T D N T T N D F T D N D S D N S D N RO -Mike Hill Week of April 19 Week of April 26 Week of May 3 Week of May 10 Week of May 17 M T D N T T D N VI/ T [) [) N T T D N F T D N D S D N S D N RO ADMIN JPM A-1-2rev1.doc 4 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 INITIATING CUE: Evaluate the work hour history for each of the 3 Reactor Operators. Determine which operators can take the scheduled watch for a full dayshift of 12 hours today, May 6th. If applicable, describe the conditions that would make any operator(s) ineligible to work. Consider all days after May 6th as scheduled shifts. Consider all days before May 6th as actual worked shifts. Information for Evaluator's UNSAT requires written comments on respective

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. Then annotate that comment in the section. The comment section should be used to document the reason that a step is marked as and to document unsatisfactory performance relating to management Some operations that are performed from outside of the control room may require multiple steps. These may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator perform groups of procedure steps instead of calling for each individual item to be The time clock starts when the candidate acknowledges the initiating cue. RO ADMIN JPM A-1-2rev1.doc 5

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 Operator's Name: ________________________ _ Job Title: RO JPM Title: Work Hour restrictions JPM Number: RO A-1-2 Revision Number: 1 KIA Number and Importance: KIA 2.1.5 IR: 2.9 Suggested Testing Environment: Classroom Actual Testing Environment: Testing Method: Table-Top Alternate Path: No Time Critical: No Estimated Time to Complete: 15 minutes Actual Time Used: __minutes

References:

1. EN-OM-123, Rev.2; Fatigue Management program EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes ONo 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory [J Unsatisfactory Comments:__________________________ _ Note: Any grade of UNSAT requires a comment. Evaluator's Name: _____________(Print) Evaluator's Signature: Date: _____ RO ADMIN JPM A-1-2rev1.doc 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA ADMIN RO JPM #A-1-2 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT STANDARD SAT UNSAT Comment Number 1. Obtain a controlled copy of procedure EN-OM-123 Rev.2; Fatigue Management program The applicant obtains a controlled copy of EN-OM-123 Rev.2; Fatigue Management program EXAMINER NOTE: AP-11.03 used to contain overtime rules for key station personnel. However, this information is now contained in EN-OM-123; Fatigue Management Program. 11.03 no longer applies to operators on shift and is no longer active. RO ADMIN JPM A-1-2rev1.doc 7 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 ELEMENT STANDARD SAT UNSAT Comment Number Step 5.2. Working hour limits for Applicant evaluates each covered listed operator limitations of Work hour limits for performing Covered consist of three components; maximum minimum breaks and Days Off (1 ) The maximum ceilings apply at all times are maximum 16 work hours in any hour 26 work hours in any hour period, 72 hours in any 7 The minimum break which apply at all times are minimum 10-hour break successive periods, except that 8-hour break is when necessary accommodate a scheduled between schedules or shifts, 34-hour break in any 9 day (3) EN-OM-123; step describes (a) For Operators a 12 hour shift, requirement is average a minimum 2.5 days off per The average days off week is averaged over shift cycle of up to weeks in RO ADMIN JPM A-1-2rev1.doc 8 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION ADMIN RO JPM #A-1-2 iSTANDARD SAT UNSAT Comment Number *3. Evaluate John Smith for Applicant determines Smith can NOT take the because he would not have 34 hour uninterrupted break the nine days from May 1 May *4. Evaluate Bill Waters for Applicant determines Waters can NOT take the because he would exceed 16 hours in a 24 hour requirement. The night shift May 5 will end at 7 am Day shift May 6 starts at 7 So with no time off shifts, will end up working hours Mike Hill can work the shift. *5. Evaluate Mike Hill for overtime. He would have a 36 hour break from May 4 to May 6 and for the week he will have 72 hours which is allowed, and for the cycle he will have 13 days off. The MDO, when working a five week cycle . requires 12.5 days off, which rounded up is 13 days off. Therefore he meets the MDO requirement. Examiner: Terminate the task at this point JPM Stop Time _____ RO ADMIN JPM A-1-2rev1.doc 9 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Handout Page TASK CONDITIONS: A Reactor Operator has called in sick for Thursday, May 6th Day Shift. The following is the recent work hour history of 3 Reactor Operators. Their hours worked were and are in the Main Control Room during Mode 1, except for the training week. Dayshift 7:00 am -7:00 pm Nightshift 7:00 pm -7:00 am Training 7:00 am -3:30 pm The schedules show the day that each work shift begins. RO -John Smith M T W T F S S Week of April 12 T T T T T Week of April 19 D D Week of April 26 D D N N Week of May 3 N N D D D Week of May 10 N N N RO -Bill Waters M T W T F S S Week of April 5 T T T T T Week of April 12 D D D D Week of April 19 D N N N Week of April 26 D D D D N Week of May 3 N N N RO -Mike Hill M T W T F S S Week of April 19 T T T T T Week of April 26 D D D D Week of May 3 D D N N N Week of May 10 0 D D Week of May 17 N N N N NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Handout Page INITIATING CUE: Evaluate the work hour history for each of the 3 R.eactor Operators. Determine which operators can take the scheduled watch for a full dayshift of 12 hours today, May 6th. If applicable, describe the conditions that would make any operator(s) ineligible to work. Consider all days after May 6th as scheduled shifts. Consider all days before May 6th as actual worked shifts. JAMES A. Job Performance Initiate a manual tagout for 'B' RHR pump discharge check JPM Number: RO A-2 Revision Number: 1 Date: 03/09/2010 Developed B. Litkett 04/08/10 Author Date Validated By: Facility Technical Representative Date Review By: Examiner Date Approved By: Chief Examiner Date RO ADMIN JPM A-2rev1.doc JOB PERFORMANCE MEASURE VALIDATION NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Technical changes and modifications: Not Applicable RO ADMIN JPM A-2rev1.doc REVISION RECORD (Summary): This JPM is the original revision O. REFERENCES EN-OP-102 OP-13 FM-208 TOOLS AND EQUIPMENT Current copies of OP index and references, SET UP REQUIREMENTS Applicant has been assigned to prepare a tagout. EVALUATOR NOTES Examiner's copy of component positions (Answer Key) is provided. The Applicant should demonstrate proper use of all HU tools during the performance of the procedure. Manual tag sheet is used. If Applicants ask, then, state "SOMs is out of service and SM has directed use of manual tagout for this work". If Applicant asks for a copy of the work order state this was reviewed and no additional information was obtained.

Information for Evaluator's UNSAT requires written comments on respective

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the Applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The time clock starts when the Applicant acknowledges the initiating cue. RO ADMIN JPM A-2rev1.doc Operator's Job Title: JPM Title: Initiate a manual tagout for '8' RHR pump discharge check valve replacement JPM Number: RO Aw2 Revision Number: 0 KIA Number and Importance: KIA 2.2.13 IR: 4.1 Suggested Testing Environment: Classroom Actual Testing Environment: Testing Method: Table-Top Alternate Path: No Time Critical: No Estimated Time to Complete: 60 minutes Actual Time Used: __minutes

References:

EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes No 2. Was the task standard The operator's performance was evaluated against the standards contained in this JPM, has been determined to be: Satisfactory 0 Comments:__________________________Note: Any grade of UNSAT requires a comment. Evaluator's Name: ___________ .___(Print) Evaluator's Signature: Date: _____ RO ADMIN JPM A-2rev1.doc TASK CONDITIONS: Currently all systems are operable INITIATING CUE: A tagout is required on the "B" RHR system to conduct repairs on 10RHR-42B; discharge check valve. Work scope is to replace valve internals. Shift Operations Management System is out of service and SM has directed use of manual tagout for this work. You have been directed to prepare a manual tagout. You are responsible for required hang positions and sequence of the components. Inform the Operations Supervisor when you have completed the tagout. RO ADMIN JPM A-2rev1.doc PERFORMANCE JPM Start Time _____ ELEMENT STANDARD SAT UNSAT Comment Number 1. Applicant determines EN-OP-1 02-01; Applicant uses EN-OP-1 02-01 ; attachment 9.2 and 9.3; OP-13; FM-20A attachment 9.2 and 9.3; OP-and drawings 13;FM-20A and drawings Evaluator CUE: Can provide blank

Evaluator CUE: Can provide copy of EN-OP-1 02-01; attachment 9.2 blank copy of EN-OP-1 02-01 ; and 9.3 after applicant determines attachment 9.2 and 9.3 after tagging sheets. applicant determines tagging sheets. 2. Applicant reviews the isolation The Applicant determines boundaries.

tagout boundary 3.(*) 1-10 -10P-3B; RHR B PUMP

Applicant selects 1-10 -10P* CONTROL SWITCH in auto after stop; 3B; RHR B PUMP CONTROL sequence 1.
SWITCH in auto after stop; sequence 1. 4. (*) 1-10 -10P-2B; RHR B KEEPFULL Applicant selects 1-10 -1 PUMP CONTROL SWITCH; STOP;
2B; RHR B KEEPFULL PUMP sequence 1. CONTROL SWITCH; STOP;
seq uence 1. 5. (*)1-71-71MCC-163-0E1; 10P-2B; Applicant selects RHR B KEEPFULL PUMP BREAKER; 71 MCC-163-0E1; 10P-2B; OFF/REMOVED, sequence 2.
RHR B KEEPFULL PUMP BREAKER; OFF/REMOVED, I sequence 2. 6. (*) 1-71 --71-10540 BKR CLOSE FUSE; Fuses removed; sequence 2. i Applicant selects 1-71 -10540 BKR CLOSE FUSE; I Fuses removed; sequence 2. 7. (*) 1-71 -CKTBKR-71-10540 racked Applicant selects 1-71 -out/removed; sequence 3. CKTBKR-71-'I0540 racked out/removed; sequence 3. I 8. (*) 1-71 --71-10540 BKR TRIP Applicant selects 1-71 -FUSES; fuses removed; sequence 4. i 10540 BKR TRIP FUSES; I fuses removed; sequence 4. I RO ADMIN JPM A-2rev1.doc 9.(*) 1-10 --VALVE 10RHR-45B;

'B' RHR discharge isolation valve, CLOSED, *sequence 5. 10.(*) 1-10 --10MOV-13B SW] TORUS SUCT VALVE; sequence 11. (*) 1-10-10MOV-15B SHUTDOWN CLG VLV; sequence 12. (*)1-71 -71 MCC-163-0J4; 13B RHR PUMP B SUCT FROM SUPPRESSION POOL ISOL VALVE;OFF/REMOVED; sequence 7. 13. (*) 1-71 -7'IMMC-163-0D1; 15B RHR PUMP SUCT SHUTDOWN COOLING ISOL VALVE; OFF/REMOVED; sequence 7. 14. (*) 1-10 -VALVE-10MOV-15B; RHR PUMP B SUCT Shutdown Cooling ISOL, CLOSED, sequence 8. 15. (*) 1-10-VALVE-10MOV-13B; RHR PUMP B SUCT TORUS ISOL VALVE; CLOSED, sequence 8. 16. (*) 1-10-VALVE-10RHR-251B; RHR PUMP B SUCT DRAIN VALVE; CLOSED; sequence 9. 17. (*) 1-10 -VALVE-10RHR-28B; RHR PUMP B MIN FLOW ISOL VALVE; CLOSED; sequence 9. RO ADMIN JPM A-2rev1.doc STANDARD SAT UNSAT Comment Number Applicant selects VALVE 10RHR-45B; 'B' RHR discharge isolation valve, CLOSED, sequence 5. Applicant selects 1-10 10MOV-13B [KEYLOCK SW] TORUS SUCT VALVE; CLOSED; sequence 6. Applicant selects 10MOV-15B (SW); SHUTDOWN CLG VL V; CLOSED; sequence 6. Applicant selects 1-71 -71 MCC-163-0J4; 10MOV-13B RHR PUMP B SUCT FROM SUPPRESSION POOL ISOL VALVE; OFF/REMOVED; sequence 7. Applicant selects 1-71 -71MMC-163-0D1; 15B RHR PUMP SUCT SHUTDOWN COOLING ISOL VALVE; OFF/REMOVED; sequence 7. Applicant selects VALVE-10MOV-15B; RHR PUMP B SUCT Shutdown Cooling ISOL, CLOSED, sequence 8. Applicant selects 10MOV-13B; RHR PUMP B SUCT TORUS ISOL VALVE; CLOSED, sequence 8. Applicant selects 10RHR-251B; RHR PUMP B SUCT DRAIN VALVE; CLOSED; sequence 9. Applicant selects 1-10 VALVE-10RHR-28B; RHR PUMP B MIN FLOW ISOL I I CLOSED; sequence ELEMENT 18.(*) 1-10-VALVE-1 ORHR-91 B; RHR KEEP-FULL PUMP B SUCT ISOL VALVE;CLOSED; sequence 9. 19.(*) 1-1 0-VALVE-1 ORHR-250D; RHR Pump D DISCH DRAIN VALVE, CLOSED, sequence 9. 20.(1) 1-10-VALVE-10RHR-250B; RHR PUMP B DISCH DRAIN VALVE; OPEN; sequence 10. 21.(1) 1-10-VALVE-10RHR-253; RHR Pumps B & D DISCH DRAINS TO EQUIP SUMP ISOL VALVE; OPEN; sequence 10. 22.(1) 1-10-VALVE-10RHR-682; RHR PUMP B DISCH DRAIN VALVE; UNCAPPED & OPEN; sequence 10. 23.(1 )1-10-VALVE-10RHR-698: RHR PUMP B DISCH SPARE INSTRUMENTATION ISOLATION VALVE; UNCAPPED & OPEN; sequence 10. EXAMINER NOTE 1: Other methods of draining the system are available. Only 1 vent and drain valve needs to be open. Task is complete. STANDARD SAT UNSAT Comment Number Applicant selects 1 ORHR-91 B; RHR FULL PUMP B SUCT ISOL VALVE; CLOSED; sequence 9. Applicant selects 1-10-VAL 10RHR-250D; RHR Pump D DISCH DRAIN VALVE, CLOSED, sequence 9. Applicant selects 10RHR-250B; RHR PUMP B DISCH DRAIN VALVE; OPEN; sequence 10. Applicant selects 10RHR-253; RHR Pumps B & D DISCH DRAINS TO EQUIP SUMP ISOL VALVE; OPEN; sequence 10. Applicant selects 10RHR-682; RHR PUMP B DISCH DRAIN VALVE; UNCAPPED & OPEN; sequence 10. Applicant selects 10RHR-698: RHR PUMP B DISCH SPARE INSTRUMENTATION ISOLATION VALVE; UNCAPPED & OPEN; sequence 10. EXAMINER NOTE 1: Other methods of draining the system are available. Only 1 vent and drain valve needs to be open. RO ADMIN JPM A-2rev1.doc ANSWER KEY Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.2 Clearance: Manual -Component to be worked: 'B' RHR pump

Description:

Repair 1 ORHR-42B -replace valve internals Placement 1.) Ensure MOVs are CLOSED prior to tagging open 2.) Ensure condensate transfer is for keepfull for '0' Pump. 10P-2B and 10P-3B are out of service 3.) Rack out breaker 71-10540 per OP-46A Hazards: 1.) Residual water in piping is possible. Possible contaminated water Restoration Inst: 1.)Ensure RHR B is filled and vented prior to restoration 2.) Rack in breaker 71-10540 per OP-46A Attribute LCO Work Order Number Description 12345678910 Replace 10RHR-42B internals Status Description Prepared Technical Reviewed Approved Tags Verified Hung Tags Verified Removal Approved Removal Tags Verified Removed Tags Verified T AGOUT COVER Tagout: Attribute Value User Verification Date RO ADMIN JPM A-2rev1.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINATION ATTACHMENT 9.3 ANSWER TAGOUT TAGS SHEET CI T .. Tag Place. Place. Rest Restoration Rest. 2 no Placement!

erial Tag Equipment Description Place. Placement 1st Verif 2nd Verif .Seq Configuratio Rest. 1 st Verif Verif Removal No. Type Equipment Location Seq. Configuration DatelTime DatefTime n DatefTime DatelTime Tag Notes D 10P-3B; 'B' RHR pump control 1 Auto after Stop switch 10P-2B; 'B' RHR Keep full pump 1 Stop I control switch 1-71-71 MCC-163-0E1 2 OFF! REMOVED 1-71 --71-10540 BKR CLOSE 2 FUSE D 1-71 -CKTBKR-71-10540 3 1-71 --71-10540 BKR TRIP 4 FUSES 1-10 -VALVE 10RHR-45B;

'B' 5 RHR DISCHARGE D 1-10 -10MOV-13B [KEYLOCK 6 SW] TORUS D 1-10 10MOV-15B (SW); 6 SHUTDOWN CLG VL 1-71-71 MCC-163-0J4; 10MOV-7 138 REMOVED 1-71-71 MCC-163-0D1

10MOV-7 15B REMOVED *1-10 VALVE-10MOV-1S8; RHR B CLOSED PUMP 8 SUCT Shutdown Cooling ! ISOL 1-10-VALVE-10MOV-13B; RHR B PUMP 8 SUCT TORUS b-1-10-VALVE-10RHR-2518; RHR 9 PUMP 8 SUCT DRAIN 1-10 -VALVE-10RHR-2BB; RHR 9 PUMP 8 MIN FLOW ISOL

RO ADMIN JPM A-2rev1.doc C NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-2 ATTACHMENT 9.3 ANSWER TAGOUT TAGS SHEET 0 1-10-VALVE-10RHR-918; RHR 9 KEEP-FULL PUMP 8 SUCT 0 1-10-VALVE-10RHR-250D; RHR 9 CLOSED Pump 0 DISCH DRAIN VALVE Note 0 1-10-VALVE-10RHR-2508; RHR 10 OPEN 1 PUMP 8 DISCH DRAIN VALVE Note 0 10RHR-253;

'8' and '0' RHR 8 & 0 10 OPEN 1 DISCH DRAINS TO EQUIP SUMP ISOL VALVE Note 0 1-10-VALVE-10RHR-682; RHR 10 UNCAPPED 1 PUMP 8 DISCH DRAIN VALVE and OPEN Note 1-10-VALVE-10RHR-698: RHR 10 UNCAPPED PUMP 8 DISCH SPARE and OPEN INSTRUMENTATION ISOLATION VALVE NOTE 1: Only 1 vent and drain valve needs to be open. JPM Stop Time _____ RO ADMIN JPM A-2rev1.doc 11 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-2 HANDOUT PAGE TASK CONDITIONS: Currently all systems are operable INITIATING CUE: A tagout is required on the "B" RHR system to conduct repairs on 10RHR-42B; discharge check valve. Work scope is to replace valve internals. Shift Operations Management System is out of service and SM has directed use of manual tagout for this work. You have been directed to prepare a manual tagout. You are responsible for required hang pOSitions and sequence of the components. Inform the Operations Supervisor when you have completed the tagout. RO ADMIN JPM A-2rev1.doc JAMES A. Job Performance Liquid Radwaste Potentiometer JPM Number: RO Revision Number: 0 Date: 03/04/2010 Developed T. Hedigan 03/04/10 Author Date Validated By: Facility Technical Representative Date Review By: Examiner Date Approved By: Chief Examiner Date RO ADMIN JPM A*3.doc JOB PERFORMANCE MEASURE VALIDATION NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the ..IPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Technical changes and modifications: Not Applicable RO ADMIN JPM A-3.doc REVISION RECORD (Summary):

1. This JPM is the original revision O. JPM Setup Instructions:

Provide applicant with the following:

JPM handout sheet
Attachment 10 of SP-01.05 , Wastewater Sampling and Analysis
Sample Activity vs. Alarm Pot Setting graph TASK Current plant conditions are as
The plant is at 70% power
2 Circulating water pumps (36P-1A1B) running
2 Service water pumps (46P-1 AlC) running
Liquid rad monitor (17RM-350) reading from EPIC-A-1209 29.8cps
Liquid rad monitor (17RM-350) background from the 09-14 Panel 22.0cps
Liquid rad monitor (17RM-350)

K-factor from the 09-14 Panel 2.10E-7uci/ml/cps INrnATING CUE: The Shift Manager has directed you to independently verify the following data, complete SP-01.05, Wastewater Sampling and Analysis, Attachment 10, and determine HI/HI and HI potentiometer settings. Tank Discharge Flow Rate (maximum) DFR 200gpm Tank Activity (ACT) uCi/ml (from discharge permit) 2.29E-6uci/ml Required Dilution Factor (OF) (from discharge permit) 1.0 Tempering gate/flow 0% Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the Applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The time clock starts when the Applicant acknowledges the initiating cue. RO ADMIN JPM A-3.doc ____ _ Operator's Name: _______________________ _ Job Title: RO JPM Title: Liquid Radwaste Potentiometer Settings JPM Number: RO A-3 Revision Number: 0 KIA Number and Importance: KIA 2.3.11Ability to control radiation releases. IR: 3.8 Suggested Testing Environment: Classroom/Simulator Actual Testing Environment: Testing Method: Table-Top Alternate Path: No Time Critical: No Estimated Time to Complete: 15 minutes Actual Time Used: __minutes

References:

1. SP-01.05 , Wastewater Sampling and Analysis, Rev. 10 2. SP-03.07 , Liquid Process Radiation Monitors, Rev. 6 EVALUA1"ION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

D Yes No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory Unsatisfactory Comments:__________________________ _ Note: Any grade of UNSAT requires a comment. Evaluator's Name: _____________(Print) Evaluator's Signature: Date: RO ADMIN JPM A-3.doc NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time ____ ELEMENT STANDARD SAT UNSAT Comment Number 1. APPLICANT TRANSCRIBES DATA APPLICANT TRANSCRIBES i TO ATTACHMENT 1 #1 THROUGH DATA TO ATTACHMENT 1 #1 9. THROUGH 9. 2. APPLICANT CALCULATES Canal APPLICANT CALCULATES Flow Rate (CFR) ATTACHMENT 1 Canal Flow Rate (CFR) #10. ATTACHMENT 1 #10. 10.276,000

3. APPLICANT CALCULATES Canal APPLICANT CALCULATES Dilution Factor (CDF) Canal Dilution Factor (CDF) ATTACHMENT 1 #11. . 11. 7.25 E-4 4. APPLICANT CALCULATES APPLICANT CALCULATES Fraction of Allowed Dilution (FL) Fraction of Allowed Dilution ATTACHMENT 1 #12. (FL) 12.7.25 E-4 i 5. APPLICANT CALCULATES APPLICANT CALCULATES Background Correction Activity Background Correction Activity I (BCA) ATTACHMENT 1 #13. i 13. 1.638 E-6 6. APPLICANT CALCULATES Hi/Hi setpoint value ATTACHMENT 1 APPLICANT CALCULATES Hi/Hi setpoint value I #14. 14. 1.58 E-3 i 7. APPLICANT CALCULATES Hi . APPLICANT CALCULATES Hi setpoint value ATTACHMENT 1 setpoint value #15. 115. 7.91 E-4 I RO ADMIN JPM A-3.doc ELEMENT 8. (*)Obtain 17RM-350 potentiometer setting for Hi-Hi setpoint from Sample Activity vs. Alarm Pot Setting graph 9. (*) Obtain 17RM-350 potentiometer setting for Hi setpoint from Sample Activity vs. Alarm Pot Setting graph

Task is complete.

JPM Stop Time _____ STANDARD ! SAT I UNSAT Comment Number Applicant determines records potentiometer setting for setpoint from Sample vs. Alarm Pot Setting 16.7.3 turns (7.2-7.4) Applicant determines records potentiometer setting for

setpoint from Sample Activity vs. Alarm Pot Setting graph i 17.7.4 turns (7.3-7.5)

RO ADMIN JPM A-3.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINATION ADMIN RO JPM #A-3 PAGE 1 OF 2 IIAD cm,T'FCJlTfII

1. ll'IIRIber of :r'I1JIftbllJ cd.rculat.\:DiIJ PIII'IPII

.2. Nwobez: ot J:UZlIdllsr eervi<:e _tel: pwtplI

. TGnl!: Flow RII.t:e IlfalIl_ I ltll1Rl 1....-0 0 ,! ftIIlc A\;\;:!.vlty (l.Cfh 2. *'21 c -<t? (.lCI.hIl 1.0 DUlltl.... Ii. u...14 IIiI<Iooute Jlcmitor 11'I'IOf..UOI nedillQ 110111'1" abQUld 1>* ..iutaiMc1 .... _ 1000 .;pII. 7. Liquid * .IIoIU.tor (lTRM-nOI

!,>OIIted 22.Q. 8. ldquid I!4dwute _.l.to.o: (111\K-3501 IC-'actor, '2, ! I b **7 ,. pte tlaw {lSPlC""-lM1) cu.c::ml4'TQl9S 1.0. ean.l 1'1_ Rate (cn:! (\lI*) en. .. HI CifrlO J: l2O,lIOI)) .. (t nM<* _tel" Pl'IIIJIl X P,OOO)! X [1 -,- I cn: .. Hil X l20.ooC} .. (til lC 1I,OOOIl X t1 -lit I CPR

I( j... X l.n.OOOI .. I '2. X UI.oaO)j x (1 -{__

1001 en-+,)l",OOD IJPIII 11. Inlul:l<m PaCl'.a..: CDr .. fl'IIl* Ol..mugre rt_ Rate) I fl'low CDr .. e:f3) I CDr .. f :z CDr" (S(o-i U. I'raceion of I:lUution _. F,IIIII'-:' be ......... 1.0 for F. .. (e-l _or) x t1tI4>:h:ed .Di.l:flt:1<HI

v. .. !flU JI (151 _ 'If." ] '4 f'iS to x _______..2.]:; ')<,(0-1 0% RO ADMIN JPM A-3.doc I' -I... }lC11l11l

14. C.lwl.t.. liVlii vUu. in Hi/Hi **tpoinr. value" [Tanl< Activity I (2 I F.) I + Hi/lU lJetpoint:

"",lue -[.4 I 13 X fUll + IIU) 1fi/Hi .etpoltrt: value. [1. i1..'l "/0-" I (2 II 7.1.s:: "PI] Hi/Iii setpob>t _lue" IS )C \0-J

15. t:al.ClllAt.

1(1 **tpol.ut value in B1 a.tpoint value" 1Tanl< Activity I 14 It tr.)) + Hi setpcint ....lQe s t... I (4 X 113) I + (tll) _'-I lii 1HltP91nt V!tl1l6' I 4*2,111'((("', 14 X ?Z)t!O II + c -'I III Al:l)Qint value " 1

11 X I () I'ctfllll Obtain l'7:R11-nO l!1lm 411...... p!)tenti.....tott Killli. ....tpoint value fr... cur:c..,e

,,{</,\lid Radwut.. -Uter 'S<<mple Actl.vity "r:!\Alm:m :POt Hi/Hi Alum potenti.ometer HItting ],'"3 (t. -'),.1) Obtain 1'7:R11-3S0 Iii alcm potent!oMter wr1ng 111 Atpoint value 8<lt.ivity, fr"'" =an1: Liquid 'I\aCIwa"te l<<onit<>1" 'Smple .l\Ct::f.v}1:y VU. llettinq-a1 J\lam pot...UQ_.... e.t.ting 7, 'f (1,3 -7.$'") Perfonlftd (tV A f f \

.1\2 Print I ljilj'n I !)ate 1$. I!nt:er lii ,ud m/lU <>.lam on >>t.aha:rg<o (Aee.ahment:.

2J. 10 UI H'l'lIICIIBD '1'0 DI8CBAl1f.D: S'SIiIIUlt' I SP-Ol.O!;l . Rev. -1.IL RO ADMIN JPM A-3.doc I'<U AVMtJ'll J1'*iVI HANDOUT TASK Current plant conditions are as

The plant is at 100% power
2 Circulating water pumps (36-1A1B) running
2 Service water pumps (46-1 AlC) running
Liquid Rad Monitor (17RM-350) reading from EPIC-A-1209 29.8cps
Liquid Rad Monitor (17RM-350) background from the 09-14 Panel 22.0cps
Liquid rad monitor (17RM-350)

K-factor from the 09-14 Panel 2.10E-7ucilml/cps INITIATING CUE: The Shift Manager has directed you to independently verify the following data, complete SP-01.05, Wastewater Sampling and Analysis, Attachment 10, and determine HI/HI and HI potentiometer settings. Tank Discharge Flow Rate (maximum) DFR 200gpm Tank Activity (ACT) uCi/ml (from discharge permit) 2.29E-6uci/ml Required Dilution Factor (OF) (from discharge permit) 1.0 Tempering gate/flow 0% RO ADMIN JPM A-3.doc

0 o )::. o Liquid Radwaste Effluent Monitor Sample Activity vs. Alarm Pot Setting s:: 9 Jj J-. I ... -++-_" i.-----r-. -t.. -..+ .... )::. I _, r l---:-t++

II! 1.1 __. .+11-.. rTn I t--lt-*l+/-****-J-**r, __ .... g-"li;;iLcao.**l--r-++- Y=0.2lo(,)+8.u+. . it.

AlarmseftillfJ.

ot sam may. be. activity(x)..t..I I I I T ..____....,_' __ -1.t.. __I ___.:;; ._ , 8 ,-*'1 1 Nature/log SoII/8 for alarm pot seft!!!!l<r.J . _. " -+ .. " ;t-i! . _ .-. 'TCH Hrr*..*=!-** J tiL .._,_ .1>I I-......, _ f... 'r o 1 'pie .. I! I _ _ 1"'1 III High Alarm VUI YQ ! . i--_.__. I.. :J... -"*.+--...."" I'" ._ . J.... f* G 7* I I I 1..._ . I -'-r-.-:::;;,... ... .....' j--.__ .. -,,_.. -'-.-.-. --.... c: r"" '-r""'! 1 :.. ) .. "j_'"=-->. +1.-1-++-- ....--.-. -. p...". .... A .__ '... i..t-j ,--+IU 0-f***-+-+. 1--t-t -....W' : J. '0 f j Q. ------+-I . I T __ -..-f---... ,..... 1_+_ 6 ___-.--- f-........ -r --. --1"'1 c.j E I::':: t ---lHigh-High Alarm _r __ +_ :( i ----*-H 1 I I I --H-. -'--.H _. I I 1jJ IlL f--f _g.. 1-__..___ + ,-1 , t*1'y== 0.2ln(x) + L6r-I I 1..__.._. -j'+++hl 5 TT-f I--!-' -'-I-i i-* 1-"'1-i I +,**1 """----1'--t--!. f-._-... -.--..-._ .... -. ..*.,.-. -f**** --- j _"_ ...f-!--1-. . .._.__ c'.,

__"..'----t 4l-l+t 1+ +-;:

t e----'=-'=:=-rHfll 1.0E-7 1.0E-6 1_0E-5 1.0E-4 1.0E-3 1.0E-2 1.0E-1 Sample Activity (uCilml) (x) NOTE: ------>>INCREASING ACTIVITY ***m ___>> Cal Date 711512009 -_._-._------,

HIGH AlARM POT .. HIGH-HIGH ALARM POT 00 Not Use After I I I 6 I 0 1 7/1512009 Prepared By:

..4 PAGE 1 Of 2 L N\unb"ll' pt running circulat.ing "t.u pumplli '36l"-lA/B/C), 2. Numb'Jl of nmninq service water* P\lJrII)I\I 461'-1I"'B/Cl; J. TanK t'ischnge Flow Rate (Maximum) (OrR): ----qpm 4. Tank Activlty (ACT): ___________ kc:ltgrmmd !lhould be _lnt..inli'd LIISII ftU lCOO CPl!. ___ Cj)S1. L! qu I ct kadwast@ Mor.i t.OI'" 111RM-3 poscoo backgl'"t>und; B. Liquid l'ladwaste Monitor (l'IRM-3S0) i(-Factor; Tel11petin\;l \;late flow (EPrC-A-'}S-411 CALCtrr,Jl.TIQNS r III X :;aO,OOOI

if:! X a,Oool X 11 -Wi / 1(0): ({ ______ J( DO,IlOOI * \ ____________

l( :8,000J1 J( (1 -(______l 1(01) crR 11. Can.l Factor (CDF) ________________ __F. lUll X F, X __________________wJ\s'rE!WA.T£R SAMPLING AND ANALYSIS RO ADMIN JPM A-3.doc LIOUID RADWASTE EFFLUENT HOIU:IDR ALARM POT SETTING DETERVJNATION WORKSHEET PAGE 2 OF 2 C6LCUV.rIONS (Cont) B. Background Correction Activity (OCAl in ./.ICi/rnl B<:A (Current 17R.M-350 readinq -1?R.M-350 background) X K-Factor B<:A (f6 -17) X (*8) ) X _______ OCA

t4. Calculate Hi/Hi setpoint value in HiIHi setpoint value [Tank Activity I (2 X p.)] + Rim! setpolnt value [14 I (2 K .121 J * (2 X ____Hi/Hi setpoint value I J + _______ -"CUml Hi/Hi ""tpoint value 1 S. Calculat-e Hi lietpoint value in Hi setpoint value = ITa.nk Activity (4 x F,J J .Hi secpolnt value (14 l (4 X f121 Hi set:point value = i (4 X n Hi setpoint value Obtain 17RM-3S0 HilHi alarm potentiomet.er sett.ing.

using Ili/Hi setpoint value activity, from current Liquid Radwaste Monitor 'Sample Activity vrs. Alarm Pot Setting" graph. HUHi Alarm potentiometer settin", Obtain 17R.M-350 Hi alarm potentioll\Elter Betting, using Hi setpoint valu<! activity, from current I.iquid Radwaste Monitor 'sample Activity vrs. Alann Pot getting" graph. Hi Alarm pot.ent iClmeter "etc ing Performed by; Independently verify calculations AND alarm potentiometer seetinqs. Independent verification Print I Sign I Enter and HilHi <<l<<rm potentiometer settings on Disch4r\le permit (Attachment

21. SP-Ol.05 WASTEWATER SAMPLING Rev. -l.IL RO ADMIN JPM A-3.doc LIQUID RADWASTE EFFLUENT MONITOR ALARM POT SETTING DETERMINATION (CANDIDATE HANDOUT) DATA COLLECTION

1. Number of running circulating water pumps (36P-1 AlBIC): 2. Number of running service water pumps (46P-1AlB/C):

3. Tank Discharge Flow Rate (Maximum) (DFR): ____gpm 4. Tank Activity (ACT): ____uCi/ml 5. Required Dilution Factor (DF): 6. Current Liquid Radwaste Monitor (17RM-350) reading (EPIC-A-1209):

____cps Note: Background should be maintained LESS THAN 1000 cps. 7. Liquid Radwaste Monitor (17RM-350) posted background: ____cps 8. Liquid Radwaste Monitor (17RM-350) K-Factor: ____uCi/ml/cps

9. Tempering Gate Flow (EPIC-A-3547):

---_% CALCULATIONS

10. Canal Flow Rate (CFR) (gpm) CFR = [(# Circ pumps x 120,000) + (# Service water pumps x 18,000)] x [1 (% tempering CFR = [(#1 x 120,000 + (#2 x 18,000)] x [1 -

CFR::: [( X 120,000) + ( x 18,000)] x [1 -( CFR = 11. Canal Dilution Factor (CDF) CDF = (Tank Discharge Flow Rate) 1 (Canal Flow CDF = (#3) / CDF=( )/( _____CDF= _____________12. Fraction of Allowed Dilution (FL) Note: FL must be LESS THAN 1.0 for discharge. FL =(Canal Dilution Factor) x (Required Dilution Factor) FL = (#11) xFL=( )x( ________FL= ______________RO ADMIN JPM A-3.doc LIQUID RADWASTE EFFLUENT MONITOR ALARM POT SETTING DETERMINATION (CANDIDATE HANDOUT) CALCULATIONS (Cont.) 13. Background Correction Activity (BCA) in uCilml BCA = [(Current 17RM-350 reading) (17RM-350 background)] x (17RM-350 BCA =(#6 -#7) x BCA::: ( ) BCA = uCi/ml 14. Calculate Hi/Hi setpoint value in uCi/ml: Hi/Hi setpoint value =[Tank Activity / (2 x FL) ] + Hi/Hi setpoint value =[#4/ (2 x #12)] + Hi/Hi setpoint value = [ / (2 x -::-:-:--:- ____ ) ] + _______Hi/Hi setpoint value = 15. Calculate Hi setpoint value in uCi/ml: Hi setpoint value = [Tank Activity I (4 x FL)] + Hi setpoint value [#4/ (4 x #12)] + Hi setpoint value = [ I (4 x ) 1+ _______Hi setpoint value = 16. Obtain 17RM-350 Hi/Hi alarm potentiometer setting, using Hi/Hi setpoint value activity, from current liquid Radwaste "Sample Activity vs. Alarm Pot Setting" Hi/Hi Alarm Potentiometer setting ____________17. Obtain 17RM-350 Hi alarm potentiometer setting, using Hi setpoint value activity, from current liquid Radwaste "Sample Activity vs. Alarm Pot Setting" Hi Alarm Potentiometer setting _____________ _ Performed by: 18. Independently verify calculations AND alarm potentiometer settings. Independent Verification: Print / Sign / Date 19. Enter Hi and Hi/Hi alarm potentiometer settings on Discharge permit (Attachment 2). RO ADMIN JPM A-3.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINATION JAMES A. Job Performance Core Thermal Power Calculated JPM Number: SRO Revision Number: 2 Date: 04/08/2010 Developed T. Hedigan 04/08/10 Author Date Validated By: Facility Technical Representative Date Review By: Examiner Date Approved By: Chief Examiner Date SRO ADMIN JPM A-1-1rev2.doc NRC JAMES A. FlrZPA TRICK INITIAL EXAMINA TION JOB PERFORMANCE MEASURE VALIDATION CHECKLIST All steps of this checklist should be performed upon initial validation. Prior to JPM revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this ..IPM matches the most current revision of that procedure: Procedure Rev. Date ______ Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Technical changes and modifications: Not Applicable SRO ADMIN JPM A-1-1rev2.doc 2

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON REVISION RECORD (Summary):

1. This JPM is the original revision O. JPM Setup Instructions:

ITEM: 1.512 6.3.55 12.5.44 2.425 7. 79 13.5.55 3.160 8. 1057 14.423.6/423.6 4.155 9.59 15. 423.6/423.6

5. 3.85 11.870 Turbine first stage pressure is 667.4 psig Provide applicant with the following:

JPM handout sheet
RAP..7.3.03, CORE THERMAL POWER EVALUATION, Rev 13
Calculator
ASME Steam Tables
Attachment 1 partially filled out.
Attachment 2 partially filled out. TASK CONDITIONS:

Current indicated reactor power is 100% on APRM's. Plant data has been recorded for steps 1 through 15 of attachment

1. Turbine first stage pressure is 667.4 psig and has been recorded on attachment

2. INITIATING CUE: Perform section 9.3, Core Thermal Heat Balance Verification, of RAP*7.3.03 , CORE THERMAL POWER EVALUATION.

EPIC computer pOints are not available. Items 14 and 15 were obtained from 02TT-168A1C and BID on attachment

3. Determine what plant action, if any, is required.

SRO ADMIN JPM A-1-1rev2.doc 3 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of 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 time clock starts when the candidate acknowledges the initiating cue. SRO ADMIN JPM A-1-1rev2.doc 4

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA Operator's Name: _______________________

_ Job Title: SRO JPM Title: Core Thermal Power Calculated Manually JPM Number: SRO A-1-1 Revision Number: 1 KIA Number and Importance: KIA 2.1.18 IR: 3.8 Suggested Testing Environment: Classroom/Simulator Actual Testing Environment: Testing Method: Table-Top Alternate Path: No Time Critical: No Estimated Time to Complete: 75 minutes Actual Time Used: __minutes

References:

RAP*7.3.03 , CORE THERMAL POWER EVALUATION, Rev 13 RAP-7.3.16 , PLANT POWER CHANGES, Rev. 46 ST-5D, APRM CALIBRATION, REV. 3 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

0 Yes No 2. Was the task standard The operator's performance was evaluated against the standards contained in this JPM, and has determined to be: Satisfactory Comments:__________________________Note: Any grade of UNSAT requires a Evaluator's Name: _____________Evaluator's Signature: SRO ADMIN JPM A-1-1rev2.doc 5 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON NOTE: Critical Element( s) indicated by

in Performance Checklist PERFORMANCE CHECKLIST:

JPM Start Time _____ ELEMENT STANDARD SAT UNSAT Comment Number (*) Applicant calculates reactor Applicant calculates power using first stage turbine power using first stage pressure. 100.2 Applicant calculates average Correctly calculates feedwater temperature and compensated com pensated feed flow. 16. data on Attachment 1 items 17. through 18. 3.6 3.6 20. 0.99862 21. 0.99862 22. A=S,43 (S.40-S,46)

23. 8=S.S4 (S.S1-S.S7)

Correctly determines enthalpy Applicant uses the ASME steam from steam tables. tables to calculate Items 24 30 on attachment 24.1190.7 (1190-1191,4) 2S. 639.6 Note: Steam tables will not be able 26. 401.S (398-40S) be used to determine the enthalpy compressed water. Items number 26, 27. 401.S

28. S02.0 (498-S06)

29. 403.0 (399-407) i 30. 6S.9 (61.9-69.9)

I SRO ADMIN JPM A-1-1rev2.doc 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA ELEMENT Applicant calculates items 31 through 34 on attachment

1. Applicant calculates items 35 through 36 on attachment

1. Applicant calculates items 37 through 39 on attachment

1. Applicant calculates items 41 on attachment

1. 7. (*)Applicant calculates items 42 through 43 on attachment

1. 8. (*) Applicant compares the two methods and determines that they are within 5%. No further action required per attachment

2. STANDARD SAT UNSAT Comment Number Correctly calculates Q to feedwater.

31.10.97 (10.91-11.03)

32. 401.5 (398-405) 33.1190.7 (1190-1191.4) 34.2537.9 (2532.9-2542.9)

Correctly calculates Q to CRD flow. 35..037 (.036-.038)

36. 12.2 (11.9-12.5)

Correctly calculates Q to Cleanup system. 37..157 (.155-.159) 38.98.98 (96.98-100.98) I 39.4.55 (4.35-4.75) Correctly calculates QPUMP 41.6.88 (6.68-7.08) Correctly determines core thermal power. 42.2548.8 (2447-2650)

43. 100.5 (96.5-'104.5)

Applicant compares the two methods and determines that they are within 5%. No further action required per attachment

2. SRO ADMIN JPM A-1-1rev2.doc 7

NRC JAMES A. FITZPATRICK INITIAL ELEMENT (*) Applicant states that current reactor power is above license limit and would lower power to ensure below 100% License Limit, 2536 Mwth. Note: Even if heat balance is below 100% the turbine power is above 100% and should be addressed. Task is complete. JPM Stop Time _____ STANDARD SAT UNSAT* Comment Number RAP-7.3.16 step 7.1.1 requires power to be lowered if the 12 minute average exceeds the Licensed Power Level. Applicant may also state that would adjust APRM's per 5d APRM Calibration. SRO ADMIN JPM A-1-1rev2.doc 8 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON HEAT BALANCE CALCULATION SHEET Page 1 of 1 PERFORMED BV: ____________ _ DATErnME: ________ PURPOSE: 2. Cleanup Outlet 9-4 1 2TSS*142POS 4 Y2 ,"" OF 3. Cleanup Flow A 9-4 /c.o GPM 4. Cleanup Row B 9*4 1.1<: GPM 5. Power to Recirc. PUmP 9-4 RWR MG A GEN PWR MW 6. Power to Reclrc. Pum!) 9-4 RWR MG B GeN PWR J.s:fi MW 11. Gross MW Electric 9-7 MAIN GEN MW ff10 GMWE '12. Feodwater Flow loOP A IH OOFI-89A f"cf"l MLBIHR *'3. Feedweter Row loaD B 9*5 OOfl-8SB MlB/HR 14. TFWA UM PTIO 407/410 or 9*21 </:1-3.6. 15J;li{JF

15. TFWB uMPTl0406f41tor 9-21

't'..2.3.(./'fZJ.,oF F/!EDWA TER FLOW CALCWA'16. AvurageTFWA(407+410)120r(168A+168C)/2 I.;;n.(;, '17. Aver8Qt TFWB (408'+411112 or (168B+ 1680112 1.1.2.3.6. *18. Delta T Loop A IOTA} -lFWA -420 j. c.. *'9. Delta T LooD a'IOTS) -TFWB -420 J. (" '20. C.F. '" 1.0", {DTA*[-3.8064E-4 + (DTA*-4.4310E*7Jl) DTB*[-3.B064E-4'" (DTB**4.4310E-7IU (J f.--.-;*2=.!2::..--"Com== A 1#12' 120) [<"lliC '23. ComP808 B' . /113

121)

ITEM DATA USED VAL 24. Ie, I L.,o.1J.L,*u -/I'll. BT in "25.' tlFG -. '8 .... "... bill I. "LC. .J..1.:l'il "26. HFWA 18 #16 ble' vol - BTUILB '27.. HFWB 18,117 ASMETable (/OI.C('3'H/-!f<J:) BTU/LS 28. la, '1, ASME Table r", BTUIt.B HCR 18 110,ASME Table (tc t.I.9-'!f)BTUILB PARAMETER EQUATION (ITEM rsJ VALUE UNITt; 31. Total Feedflow (122 +1231 10 ________ -::-;'" J!ll:#23)](#31.tA11. S:U.%'-4<ld ______ LJ1034. /131*(133-'3211/3.413

36. [(#9* 0.498E-31

'" (#Sa* O.49SE-Sll

()3)( ,03&'

MLBiHR 38. a to *

37. Total CV flow 113 + 141 *(0.49812-3) . /£) { .lll-,/5"9. MlBIHR 38. HCUI HCUO 1#28 -1291 f9J.BTUILB 39*. Oto CleanunSvs 1#38' #37J13.413

'I. S-:,,(<,(,Jr*Y.7.r)MWt

Not Applicable when Attachment 6 is used. Contact Operations to determine if this is performed to satisfy Tech. Specs: DVES DNO
If Ves, Second Verifier:

___________ Date{Time: __________ Date{Time: _________Reviewed By: ___Reactor Engineering $upwft:ltendent -This a Quality Record RAP-7.3.03 CORE THERMAL POWER EVALUATION ATTACHMENT Rev. No. -ll.. GY. ktI/\ y Page 11 of 16 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TfON VERIFICATION OF CORE THERMAL HEAT BALANCE Page 1 of 1 DATE/TIME: First stage pressure from EPIC 1299: Co '") psig [(0.1362

1Bt stg pr) + 9.3]
l 0 D. d-.. % power Reactor power calculated from heat balance .. 100.)' % power (96.5""-/0 (fS) The two methods are within 5% of rated power of each other. DYES o NO If Not within 5%, investigation initiated.

DYES o NO If GRBATER THAH 5%, and unexplained, General Manager Plant Operations notified. DYES o NO Sign Date Per.formed By: Reviewed By: EN m. ..... RAP-7.3.03 CORE*THERMAL POWER EVALUATION ATTACHMENT 2 No . ...1L 12 of 16 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA HANDOUT PAGE TASK CONDITIONS: Current indicated reactor power is 100% on APRM's. Plant data has been recorded for steps 1 through 15 of attachment

1. Turbine first stage pressure is 667.4 psig and has been recorded on attachment

2. INITIATING CUE: Perform section 9.3, Core Thermal Heat Balance Verification, of RAP-7.3.03 , CORE THERMAL POWER EVALUATION.

EPIC computer points are not available. Items 14 and 15 were obtained from 02TT-168A1C and BID on attachment

3. Determine what plant action, if any, is required.

SRO ADMIN JPM A-1-1rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON VERIFICATION OF CORE THERMAL HEAT BALANCE Page 1 of 1 _________1_______DATE/TIME: First stage pressure from EPIC 1299: t (p 7, 'i psig [(0.1362

1-stg prJ + 9.3]
_________% power Reactor power calculated from heat balance
_____% power The two methods are within 5% of rated power of each other. DYES o NO If within 5%, investigation initiated.

DYES o NO If GllBATBR THA.W 5%, and une>;;plained, General Manager Plant Operations notified. DYES o NO .Print Si;n Date Performed By: RAP-T.3.03 CORE THERMAL POWER EV,ALUl\TION ATTACHMENT 2 Rev. No. 13 .. Page 12 of 16 NRC JAMES A. FITZPATRICK INITIAL EXAMINA HEAT BALANCE CALCULATION SHEET page 1 of 1 PERFORMED BY: ____________ _ DATEfTlME: _______ PURPOSE' ITEM PARAMETER PANEL INSTRUMENT VALUE IJNITS 1. Cleanup Inlet 94-12TS5-142 POS 1 !r 1:J Of 2. CleenupOutlet 94-12TSS-142POS 4 °F 3. CleanuP flow I>. 94-Ibe GPM 4. Cleanup Flow B 9-4 irS' GPM 6. Ptlwer to RecirQ. Pomp A 94-RWR MG A GEN PWR 1. SS"" MW 8. Power to Roclrc. Pump B .J SS" MW RgENPWR 7. Total Core 9-6 02-3 -95 _'7 "i Mlb/hr 8. Reactor Pnm;ure (pskl + 14.11 9*5 06 105'"'1 PSIA 9. CRD Flow to Reactor 9*6 031'/-310 5"1 GPM 9a RWfI & RWCU Pump Seal FlOwe Constant 15 GPM 10. CRD Systtll'n Temp 95 °F 11. GrOA MIN Electric GMWE*12. Feedwater Flow laopA .,.

1,/<1. MLBlHR "13. Feedw8ter fluw Loop B 9-6 S ..('SO MLB/HR 14. TFW=4011410or 9*21 TFW6 4081411 or 9-21 02TT . I./:H. , I , FEEDWATER FLOW CAL *16. Average TFWAJ407+4101l2 ur {168A+ 16SCll2 *'7. AverllQe TFW6 (408+411112 or 1168B+ 168D)l2 "18. Delta T Loop A IOTA)
TFWA
420 "19. Delta T Loop BIOTB) a TFWB* 420 "20. C.F. '" 1.0 + {DTA*(-3.8084E-4

+ "21-C.F... t.O + {DTS*(-3.8064E-4

22. Compensated Flow A '#12 * *23. Compensated Flow B' 1#13
1211 ITEM DArA USED VALUE UNITS 24. la, ASMETable

....'25.. HFG ' 118,'

8 #16, ii= *27. 118, BTu/LB #8.11 .Table.29. 18,112, Table-= 30. #8, #10. Table EQUA TION (ITEM trIlL VALUE UNITS 31. Total Fesdflow 1#22 + MLBIHR 32. Feedwatcr Enthalpy [(#26"11221 T BTU/LB 38. Stltam Enthalpv 1124 aTU/LB 34. o to, feedwater (OFW) 1131*(133 MWt 36. CRD flow 1119

0.498E-31

+ lISa

0.498&3))

38. o to 1135 "'#33 -#3QlJf3.413

37. Tota' CU flow 113 + 141 *(0.49BE*31 E= 38.

1128* BTU/LS 39. o to Cleanup Sva IN38

137113.413 4(1. VessEll ambient IQlIS 1.1 41. OPUMP 1115 + #6)
MWt 42. Core Thermal Power 11134+ #36 + #39 + #40* #41\ 43 CTPf2536 (#42/2638)*

J.OO

Not Applicable when Attachment 5 is used. Contact Operations to determine jf this is performed to satisfy Tech. Specs: DYES ONO
If Yes, Seoond Verifier:

____________ DatefTime:. __________ Datemme: __-'-_______Reviewed By: ___Reactor engineering Supenr,ltendent -This l! a Quality Record RAi?-7.3.03 CORE THERMAL POWER EVALUATION ATTACHMENT 1, Rev. No . ...lL Page 11 of 16 I NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON Heat Balance Calculation Sheet (SRO Candidate Worksheet) liTEM PARAMETER

1. Cleanup Inlet Temp. 2. Cleanup Outlet Temp. 3. CleanuQ Flow A 4. Cleanup Flow B 5. Power to Recirc. PumQ A 6. Power to Recirc. Pump B 7. Total Core Flow 8. Reactor Pressure (psig + 14.7) 9. CRO Flow to Reactor 9a. RWR & RWCU Pump Seal Flows 10. CRO System Temp 11. Gross MW

12. Feedwater Flow loop *13. Feedwater Flow loop 14. TFWA, use PTIO 407/410 or 15. TFWB, use PTIO 408/411 or FEEDWATER FLOW CALCULATIONS
16. Average TFWA 407+410) 12 or (168A+168C) 12 *17. Average TFWB 408+411) 12 or (168B+1680) 12 *18. Delta T loop A OTA) -TFWA-420 *19. Delta T loop B OTB) =TFWB -420 I *20. C.F. =1.0 + {OTA x [-3.8064E-4

+ (OTA x -4.4310E-7)]} I *21 C F .. = 1 0 + {DTB x [-3 8064E-4 + (DTB x -4.431 OE-7)]} PANEL 09-4 09-4 09-4 09-4 09-4 09-4 09-5 09-5 09-5 09-7 09-5 09-5 09-21 09-21 INSTRUMENT 12TSS-142, POS 1 12TSS-142, POS 4 12FI-126A 12FI-126B RWR MG A GEN PWR RWR MG B GEN PWR 02-30PRlFR-95 06PR/FR-98 03FI-310 Constant Constant MAINGENMW 06FI-89A 06FI-89B 02TT -168A/C 02TT-168B/0 *22. Compensated Flow A *23. Compensated Flow B PARAMETER

24. HS 25. HFG *26. HFWA *27. HFWB 28. HCUI 29. HCUO

31. Total Feedflow 32. Feedwater Enthalpy 33. Steam Enthalpy 34. Q to FeedwaterjQFW)

35. CRO f1owjWCR)

36. Q to CRO FlowjQCRJ

37. Total CU f1owJWCU)

38. HCUI-HCUO 39. Q to Cleanup Sys 40. Vessel Ambient loss 41. QPUMP 42. Core Thermal Power 43. CTP 12536 J#12 x #20) (#13 x #21) ITEM DATA USED #8 ASMETable

8 ASME Table #8,#16 ASME Table #8,#17 ASME Table #8,#1 ASME Table #8,#2 ASME Table #8,#10 ASME Table EQUATION (ITEM #'S) (#22 + #23) {(#26 x #22) + (#27 x #23)} 1#31 1#24 -(0.000 x #25J) J#31 xJ#33 -#32J} /3,413 J(#9 x 0,498E-3)

+ (#9a x 0.498E-3)}

35 xJ#33 -#30)} /3.413 #3 + #4) x (0.498E-3)
28 -#29) #38 x #37) /3.413 J#5 + #6) x 0.93 (#34 + #36 + #39 + #40 -#41) (#42/2536) x 100 VALUE 512 425 160 155 3.85 5.44 5.55 423.6 I 423.6 423.61 423.6 VALUE VALUE 1.1 UNITS OF i OF GPM I GPM I MW MW i Mlb/hr PSIA GPM GPM OF GMWE Mlb/hr Mlb/hr OF I OF Mlb/hr Mlb/hr UNITS BTUllb BTUllb I BTU/lb BTU/lb I BTUllb BTU/lb BTUllb UNITS Mlb/hr BTU/lb BTUllb MWt Mlb/hr MWt Mlb/hr BTU/lb MWt I MWt MWt MWt %

Not applicable when Attachment 5 is used. SRO ADMIN JPM A-1-1rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-1-1rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION CONTAINS SENSITIVE INFORMATION

-NOT FOR PUBLIC Developed By: Validated By: Review By: Approved By: JAMES A. Job Performance Determine Required Event JPM Number: SRO Revision Number: Date: 03/05/2010 P. Author Facility Technical Representative Examiner Chief Examiner L 03/05/10 Date ! Date Date Date SRO ADMIN JPM A-1-2rev1.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON CONTAINS SENSITIVE INFORMATION -NOT FOR PUBLIC JOB PERFORMANCE MEASURE VALIDATION NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date _______ Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Technical changes and modifications: Not Applicable SRO ADMIN JPM A-1-2rev1.doc 2

r----NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Ls!!!!!..AINS SENSITIVE INFORMA TION -NOT FOR PUBLIC DISCLOSURE REVISION RECORD (Summary):

1. This JPM is the original revision 1. JPM Setup Instructions:

Provide applicant with the following:

JPM handout sheet
Access to all plant procedures TASK CONDITIONS:

The plant is operating normally at full power with no evolutions in progress when the following events occur. AtT=O An electrician reports a large fire at Normal Station Service Transformer T*4. There are several wooden pallets laying against the transformer engulfed in flames. A large gas can is on the ground beside the pallets. At T= 2 min Alarm 09*8*5*16, NSS XSFMR T*4 SUDDEN PRESS is received as the control room is dispatching the fire brigade, The reactor scrams automatically. All rods fully insert.

EDG Band D have started and are carrying their buses. At T =8 min Breakers 10212 and 10412 CANNOT be closed to restore power to Buses 10200 and 10400, respectively. An operator reports from the East Electric Bay that it appears someone has wedged steel rods into the front of the breaker housings, jamming the trip mechanisms for Breakers 10212 and 10412. Maintenance must be performed before these breakers can be closed. At T = 13 min The fire brigade leader reports the fire is out, Transformer T-4 appears intact, NO oil is leaking from the transformer. The 10100, 10300 and 10500 buses are now powered from Reserve Station Transformer T*3. SRO ADMIN JPM A-1-2rev1.doc 3

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON CONTAINS SENSITIVE INFORMA TION -NOT FOR PUBLIC DISCLOSURE INIl"IATING CUE: You are an extra SRO on shift. The Shift Manager directs you to determine:

1) the operations procedures that must be entered to mitigate the event conditions (examples:OP, AOP, EOP) 2) regarding off-site notification(s), what organization(s) or individual(s) must be notified and the required time limit(s) if applicable

3) The procedures which identify regulatory basis for any required notification(s) determined in Item #2 above Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this ,,'PM. 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 time clock starts when the candidate acknowledges the initiating cue. SRO ADMIN JPM A-1-2rev1.doc 4 NRC JAMES A. FITZPATRICK INITIAL EXAMINA CONTAINS SENSITIVE INFORMATION -NOT FOR PUBLIC Operator's Name: _______________________ _ Job Title: SRO JPM Title: Determine Required Event Followup JPM Number: SRO A-1-2 Revision Number: 0 KIA Number and Importance: KIA 2.1.20 IR: 4.6 Suggested Testing Environment: Classroom/Simulator Actual Testing Environment: Testing Method: Table-Top Alternate Path: No Time Critical: No Estimated Time to Complete: 15 minutes Actual Time Used: __minutes

References:

Information Reporting Requirements, Rev 13 EOP-2, RPV Control, Rev 9 Reactor Scram, Rev 43 Operation During Plant Fires, Rev 18 Security Threat, Rev. 11 AOP-17, Loss of 10400 Bus, Rev 17 IAP-2, Classification of Emergency Conditions, Rev 28 EAP-1.1, Offsite Notifications, Rev 65 Emergency Plan Implementation Checklist. Rev 39 Notifications and Response to Operational Concerns Rev 10 EAP*3; Fire Rev 25 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes ONo 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory Unsatisfactory Comments:__________________________ _ SRO ADMIN JPM A-1-2rev1.doc 5 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON CONTAINS SENSITIVE INFORMATION -NOT FOR PUBLIC Note: Any grade of UNSAT requires a comment. Evaluator's Name: ____________ {Print) Evaluator's Signature: ____________ _ Date: ____ NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE SRO ADMIN JPM A-1-2rev1.doc 6 NRC JAMES A. FITZPATRICK INITIAL EXAMINA CONTAINS SENSITIVE INFORMATION -NOT FOR PUBLIC JPM Start Time _____ STANDARD SAT UNSAT.I Comment

Number i (*) The applicant determines the Applicant identifies each of the operations procedures that must be following procedures:

entered to mitigate the event

EOP-2 (low RPV level, conditions.

normal for a scram) AOP-1 (for the scram) AOP-17 (for the 10400 Bus loss) AOP-28(for the fire) AOP-70 (for the security event I tampering) Note: Applicant may also identify other procedures that provide administrative guidance. Their identification is not critical to the JPM. However, any additional identified procedures must be appropriate to the plant conditions. Examples include: -Emergency Plan (IAP-2, EAP-1.1, EAP-3) -OP system procedures for electrical bus re-alignment Applicant identifies NRC (*) Applicant determines NRC prompt notification required notification requirement per AP-within 1 hour by ENS phone 03.04. per AP-03.04 Attachment 2, Examiner NOTE: SAE is due to an Item 138, based on intrusion into a vital area of the East 50.72(a)(3) after declaration of Electric bay. an Emergency Class (SAE under IAP-2, Category 8.1.9.) 3. (*) Applicant determines E-Plan Applicant identifies E-Plan ERO callout required. I ERO callout required. ..... NRC JAMES A. FITZPA TRICK INITIAL EXAMINA CONTAINS SENSITIVE INFORMATION -NOT FOR PUBLIC ELEMENT (*) Applicant determines off-site agency notification requirements under E-Plan. 5. Applicant determines corporate notification per AP12.11 Task is complete. STANDARD Applicant identifies personnel I agencies that must be contacted

1) under EAP-1.1 Offsite Notifications: New York State Oswego County

Nine Mile Point Unit #1 Nine Mile Point Unit #2 NRC Operations Center NRC Resident Inspector Security Call-outs
within 15 minutes of making EAL declaration. under IAP-1, Emergency Plan Implementation Checklist Item B: NRC via ENS phone within 15 minutes of recognition of security-based emergency.

1) under AP 12-11 Notify for EP Entry Unplanned Power change Reportable event (covered above in step 2) Fire actuation Plant fire Security Threat SAT UNSAT Comment Number i JPM Stop Time _____ SRO ADMIN JPM A-1-2rev1.doc 8

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON CONTAINS SENSITIVE INFORMATION -NOT FOR PUBLIC DISCLOSURE HANDOUT PAGE TASK CONDITIONS: The plant is operating normally at full power with no evolutions in progress when the following events occur. At T= 0 An electrician reports a large fire at Normal Station Service Transformer T-4. There are several wooden pallets laying against the transformer engulfed in flames. A large gas can is on the ground beside the pallets. At T= 2 min Alarm 09-8-5-16, NSS XSFMR T-4 SUDDEN PRESS is received as the control room is dispatching the fire brigade, The reactor scrams automatically. All rods fully insert.

EDG Band D have started and are carrying their buses. At T = 8 min Breakers 10212 and 10412 CANNOT be closed to restore power to Buses 10200 and 10400, respectively. An operator reports from the East Electric Bay that it appears someone has wedged steel rods into the front of the breaker housings, jamming the trip mechanisms for Breakers 10212 and 10412. Maintenance must be performed before these breakers can be closed. At T = 13 min The fire brigade leader reports the fire is out, Transformer T-4 appears intact, NO oil is leaking from the transformer. The 10100, 10300 and 10500 buses are now powered from Reserve Station Transformer T -3. INITIATING CUE: You are an extra SRO on shift. The Shift Manager directs you to determine:

1) the operations procedures that must be entered to mitigate the event conditions (examples:OP, AOP, EOP) 2) regarding off-site notification(s), what organization(s) or individual(s) must be notified and the required time limit(s) if applicable

3) the procedural or regulatory basis for any required notification(s) determined in Item #2 above NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION JAMES A.

Job Performance Use Station Drawing to Predict Impact of Component Failure and Evaluate Technical Specification Implications JPM Number: SRO A-2 Revision Number: 0 Date: 03/10/2010 Developed By: .:;,.P,:;..' P:...r::.,;:e;.;:;s.=,b ...._________y 03/10/10 Author Date Validated Facility Technical Representative Review Examiner Approved Chief Examiner SRO ADMIN JPM A-2.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION 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 8 through 11 below. Technical changes and modifications:

1. Not Applicable SRO ADMIN JPM A-2.doc 2 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON REVISION RECORD (Summary): This JPM is the original revision O. JPM Setup Instructions: Stage the following references for the applicant's use: HPCI System Elementary Diagrams Sheets 1 thru 9 (File Numbers 1.61-140 thru 1.61-148, also referenced as Vendor Dwgs 791 E471 Sh1 thru 9) Fitzpatrick Station Technical Specifications Entergy Nuclear Management Manual EN-OP Series Procedures Plant Piping Drawings (to include the HPCI system drawings)

TASK STANDARD: Determine broken lead causes Relay 23-K51 to initiate 1 of 2 required signals to automatically open HPCI Torus Suction Isolation Valves 23MOV-57 and 23MOV-58. Determine HPCI Torus Suction Isolation Valves 23-57 and 23-58 will not automatically re-position on the failure. Determine system remains functional as valves will reposition upon valid CST low level signal (low level initiation is one out of two, taken twice, with one signal effectively actuated). Determine HPCI remains OPERABLE, based on TS 3.3.5.1 Action D completion time and bases discussion. (TS Table 3.3.5.1-1, Item 3.d.) Identify required Tech Spec actions as follows: Per 3.3.5.1 Action D, place affected. low level channels in trip OR align HPCI pump suction to the suppression pool within 24 hours SRO ADMIN JPM A-2.doc 3 NRC JAMES A. FITZPATRICK INITIAL TASK You are the CRS The plant is operating in a normal alignment at stable 75% power conditions. Electricians have reported a broken (disconnected) power supply lead to HPCI Relay K51 at Terminal Point NO other damage is INITIATING CUE: You are directed to:

determine how this failure impacts HPCI components
determine if the HPCI system is functional
determine if the HPCI system is operable
identify required Tech Spec actions, if any Information for Evaluator's UNSA T requires written comments on respective
Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this 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 time clock starts when the candidate acknowledges the initiating cue. SRO ADMIN JPM A-2.doc 4

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Operator's Name: _______________________

_ Job Title: SRO JPM Title: Use Station Drawing to Predict Impact of Component Failure and Evaluate Technical Specification Implications JPM Number: SRO A-2 Revision Number: 0 KIA Number and Importance: KIA 2.2.41, Ability to obtain and interpret station electrical and mechanical drawings. (3.5, 3.9) Suggested Testing Environment: Classroom/Simulator Actual Testing Environment: Testing Method: Table-Top Alternate Path: No Time Critical: No Estimated Time to Complete: 27 minutes Actual Time Used: __minutes

References:

HPCI System Elementary Diagrams Sheets 1 thru 8 (File Numbers 1.61-140 thru 148, also referenced as Vendor Dwgs 791E47'! Sh1 thru 9) Fitzpatrick Station Technical Specifications Entergy Nuclear Management Manual EN-OP-104Rev.4, Operability Determinations

HPCI Plant Piping Drawings; FM-25A, Rev.71 and FM-25B, Rev.33 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes DNo 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory Unsatisfactory Comments:__________________________ _ Note: Any grade of UNSAT requires a Evaluator's Name: _____________Evaluator's Signature: SRO ADMIN JPM A-2.doc 5 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT ! STANDARD SAT: UNSAT Comment Number Applicants review the handout Applicants review sheet and ask any questions conditions and initiating regarding the initial conditions Examiner Cue: initiating cues. Hand the applicant HPCI Elementary Drawings (9 I drawings, see references) and . the cue handout sheet. Review HPCI System Elementary Applicant determines Drawings. Determine how this normally energized, is failure impacts HPCI components. energized by the resulting in one of the two required signals to auto open HPCI suppression pool suction valves 23MOV-57 and 23MOV-58. Applicant identifies valves do not auto open on the failure but would open if low CST level sensed on other CST via channels (LS 23-74A or LS 23-75A) Examiner Note: Sht 3 (H-9) Sht 1 (A-2/3, K-6)* Sht 8 (H-S, H-6) *3. Determine system Applicant determines remains functional as will reposition upon valid low level signal from the CST {low level initiation is out of two, taken twice, one signal actuated}. A low level in 'A' will still perform the suction swap function. ; can still be operated manually. I SRO ADMIN JPM A-2.doc 6 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON ELEMENT STANDARD SAT UNSAT Comment Number *4. Determine system operability. Applicant determines HPCI remains operable. Examiner Note: TS 3.3.5.1 Action D directs system INOPERABILITY declaration. However, the completion time is "from discovery of loss of HPCI initiation which indicates the inoperability call is required for failures that result in loss of ability to auto swap. The TS bases explain "For Required Action D.1, the Completion Time only begins upon discovery that the HPCI System cannot be automatically aligned to the suppression pool due to two inoperable, untripped channels in the same Function." *5. Determine required Tech Spec Applicant identifies required actions. Tech Spec actions as follows:

TS 3.3.5.1 Action D.2.1, place affected low level channels in trip OR TS 3.3.5.1 Action D.2.2, align HPCI pump suction to the suppression pool within 24 hours Examiner Note: See note in preceding JPM step. Critical that applicant identifies 3.3.5.1 Actions D.2.1 or D.2.2 and no other actions. SRO ADMIN JPM A-2.doc 7 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION HANDOUT PAGE TASK CONDITIONS:

You are the CRS The plant is operating in a normal alignment at stable 75% power conditions. Electricians have reported a broken (disconnected) power supply lead to HPCI Relay K51 at Terminal Point NO other damage is INITIATING CUE: You are directed to:

determine how this failure impacts HPCI components
determine if the HPCI system is functional
determine if the HPCI system is operable
identify required Tech Spec actions, if any NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION Job Performance Measure Determine Radiation Controls JPM Number: SRO A-3 Revision Number: 2 Date: 03/30/2010 Developed By: Bernard Litkett 04108/2010 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Examiner Date SRO ADMIN JPM A-3rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM JOB PERFORMANCE MEASURE VALIDATION NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate ..!PM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Review Questions and Comments: SRO ADMIN JPM A-3rev2.doc 2 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM REVISION RECORD (Summary): New JPM. JPM Setup Ensure the following documents are available in the exam EN-RP-201, Rev.3, Dosimetry Administration EN-RP-202, Rev.7, Personnel Monitoring EAP-15, Rev. 11 Emergency Radiation Exposure Criteria and control. Copies of attachment 4; Emergency Exposure authorization form. Instructions for explaining how to administer; Provide page 1 of handout sheet to applicant. If/when applicant returns handout with explanation that needs to authorize an emergency radiation exposure then, provide page 2 of handout sheet to applicant. TASK Determine which 2 workers must have Emergency exposure controls put in place due to anticipated during response to emergency SRO ADMIN JPM A-3rev2.doc 3 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM TASK The plant is at 15% power. A Site Area Emergency has been declared due to a steam line rupture with significant fuel damage. Entry is required into the MSIV Room to close the outboard MSIVs to prevent event escalation. Job conditions are as follows: Two individuals are required to complete the job. Each worker is expected to receive 500 mR in transit to the Main Steam line access door AND the same amount again while exiting the plant. Each worker is expected to spend 2 minutes in an 800 mRlhr field in transit from the Main Steam line access door to the job site AND the same amount again while exiting the plant. The job site is against the outer Containment Wall in a 2 Rlhr field. . The job will take 1.5 hours at the job site with both workers working the full time. Five workers are preparing to be briefed to complete the task. Technician Sex Age Marital Dept Volunteer TLD Pregnant Status 1. John Tech M 45 123-45-6789 Married Maint No 145678 NfA 2. Henry Work M 33 987-65-4321 Single Ops Yes 235699 NfA 3. Jane Riley F 35 345-54-2456 Married Ops Yes 875231 No 4. Bill Smith M 40 587-14-8741 Single Maint Yes 632587 NfA 5. Mike Long M 47 512-57-2358 Married Ops Yes 421489 NfA 6. None of the individuals has ever received an emergency exposure.

7. During an initial entry under a modified RWP the workers received the following dose: Technician 1 received 600 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1399 mR for the year. Technician 2 received 600 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1399 mR for the year. Technician 3 did not enter the area, has 1000 mR total exposure for the year. Technician 4 received 900 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1678 mR for the year. Technician 5 received 900 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1678 mR for the year. 8. The TSC has not been staffed yet. INITIATING CUE: Anticipate dose to be accumulated by each worker. Select two (2) workers to complete the task. Authorize work using the appropriate exposure limits to allow completion of the required task. SRO ADMIN JPM A-3rev2.doc 4

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 Information For Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of 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 time clock starts when the candidate acknowledges the initiating cue. SRO ADMIN JPM A-3rev2.doc 5 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM Operator's Name: ________________________ __ Job Title: 0 NLO RO [8J SRO CSTA SRO Cert JPM Title: Perform ED Functio ns JPM Number: SRO A-3 Rev ision Number: 0 KIA Number and Importance: KIA Generic 2.3.4 (3.7) Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Simulate Alternate Path: No Time Critical: No Estimated Time to Complete: 30 minutes Actual Time Used: ___,minutes

References:

1. EN-RP-201 J Rev.3, Dosimetry Administration

2. EN-RP-202, Rev.7, Personnel Monitoring

3. EAP-15, Rev. 11, Emergency Radiation Exposure Criteria and control EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

[J Yes 0 No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory 0 Unsatisfactory Comments: Note: Any grade of UNSAT requires a Evaluator's Name: ______________Evaluator's Signature: Date: ____SRO ADMIN JPM A-3rev2.doc 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 This JPM is used to test generic knowledge in calculation of overall dose and control mechanisms to the selection of individuals to continue or perform work in high dose areas. This JPM tests mathematics and understanding of stay times and the authorization of emergency radiation This is a new JPM. SRO ADMIN JPM A-3rev2.doc 7 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT STANDARD SAT UNSAT Comment Number EXAMINER EXAMINER NOTE: Examiner to provide page 1 Examiner to provide page 1 of handout sheet to handout sheet to Determine dose to be received for each *2. For each worker, the applicant: Determine anticipated Dose

Time = dose from task Rate performance in the work 2000 mRlhr
1.5 hr = 3000 Determine anticipated Dose + Dose = dose from transit to and To From from the Main Steam Location chase 500mR + 500 mR = 1000 Determine anticipated Dose
Time = dose from transit to the Rate work area in the steam 800 mRlhr * (2 min/60) = Determine anticipated Dose
Time = dose from transit from Rate the work area in the 800 mRlhr * (2 min/60) = 26 I steam chase. Determine the total dose Task + Travel + Transit =for each worker from Dose Dose Dose @a through 3000 + 1000 + (26*2) =4052 mR *3. Determine that task
The applicant determines that performance is not allowable dose is greater than the per normal controls.

4500 mR administrative limit radiation exposure per EN-RP-201 and the 5000 mR federal limit I SRO ADMIN JPM A-3rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON *4. Determines that emergency exposure controls are required per EAP-15. EXAMINER NOTE: Examiner should only provide EAP-15 and handout sheet page 2 if the applicant determines emergency radiation exposure authorization is required. SRO ADMIN JPM A-3 STANDARD SAT UNSAT Comment Number *The applicant evaluates the total expected dose and recognizes that emergency exposure controls are required to raise the limit above 5 R for each individual per EAP-15 EXAMINER NOTE: Examiner should only provide EAP-15 and handout sheet page 2 if the applicant determines emergency radiation exposure authorization is required. SRO ADMIN JPM A-3rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION SRO ADMIN JPM A-3 ELEMENT STANDARD SAT UNSAT Comment Number *4.a Implements EAP-15; step The applicant Implements 15;step 4.2.1 .. Selects a TEDE of up to 10 Rem from dose Selects personnel for Task The applicant using per Step 4.3 identified workers verifies -Personnel selected -are not declared -Volunteers should be more 45 years of age, if -have not received a emergency have not received a planned special exposure Recognizes no initial condition specifies one of these abnormal conditions

5. Applicant does not complete Applicant does NOT complete Attachment 4 for Technician 1 . Attachment 4 for Technician 1 to to authorize the emergency authorize the emergency exposure.

exposure. John Tech did not volunteer

6. Applicant does not complete Applicant does NOT Attachment 4 for Technician 2 Attachment 4 for Technician 2 to authorize the emergency authorize the emergency exposure.

Henry Work is the youngest of Examiner five technicians. Although this individual is the Examiner Note: youngest he also has the Although this individual is the lowest dose. lAW EAP-15 this youngest he also has the lowest is acceptable to select him. dose. lAW EAP-15 this is acceptable to select him.

7. Applicant does not complete Applicant does NOT complete Attachment 4 for Technician 3 Attachment 4 for Technician 3 to to authorize the emergency authorize the emergency exposure.

I exposure. Jane Riley is the second youngest of i the five technicians. SRO ADMIN JPM A-3rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ELEMENT *8. Completes Attachment 4 for Technician 4 to authorize the emergency exposure based on he has volunteered for the emergency exposure and his age. Although he is only 40 years, procedure EAP-15 step 4.3.4 states, volunteers should be more than 45 years of age, if possible.

9. Completes Attachment 4 for Technician 5 to authorize the emergency exposure based on his age and that he has volunteered for the emergency exposure. (Examiner Cue: "You may stop here, you have met the termination criteria for this "IPM") JPM Stop Time _____
Completes Attachment 4 Section A for Technician 4, Bill Smith per the attached mark-up of attachment

4. Note: The Employer I JAF Dept block is NOT a Critical component of this Step.

Completes Attachment 4 Section A for Technician 5, Mike Long per the attached mark-up of attachment

4. Note: The Employer I JAF Dept block is NOT a Critical component of this Step. N/A SRO ADMIN JPM A-3 SAT UNSAT Comment Number i i I SRO ADMIN JPM A-3rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON . l SRO ADMIN JPM A IJswel I{e'l ...... ...."".,....

.... page 1 of 2 EMERGENCY ,EXPOSURE 'AUTHORIZATION FORM SBCTION A Name of Individual to Receive Exposure: B iil Snit h SSN: S1 14 14 i . TLD Eadge No.; Employer/JAF Department: \1 -Mai;,.d-ew Nee I Date of 1'9Mis Authorized Exposure Limit: to I f I j Director:___ Jt..;....t t:;..**__-_--,-____--'" ...... (Signature) Date'; look{s DGk SECTION B I have volunteered to perform the task(s) during which I will receive the emergency exposure and I have been briefed on the potential biological consequences of the proposed emergency exposure, Indi vidual J to Recy:n i Exposure; 'Z.i.&l. (Signature) Date: Inaividual conducting Briefing: (Signature) Date: EMERGENCY RADIATION EAP-15 ATTACHMENT 4 EXPOSURE CRITERIA Rev. No. .J:.l... page of AND CONTROL NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 /' .. *AAFSw£jC-Key .A.-rAC8MENT 4 Page 1 of 2 r . EXPOStJREAUTHORIZATION SECTION A Name of Individual 'to Receive Exposure: diKe l-oN5 SSN: $ 12* 5"J-;l,lSr* TLD Badge No: i/2 (V l q Employer/JAF Department: IN 0ftl'd/lON 5 Date of Pt.uthorizat:.iol'l1 1vriay\ ( IJ, /( Authorized Exposure Limit: /0 Ui1 Emergency

. Direotor:

yo" ( {rs 116iv(:e ' (Signature) Date': -fetiPy's 1Ja.+e SECTION B I have volunteered to perform the task(s) during which I will the emergenoy exposure and I have been briefed on the potential biological oonsequenoes of the proposed emergency exposure. Individual Conduoting Briefing: (Signature) Date: EMERGENCY RADIATION EAP-15 ATTACHMENT 4 EXPOSURE CRITERIA Rev. No. Page of AND CONTROL NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 HANDOUT PAGE 2 TASK CONDITIONS:

1. Five workers are preparing to be briefed to complete the task: Technician Sex Age SSN Marital Dept Volunteer TLD Pregnant Status 1. John Tech M 45 123-45-6789 Married Maint No 145678 N/A 2. Henry Work M 33 987-65-4321 Single Ops Yes 235699 N/A 3. Jane Riley F 35 345-54-2456 Married Ops Yes 875231 No 4. Bill Smith M 40 587-14-8741 Single Maint Yes 632587 N/A 5. Mike Long M 47 512-57-2358 Married Ops Yes 421489 N/A 2. None of the individuals has ever received an emergency exposure.

SRO ADMIN JPM A-3rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA SRO ADMIN JPM HANDOUT PAGE 1 TASK CONDITIONS: The plant is at 15% power. A Site Area Emergency has been declared due to a steam line rupture with significant fuel damage. Entry is required into the MSIV Room to close the outboard MSIVs to prevent event escalation. Job conditions are as follows: Two individuals are required to complete the job. Each worker is expected to receive 500 mR in transit to the Main Steam line access door AND the same amount again while exiting the plant. Each worker is expected to spend 2 minutes in an 800 mRlhr field in transit from the Main Steam line access door to the job site AND the same amount again while exiting the plant. The job site is against the outer Containment Wall in a 2 Rlhr field. The job will take 1.5 hours at the job site with both workers working the full time. Five workers are preparing to be briefed to complete the task. During an initial entry under a modified RWP the workers received the following dose: Technician 1 received 600 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1399 mR for the year. Technician 2 received 600 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1399 mR for the year. Technician 3 did not enter the area, has 1000 mR total exposure for the year. Technician 4 received 900 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1678 mR for the year. Technician 5 received 900 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1678 mR for the year. The TSC has not been staffed yet. INITIATING CUE: Anticipate dose to be accumulated by each worker. Select two (2) workers to complete the task. Authorize work using the appropriate exposure limits to allow completion of the required task. SRO ADMIN JPM A-3rev2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON 512010 JAMES A. Job Performance Determine Protective Action Recommendations and Complete Event Notification Form JPM Number: SRO A-4 Revision Number: 1 Date: 04/1212010 Developed .::.,.P.:.,.;. ________ 04/12/10 Author Date Validated By: Facility Technical Representative Date Review By: Examiner Date Approved By: Chief Examiner Date SRO ADMIN JPM A-4rev1.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JOB PERFORMANCE MEASURE VALIDATION CHECKLIST All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Technical changes and modifications: Not Applicable SRO ADMIN JPM A-4rev1.doc 2 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA REVISION RECORD (Summary):

1. This JPM is the original revision 1. JPM Setup Instructions:

1. Hand out the following materials:

Calculator
Blank EAP-1.1 Attachment 1 Notification Form
Legible EAL Flowchart
Legible EAP-4 Attachment 1 Flowchart

2. Handout copies of following procedures:

EAP-4.1, Release Rate Determination, Rev 19
EAP-42, Obtaining Meteorological Data, Rev 23
IAP-2, Classification of Emergency Conditions, Rev 28
IAP-1, Emergency Plan Implementation Checklist, Rev 39
EAP-1.1, Offsite Notifications, Rev 65 3. Have copies available of following procedure:
EAP-4, Dose Assessment Calculations, Rev 39 TASK STANDARD:

1. Complete the upgrade offsite notification message form, including correct PARs. SRO ADMIN JPM A-4rev1.doc 3

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON TASK CONDITIONS: At 0342 today (May 12, 2010), an earthquake with a magnitude of 0.08g caused a loss of offsite power. Plant conditions: At 0342, a large break LOCA occurred. The reactor automatically scrammed. Multiple failures in safety systems caused the operators to conduct an emergency depressurization. RPV level dropped to minus (-) 9". Drywell pressure peaked at 55 psig. Secondary containment radiation levels increased to >EOP-5 Maximum Normal values in the Reactor Building 344 foot elevation. At 0352, a Site Area Emergency was declared with a release in progress based on an unisolable MSL break outside primary containment. At 0401, the initial offsite notification message was transmitted. ERO is staffing the emergency response facilities. Neither the TSC nor the EOF has been fully activated (the earthquake caused damage to local roads). At 0412, (when you start the '"'PM) the following plant conditions exist: Drywell pressure has dropped rapidly to 3 psig. RPV level = minus (-) 9", going up slowly. You are the Emergency Director until relieved and have just declared an EAL upgrade to General Emergency at Time 0412. EAL upgrade based on radioactivity release as indicated on effluent radiation monitors, exceeding EAL threshold for >15 minutes. NO other General Emergency EAL thresholds have been reached. Stack flow rate = 12,000 cfm, with 1 SGT train and 1 stack dilution fan operating. (continued on next page) SRO ADMIN JPM A-4rev1.doc 4 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON

EPIC uRad Release" screen shows the following relating to the offsite release: HIGH RANGE CONTINUOUS OFFSITE REL RATES I i LOCATION RATES X CF CIISEC I STACK 11,700 MRlHR CF 2.9718E+04 CIISEC TURB BLDG EXH OMRlHR CF O.OOOOE+OO CI/SEC RADW BLDG EXH OMRlHR CF O.OOOOE+OO CIISEC i
Meteorological conditions are provided in the following EDAMS report: Emergency Meteorology Report Last 15 Minute Emergency Meteorology Report Data Data from Nine Mile Point Met System Date: 51l 211 0 Time (Local): 4:00:00 Elevated Ground 200' Wind Dir From 271 (deg) 30' Wind Dir From (Main) 261 (deg) 200' Wind Speed 6.1 (mph) 30' Wind Speed (Main) 3.8 (mph) 200' Delta Temperature

-1.49 (deg F) 100' Delta Temperature -.56 (deg F) Stability Class C Stability Class D 30' Air Temperature 45.6 (deg F) Precipitation (15 min) 0.00 (in) SRO ADMIN JPM A-4rev1.doc 5 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON INITIATING CUE: Complete the required E-plan upgrade notification form for the current conditions. THIS IS A TIME*CRITICAL JPM. Information for Evaluator's UNSAT requires written comments on respective

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of 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 time clock starts when the candidate acknowledges the initiating cue. SRO ADMIN JPM A-4rev1.doc 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA Operator's Job Title: JPM Title: Determine Protective Action Recommendations and Complete Event Notification Form JPM Number: SRO A-4 Revision Number: 1 KiA Number and Importance: KIA 2.4.38, Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. (4.4) Suggested Testing Environment: Classroom/Simulator Actual Testing Environment: Testing Method: Table-Top Alternate Path: No Time Critical: Yes Estimated Time to Complete: 12 minutes Actual Time Used: __minutes

References:

IAP-2, Classification of Emergency Conditions, Rev 28
EAP-1.1, Offsite Notifications, Rev 65
IAP-1, Emergency Plan Implementation Checklist, Rev 39
EAP-4.1, Release Rate Determination, Rev 19
EAP-4, Dose Assessment Calculations, Rev 39
EAP-42, Obtaining Meteorological Data, Rev 23 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes DNo 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory 0 Unsatisfactory Comments:__________________________ _ Note: Any grade of UNSAT requires a comment. SRO ADMIN JPM A-4rev1.doc 7 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Evaluator's Name: _____________Evaluator's Signature: Date: ___SRO ADMIN JPM A-4rev1.doc 8 NRC JAMES A. FfTZPA TRICK INITIAL EXAMINA TION NOTE: Critical Element(s) indicated by'* in Performance Checklist. PERFORMANCE JPM Start Time _____ ELEMENT Applicants review the handout sheet and ask any questions regarding the initial conditions or initiating cues. Handout the references with handout sheet and the cue Examiner Cue: Remind applicant the task is time critical. Obtains Notification Form (Attachment 1 of EAP-1.1, Offsite Notifications) Record the correct Record the correct date and Determine release rate using EAP-4 and EAP-4.1 (Step 4.1.2 or Attachment 2 from mrlhr " 2.54 factor) Record the radioactive information based on Attachment STANDARD SAT UNSAT Comment Number Applicants review initial conditions and initiating cues. Start the JPM. Record START Time: Applicant completes Notification Form Item #2, circling "B. Actual Event". Applicant completes Notification Form Item #3, circling "d. General Applicant completes Notification Form Item #4, recording today's date (5/12/2010) and event declaration time (0412) Applicant determines release rate is 29,718 Ci/sec. Applicant completes Notification Form Item #5, circling "C. Release ABOVE federal limits Technical Sl2ecification" . SRO ADMIN JPM A-4rev1.doc 9 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ELEMENT Determine and record the protective active recommendations using EAP-4 Attachment 1, Tables 4.1.1 and 4.1.2. Record appropriate EAL number and brief description. Record reactor status. Record appropriate wind speed Record meteorological stability class as determined using provided data per EAP-42. Turn in notification form within required time. STANDARD Applicant completes Notification Form Item #6, circling "B. EVACUATE and IMPLEMENT the KI PLAN for the following ERPAs and All remaining ERPAs MONITOR the EMERGENCY ALERT SYSTEM" and by circling ERPAs # 1,2,3,4,7,9,26,27. Examiner Note: These are 2 mile radius and 5 mile downwind ERPAs. Applicant Notification Form Item recording EAL # 5.1.4 I brief description "high elevated rad release rate from main vent stack". Applicant completes Notification Form Item #8,

circling "B. Shutdown" and date time of 5/12/10 at 0342. Records wind speed by filling
in Notification Form Item #9 as I "A. 6.1 Miles/Hour at elevation 200 Feet (Elevated)".

Determines Stability Class "C", based on wind direction

variation and 30 to 200 foot delta T. Records stability class by circling "C Neutral" in Notification Form Item #11. Applicant turns in notification form within 15 minutes of start of JPM. Record Stop Time: SAT UNSAT Comment Number i I I I SRO ADMIN JPM A-4rev1.doc 10 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON 512010 JPM ANSWER KEY INEQRMllTION Page 1 of 1 i lil't.iIAIE RAUlOUJGICAL EMERGE:-;C\'DATA i ..'<_**

PMl.I I Nouf.clltlilli 1/ M

_ r1h1!o Is III MjlQn "I> ,nMlIrllllllhlt JlIrMS A.

Plllnl SliIntily lor <;()Ili\,mlTdlO'l

(CMdiJd roll cIlIIll) <IC.'U!Ie Ill;;, ! SWlOOS:) m New YOtk 81M. Wllltl\lng Point 1JS[!00wt!90 Counl)' Wllitftln!I Point HIM Uile Point UnIt.1 m tfI"e Milt 1"oinl Unil f2 I mou: (mi.2E... OTHER) ED Approval:

Applicant Signature Ge.tERAL INFORMATION checked indicates cli.

in statuI, NOT for CIt '*' n I e1 lDarll) __.__.M.**.. tM.ITiIIWI

__* 24 HourCillClk "la:" FU!CS a. 0tM0rI . A< An """,,nl Emer Dr B< An E\cmsc: ___1 __________________. 3 n.., Emer1l"'n(lY l$: A UN\ISUAL EVEJ'I,'T C SITE AIte" EMERGENCX ...;A;.;;L=E:;;.IlT-_ I D. GENERAL EMf.ROENCV 4< CllluifimliQI'\ tl..dllTe!l ',1\: 05/1212010 Rel",,14' "I .4.< B< lI.elcal'C BELOW T Vi LYflJ.L..1l.ELW,t,.j WOR/flfo" $H()UW COIV.'illleR SHELTER-IN* nAt£; + {,tIKI; Kilt tvAOJUl(1!"f C. SHf:tTtR-IN*PLACE liIld KI PlAN for ttl<: fo!lo....il1!! ERPA$:md AII..-1l1iImln, E.RPAs .'10NITOR the EMHRGRSt\' ALERT S,"STEM -1 6 7 8 22 n 15 26 n 28 29 elevated radioactivity release from main vent stack ru.,. l!.i(,rm><I"," CJ NiIw York Stahl W.miI>W Polnl 0fIWI00 eo....., W ... "I,. "J_I/.$ A. *"uf'all1Ci< MId... P"""", PI.1nt otIl JPM ANSWER KEY EAP-l.l ATTACHMB1.fT 1 OFFSITE NOTIFICATIONS Rev. No. Page -1l-of SRO ADMIN JPM A-4rev1.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINA HANDOUT PAGE TASK CONDITIONS: At 0342 today (May 12,2010), an earthquake with a magnitude of 0.08g caused a loss of offsite power. Plant conditions: At 0342, a large break LOCA occurred. The reactor automatically scrammed. Multiple failures in safety systems caused the operators to conduct an emergency depressurization. RPV level dropped to minus (-) 9". Drywell pressure peaked at 55 psig. Secondary containment radiation levels increased to >EOP-5 Maximum Normal values in the Reactor Building 344 foot elevation. At 0352, a Site Area Emergency was declared with a release in progress based on an unisolable MSL break outside primary containment. At 0401, the initial offsite notification message was transmitted. ERO is staffing the emergency response facilities. Neither the TSC nor the EOF has been fully activated (the earthquake caused damage to local roads). At 0412, (when you start the JPM) the following plant conditions exist: Drywell pressure has dropped rapidly to 3 psig. RPV level = minus (-) 9", going up slowly. You are the Emergency Director until relieved and have just declared an EAL upgrade to General Emergency at Time 0412. EAL upgrade based on radioactivity release as indicated on effluent radiation monitors, exceeding EAL threshold for >15 minutes. NO other General Emergency EAL thresholds have been reached. Stack flow rate = 12,000 cfm, with 1 SGT train and 1 stack dilution fan operating. (continued on next page) i NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON

EPIC uRad Release" screen shows the following relating to the offsite release: HIGH RANGE CONTINUOUS OFF SITE REL RATES . LOCATION RATES X CF = CI/SEC STACK 11,700 MRlHR CF 2.9718E+04 CIISEC TURB BLDG EXH OMRlHR CF O.OOOOE+OO CIISEC RADW BLDG EXH OMRlHR CF O.OOOOE+OO CI/SEC
Meteorological conditions are provided in the following EDAMS report: Emergency Meteorology Report Last 15 Minute Emergency Meteorology Report Data Data from Nine Mile Point Met System Date: 5112110 Time (Local): 4:00:00 Elevated Ground 200' Wind DirFrom 271 (deg) 30' Wind Dir From (Main) 261 (deg) 200' Wind Speed 6.l (mph) 30' Wind Speed (Main) 3.8 (mph) 200' Delta Temperature

-1.49 (deg F) 100' Delta Temperature -.56 (deg F) Stability Class C Stability Class 30' Air Temperature 45.6 (deg F) Precipitation (15 min) 0.00 NRC JAMES A. FITZPATRICK INITIAL EXAMINATION INITIATING CUE: Complete the required E-plan upgrade notification form for the current conditions. THIS IS A TIME-CRITICAL JPM. James A. Fitzpatrick Generating Job Performance Initiate RCIC in Pressure Control with Speed Control Failure JPM Number: 8-1 Revision Number: 1 Date: 1/13/10 Developed __tt_________ 4/08/10 Author Date Validated By: Facility Date Review By: Date Approved By: Chief Date SIM JPM S-1rev1.doc JOB PERFORMANCE MEASURE VALIDATION CHECKLIST All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this ..IPM matches the most current revision of that procedure: Procedure Rev. Date Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. 2 SIM JPM S-1rev1.doc REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

1. Initialize the simulator to IC-38. 2. Establish the following simulator conditions:

A Plant in a post scram condition with RPV level betwElen 177" and 222.5" B. RPV pressure between 700 psig and 1000 psig and rising slowly C. Main Steam Isolation Valves closed. 3. Insert malfunction RC07 selected high speed failure 4. HPCI is not available. TOOLS AND EQUIPMENT None TASK STANDARD: Successfully initiate RCIC in the Pressure Control Mode re-establish control after a speed control failure. TASK CONDITIONS:

1. Plant is in a post-scram condition with RPV level between 177" and 222.5". 2. RPV pressure is between 700 psig and 1000 psig and rising slowly. 3. Main Steam Isolation valves are closed. 4. HPCI is not available.

INITIATING CUE: You are the RO, The CRS directs you to start the RCIC System for RPV pressure control. Maximize heat removal with RCIC to minimize SRVoperations. Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The timeclock starts when the applicant acknowledges the initiating cue. SIM JPM S-1rev1.doc 3 Operator's Name: ____ Job Title: 0 NLO I RO I SRO 0 STA 0 SRO Cert JPM Title: Initiate RCIC in the Pressure Control Mode re-establish control after a speed control failure. JPM Number: 5-1 Revision Number: 0 KIA Number and Importance: KA 217000; A4.07; 3.9; 3.8 Suggested Testing Environment: Simulator Actual Testing Environment: Testing Method: Perform in Simulator Alternate Path: Yes Time Critical: No Estimated Time to Complete: 20 min. Actual Time Used: ---minutes

References:

NUREG 1123, 217000; A4.07; 3.9; 3.8 OP-19; 0.2 Reactor Core Isolation Cooling System, Current Revision or posted attachment panel EN-OP-115, Conduct of Operations, Paragraph 5.3 Manual Control of Automatic Systems EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes 0 No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory Unsatisfactory Comments:__________________________ _ Note: Any grade of UNSAT requires a Evaluator's Name: ______________Evaluator's Date: _____ SIM JPM S-1rev1.doc 4

== Description:==

This JPM has the applicant initiate RCIC in the Pressure Control Mode using OP-19 or posted instructions at panel 09-4. Maximize heat removal with RCIC to minimize SRV operations. SIM JPM S-1rev1.doc 5 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-1 NOTE: Critical Etement(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT STANDARD SAT UNSAT I Comment i Number 1. Obtain a controlled copy of posted The applicant locates and attachment, RetC MANUAL START UP obtains from a controlled copy FOR RPV PRESSURE CONTROL; OP-of OP-19; 0.2. 19,0.2 or posted instructions at panel Applicant should verify that 09-4. CST level is greater than 79.5 inches. Caution: Operating RCIC in pressure control mode with suction from the CST and CST level below 79.5 inches could cause vortexing.

2. (step 0.2.1) Verify HPCI auto-Applicant verifies that there is initiation condition is clear no HPCI automatic initiating condition present of high drywell pressure or low RPV water level. EVALUATOR NOTE..,;, HPCI is not available

3. (Step 0.2.2) Verify Annunciator 09-4-Applicant verifies Annunciator 0-32 RCIC LOGIC RX LVL HI is clear. 09-4-0-32 RCIC LOGIC RX LVL HI is clear. I 4. (Step 0.2.3) Align RCIC to CSTs as Applicant verifies:

follows. a. CST Suct VLV a. Ensure open CST SUCT VL V 18 red -open 13MOV-18 indicating light is on. b. Ensure closed the following valves: b. INBO TORUS SUCT

INBO TORUS SUCT 13MOV-41 13MOV-41 -closed
OUTBD TORUS SUCT i c. OUTBO TORUS SUCT 13MOV-39 -closed 39 I I SIMULATOR BOOTH OPERATOR EVALUATOR NOTE: Insert malfunction RC07; RCIC speed This malfunction will cause control failure high. RCIC speed control to fail to high speed stop if operating in ! automatic.

SIM JPM S-1rev1.doc 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA

5.(Step 0.2.4)Open HPCI and RCIC TEST VL V TO CST 23MOV-24.
6. (Step 0.2.5) Start VAC PMP 13P-3.
7.(Step 0.2.6) Open OIL CLR WTR SUPP 13MOV-132.
8. (Step D.2.7) Open TEST VLV TO CST 13MOV-30.
9. (Step 0.2.8) Opens TURB STM SUPP VLV 13MOV-131.

CAUTION: Operating RCIC at less than 2200 rpm could cause improper oil system operation and insufficient exhaust flow resulting in check valve banging or steam flow reversals.

10. (Step 0.2.9) Verify RCIC Flow rate is approximately 400 gpm. I i STANDARD SAT UNSAT JPM 8-1 Comment Number : Applicant at Panel 09-3, opens . 23MOV-24 by placing its control switch to the OPEN position.

i I Applicant at Panel 09-4, starts . pump 13P-3 by placing its

control switch to the START position.

Applicant at Panel 09-4 opens 13MOV-132 by placing its control switch to the OPEN position. I i i Applicant at Panel 09-4 opens 13MOV-30, by placing its control switch to the OPEN position. Applicant at Panel 09-4, opens 13MOV-131, by placing its control switch to the OPEN position. Applicant adjusts RCIC flow rate is approximately 400 gpm on 13FI-91, I 81M JPM 8-1 rev1. doc 7 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA JPM ELEMENT I STANDARD SAT I UNSAT Comment Number EVALUATOR Applicant should inform the eRS of the failure of automatic Applicant should recognize Rele speed speed control of the Rele as failed high. turbine; follow guidance of EN* OP-115 to place the Rele turbine speed controller in manual. Examiner Note: The applicant may trip Rele manually when speed fails high in order to protect the Rele turbine. Examiner Note: If applicant trips RCIC they need to call out to the field to have an NPO to reset the RCIC trip throttle valve. The booth operator will reset. Examiner Note: Role Playas CRS to direct the RO candidate to take manual control and establish pressure control with Rele. For SRO candidates ask them what they recommend for i situation. 1< 11. Applicant places Rele flow Applicant places Rete flow controller in manual to control speed . controller in manual to control speed 12. (Step D.2.10) Ensure closed Applicant observes that the following green -closed indicating light for:MIN FLOW VLV 13MOV-27. STM LINE DRN TO RADW

13MOV-27 is i
13AOV-34 is STM LINE DRN TO RADW 13AOV-35
13AOV-35 is I SIM JPM S-1rev1.doc 8

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ELEMENT NOTE As RPV pressure lowers, indicated level on 02-3U-283A may rise and result in an undesired trip at the red line high level trip value. Posted attachment 3 will give an equivalent trip level for 941A1B/C indicators on panel 09-5. CAUTION Operating RCIC at less than 2200 rpm could cause improper oil system operation and insufficient exhaust flow resulting in check valve banging or steam flow reversals.

15.(Step D.2.11) WHILE controlling RPV pressure, maintain RCIC speed GREATER THAN 2200 rpm by throttling closed TEST VL V TO CST 13MOV-30.
16. (Step D.2.12) Throttle TEST VLV TO CST 13MOV-30, to obtain the desired RPV pressure control. 17. (Step D.2. 13) Startup RHR Torus cooling per Section D of OP-13B, as soon as practicable.

18. (Step D.2.14) Monitor Torus water temperature and level. JPM S-1 STANDARD I SAT UNSAT Comment Number NOTE As RPV pressure indicated level on may rise and result in undesired trip at the red high level trip value. attachment 3 will give equivalent trip level for 94/AIB/C indicators on CAUTION Operating RCIC at less than 2200 rpm could cause improper oil system operation and insufficient exhaust flow resulting in check valve banging or steam flow reversals.

At 09-4 Panel, monitors turbine speed on 13SPI-1 throttles closed 13MOV-30 ensure RCIC only runs 2200 rpm during I operation. At Panel 09-4, throttles 13MOV-30 to begin the depressurization by SRV operation. EVALUATOR: Inform the applicant that another operator has been tasked with initiating . Torus cooling. Observes EPIC or 09-3 Panel indicators to monitor Torus , water temperature and level. I SIM JPM S-1rev1.doc 9 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM 8-1 ELEMENT STANDARD SAT UNSAT Comment Number 19. (Step 0.2.15) WHEN time permits, Applicant verifies the following verify the following RCIC parameters: RCIC parameters:

Oil pump discharge pressure:
Oil pump discharge to 15 pressure:

12 to Oil temperature from cooler: GREATER THAN 60 o F.

Oil temperature cooler: Oil temperature from the turbine THAN 60 o F. bearings:

LESS THAN 160 0 F Oil temperature from the turbine bearings: LESS THAN 160 0 F EVALUATOR: Terminate the task at this point. JPM Stop Time _____ 81M JPM 8-1rev1.doc 10 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-1 HANDOUT PAGE TASK CONDITIONS:

1. Plant is in a post-scram condition with RPV level between 177" and 222.5". 2. RPV pressure is between 700 psig and 1000 psig and rising slowly. 3. Main Steam Isolation valves are closed. 4. HPCI is not available.

INITIATING CUE: You are the RO, 'The CRS directs you to start the RCIC System for RPV pressure control. Maximize heat removal with RCIC to minimize SRV operations. 81M JPM S-1rev1.doc James A. Fitzpatrick Generating Job Performance HPCI Full Flow Test JPM Number: 8-2 Revision Number: 1 Date: 02/04/2010 Developed B. Litkett 04/08/10 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Examiner Date 81M JPM 8-2rev1.doc JOB PERFORMANCE MEASURE VALIDATION I NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this ..IPM matches the most current revision of that procedure: Procedure Rev. Date _______ Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. SIM JPM S-2rev1.doc 2

REVISION RECORD (Summary):

1. Rev JPM Setup Reset simulator to IC-41. Place RHR in torus cooling mode lAW OP-13B, Section D. Start GLAND SEAL CNDSR BLOWER 23P-140. Throttle open TEST VALVE TO CST 23MOV-21 for 5 seconds. Simulator operator override RED light ON, GREEN light OFF for TEST VALVE TO CST 24. ZL023AS9-1, GREEN and ZL023AS9-2, RED. Simulator operator override TEST VALVE TO CST 23MOV-24 handswitch to ZD123AS9. (Setup Steps #5 and #6 above simulate sheared valve stem. 23MOV-24 closed, but indicates Simulator operator override MIN FLOW VALVE 23MOV-25 handswitch to ZD123AS8. (simulates switch problem which maintains min flow valve Override MIN FLOW VALVE 23MOV-25 lights a. HPZL023SA8(1) minFlow bypass valve 23MOV-25 (green) -on b. HPZL023SA8(2) minflow bypass valve 23MOV-25 (red) -off 9. Markup copy of ST-4N, HPCI QUICK-START, INSERVICE, AND TRANSIENT MONITORING TEST (1ST), completed through Section 8.3. and Venting Torus per OP-37, Section E .. Initiate EPIC four-parameter plot TRHPCI. Place 23VM-1 00 toggle switch to up position TOOLS AND EQUIPMENT Marked-up copy of ST-4N, HPCI QUICK-START, INSERVICE, AND MONITORING TEST (1ST), completed through Section 8.3 and thru Step

Stopwatches TASK STANDARD:

Start HPCI for testing in accordance with procedure. Identify the pump has inadequate (no) flow and trip HPCI before the pump is damaged. TASK CONDITIONS: The plant is operating at-power. Field personnel are briefed and stationed to support performance of ST-4N. One loop of RHR is in Torus Cooling Mode. Another operator is monitoring and controlling Torus level and temperature. Torus venting is in progress per OP-37 section E. INITIATING CUE: You are directed to continue performance of ST-4N, HPCI QUICK-START, INSERVICE, TRANSIENT MONITORING TEST (1ST) at Step S/M JPM S-2rev1.doc 3 ..IPM Title: HPCI Full Flow Test JPM Number: S-2 Revision Number: 0 KIA Number and Importance: 206000 A2.06 -High Pressure Coolant Injection System. The ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow (3.3, 3.5) Suggested Testing Environment: Simulator Actual Testing Environment: Testing Method: Perform in Simulator Alternate Path: Yes Time Critical: No Estimated Time to Complete: 15 min Actual Time Used: ___minutes

References:

I\lUREG 1123, Knowledge and Abilities Catalog for Nuclear Power Plant Operators -Boiling Water Reactors ST-4N, HPCI QUICK-START, INSERVICE, AND TRANSIENT MONITORING TEST (1ST) 3. OP-37; Venting the Torus per section E. EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

DYes D No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: D Satisfactory D Unsatisfactory Comments:___________________________ _ Note: Any grade of UNSAT requires a cornment. Evaluator's Name: _____________(Print) Evaluator's Date: SIM JPM S-2rev1.doc 4

== Description:==

This JPM has the applicant start the HPCI pump for a full flow test from the Torus back to the CST through Test MOVs 24 and 21. Upon start, the flow will remain at 0 gpm due to MOV-24 sheared stem and a failure of the Min Flow MOV-25 to open. The applicant is expected to recognize the unacceptable operational conditions and trip the HPCI pump turbine before the pump is damaged. SIM JPM S-2rev1.doc 5 NRC JAMES A. FITZPA TRICK JPM S-2 NOTE: Critical Element( s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT 1. Obtain procedure

2. (Step 8.4.7) IF RPV pressure is GREATER THAN OR EQUAL TO 165 pSig, THEN open and time OUTBO STM SUPP VLV 23MOV-16.

Opening time secs (1ST: 4.9 to 8.2) 3. (Step 8.4.8) Ensure open OUTBO STM SUPP VLV 23MOV-16. 4(Step 8.4.9) Verify the following: EPIC-0-457 HPCI STM OUTB ISO-C indicates OPEN EPIC-0-458 HPCI STM OUTB ISO-O indicates NFC STANDARD Applicant reviews completed sections of ST and begins implementation at Section 8.4 Applicant opens 23MOV-16 and records open stroke time within limits of 4.9 to 8.2 seconds. Applicant verifies OUTBO STM SUPP VLV 23MOV-16 is open. Applicant calls up EPIC points and verifies 0-457 OPEN and 0-458 NFC i SAT UNSAT Comment Number i Loss of inventory to torus will cause hotweillevel to trend down. 5. (Step 8.4.10) Automatic or manual No response compensation may be required maintain hotwell SIM JPM S-2rev1.doc 6 NRC JAMES A. FITZPA TRICK EXAMINA ELEMENT 6. (Step 8.4.11) Perform the following in any order, just before turbine startup: Initiate EPIC manual transient data capture per CDSO-3.600. IF RPV pressure is GREATER THAN OR EQUAL TO 165 psig. THEN direct I&C to start all installed transient recorder(s) at desired speed (normally 25 mm/sec). (Step 8.4.12) IF test is being performed to satisfy SR 3.5.1.9, THEN RPV pressure must be >150 psig but .::.165 pSig and HPCI steam supply pressure must be psig. 8. * (Step 8.4.13) Simultaneously perform the following: Open TURB STM SUPP VL V 23MOV-14. Start AUX OIL PMP 23P-150. IF RPV pressure is GREATER THAN OR EQUAL TO 165 psig, THEN Start stopwatches. (Step 8.4.14) IF RPV pressure is GREATER THAN OR EQUAL TO 970 psig, THEN record null voltage for approximately 1 to 2 minutes during turbine startup (cold condition). JPM S-2 STANDARD SAT UNSAT Comment Number Evaluator Cue: I&C started all installed recorders at the Evaluator Cue: Another operator has data No response required. Applicant opens 23MOV-14 and Evaluator Cue: 1.Operators are stationed stop

2. Evaluator records time HPCI was started.
HPCI start time Evaluator Cue: I&C are recording voltage. SIM JPM S-2rev1.doc 7

NRC JAMES A. FITZPA TRICK ELEMENT 10. *(Step8.4.15Verify the

Turbine speed stabilized after startup transient and remained LESS THAN 4200 rpm during the startup transient (23SPI-161 or EPIC TRHPCI speed trace)
23HOV-1 opens smoothly by local observation.
Turbine vibration is LESS THAN OR EQUAL TO limits (0.385 IPS)
Turbine accelerates smoothly (by observing TURB SPEED 161 OR EPIC TRHPCI speed trace).
HPCI pump discharge flow rate stabilizes at GREATER THAN OR EQUAL TO 3400 gpm on 108-1
MIN FLOW VLV 23MOV-25 is closed.
STM LINE DRN TO RADW 23AOV-43 is closed.
STM 1I NE DRN TO RADW 23AOV-42 is closed. 11. Acknowledge alarms. 12. (ARP Step 1) Verify open FLOW VL V

13. (ARP Step 2) Verify turbine speed and pump

14. (ARP Step 3) IF HPCI initiation signal is present. THEN ensure open:

INJ VLV 23MOV-19
PMP DISCH VL V 23MOV-20 15. * (ARP Step 4) Consider securing HPCI if flow can not be restored.

SIM JPM S-2rev1.doc STANDARD Applicant notes HPCI pump discharge flow rate does NOT stabilize at E:3400 gpm AND Min Flow Valve 23MOV-25 is closed. CUE: If applicant informs CRS that pump is running without adequate flow, then acknowledge the report. EXAMINER NOTE: Applicant may trip the HPCI pump at this time. If so, terminate the JPM. Applicant acknowledges alarms and refers to 09-3-3-15 HPCI PMP FLOW LO Applicant determines MOV-25 is not open. Applicant determines speed is normal and pump discharge pressure is high. No response required. HPCI initiate signal not present. Applicant trips HPCI pump. JPM S-2 SAT UNSAT Comment Number 8 NRC JAMES A. FITZPA TRICK NOTE ELEMENT STANDARD SAT TO EXAMINER: JPM 8-2 UNSAT Comment Number 1. IF applicant stops HPCI pump, THEN TERMINATE THE JPM. IF applicant does NOT stop HPCI pump, THEN ALLOW JPM TO CONTINUE to provide opportunity for applicant to stop HPCI pump before it becomes damaged from inadequate flow. JPM should be terminated after several minutes of pump operation without flow. NOTE TO EXAMINER: The following steps may be performed if applicant does not immediately recognize need to trip HPCI pump. (Step 8.4.16) IF RPV pressure is GREATER THAN OR EQUAL TO 165 psig, THEN perform the following in any order or concurrently: WHEN all parameters have stabilized on EPIC plot TRHPCI, AND AT LEAST two minutes have elapsed, direct I&C to stop all installed transient recorder(s). Record the following:

23HOV-1 response time
23HOV-1 opening time (1ST: 15.4 to 25.6 sees)
23MOV-14 opening time (1ST: 6.4 to 10.5 sees) EVALUATOR CUE: I&C has stopped recorders.

Times are as follows: 23HOV-1 response time =19.3 sec 23HOV-1 opening time =17.4 sec 23MOV-14 opening time =8.1 sec NOTE TRHPCI printout is required within 15 minutes of turbine startup to ensure starting transient is included on plot. NOTE Test may be continued before the next step is complete. 81M JPM 8-2rev1.doc 9 NRC JAMES A. FITZPA TRICK EXAMINAJPM 8-2 ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR CUE: I&C is 17. (Step 8.4.17) reviewing data. IF RPV pressure is THAN OR EQUAL TO 165 THEN I&C or Engineering recorder and verify HPCI flow rate GREATER THAN EQUAL TO 3400 within 60 seconds HPCI flow rate

GREATER THAN EQUAL TO 3400 gpm 60 seconds from and through NOTE: HPCI response time measured from Step until flow rate reaches remains GREATER OR EQUAL TO 3400 HPCI response time recorder trace is THAN 60 No response required.

RPV (Step8.4.18) pressure is greater than 165 IF RPV pressure is LESS THAN 165 psig.psig, THEN review EPIC TRHPCI trace and verify the following: HPCI flow rate GREATER THAN OR TO 3400 HPCI flow rate GREATER THAN OR TO 3400 gpm I 81M JPM 8-2rev1.doc 10 NRC JAMES A. FITZPA TRICK EXAMINA JPM S-2 ELEMENT STANDARD SAT UNSAT Comment Number CAUTION Failure to closely monitor HPCI pump discharge pressure could result in exceeding HPCI piping design pressure of 1320 psig. 19. (Step 8.4.19) Establish HPCI pump pressure as IF RPV pressure is THAN OR EQUAL TO 970 THEN throttle TEST VL V TO 23MOV-21 to establish BOTH of following HPCI turbine speed THAN 2100 rpm on SPEED HPCI pump discharge GREATER THAN OR TO 1250 psig on DISCH (Step 8.4.19 continued) Not apPlicahble. 9R P V is greater t an 7 OIF RPV pressure is LESS THAN psig, EXAMINER: The pump has been running without flow for several minutes. Terminate the task at this point. JPM Stop Time _____ SIM JPM S-2rev1.doc 11 NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-2 HANDOUT PAGE TASK CaNon-IONS:

1. The plant is operating at-power.

2. Field personnel are briefed and stationed to support performance of ST-4N. 3. One loop of RHR is in Torus Cooling Mode. 4. Another operator is monitoring and controlling Torus level and temperature.

5. Torus venting is in progress per OP-37 section E. INITIATING CUE: You are directed to continue performance of ST-4N, HPCI QUICK-START, INSERVICE, AND TRANSIENT MONITORING TEST (1ST) at Step 8.4.7. SIM JPM S-2rev1.doc James A. Fitzpatrick Generating Job Performance Reactor Scram with a Control Rod Insertion JPM Number: S-3 Revision Number: 1 Date: 1/13/10 Developed By:

______ 4/08/10 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Examiner Date S/M JPM S-3rev1.doc JOB PERFORMANCE MEASURE VALIDATION NOTE: All steps of this checklist should be performed upon initial validation. Prior to usage, revalidate JPM using steps 8 through 11 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, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review. 7. Critical steps meet the criteria for critical steps and are identified with asterisk 8. Verify the procedure referenced by this JPM matches the most revision of that Procedure Rev. Date _____9. Pilot test the a. verify cues both verbal and visual are free of conflict, b. ensure performance time is

10. If the JPM cannot be performed as written with proper responses, revise the 11. When JPM is revalidated, Examiner sign and date JPM cover S/M JPM S-3rev1.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

Reset the simulator to appropriate IC-48, Reactor Power should be approximately 5%. Insert Malfunction (RD13; 18:27) for Stuck Rod for a FUll-out Control Rod 18:27. TOOLS AND EQUIPMENT

1. Key to bypass RWM TASK STANDARD:

Insertion of Manual Reactor Scram with a Control Rod insertion failure TASK CONDITIONS:

1. The reactor is operating near 5% reactor power and conditions exist that require a reactor scram. INITIATING CUE: You are the RO. The CRS directs you to manually scram the reactor and carry out the actions of AOP-1. Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The timeclock starts when the applicant acknowledges the initiating cue. SIM JPM S-3rev1.doc 3 ---Operator's Name: ______----___ Job Title: 0 NLOI RO

SROD STA 0 SRO Cert ..IPM Title: Insertion of Manual Reactor Scram with a Control Rod insertion failure JPM Number: S-3 Revision Number: 0 KIA Number and Importance:

KA 212000 A4.01 4.6 (SRO) Suggested Testing Environment: Simulator Actual Testing Environment: Testing Method: Perform in Simulator Alternate Path: YES Time Critical: No Estimated Time to Complete: 20 min. Actual Time Used: minutes

References:

1. NUREG 1123,212000 A4.01 4.6 (SRO) 2. AOP-1; Reactor Scram, Rev.43 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

0 Yes 0 No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory D Unsatisfactory Com me nts:_____________________________Note: Any grade of UNSAT requires a Evaluator's Name: _____________Evaluator's Signature: 81M JPM 8-3rev1.doc 4 Descri12tion: This JPM will require insertion of Manual Reactor Scram with a Control Rod insertion failure SIM JPM S-3rev1.doc 5 NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION JPM $-3 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT STANDARD SAT . Comment Number

1.(Step E.1) If a manual scram is Applicant depresses required, THEN depress the following manual scram push push MANUAL SCRAM A NOTE: The applicant should MANUAL SCRAM B observe: Annunciators 09-5-1-13, 14, RPS MAN SCRAM alarms. SCRAM GROUPS 1, 2, 3, 4 I liqhts are off.
2. (Step E.2) Place RX MODE switch Applicant places RX in SHUTDOWN.

switch in the I position. I NOTE: The immediate operator actions in Steps 3 through 7 may be performed

3. (Step E.3) Fully insert the IRMs and Applicant select and drive SRMs. fully all IRMs and NOTE: Since low power IRMs Since low power IRMs are already already i inserted.

4. (Step EA) Verify reactor power is Applicant verifies rapidly lowering using any of the rapidly lowering using one following nuclear instrumentation the responses:

APRM APRMs recorders or downscale indicate indicating lights and/or observing Fully inserted IRMs trending the APRM down (recorder selector switch lights are to IRM position)
Fully inserted Fully inserted SRMs trending trending down for those IRMs selected the
Fully inserted SRMs trending down on I recorder or meters I I 81M JPM 8-3rev1.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON T

5. (Step E.5) Verify the reactor will remain shutdown under all conditions without boron using one or more of the following methods: Green FULL IN light on full core display (preferred method) Rods In Monitor Program indication (EPIC Screen RIMP) SPDS plant display control rods full-in indication Four rod display notch position indication EPIC full core rod scan notch position 6. (Step E.6) If multiple rods are withdrawn.

then initiate ARI. 7. (Step E.7) Ensure closed SDIV vent and drain valves. SAT Applicant using one or more of the methods listed observes that one control rod is full out. all others are full in and informs CRS that one rod is full out. Applicant observes that only 1 rod is full out, all others are full in. NOTE: It is plausible that the applicant could initiate ARI due to the rod not full in. This would however. be contrary to the guidance in AOP-1. With the RD13 simulator malfunction inserted the rod will not insert. Applicant observes SDIV vent and drain valve position indicating lights. Verify that the green (closed) lights come on after the red (open) indicating lights go off. JPM S-3 Comment Number SIM JPM S-3rev1.doc 7 NRC JAMES A. FITZPATRICK INITIAL EXAMINA ELEMENT B. (Step E.B) WHEN APRM's are downscale, THEN perform the following:

a. Ensure Main Turbine is tripped. b. Verify 4 KV loads transfer to reserve power. 9. (Step E.9) If circulating water pumps are tripped, then ensure closed MSIV's. 10. (Step E.10) If both recirc pumps are tripped, then minimize RPV bottom head cooldown per Attachment 6 of AOP-1. EVALUATOR CUE: If recirc have tripped, inform applicant Attachment 6 of AOP-1 will performed by another

11. (Step F.1.1) IF any control rod §.. NOT full in, AND NO EOP-3 entry condition is present, THEN perform attachment 4 or 5 as directed by the SM or CRS. EVALUATOR CUE: When asked, CRS directs inserting control rod with RMCS apJ)licant selects attachment

4. SIM JPM S-3rev1.doc STANDARD Applicant ensure main turbine is tripped by observing:

a. Annunciator 09-5-2-9 MAIN TURB TRIP is in alarm Amber (tripped) light is on at EHC control on 09-5 Panel Position indicating meters for main turbine SV's, CV's and CIV's indicate 0% at EHC control. b. Verify 4KV loads transferred by observing greater than 3.9 KVon: Bus 10500 volt meter on Panel 09-B. Bus 10600 voltmeter on Panel 09-B. Applicant observes circulating water pumps A and/or B running with red indicating light on. Applicant observes Recirc pumps status by checking red/green light indication and/or pump flows. EVALUATOR CUE: If recirc pumps have tripped, inform applicant that Attachment 6 of AOP-1 will be performed by another operator.

EVALUATOR CUE: When asked, CRS directs inserting control rod with RMCS. Applicant selects attachment

4. JPM S-3

SAT UN5AT I Com Number i 8 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA ELEMENT
12. (Attachment 4, step 2) Place RWM keylock switch in BYPASS in RWM console. 13.(Attachment 4, step 3) Reset Reactor Scram as follows: If ARI has actuated then reset ARlo EVALUATOR CUE: ARI should not have actuated during the scram, but if it did then reset it per Attachment 4, step 3 14. (Attachment 4, step 3.b) Verify Annunciator 09-5-1-33 MODE SW IN SHUTDOWN TRIP BYPASSED is in alarm. 15. (Attachment 4, step 3.c) Place SDIV HI LVL TRIP keylock switch in BYPASS. 16. (Attachment 4, step 3.d) Place RX SCRAM RESET switch to group 2 & 3 then to 1 & 4, spring return to NORM. CAUTION: If only RPS Group 1 and 4 is reset, SDIV vent and drain valves will open, creating a drain path from the RPV, through the RPS Group 2 and 3 scram outlet valves, to the Reactor Building equipment drain sumps. 17. (Attachment 4,step 3.e) Verify RPS A and B Scram Group 1, 2, 3, and 4 lights are on. 18. (Attachment 4,step 3.f) Verify closed all scram inlet and outlet valves using one or a combination of the following methods: Blue SCRAM lights on FULL CORE DISPLAY Local valve position indication

19. (Attachment 4,step Verify open SDIV vent and drain SAT Applicant places RWM keylock switch in BYPASS. EVALUATOR CUE: ARI should not have actuated during the scram, but if it did then reset it per Attachment 4, step 3 Applicant verifies 09-5-1-33 is in alarm. Applicant places SDIV HI L VL TRI P keylock switch in BYPASS. Applicant places RX SCRAM RESET switch in group 2 &3, then to group 1 &4, spring return to NORM. Applicant verifies RPS A and B Scram Groups 1, 2, 3, and 4 lights are on. Applicant verifies all blue SCRAM lights are out on FULL CORE DISPLAY. Applicant verifies red open lights are on and green closed lights are out for SDIV vent and drain valves at panel 09-5. JPM 8-3 UNSAT Num k81M JPM 8-3rev1.doc 9

NRC JAMES A. FITZPA TRICK INITIAL JPM ELEMENT STANDARD SAT UNSAT umber 20a. (Attachment 4,step 3.i) a. Applicant observes that When the following annunciators are annunciators clear: 09-5-1-1 and 09-5-1-44 are

09-5-1-1 SDIV A or B HI LVL clear. TRIP
09-5-1-44 SDIV A or B NOT Applicant places SDIV HI LVL DRAINED TRIP keylock switch in Place SDIV HI LVL TRIP keylock switch I in EVALUATOR CUE: The next step may be performed after rod insertion as there is only one rod 21. (Attachment 4,step 3.j) Perform post scram reset control rod position check per section G.2. as soon as practicable.
22. (Attachment 4, step 6) Raise CRD drive water differential pressure using one or more of the following methods in the listed order of priority:

CAUTION: Drive water differential pressure is limited to less than 600 psid with reactor pressure below 650 psig to prevent damage to drive mechanism seals. EVALUATOR CUE: If asked, inform applicant to use the first priority option. Other options may be selected and utilized. Close CRD DRV WTR PRESS VL V 03MOV-20 Raise CRD System flow using CRD FLOW CNTRL 03FIC-301 Start second CRD pump Close 03CRD-56 (CRD charging water supply header isol valve) Close the following valves: 03CRD-177A (CRD water pump A min flow isol valve) 03CRD-177B (CRD water pump B min flow isol valve) Goes to section G.2 for post scram reset control rod position check. Applicant closes or throttles closed 03MOV-20 without exceeding 600 psid drive water DIP to establish elevated drive water DIP. EVALUATOR CUE: If asked, inform applicant to use the first priority option. Other options may be selected and utilized. EVALUATOR NOTE: 03MOV -20 is throttled but indicates closed. 81M JPM 8-3rev1.doc 10 II NRC JAMES A. FITZPA TRICK INITIAL EXAMINA

23.{Attachment 4, step 7) Attempt to insert each withdrawn control rod in the order specified in Attachments 1,2 and 4 as follows: a. Select control rod on ROD SEL matrix. b. Insert control rod using one of the following switches: ROD MOVEMENT CNTRL ROD EMERG 11\1 NOTCH OVERRIDE 24. Reports that all rods are full in.

SAT Applicant selects stuck rod on ROD SEL matrix. Inserts rod to full using either the MOVEMENT held in the IN Holding the ROD EMERG IN NOTCH OVERRIDE IN EMERG RODIN. Reports all rods are full in. EVALUATOR: Terminate the task after reports all rods are full in. JPM Stop Time _____ SIM JPM S-3rev1.doc JPM S-3 Com .. Num 11 NRC JAMES A. FITZPA TRICK INITIAL JPM S-3 HANDOUT PAGE TASK CONDITIONS:

1. The reactor is operating near 5% reactor power and conditions exist that require a reactor scram. INITIATING You are the RO. The CRS directs you to manually scram the reactor and carry out the actions of SIM JPM S-3rev1.doc James A. Fitzpatrick Generating Job Performance SPRAY THE DRYWELL WITH RHRSW (ALTERNATE PATH) "IPM Number: S-4 Revision Number: 2 Date: 1/20/10 Developed

_______ 4/08/10 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Date SIM JPM S-4rev1.doc JOB PERFORMANCE MEASURE VALIDATION NO"rE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate ..IPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in*plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. SIM JPM S-4rev1.doc 2

REVISION RECORD (Summary):

1. Rev JPM Setup

1. Simulator should be reset to an IC-46 that has the following conditions: Reactor level is at T AF OW spray is required with temperature and pressure within OWSIL RHR Pump 'A' and 'C' is not available for OW spray. RHR 'A' and 'C' breakers are racked out. (RH42A -RHR A racked out and RH42C -RHR C racked out.) Insert RH12 TORUS OUTLET VLV (151B) TO RHR LOOP B to close valve and use override to have the valve indicate open. (OL-RHZL010151B(1)

Mimic RHR Suct from JP (green light off)-reset (OL-RHZ1 01 0151 B(2) Mimic RHR Suct from JP (red light on) -reset TOOLS AND EQUIPMENT

1. None TASK STANDARD:

Due to RHR strainers clogged, drywell sprays will be performed using RHRSW as alternate containment spray in service lAW EP-14; Rev. 3 TASK CONDITIONS: A steam leak in the drywell has occurred and a reactor scram was performed. The CRS has implemented the appropriate EOPs. ESW is in service. Suppression chamber pressure is greater than 15 psig. 'A' loop of RHR was OOS for maintenance prior to the transient and is unavailable. Both reactor Recirc pumps are shutdown and all drywell cooling fans have been stopped. Drywell sprays are required for High Drywell temperature lAW with the EOPs. RPV level is being restored with HPCI. Torus Spray Valve 10MOV-38B has failed to open. INITIATING CUE: You are the RO. The CRS has directed you to lineup to spray the Drywell using 'B' and 'D' RHR pumps. Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

S/M JPM S-4rev1.doc 3 Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The timeclock starts when the applicant acknowledges the initiating cue. 81M JPM 8-4rev1.doc 4

Operator's Job Title: 0 NLO ISRO DSTA o SRO JPM Title: SPRAY THE DRYWELL WITH RHRSW (ALTERNATE PATH) JPM Number: S-4 Revision Number: 2 KlA Number and Importance: KA 226001 A2.15 3.6, 3.8 Suggested Testing Environment: Simulator Actual Testing Environment: Testing Method: Perform in Simulator Alternate Path: YES Time Critical: No Estimated Time to Complete: 20 min. Actual Time Used: ___minutes

References:

1. NUREG 1123, 226001 A2.15 3.6, 3.8 2. Posted instructions for Drywell Spray startup. OP-138, RHR Containment Control, Attachment

3. 3. EP-14,$ection 5.2 Alternate Containment Sprays, Rev. 3 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes 0 No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory Unsatisfactory Comments: Note: Any grade of UNSAT requires a Evaluator's Name: _______________________Evaluator's Signature: Date: ____SIM JPM S-4rev1.doc 5

== Description:==

This JPM will have the applicant place drywell spray using '8' and '0' RHR pumps in service lAW the posted attachment but due to strainer clogging will have to re-align and spray the Drywell with alternate containment sprays -RHRSW loop '8' cross-tie containment spray (drywell) in service. 81M JPM 8-4rev1.doc 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-4 NOTE: Critical Element( s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT 1. Applicant obtains posted instructions for Drywell Spray 2. Ensure the following components are tripped: RWR Pumps

02-2P-1A
02-2P-1 B Drywell Cooling Fans
68FN-2A, B, C, and 0
68FN-4A, B, C, and 0 3. Applicant verifies drywell temperature and pressure are within the Drywell Spray Initiation Limit
4. IF RPV water level is LESS THAN 10 inches on fuel zone water level indication, AND the EOPs permit diverting LPCI flow, THEN place OW & Torus Spray VLV OVERRIDE OFFUEL ZONE LVL 10A-S18A(B) keylock in MANUAL OVERRD
5. Place SPRAY CNTRL switch to MANUAL, spring return 6. Verify white SPRAY PERM DS67B light is S/M JPM S-4rev1.doc

! STANDARD Applicant obtains posted instructions for Drywell Spray Applicant ensures following components RWR Pumps

02-2P-1A
02-2P-1 B Drywell Cooling Fans
68FN-2A, B, C, and 0
68FN-4A, B, C, and 0 Applicant verifies drywell temperature and pressure are within the Drywell Spray Initiation Limit. Applicant verifies IF RPV water level is LESS THAN 10 inches on fuel zone water level indication, AND the EOPs permit diverting LPCI flow, THEN place OW & Torus Spray VL V OVERRIDE OFFUEL ZONE LVL 10A* S18A(B) keylock in MANUAL OVERRD Applicant places SPRAY CNTRL 1 OA-S 17B switch to MANUAL, spring return to normal. Applicant verifies white SPRAY PERM 10A-DS67B light is on. T UNSAT ' Comment I SAT Number i ! ! I 7 NRC JAMES A. FITZPA TRICK INITIAL JPM 8-4 ELEMENT STANDARD SAT UNSAT Comment Number CAUTION CAUTION Starting an RHR pump in an RHR loop Starting an RHR pump in an that is not full could result in severe RHR loop that is not full could water hammer and equipment damage. result in severe water hammer RHR piping shall be full prior to and equipment damage. RHR manually starting an RHR pump in that piping shall be full prior to loop. manually starting an RHR pump in that loop. 7. Ensure available RHR pumps in RHR Applicant ensures available Loop B are running: RHR pumps in RHR Loop B
RHR PMP 10P-3B are running:
RHR PMP 10p*3D
RHR PMP 10p*3B
RHR PMP 10P*3D
8. Open DW SPRAY OUTBD VLV Applicant opens DW SPRAY 10MOV-26B.

OUTBD VLV 10MOV*26B. SIMULATOR BOOTH OPERATOR SIMULATOR BOOTH Insert RH12 TORUS OUTLET VLV OPERATOR (151B) TO RHR LOOP B to close valve Insert RH 12 TORUS OUTLET and use override to have the valve VLV (151B) TO RHR LOOP B indicate open. to close valve and use override to have the valve Malfunction to clog RHR Suction indicate open. strainers and produce indications of Malfunction to clog RHR severe cavitation due to insufficient Suction strainers and produce NPSH will be evident once flow is indications of severe cavitation commenced. due to insufficient NPSH will be evident once flow is i commenced.

9. Throttle DW SPRAY INBD VLV Applicant throttles DW SPRAY 1 OMOV*31 B to establish desired drywell INBD VLV 10MOV-31B to spray flow rate. establish desired drywell spray flow rate. 10. WHEN RHR Loop B flow is Applicant ensures WHEN RHR GREATER THAN 1500 gpm, ensure Loop B flow is GREATER closed MIN FLOW VLV 10MOV-16B THAN 1500 gpm, ensure closed MIN FLOW VLV 10MOV*16B
11. Applicant should recognize RHR Applicant should recognize strainer are clogged by fluctuating RHR strainer are clogged by motor amps and discharge pressure.

fluctuating motor amps and discharge pressure. 81M JPM 8-4rev1.doc 8 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON CAUTION Blockage of EGGS pump suction strainers could occur due to debris in the Torus. Within the latitude provided by EOPs to restore and maintain parameters within specified limits, potential mitigative actions may include: Minimizing EGGS flow or removing affected EGGS pumps from service Alternating EGGS pumps from one division to another, if available. Shifting EGGS pump suction to another source,if available Operation of alternate injection sources

12. Ensure the following RHR pumps are stopped: RHR PMP 10P-38 RHR PMP 10P-3D
13. Applicant ensures WHEN RHR Loop 8 flow is LESS THAN 1500 gpm, ensure open MIN FLOW VLV 16B STANDARD SAT CAUTION Blockage of EGGS pump suction strainers could occur due to debris in the Torus. Within the latitude provided by EOPs to restore and maintain parameters within specified limits, potential mitigative actions may include: Minimizing EGGS flow removing affected pumps from Alternating EGGS from one division another, if Shifting EGGS suction to another source,if Operation of injection Applicant ensures pumps are stopped. EVALUATOR:ObseNe applicant identifies the pumps are stopped. Applicant ensures WHEN RHR Loop B flow is LESS THAN 1500 gpm, ensure open MIN FLOW VLV 10MOV-168 JPM 8-4 UNSAT Comment Number 81M JPM 8-4rev1.doc 9

NRC JAMES A. FITZPA TRICK INITIAL EXAMINAELEMENT

14. Applicant should recognize need to use Alternate Drywell EVALUA TOR CUE FOR SRO: If necessary ask applicant recommend a course of EVALUATOR CUE FOR RO: If necessary ask applicant What alternate methods are available for to spray the drywell? RHRSW FIRE PROTECTION

15. Obtain a controlled copy procedure and selects the section to 1 6. Reviews precautions, prerequisites and special instructions associated with the procedure: This procedure shall be used only when no RHR pumps are available for containment spray. This procedure secures LPCI

injection in order to maximize spray flow. The SM or CRS will determine the priority between containment spray or RPV injection. If using only one RHR subsystem, drywell and torus should be sprayed individually to maximize spray flow. The minimum drywell spray flow for an effective spray pattern is 5260 gpm for RHR Subsystem A and 4420 gpm for RHR Subsystem

8. Minimum torus spray flow for an effective spray pattern is 600 gpm. Fire water cross-tie spray flow is approximately 1000 gpm. Using this method for drywell spray might not achieve the desired effect. S/M JPM S-4rev1.doc Applicant should recognize the need to use Alternate Drywell Spray; EP-14 EVALUA TOR CUE: Once the RO or SRO states RHRSW is an alternate method for drywell spray, state "Use 'B' RHRSW to spray the drywell. EVALUATOR NOTE: Applicant may perform step F.B of OP*13B; RHR Loop B shutdown from Torus Cooling or Containment Spray Mode before going to EP-14. Obtains a controlled copy of EP-14 and selects section 5.2 to perform. Reviews applicable section of the procedure and notes requirements for Drywell spray flow rate. JPM S-4 SAT UNSAT Comment Number I I 10 NRC JAMES A. FITZPA TRICK INITIAL EXAMINAJPM S-4 ELEMENT STANDARD SAT UNSAT Comment Number 17. Verify the following RHR pumps are stopped:

RHR PMP 10P-3B
RHR PMP 10P-3D Applicant verifies pumps are stopped. ! EVALUA TOR: Observe applicant identifies the pumps are stopped. 18. Ensure closed at least one of the following valves:
DW SPRAY OUTBD VLV 26B
DW SPRAY INBD VLV 10MOV-31B Applicant ensures at least one of the valves is closed. EVALUA TOR: Observe ! applicant identifies the i valves are closed. 19. Ensure closed at least one of the following valves:
RHR TEST TORUS CLG & SPRAY 10MOV-39B
TORUS SPRAY INBD VLV 38B Applicant ensures at least one of the valves is closed. ! EVALUA TOR: Observe applicant identifies the valves are closed. 20. Ensure closed at least one of the following valves:
RHR TEST TORUS CLG & SPRAY 10MOV*39B
RHR TEST &TORUS CLG 10MOV* 34B Applicant ensures at least one of the valves is closed. EVALUATOR:

Observe applicant identifies the valves are closed. I 21. Ensure closed at least one of the following valves:

LPCIINBD INJ VLV 10MOV*25B
LPCI OUTBD INJ VLV 10MOV-27B Applicant ensures at least one of the valves is closed. ! EVALUA TOR: Observe applicant identifies the valves are closed. I
22. Ensure available RHRSW pumps in RHRSW Loop B are running:
RHRSW PMP 10P-1 B
RHRSW PMP 10P-1D Applicant ensures pumps are started. EVALUATOR:

Observe applicant starts the pumps.

23. Ensure RHRSW DISCH VLV FROM HX B 10MOV-89B is throttled to establish 2500 to 4000 gpm per RHRSW pump. Applicant throttles HX discharge valve 5000 to 8000 gpm on 10FI-132B.

EVALUATOR: Observe applicant throttles valve to i required flow. I I S/M JPM S-4rev1.doc NRC JAMES A. FITZPA TRICK INITIAL JPM S-4 ELEMENT STANDARD SAT UNSAT Comment Number 24. NOTE: Reviews NOTE and Steps 5.2.8 and 5.2.9 may be requirements for alternating performed and repeated in any order to between drywell and torus as alternate between drywell and torus . necessary. spray. EVALUA TOR: Acknowledge

if applicant states that the order may be alternated as necessary.
25. IF drywell spray is required, THEN Applicant opens the valves. perform the following:

o RHRSW to RHR Ensure open the following valves: 148B o RHRSW to RHR 10MOV-148B o RHRSW to RHR o RHRSW to RHR 26. Verifies the following are tripped: Applicant verifies the pumps o RWR PMP 02-2P-1A and fans are tripped or trips o RWR PMP 02-2P-1 8 them. o DW CLG FN 68FN-2A o DW CLG FN 68FN-28 o DW CLG FN 68FN-2C EVALUATOR: o DW CLG FN 68FN-2D This step was previously o DW CLG FN performed. o DW CLG FN 68FN-48 o DW CLG FN 68FN-4C o DW CLG FN 68FN-4D i

27. Verify drywell temperature and Applicant verifies the DWSIL pressure are within the Drywell Spray within the curve. Initiation Limit. EVALUA TOR: Acknowledge when applicant states that the drywell temperature and pressure are within the DWSIL. 28. IF RPV water level is less than 10 Applicant verifies the RPV inches on fuel zone water level level is less than TAF and indication, THEN place DW &TORUS . places keylock switch in SPRAY VLV OVERRIDE OF FUEL OVERRIDE.

ZONE L VL 1 OA-S 188 keylock switch in EVALUATOR: MANUAL OVERRD. This step was previously performed IApplicant reviews NOTE and The following step must be performed requirements for DW spray each time drywell spray is initiated or initiation. re-initiated. I S/M JPM S-4rev1.doc 12 NRC JAMES A. FITZPA TRICK INITIAL ELEMENT STANDARD SAT *29. Place SPRAY CNTRL 10A-S17B Applicant places spray control switch to MANUAL, spring return to switch to MANUAL. normal. 30. Verify white SPRAY PERM Applicant verifies SPRAY DS67B light is on. PERM light is ON. 31. Ensure closed RHRSW DISCH VLV Applicant ensures RHRSW FROM HX A 10MOV-89B. DISCH VLV FROM HX A 10MOV-89B is closed.

32. Ensure open OW SPRAY OUTBD Applicant ensures DW SPRAY VLV 10MOV-26B.

OUTBD VLV 10MOV-26B is open.

33. Throttle OW SPRAY INBD VLV Applicant throttles DW SPRAY 10MOV-31B to establish desired flow INBD VLV 10MOV-31B spray while maintaining RHRSW pump motor control switch to establish current LESS THAN OR EQUAL TO desired flow and pump max normal amps. ampere relationship.

EVALUATOR: Terminate the task at this pOint JPM Stop Time _____ JPM S-4 UNSAT Comment Number SIM JPM S-4rev1.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA JPM S-4 HANDOUT PAGE TASK CONDITIONS:

1. A steam leak in the drywell has occurred and a reactor scram was performed.

2. The CRS has implemented the appropriate EOPs. 3. ESW is in service. 4. Suppression chamber pressure is greater than 15 psig. 5. 'A' loop of RHR was OOS for maintenance prior to the transient and is unavailable.

6. Both reactor Recirc pumps are shutdown and all drywell cooling fans have been stopped. 7. Drywell sprays are required for High Drywell temperature lAW with the EOPs. 8. RPV level is being restored with HPCI. 9. Torus Spray Valve 10MOV-38B has failed to open. INITIATING CUE: You are the RO. The CRS has directed you to lineup to spray the Drywell using 'B' and '0' RHR pumps. SIM JPM S-4rev1.doc James A. Fitzpatrick Generating Job Performance Manual Isolation and Verification of Reactor Building Ventilation System JPM Number: S-5 Revision Number: 1 Date: 1/13/10 Developed Bernard Litkett Author Validated Facility Representative Review Examiner Approved Chief Examiner SIM JPM S-5rev1.doc JOB PERFORMANCE MEASURE VALIDATION NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date 'Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When "IPM is revalidated, Examiner sign and date JPM cover page. S/M JPM S-5rev1.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

1. Reset to IC-114 or any IC that supports isolating Reactor Building Ventilation.

2. A copy of OP-51A; Reactor Building Ventilation, section G.1 3. A copy of OP-20; Standby Gas treatment, section D.1 TOOLS AND EQUIPMENT

1. None TASK STANDARD:

Manual Isolation and Verification of Reactor Building Ventilation System TASK CONDITIONS: Reactor Building Ventilation manual isolation is required to support a maintenance activity. Standby Gas Treatment System must be started to support the manual isolation of the Reactor Building. INITIATING CUE: You are the RO. The CRS has directed you to manually isolate the Reactor Building System per Information for Evaluator's UNSAT requires written comments on respective

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The timeclock starts when the applicant acknowledges the initiating cue. SIM JPM S-5rev1.doc 3 ____ _ Operator's Job Title: 0 NLO ISRO DSTA o SRO JPM Title: Manual Isolation and Verification of Reactor Building Ventilation System JPM Number: S-5 Revision Number: 0 KIA Number and Importance: KA 288000 K4.02 3.6, 3.8 Suggested Testing Environment: Simulator Actual Testing Environment: Testing Method: Perform in Simulator Alternate Path: No Time Critical: No Estimated Time to Complete: 15 min. Actual Time Used: ___minutes

References:

1. NUREG 1123, 288000 K4.02 3.6, 3.8 2. Reactor Building and Ventilation System OP-51A; Sections G.1 and G.2, Rev.48 3. Standby Gas Treatment System OP-20: section D.1, Rev. 36 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory Unsatisfactory Comments:__________________________ _ Note: Any grade of UNSAT requires a Evaluator's Name: ______________Evaluator's Signature: Date: SIM JPM S-Srev1.doc 4

== Description:==

This JPM has the applicant perform a manual isolation and verification of reactor building ventilation system SIM JPM S-Srev1.doc 5 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA NOTE: Critical Element(s) indicated by

in Performance Checklist.

JPM 8-5 PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT STANDARD SAT UNSAT Comment Number 1. Obtain a controlled copy of procedure OP-51A; Sections G.1 and G.2 and OP-20. The applicant determines where to obtain a controlled copy of OP-51A and OP-20. (Control Room, Merlin) EVALUATOR NOTE: Applicant may use hard card for 20. This jpm was written for OP*20. EVALUATOR NOTE: Applicant may use hard card for OP-20. This jpm was written for OP*20. 2. Review precautions associated with the procedure Applicant review Section C of the procedure and notes precaution relating to changing building ventilation line-ups.

3. Selects the correct section to perform the task. Applicant reviews Section G of the procedure and selects Section G.1 for Manual Isolation.

4. Ensure SBGT is running per OP-20. 5. Selects the correct section to perform the task. Applicant obtains a current copy of OP-20 and reviews precautions associated with the operation of the SBGT System. Applicant reviews the procedure and selects Section D.1 for the "An SBGT Train. EVALUATOR CUE: Act as the CRS/SNO and when asked, order the "An SBGT Train started. If asked, inform operator that no painting, welding or smoke fumes have been in the Reactor Building in the last 24 hours. EVALUATOR CUE: Act as the CRS/SNO and when asked order the "An SBGT Train started. If asked, inform operator that no

painting, welding or smoke I fumes have been in the I Reactor Building in the last 24 hours. I 81M JPM 8-5rev1.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION JPM S-5 ELEMENT STANDARD SAT UNSAT Comment Number

6. Ensure OPENS the following:

Applicant at the 09-75 locates the control switch ABOVE EL 369' SUCT. OPENS the following valve: . 01-125MOV-11

7.Ensure OPEN "A" Inlet Applicant locates and OPENS

8. Verify the following system Applicant observes and on verifies component during the startup of the SBGT White light for AIR HTR

White light for AIR is is ON. Red light for AIR HTR Red light for AIR HTR 01 5A is ON. 125E-5A is TRAIN A CLG VLV 100A is
TRAIN A CLG VLV 125MOV-100A FN DISCH 01-125MOV-15A is CLOSED. TRAIN A FN 01-125FN-1A is
FN DISCH running. 15A is OPEN. TRAIN A FN 01-125FN-1A is running. 9. SBGT to EVALUATOR CUE: TORUS Venting SBGT "A" is not being used support any of these Drywell ! This step is not on the HPCI Operation
card for OP-20. MSLCS Operation AGT System Operation SIM JPM S-Srev1.doc 7

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA ELEMENT 10. IF SBGT "B" is shutdown" Verify open 01-125MOV-100B Verify flowrate on SGT flow 106A 11. Applicant verifies Rx Building differential pressure

12. Depress pushbuttons: (OP-51A; G.1): RB VENT ISOL A RB VENT ISOL B JPM S-5 STANDARD I SAT UNSAT Comment Number For the "B" SBGT train: Applicant verifies open "B" CLG VLV 100B. (this step is not on hard Applicant verifies flowrate SGT flow RB un-isolated Approximately RB isolated Approximately 5600 Applicant verifies Rx DIFF 01-125DPI-100A is less . negative than -.25 inches Applicant at the 09-75 locates the pushbuttons and both isolation SIM JPM S-5rev1.doc 8

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ELEMENT 13. Verifies the following to ensure Reactor Building Ventilation Isolation (OP-51A; G.2) INBD SUPP ISOL66AOV-100A CLOSED OUTBD EXH ISOL66AOV-101A CLOSED BELOW EL 369' RECIRC 105 OPEN EL369' RECIRC 66AOD-108; OPEN OUTBD SUPP ISOL66AOV-100B; CLOSED INBD EXH ISOL66AOV-10'1 B CLOSED SUPP FN 66FN-5A, 5B, 5C (2 OF 3)ON BELOW EL369' EXH FN 66FN-12A OR 66FN-12B: ON EL369' EXH FN 66FN-13A AND 13B; OFF TK EXH FN 66FN-35; OFF CRESC SUPP FN 66FN-26A OR 66FN-26B; ON SBGT SYSTEM; RUN PER OP*20 RX BLDG DIP; -0.25 TO -2.5 in. WATER GAUGE STANDARD Applicant at the 09-75 panel verifies the isolation using the posted attachment or OP-51A INBD SUPP ISOL 100A; CLOSED OUTBD EXH 66AOV-101A; BELOW EL 369' 66AOD-105; EL369' RECIRC 108; OUTBD SUPP 66AOV-100B; INBD EXH ISOL 101 B; SUPP FN 66FN-5A, 5C (TWO OF 3); BELOW EL 369' EXH FN 66FN-12A OR 66FN-12B; ON EL369' EXH FN 66FN-13A AND 66FN-13B; OFF TK EXH FN 66FN-35; OFF CRESC SUPP FN 26A OR 66FN-26B; SBGT SYSTEM; RUN PER OP-20 RX BLDG DIP; -0.25 TO -2.5 in. WATER GAUGE JPM S-5 SAT UNSAT Comment Number I I EVALUATOR: Terminate the task at this point. JPM Stop Time ____ SIM JPM S-5rev1.doc 9 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION JPM S-5 HANDOUT PAGE TASK CONDITIONS: Reactor Building Ventilation manual isolation is required to support a maintenance activity. Standby Gas Treatment System must be started to support the manual isolation of the Reactor Building. INITIATING CUE: You are the RO. The eRS has directed you to manually isolate the Reactor Building Ventilation System per OP-51A. S/M JPM S-5rev1.doc James A. Fitzpatrick Generating Job Performance PERFORM ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST JPM Number: 5-6 Revision Number: 1 Date: 2/02/10 Developed _______ 4/12/10 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Examiner Date SIM JPM S-6rev1.doc

JOB PERFORMANCE MEASURE VALIDATION NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date Pilot test the "IPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. SIM JPM S-6rev1.doc 2

REVISION RECORD (Summary): Rev 1 JPM Setup Instructions: Initialize the simulator to IC-41 Obtain a controlled copy of ST-9BB, EDG B &D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST. Initial as complete Section 4.0, 5.0 and Steps 8.1 through and including Steps 8.12. Copies of EDG Demand Log for EDG B & D forms from OP-22, DIESEL EMERGENCY Simulator booth operator simulate strainer clogging sometime after EDG carrying bus load by: a.) Overriding ESW pump strainer dip alarm on (09-6-2-24) on trigger #1 b.) Indications on control board should show pump running when model knows it is not running, EPIC flow point will show no flow 5. Simulator booth operator to override MAINT switches for EDG Band D and place in MAINT on trigger #2. TOOLS AND EQUIPMENT Stopwatch Synchronizing Switch TASK STANDARD: Perform surveillance test ST-9BB EDG B &D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST. Determine EDGs have no cooling and shutdown prior to engine damage. TASK CONDITIONS: The plant is at power. All steps up to step 8.12 have been completed sat INITIATING CUE: You are the RO. The CRS directs you to perform ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST, commencing at Step 8.13 for EDG B & D. Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The timeclock starts when the applicant acknowledges the initiating cue. SIM JPM S-6rev1.doc 3 SIM JPM S-6rev1.doc 4 ---Operator's Name: ----_r----- ___ Job Title: 0 NLO I RO

SRO OSTA o SRO Cert JPM Title: Perform the Emergency Diesel Generator Load Test (S/U and Load EDG's) JPM Number: S-6 Revision Number: 1 KIA Number and Importance:

KA 264000; A4.04; 3.7; 3.7 Suggested Testing Environment: Simulator Actual Testing Environment: Testing Method: Perform in Simulator Alternate Path: Yes Time Critical: No Estimated Time to Complete: 30 min. Actual Time Used: minutes

References:

1. NUREG 1123, 264000; A4.04; 3.7 ; 3.7 2. ST-9BB; Rev.11, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST. 3. OP-22; Rev. 53; DIESEL GENERATOR EMERGENCY POWER. 4. Alarm response for ESW strainer (09-06-2-24)

EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes 0 No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory Unsatisfactory Comments:_________________________ _ Note: Any grade of UNSAT requires a comment. Evaluator's Name: _____________(Print) Evaluator's Signature: ____________ _ Date: _____ S/M JPM S-6rev1.doc 5

== Description:==

This JPM asks the applicant to perform ST-9BB; EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST. SIM JPM S-6rev1.doc 6 NRC JAMES A. FITZPA TRICK EXAMINA JPM S-6 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT : STANDARD I SAT UNSAT Comment Number i 1. Obtain a controlled copy of Obtains a controlled copy of procedure ST-9BB; Rev.11, EDG B & D ST -9BB; Rev.11 FULL LOAD TEST AND ESW PUMP OPERABILITY TEST i 2. Reviews the precautions Reviews the precautions, making note of any that are I applicable i 3. Select the correct section to perform Applicant selects step 8.13 of the task. ST-9BB EVALUA TOR CUE: If asked, the other ROs will perform the stopwatch function. I

4. Simultaneously place the EDG B & Applicant simultaneously D control switches to START and start places the EDG B & D control stopwatch switches in START and starts EVALUATOR CUE: If asked, the stopwatch i second RO will perform the stopwatch
EVALUATOR CUE: If asked, function. . the other ROs will perform the stopwatch function.

5. If EDG frequency does not stabilize If EDG frequency does not between 58 and 62 Hz after reaching stabilize between 58 and 62 normal voltage, then immediately place Hz after reaching normal the affected EDG CNTRL switch in voltage, then applicant STOP. immediately places the affected EDG CNTRL switch in STOP. I SIM JPM S-6rev1.doc 7

NRC JAMES A. FITZPA TRICK EXAMINA TlON ELEMENT 6. EVALUA TOR CUE: If asked, the other ROs perform the stopwatch function. Step 8.15 Operator 1 time: 6.92 sec

Step 8.16 Operator 2 time: 7.05 sec Step 8.17 Operator 3 time: 8.46 sec
Step 8.18 Operator 1 to record
frequency and voltage 7. Verify the following:

EDG B & D TIE BKR 10604 is

closed. ESW Pump 46P-2B is running.
8. Trip EDG B & D TIE BKR 10604, allow switch to spring return to AUTO and record time. 9. Applicant records frequency.

10. Verify EPIC-D-732 closed and open on alarm typer. STANDARD SAT EVALUATOR CUE: If the other ROs perform stopwatch Step 8.15 Operator 1 time: 6.92 sec Step 8.16 Operator 2 time: 7.05 Step 8.17 Operator 3

8.46 sec Step 8.18 Operator 1 record frequency Applicant verifies the following: EDG B & D TIE 10604 is ESW Pump 46P-2B is
running. Applicant trips EDG B & D TIE BKR 10604, allow switch to . spring return to AUTO and record time. Applicant records frequency.

Applicant verifies closed and open on JPM S-6 UNSAT Comment Number SIM JPM S-6rev1.doc 8 NRC JAMES A. FITZPA TRICK EXAMINA TlON ELEMENT

11. Place the following switches in DROOP: EVALUATOR NOTE: (When placed in droop the following alarms will annunciate.)

09-8-4-5 EDG B FUEL CUTOFF OR CNTRLS OFF NORMAL 09-8-4-8 EDG 0 FUEL CUTOFF OR CNTRLS OFF NORMAL EDG B GOV MODE EDG D GOV MODE 12. IF an EDG functions improperly while paralleled with 10600 bus, THEN perform the following: Trip associated EDG load breaker. Shut down malfunctioning EDG per Section G of OP-22 (Single EDG Shutdown from Control Room). Shut down other EDG per Section

G of OP-22 (Single EDG Shutdown from Control Room)

Initiate a WR to troubleshoot EDG.

OR Applicant may determine OP-22 G.17 Emergency EDG Shutdown is more appropriate.

EVALUA TOR Note: No issues with EDG at this time. EDGs are operating as expected. EVALUA TOR CUE: If asked, the other ROs will initiate a WR STANDARD SAT UNSAT Comment Number Applicant places the following switches in DROOP: EDG B GOV MODE EDG D GOV MODE Applicant reviews steps. EVALUA TOR Note: No issues with EDG at time. EDGs are operating expected. Apllicant come back to this when ESW flow fails EVALUA TOR CUE: If asked, the other ROs will initiate a WR i S/M JPM S-6rev1.doc 9 NRC JAMES A. FITZPA TRICK EXAMINA TlON ELEMENT CAUTION Operation of the T -4 load tap changer during paralleling and loading of the EDG could cause the EDG to trip. 13. While performing the next 2 steps do not operate the T -4 load tap changer. NOTE Steps 14 and 15 may be performed in any order per SM direction.

14. Parallel EDG B with the 10600 Bus as follows.

15. Place EDG B LOAD BKR SYNCH SW in ON.
16. Adjust EDG B VOL T REG to match INCOMING and RUNNING voltages.
17. Adjust EDG B GOV to rotate synchroscope slowly in the FAST direction (clockwise).

NOTE Steps 18 and 19 may be checked after step 19 is complete

18. When EDG B and the 10600 BUS are in phase (synchroscope at 12 o'clock) close EDG B LOAD BKR 10602. Aunniciator 9*8*4-3 EDG B LOAD BKR 10602 CLOSED will alarm when breaker is closed. JPM 8-6 STANDARD SAT UNSAT Comment Number ! Operation of the T -4 load changer during paralleling loading of the EDG cause the EDG to
While performing the next I steps do not operate the T-4 load tap changer. Steps 14 and 15 may performed in any order per SM Parallel EDG B with the Bus as Applicant places EDG B BKR SYNCH SW in Applicant matches (EDG) and RUNNING 10600) voltages with EDG VOL T REG Applicant adjusts EDG B to rotate synchroscope in fast NOTE Steps 18 and 19 may checked after step 19 Applicant places the switch 10602, EDG B BKR, to CLOSE synchroscope is at Aunniciator 9*8-4-3 EDG B LOAD BKR 10602 CLOSED will alarm when breaker is closed. I 81M JPM 8-6rev1.doc 10 NRC JAMES A. FITZPA TRICK ELEMENT
19. Adjust EDG B GOV to raise EDG B load between '100 to 300 kW. 20. Place EDG B LOAD BKR SW in OFF and removes sync 21. IF EDG B is the second diesel paralleled THEN, balance EDG Band D using voltage regulator{s) to establish LESS THAN 100 KVAR difference between EDG Band EDG D.
22. Adjust EDG B GOV to raise EDG B load to 2600 kW over 3 to 5 minutes in approximately 800 kW increments EVALUA TOR CUE: State after initial 800 kW increment, "for JPM 1.5 minutes have passed", after next 800 kw increment state "a total of 3 minutes have passed." 23. Parallel EDG D with the 10600 Bus as follows
24. Place EDG D LOAD BKR SYNCH SW in ON
25. Adjust EDG D VOL T REG match INCOMING and
26. Adjust EDG D GOV to synchroscope slowly in the direction NOTE Steps 27 and 28 may be checked after step 28 is complete SIM JPM S-6rev1.doc STANDARD Applicant places the EDG B GOV switch to RAISE and loads EDG B between 100 to 300 kW. Applicant places the EDG B LOAD BKR SYNCH SW to OFF removes sync switch handle. IF EDG B is the second diesel paralleled THEN, balance EDG Band D using voltage regulator(s) to establish LESS THAN 100 KVAR difference between EDG Band EDG D. Applicant adjusts EDG B GOV to raise EDG B load to 2600 kW over 3 to 5 minutes in 800 kW increments EVALUATOR CUE: State after initial 800 kW increment, "for JPM 1.5 minutes have passed", after next 800 kw increment state "a total of 3 minutes have passed." Parallel EDG D with the 10600 Bus as follows Applicant places EDG D LOAD BKR SYNCH SW in ON Applicant matches INCOMING (EDG) and RUNNING (bus 10600) voltages with EDG D VOL T REG adjustments Applicant adjusts EDG D GOV to rotate synchroscope slowly in fast direction NOTE Steps 27 and 28 may be checked after step 28 is complete JPM S-6 SAT UNSAT Comment Number 11 NRC JAMES A. FITZPA TRICK
27. When EDG D and the 10600 BUS are in phase (synchroscope at 12 o'clock) close EDG D LOAD BKR 10612
28. Adjust EDG D GOV to raise EDG B load between 100 to 300 kW 29. Place EDG D LOAD BKR SYNCH SW in OFF and removes sync switch handle.
30. IF EDG D is the second diesel paralleled THEN, balance EDG Band D using voltage regulator(s) to establish LESS THAN 100 KV AR difference between EDG Band EDG D.
31. Adjust EDG D GOV to raise EDG B load to 2600 kW over 3 to 5 minutes in approximately 800 kW increments EVALUA TOR CUE: State after initial 800 kW increment, "for JPM 1.5 minutes have passed", after next 800 kw increment state "a total of 3 minutes have passed.".

Simulator booth operator simulate strainer clogging a.) Overriding ESW pump strainer dIp alarm on (09-6-2-24) STANDARD Applicant places the control switch 10612, EDG D LOAD BKR, to CLOSE when synchroscope is at 12:00 . Applicant places the EDG D

GOV switch to RAISE and loads EDG B between 100 to 300kW Applicant places the EDG D LOAD BKR SYNCH SW to OFF and removes sync switch handle. IF EDG D is the second diesel paralleled THEN, balance EDG Band D using voltage regulator(s) to establish LESS THAN 100 KVAR difference between EDG Band EDG D. Applicant adjusts EDG D GOV to raise EDG B load to 2600 kW over 3 to 5 minutes in 800 kW increments . EVALUATOR CUE: State after initial 800 kW increment, "for JPM 1.5 minutes have passed", after next 800 kw increment state "a total of 3 minutes have passed." JPM S-6 SAT UNSAT Comment Number i i I I SIM JPM S-6rev1.doc 12 NRC JAMES A. FITZPA TRICK EXAMINAELEMENT 32. Applicant responds to ARP 09-6-2-24 and recognizes ESW 'B' pump strainer has HI DIP Simulator booth operator simulate strainer clogging a.) Indications on control board should show pump running EVALUATOR Evaluator is to log the time annuciator 09-06-2-24 EVALUATOR CUE: Evaluator is to tell applicant this is your alarm. SIMULATOR BOOTH OPERATOR:

simulate strainer clogging. a.) if after 10 minutes of operation and the applicant has not tripped 'B' and '0' EOG. The Booth Operator is to trip 'B' and '0' EDG. STANDARD Annunciator: 09-6-2-24 for ESW PMP A or B STRAINER DIFF PRESS HI Applicant responses to ARP 09-6-2-24. EVALUA TOR CUE: If applicant does not reference EPIC point EPIC A-711, asks is there anyway to check ESW flow? EPIC-A-711: ESW Loop ESW flow is zero EVALUATOR CUE: If applicant calls up ESW Pp B Strainer DIP. The cue is that DIP is the max value for the instrument If applicant responds to shift strainer basket respond that the strainer baskets have been swapped. Strainer basket DIP is still high. CRITICAL TASK EVALUATOR NOTE: If EDG destroyed, terminate this JPM, applicant critical task to shutdown EDG within 10 minutes not met. EVALUATOR CUE: If applicant calls NPO for EOG reply' Jacket temperature is 170 0 and JPM SAT I UNSAT Comment Number Log Time For annuciator 09-6-2-24 SIM JPM S-6rev1.doc 13 NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-6 ELEMENT STANDARD SAT UNSAT Comment Number

33. IF an EDG functions improperly Applicant refers to step 8.24 while paralleled with 10600 bus, (or step 12 of JPM) and THEN applicant performs the following:

performs actions: if an EDG functions improperly while paralleled with 10600 Applicant may determine OP-22 bus, THEN applicant performs G.17 Emergency EDG Shutdown is the following: more Applicant may determine OP-22 G.17 EmergencyTrip associated EDG load breaker. EDG Shutdown is more appropriate.Shut down malfunctioning EDG Section G of OP-22 (Single EDG Shutdown from Control

Trip associated EDG load Shut down other EDG per Section G of OP-22 (Single EDG from Control Room)
Shut down EDG per Section G of Initiate a WR to troubleshoot EDG. 22 (Single EDG Shutdown from Control Room).EVALUATOR CUE: If asked, the other ROs will initiate a Shut down other EDG Section G of WR (Single EDG Shutdown EVALUATOR NOTE: from Control Room) Step OP-22 G.6.1 contradicts a critical
Initiate a WR to step in the if using OP-22 to troubleshoot EDG. shutdown the EDG until after 10 EVALUA TOR CUE: minutes have elapsed( cylinder cooldown time) If asked, the other ROs will initiate a WR EVALUATOR CUE: If asked by the applicant to bypass the 10 minute coo/down time; Allow the applicant to bypass the 10 minute wait in the procedure and shutdown the EDG to prevent damage. SIM JPM S-6rev1.doc 14 NRC JAMES A. FITZPA TRICK ELEMENT
34. Ensure EDG load breakers are tripped and placed in PULL TO LOCK position.
EDG B; 71-10602
EDG D; 71-10612 STANDARD Applicant ensures load breakers are tripped and placed in PULL TO LOCK position.
EDG B; 71-10602
EDG D; 71-10612 JPM 8-6 SAT UNSAT Comment Number EVALUATOR:

Terminate the task at this point if EDGs load breakers are tripped.

35. OP*22; G*17 EMERGENCY EDG SHUTDOWN.
36. Ensure EDG load breakers are tripped and placed in PULL TO LOCK position.
EDG B; 71-10602
EDG D; 71-10612
37. Ensure EDG tie breaker is tripped
EDG BID; 10604 NOTE: The EDG BID; EDG FUEL CUTOFF OR CNTRLS OFF NORMAL annunciator will alarm at panel 09-8 in the following step. (This alarm is already in due the EDG being placed in droop)
38. Place EDG BID CONTROL SWITCH in MAINT at panel BID. SIMULATOR BOOTH OPERATOR:

Override MAINT switches for EDG B and D. Place in MAl NT

39. Place EDG BID CNTRL switches to STOP at panel 09-8. OP-22; G-17 EMERGENCY EDG SHUTDOWN.

Applicant ensures load breakers are tripped and placed in PULL TO LOCK position.

EDG B; 71-10602
EDG D; 71-10612 Applicant ensures EDG tie breaker is tripped.
EDG BID; 10604 NOTE: The EDG BID; EDG FUEL CUTOFF OR CNTRLS OFF NORMAL annunciator will alarm at panel 09-8 in the following step. (This alarm is already in due the EDG being placed in droop) Applicant contacts in plant operator to place EDG BID CONTROL SWITCH in MAINT at panel 93ECP-BID. SIMULATOR BOOTH OPERATOR:

Override MAINT switches for EDG Band D. Place in MAINT. Applicant places EDG BID CNTRL switches to STOP at panel 09-8. EVALUATOR: Terminate the task at this point. JPM Stop Time _____ 81M JPM 8-6rev1.doc 15 NRC JAMES A. FITZPA TRICK JPM S-6 HANDOUT PAGE TASK CONDITIONS:

1. The plant is at power. 2. All steps up to step 8.12 have been completed sat INITIATING CUE: You are the RO. The CRS directs you to perform ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST, commencing at Step 8.13 for EDG B & D. SIM JPM S-6rev1.doc James A. Fitzpatrick Generating Job Performance SRM SIGNAL TO NOISE RATIO DETERMINATION TEST (ST-5H) JPM Number: S-7 Revision Number: 1 Date: 2/3/10 Developed =B.;::.er::...:,n:,::a:.:..;:rd=-=Li:.:;:tk;.;:.;::e:.:.;tt=--

______ 4/08/10 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Examiner Date SIM JPM S-7rev1.doc JOB PERFORMANCE MEASURE VALIDATION NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant. control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date ______ Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date ..IPM cover page. SIM JPM S-7rev1.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

1. Initialize the simulator to an IC-48 with the plant in Mode 3. 2. Copy of ST-5H; Rev.2; SRM Signal to Noise Ratio Determination Test (ST-5H); section 8.2. 3. Simulator Booth operator ensure remote RP-26 is installed on trigger #1. 4. Range IRM's. 5. Deselect SRMsIIRMs.

TASK STANDARD: Applicant is to perform SRM Signal to Noise Ratio Determination Test; ST-5H; Section 8.2 for SRM 'A'. TASK CONDITIONS:

1. The plant is in Mode 3. INITIATING You are the RO. The CRS directs you to perform the SRM Signal to Noise Ratio Determination ST-5H; Section 8.2 for SRM 'A'. The prerequisites steps 4.1 through 4.8 are completed and steps thru 8.2.4 have also been Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The timeclock starts when the applicant acknowledges the initiating cue. S/M JPM S-7rev1.doc 3 Operator's Name: ____---..._--- ___ Job Title: 0 NLO I RO I SRO DSTA o SRO Cert JPM Title: SRM Signal to Noise Ratio Determination Test; ST-5H JPM Number: S-7 Revision Number: 0 KIA Number and Importance: KA 215004; A4.07; 3.4; 3.6 Suggested Testing Environment: Simulator Actual Testing Environment: Testing Method: Perform in Simulator Alternate Path: No Time Critical: No Estimated Time to Complete: 20 min. Actual Time Used: ___,minutes

References:

1. NUREG 1123, KA 215004; A4.07; 3.4; 3.6 2. ST-5H; SRM Signal to Noise Ratio Determination Test; ST-5H; Section 8.2 for SRM 'A'. Rev.2 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Ves No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory 0 Unsatisfactory Comments:__________________________ _ Note: Any grade of UNSAT requires a Evaluator's Name: ______________Evaluator's Signature: Date: ____SIM JPM S-7rev1.doc 4

== Description:==

This JPM has the applicant perform the SRM Signal to Noise Ratio Determination Test; ST-5H; Section 8.2 for SRM 'A'. S/M JPM S-7rev1.doc 5 NRC JAMES A. FITZPA TRICK ILOT EXAMINA JPM S-7 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT 1. Obtain a controlled copy of procedure, ST-5H. 2. Reviews prerequisites, precautions, limitations and general test methods associated with the procedure.

3. Ensure SRM A may be fully withdrawn.

4. Ensure SRM A is fully inserted.

5. Ensure POWER ON light is on. 6. Declare SRM A inoperable EVALUATOR CUE: State as CRS 'A' SRM has been declared inoperable

7. Select SRM A. 8. Ensure SELECT lights are off for SRM B, C, and D. 9. Record SRM A initial count rate
10. Depress DRIVE OUT/DRIVING OUT pushbutton.

11. Verify DRIVE OUT light is on. 12. Verify DRIVING OUT light comes on. STANDARD SAT UNSAT Comment Number Applicant obtains a controlled copy of procedure and proceeds to the 09-12 panel in the Control Room. EVALUATOR:

A controlled copy of the procedure is available in the SM office. EVALUATOR CUE: All prerequisites, precautions, limitations are satisfied. Applicant ensures SRM A may be fully withdrawn. Applicant ensures SRM A is fully inserted. Applicant ensures POWER ON light is on. EVALUATOR CUE: State as CRS 'A' SRM has been declared inoperable Applicant selects SRM A. Applicant ensures SELECT lights are off for SRM B, C, and D. Applicant records SRM A initial count rate. cps. Applicant depresses DRIVE OUTIDRIVING OUT pushbutton. Applicant verifies DRIVE OUT light is on. Applicant verifies DRIVING OUT light is on. S/M JPM S-7rev1.doc 6 NRC JAMES A. FITZPA TRICK ILOT EXAMINAELEMENT

13. When SRM OUT indicating comes on, depress OUT/DRIVING OUT EVALUATOR NOTE 1. 09-5-2-21 SRM DET RETRACTED WHEN NOT PERMITTED will annunciate when SRM count rate drops below 100 cps. This alarm is expected for this condition.

2. Takes 3.5 minutes for SRM to drive out. Cue: if applicant does not report that the alarm is expected, then ask if this alarm is expected?

If answer is no then ask how to determine if the alarm is an expected alarm. If applicant can not determine that the alarm is expected then direct applicant to proceed with ST. If answer is yes then direct applicant to proceed with ST. 14. Verify the following lights are off:

DRIVE OUT
DRIVING OUT
15. Record SRM A Fu" Out
16. Depress DRIVE IN pushbutton

17. Verify top half of DRIVE IN light is on. 18. Verify bottom half of DRIVE IN light comes on. SIM JPM S-7rev1.doc STANDARD SAT Applicant depresses OUT/DRIVING pushbutton, when SRM indicating light comes EVALUATOR NOTE 1. 09-5-2-21 SRM RETRACTED WHEN PERMITTED annunciate when count rate drops below cps. This alarm is for this

2. Takes 3.5 minutes for to drive Cue: if applicant does report that the alarm expected, then ask if alarm is expected?

If is no then ask how determine if the alarm is expected

If applicant can not determine that the alarm is expected then direct applicant to proceed with ST. If answer is yes then direct applicant to proceed with ST. Applicant verifies the following lights are off:
DRIVE OUT
DRIVING OUT Applicant records SRM FULL OUT count Applicant depresses DRIVE Applicant verifies top half DRIVE IN light is Applicant verifies bottom of DRIVE IN light comes JPM UNSAT Comment Number 7 NRC JAMES A. FITZPA TRICK ILOT EXAMINA JPM ELEMENT
19. When SRM IN indicating light comes on, depress DRIVE IN pushbutton.

EVALUATOR Takes 3.5 minutes for SRM to drive

20. Verify DRIVE IN light is off
21. Deselect SRM A 22. Verify SRM A light is off.
23. Calculate signal to noise ratio for SRM A as follows: ( ) I = -8.2.11 8.2.17 8.2.17 TS > 2 24. Consider declaring SRM A operable.

EVALUATOR CUE: Applicant should state the status of SRMA. Applicant depresses DRIVE IN pushbutton, When SRM IN indicating light comes on. EVALUATOR NOTE Takes 3.5 minutes for SRM to drive in. Applicant verifies DRIVE IN light is off Applicant deselects SRM A Applicant verifies SRM A light is off. Applicant calculates signal to noise ratio for SRM A as follows: ( ) I = -8.2.11 8.2.17 8.2.17 TS>2 SAT UNSAT Comment Number EVALUATOR: Terminate the task at this point. JPM Stop Time _____ SIM JPM S-7rev1.doc 8 NRC JAMES A. FITZPA TRICK ILOT EXAMINA TlON JPM S-7 HANDOUT PAGE TASK CONDITIONS:

1. The plant is in Mode 3. INITIATING CUE: You are the RO. The eRS directs you to perform the SRM Signal to Noise Ratio Determination Test; 5H; Section 8.2 for SRM 'A'. The prerequisites steps 4.1 through 4.8 are completed and steps 8.2.1 thru 8.2.4 have also been completed.

SIM JPM S-7rev1.doc --James A. Fitzpatrick Generating Station Job Performance Perform RPV Isolation During Plant JPM Number: 8*8 Revision Number: 1 Date: 1/15/10 Developed Bernard litkett 4/08/10 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Examiner Date SIM JPM S*8rev1.doc JOB PERFORMANCE MEASURE VALlDA"nON CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When ,JPM is revalidated, Examiner sign and date JPM cover page. S/M JPM S-8rev1.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

1. Initialize the simulator to IC-48, full power. 2. Manually scram the Reactor and stabilize vessel level and pressure.

3. Manually override activate the Reactor Building West Crescent indication on the fire panel; 227' RCIC RM SD to ON. 4. Manually override start the fire pump. 5. Manually override the RCIC HOV-1 trip pushbutton so the valve will not trip. Override to normal. 6. When contacted to open breaker 71 BCB-2A-B05, Insert Malfunction RC03; Trigger 1. 7. Have 'A' Core Spray running with HS green flagged. 8. PRESET: M:CU10,RWCU 12MOV-18 Auto isolation failure. TASK STANDARD:

Successfully perform RPV isolation during Plant Fire TASK CONDITIONS:

1. A serious fire in the Reactor Building West Crescent has been confirmed by the Fire Brigade. 2. The Reactor has just been scrammed from rated power. 3. The CRS has determined that RPV isolation is desired. 4. A spurious start of 'A' Core Spray pump has occurred.

INITIATING CUE: You are the RO, The CRS directs you to perform the override actions of AOP-28 for a fire in the Reactor Building West Crescent Area. Another operator will handle the balance of plant. Information for Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this ...IPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. SIM JPM S-Brev1.doc 3 The timeclock starts when the applicant acknowledges the initiating cue. SIM JPM S-Brev1.doc 4 ____ _ Operator's Name: ------...__--- ___ Job Title: D NLO I RO I SRO DSTA D SRO Cert JPM Title: Perform RPV Isolation during plant fire JPM Number: S-8 Revision Number: 0 KIA Number and Importance: KA 286000; A4.05; 3.3; 3.3 Suggested Testing Environment: Simulator Actual Testing Environment: Testing Method: Perform in Simulator Alternate Path: No Time Critical: No Estimated Time to Complete: 15 min. Actual Time Used: ___m,inutes

References:

1. NUREG 1123, KA 286000 A4.05 3.3; 3.3 2. AOP-28, Operation During Plant Fires, Rev. 18 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? Yes No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: D Satisfactory Unsatisfactory Comments:__________________________

_ Note: Any grade of UNSAT requires a Evaluator's Name: _____________Evaluator's Signature: Date: SIM JPM S-8rev1.doc 5

== Description:==

This JPM has the operator perform RPV Isolation during Plant Fire SIM JPM S-8rev1.doc 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA JPM 8-8 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST: JPM Start Time _____ ELEMENT 1. Obtain a controlled copy of procedure AOP-28, Operation During Plant Fires. 2. Select the correct attachment perform the

3. Close CLN UP SUCT 12MOV-18.

4. Ensure close OUTBD STM VLV

5. Close STM LINE WARMING VLV 23MOV-60
6. Close Outboard MSIVs *7. Ensure closed 13MOV-16 in drywell entrance.

8. Attempt to trip TURB STOP VL 13HOV-1 at panel STANDARD SAT UNSAT Comment Number Obtains a controlled copy of AOP-28. Applicant selects Attachment 2, Step 1.1 of AOP-28 by referencing attachments 27,28 and 29. Applicant closes CLN UP SUCT 12MOV-18 by placing associated control switch on Panel 09-3 in the CLOSE position.

Applicant verifies closed 23MOV-16. Applicant closes 23MOV-60 by placing associated control switch on panel 09-3 in the CLOSE position. Applicant closes outboard MSIVs by placing associated control switches (4) on panel 09-3 in the CLOSE position. Applicant closes 13MOV-16 by placing associated control switch on Panel 09-4 in the CLOSE position. Applicant attempts to trip 13HOV-1 by depressing red TURBINE TRIP pushbutton 13A-S 17 09-4. If 13HOV-1 fails to close then perform step 9 and 10 .. 81M JPM 8-8rev1.doc 7 NRC JAMES A. FITZPA TRICK INITIAL

9.0pen breaker DC MOTOR CONTROL CENTER 71 BCB-2A-B05, (71 BMCC-1) at 71 BCB-2A in Station Battery Charger Room A. EVALUATOR:

INSERT Malfunction RC03, Role playas in-plant operator and report 71 BCB-2A-B05, (71 1) at 71 BCB-2A has been opened. 10. Ensure closed, manually if required, 13MOV-16 in drywell entrance. STANDARD Contacts in-plant operator using Gaitronics or other acceptable method and directs operator to open breaker 71 BCB-2A-B05, (71 BMCC-1) at 71 BCB-2A in Station Battery Charger Room A. EVALUATOR: INSERT Malfunction RC03, Role play as in-plant operator and report 71 BCB-2A-B05, (71BMCC-1) at 71 BCB-2A has been opened. Contacts in-plant operator using Gaitronics or other acceptable method and directs operator to ensure closed 13MOV-16. JPM S-8 SAT UNSAT Comment Number EVALUATOR: Terminate the task at this point. JPM Stop Time _____ S/M JPM S-8rev1.doc 8 NRC JAMES A. FITZPA TRICK INITIAL JPM S-8 HANDOUT PAGE TASK CONDITIONS:

1. A serious fire in the Reactor Building West Crescent has been confirmed by the Fire Brigade. 2. The Reactor has just been scrammed from rated power. 3. The CRS has determined that RPV isolation is desired. 4. A spurious start of 'A' Core Spray pump has occurred.

INITIATING CUE: You are the RO, The CRS directs you to perform the override actions of AOP-28 for a fire in the Reactor Building West Crescent Area. Another operator will handle the balance of plant. SIM JPM S-8rev1.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINA Job Performance Measure Changing In-service CRD Pump Suction Filters JPM Number: P-1 Revision Number: 1 Date: 1/15/10 Developed By: Bernard Litkett 1/15/10 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Examiner Date Plant JPM P-1.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM P-1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date ______ Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Review Questions and Comments:

Plant JPM P-1. doc 2 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA JPM P-1 REVISION RECORD (Summary):

1. None JPM Setup Instructions:

1. Copy of procedure OP-25; Rev. 79;section G.11 Tools and Equipment

1. None TASK STANDARD:

Successfully swap in-service CRD suction filters TASK CONDITIONS:

1. The plant is at 100% power. 2. The in-service CRD pump suction filter indicates 1 psid on 03PIS-246.

INITIATING CUE: You are directed to change the in-service CRD pump suction filter. Information For Evaluator's Use: UNSAT requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this ..IPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The time clock starts when the applicant acknowledges the initiating cue. Plant JPM P-1 . .doc 3 ---NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM P-1 Operator's Job Title: NLO [IISRO DSTA D SRO JPM Title: Successfully swap in-service CRD suction filters JPM Number: P-1 Revision Number: 1 KIA Number and Importance: KA 201001 A2.06; 2.9; 2.9 Suggested Testing Environment: Plant Actual Testing Environment: Plant Testing Method: Simulate Alternate Path: No Time Critical: No Estimated Time to Complete: 15 Actual Time Used: minutes

References:

1. NUREG 1123, KA 201001 A2.06; 2.9; 2.9 2. OP-25; Rev. 79;Section G.11 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes 0 No 2. Was the task standard The operator's performance was evaluated against the standards contained in this JPM, and has determined to be: Satisfactory Comments:__________________________Note: Any grade of UNSAT requires a Evaluator's Name: _____________Evaluator's Signature: Date: ____Plant JPM P-1.doc 4 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM P-1

Description:

This JPM has the applicant place the standby CRD suction filter in service and isolate the previously in-service filter. Plant JPM P-1.doc 5 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM P-1 NOTE: Critical Element(s) indicated by

in Performance Checklist.

JPM Start Time _____ ELEMENT Obtain a controlled copy of procedure OP-25; REV.79; G.11, changing in-service CRD suction filter Select the correct section to perform the task. Applicant notifies control room that suction filter will Applicant notifies Radiation Protection that potentially radioactive water will be vented from the CRD pump suction filter.

5. Perform the following the filter to be placed a.) Verify open isolation 03CRD-151A (CRD water pump 'A' Suct filter 'A' inlet isol valve) or 03CRD-151B (CRD water pump 'B' Suct filter 'B' inlet isol valve) Plant JPM P-1.doc PERFORMANCE CHECKLIST:

STANDARD SAT UNSAT Comment Number The applicant determines where to obtain a controlled copy OP-25; Rev. 79;G.11, changing CRD suction filters EVALUATORj Provide trainee a current copy of OP-25 Selects section G.11 from OP-25; REV.79. EVALUATOR: Provide applicant with copy of section G.11. Applicant notifies the control room that CRD suction filter will be changed. Applicant notifies Radiation Protection that potentially radioactive water will be vented from the CRD pump suction filter. Applicant opens inlet isolation valve. 03CRD-151 A (CRD pump 'A' Suct filter 'A' isol or 03CRD-151B (CRD pump 'B' Suct filter 'B' isol Cue: After correct operation is simulated, inform applicant that handwheel turns several rotations in CCW direction, then hits a hard stop. 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ELEMENT

5b. Crack open vent valve:
03CRD-400A (CRD water pump 'A' suct filter 'A' vent valve or
03CRD-400B (CRD water pump 'B' suct filter 'B' vent valve
5c. When water flowing from the vent is free of air, close the vent valve.
5d. Slowly open outlet isolation valve: 03CRD-152A (CRD water pump 'A' suct filter 'A' outlet isol valve) or 03CRD-152B (CRD water pump 'B' suct filter 'B' outlet isol valve) JPM P-1 STANDARD SAT UNSAT Comment Number Applicant cracks open:
03CRD-400A (CRD pump 'A' suct filter 'A' or
03CRD-400B (CRD pump 'B' suct filter 'B' EVALUATOR CUE: Valve is cracked open, water is flowing free of air from the vent. Applicants closes the vent valve when the water flowing is free of air. EVALUATOR CUE: Valve is closed. Applicant slowly opens outlet isolation valve. 03CRD-152A (CRD water 'A' suet filter 'A' outlet isol or 03CRD-152B (CRD water 'B' suct filter 'B' outlet isol EVALUATOR CUE: After correct operation is simulated, inform applicant that handwheel turns several rotations in CCW direction, then hits a hard stop. Plant JPM P-1.doc 7 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM P-1 ELEMENT STANDARD SAT UNSAT Comment Number
6. Close outlet isolation Applicant closes outlet isolation valve. valve for the filter to be removed from service
03CRD-152A (CRD water pump 'A' suct filter 'A' outlet isol valve) or
03CRD-152B (CRD water pump 'B' suct filter 'B' outlet isol valve) EVALUATOR CUE: After correct operation is simulated, inform applicant that handwheel turns several rotations in CW direction, then hits a hard stop. EVALUATOR:

Terminate the task at this point JPM Stop Time _____ Plant JPM P-1. doc 8 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM P-1 HANDOUT PAGE TASK CONOrnONS:

1. The plant is at 100% power. 2. The in-service CRD pump suction filter indicates 1 psid on 03PIS-246.

INITIATING CUE: You are directed to change the in-service CRD pump suction filter. Plant JPM P-1.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Job Performance Measure EOP Isolation Interlock Overrides -HPCI System Isolation Valves on Low Steam Supply Pressure JPM Number: P-2 Revision Number: NRC 2010 Date: 1/14/10 Developed ...;;B:;.;:e:;.;..r.;.;.na;;;;.;r:..;:;:d;..:L=it=k=e=tt _______ Author Validated Facility Representative Review Examiner Approved Chief Examiner Plant JPM P-2.doc NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM P-2 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate "IPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date ______ Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Review Questions and Comments:

Plant JPM P-2.doc 2 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM P-2 REVISION RECORD (Summary): None JPM Setup Instructions: Performance of this JPM shall be simulated. Inadvertent manipulation of a component could result in unwanted system actuations. When opening cabinets with energized equipment inside, ensure appropriate requirements are Make a copy of EP-2; Section 5.8 for use by applicant. Obtain Shift Manager approval prior to entering panel 09-32 and 99-39. TOOLS AND EQUIPMENT: Screwdriver/Nutdriver (JPM is to be simulated) TASK STANDARD: Install EOP Isolation Interlock Overrides -HPCI System Isolation Valves on Low Steam Supply Pressure TASK CONDITIONS: Emergency depressurization has been ordered due to high secondary containment (EOP-5), but only 3 SRV's can be The SM has issued direction to override the HPCI System low steam pressure isolation interlock to allow use of HPCI to rapidly depressurize the RPV lAW EOP-2. INITIATING CUE: You are the RO. The CRS directs you to override the isolation on low steam supply pressure for the HPCI System per EP-2, Isolation/Interlock Overrides. Information For Evaluator's Use: UNSA T requires written comments on respective step.

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The timeclock starts when the applicant acknowledges the initiating cue. Plant JPM P-2.doc 3 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM P-2 Operator's Name: _______________________ _ Job Title: NLO IRO ISRO DSTA SRO Cert JPM Title: EOP Isolation Interlock Overrides -HPCI System Isolation Valves on Low Steam Supply Pressure JPM Number: P-2 Revision Number: NRC 2010 KIA Number and Importance: KA 206000; A2.10; 4.0; 4.1 Suggested Testing Environment: Plant Actual Testing Environment: Plant Testing Method: Simulate Alternate Path: No Time Critical: No Estimated Time to Complete: 15 Actual Time Used: minutes

References:

1. NUREG 1123, 206000 A2.1 0; 4.0; 4.1 2. EP-2; Section 5.8; HPCI Steam Supply Valves -Low Steam Supply Pressure Isolation, Rev 7 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

0 Yes No 2. Was the task standard The operator's performance was evaluated against the standards contained in this JPM, and has determined to be: C Satisfactory Cornments: __________________________Note: Any grade of UNSAT requires a Evaluator's Name: _____________Evaluator's Signature: Date: ____Plant JPM P-2.doc 4 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA JPM P-2

Description:

This JPM has the applicant defeat HPCI System Isolation on Low Steam Supply Pressure Plant JPM P-2.doc 5 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION JPM P-2 NOTE: Critical Element(s) indicated by

in Performance Checklist.

JPM Start Time _____ ELEMENT 1. Obtain a controlled copy of procedure EP-2, Isolationllnterlock Overrides

2. Select the correct section to perform the task.

3. For 23MOV-15, disconnect lead from one of the following terminals in panel 09-32: L) L) 4. Initials for lifting lead.
5. For 23MOV-16 and 60, disconnect lead from one of the following terminals in panel 39: L) L) 6. Initials step for lifting lead. 7. Contact the Control and inform them that the steam pressure isolation been overridden per JPM Stop Time _____ Plant JPM P-2.doc PERFORMANCE CHECKLIST:

STANDARD SAT UNSAT Comment Number The applicant determines where to obtain a controlled copy of EP-2. (EOP supply cabinet, Control Room, Merlin) EVALUATORj Provide trainee a current copy of EP-2 Selects section 5.8 from EP-2. EVALUATOR: Provide applicant with copy of section 5.8. EVALUATOR: When the applicant proceeds to panel 09-32 in the Relay Room and locates and identifies terminals and states that he/she would disconnect a lead from either terminal TBC-5 or TBC-7, then inform the applicant "Lead disconnected". Initials block for lifting lead from terminal. EVALUATOR: When the applicant proceeds to panel 09-39 in the Relay Room and locates and identifies terminals and states that he/she would disconnect a lead from either terminal 00-17 or 00-18, then inform the applicant "Lead disconnected". Initials block for lifting lead from terminal. EVALUATOR: Acknowledge the communication as the CRS. EVALUATOR: Terminate the task at this point. 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM P-2 HANDOUT PAGE TASK CONDITIONS: Emergency depressurization has been ordered due to high secondary containment temperature (EOP-5), but only 3 SRV's can be opened. The SM has issued direction to override the HPCI System low steam pressure isolation interlock to allow use of HPCI to rapidly depressurize the RPV lAW EOP-2. INITIATING CUE: You are the RD. The CRS directs you to override the isolation on low steam supply pressure for the HPCI System per EP-2, Isolation/Interlock Overrides. Plant JPM P-2.doc NRC JAMES A. FITZPA TRICK INITIAL Job Performance Measure Alternate Depressurization Using SRVs From Panel 02ADS-71 JPM Number: Revision Number: Date: Developed :...:B::;.;:e:;.:.rn:.:;a::.:;r-=d:...:L::.:.,it::,:k:.:,ett=- ______ 1/19/10 Author Date Validated By: Facility Representative Date Review By: Examiner Date Approved By: Chief Examiner Date Plant JPM P-3.doc NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPMP-3 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by Examiner review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date ______ Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM. 11. When JPM is revalidated, Examiner sign and date JPM cover page. Review Questions and Comments:

Plant JPM P-3.doc 2 NRC JAMES A. FITZPATRICK INITIAL EXAMINA JPM P-3 REVISION RECORD (Summary): None JPM Setup Instructions: EP-11 ;Rev.1 , Alternate depressurization using SRVs from 02ADS-71 Obtain Shift Manager's permission prior to performing this task. Ensure Control Room is aware that the door to the remote ADS panel will be opened. TOOLS AND EQUIPMENT: Key for Remote ADS Cabinet 02ADS-71 is located in equipment cabinet near Remote Shutdown Panel 25RSP, RB 300 el., north. Key to access equipment cabinet near Remote Shutdown Panel 25RSP, RB 300 el., north. TASK STANDARD: Successfully perform alternate depressurization using SRVs from panel 02ADS-71 TASK CONDITIONS: Torus water level is 13.9 feet The Shift Manager has identified the need to use the remote ADS cabinet depressurize the RPV,per EP-11; No SRVs have been opened from the Control Room. INITIATING CUE: You are the RO. The CRS has directed you to emergency depressurize the RPV per EP-11. Information For Evaluator's UNSAT requires written comments on respective

Denotes CRITICAL steps. Number any comments in the "Comment Number" column. 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 and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the applicant to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed. The time clock starts when the applicant acknowledges the initiating cue. Plant JPM P-3.doc 3 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM Operator's Name: _______________________ _ Job Title: 0 NLO IRO STA SRO Cert JPM Title: Perform alternate depressurization using SRVs from panel 02ADS-71 JPM Number: P-3 Revision Number: 1 KIA Number and Importance: NUREG 1123,239002 A2.04; 4.1; 4.2 Suggested Testing Environment: Plant Actual Testing Environment: Plant Testing Method: Simulate Alternate Path: No Time Critical: No Estimated Time to Complete: 15 Actual Time Used: ---minutes

References:

1. NUREG 1123; 239002 A2.04; 4.1; 4.2 2. EP-11; Rev. 1; Use the remote ADS cabinet 02ADS-71 to depressurize the RPV EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily?

Yes [J No 2. Was the task standard met? The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory Unsatisfactory Comments:__________________________ _ Note: Any grade of UNSAT requires a Evaluator's Name: _____________ (, Evaluator's Signature: Date: ____Plant JPM P-3.doc 4 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM

Description:

This JPM has the applicant perform an emergency depressurization lAW EP-11. Plant JPM P-3.doc 5 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM P-3 NOTE: Critical Element(s) indicated by'" in Performance Checklist. JPM Start Time _____ ELEMENT Obtain a controlled copy of procedure Reviews associated with Torus water level shall be greater than or equal to 5.5 feet to open an SRV. Opening an SRV with Torus water level less than 5.5 feet will cause direct pressurization of the containment and possible containment damage. Reviews associated with Performance of procedure has directed by the EOPs Reviews special instructions associated with the procedure Tools and materials for this procedure are located in the equipment cabinets near Remote Shutdown Panel 25RSP and panel 71. Notify RES prior to entering the RB due to potentially changing radiation conditions. PERFORMANCE CHECKLIST: STANDARD Obtains a controlled copy of Applicant reviews applicable of the procedure and verifies water level is > 5.5 EVALUATOR CUE: When requests information regarding water level, inform applicant level greater than 13.9 Applicant reviews applicable of the Applicant reviews applicable of the SAT UNSAT Comment Number Plant JPM P-3. doc 6 NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Establish communications between the Control Room and ADS RELIEF VALVE CONTROL PANEL 71. Verify the following control switches are in SOL DEENG at panel 71: ADS &SRV 02RV-71C SRV 02RV-71 F SRV 02RV-71J SRV 02RV-71L ADS & SRV 02RV-71 B ADS & SRV 02RV-71 E ADS & SRV 02RV-71 H SRV 02RV-71K ADS & SRV 02RV-71A ADS & SRV 02RV-71D ADS & SRV 02RV-71G

7.Place CONTROL POWER breaker in ON at panel 02ADS-71. Verify in the control room, annunciator 09-4-3-3 ADS REMOTECNTRLPNLBKR CLOSED is in alarm. STANDARD SAT JPM P-3 UNSAT Comment Number Applicant proceeds to RB 300 el. and establishes communications.

EVALUATOR CUE: Inform applicant that communications have been established and you will respond as control room operator. Applicant verifies the control switches are in SOL DEENG. EVALUATOR CUE: When applicant identifies the switches, inform applicant that switches are in SOL DEENG. Applicant places CONTROL POWER breaker in ON. EVALUATOR CUE: When applicant requests information regarding response, inform applicant that control power is ON. Applicant verifies the alarm has actuated. EVALUATOR CUE: When applicant requests, inform applicant that alarm has actuated. Plant JPM P-3.doc 7 NRC JAMES A. FITZPATRICK INITIAL EXAMINA ELEMENT WHILE performing Step 5.1.7, monitor the following to verify SRV operation: Annunciator 09-4-2-6 SRV SONIC MON ALARM HI ADS & SRV ACOUSTIC MONITOR 02VMR-071 at panel 09-4 White light at SRV control switch at panel 09-4 Red SOL ENGD and green SOL DE ENG lights at panel 02ADS-71 10.IF torus water level is LESS THAN 5 .. 5 feet, THEN perform the following: Notify SM or CRS that SRVs cannot be opened. Restore panel 02ADS-71 per subsection 5.2.

11. Place one or more of the following control switches in SOL ENGD at panel 71, as necessary to establish seven SRVs open: ADS & SRV 02RV-71C SRV 02RV-71 F SRV 02RV-71J SRV 02RV-71L ADS & SRV 02RV-7'IB ADS & SRV 02RV-71E ADS & SRV 02RV-71H SRV 02RV-71 K ADS & SRV 02RV-71A ADS & SRV 02RV-7'ID ADS & SRV 02RV-71G STANDARD Applicant verifies each of the indications while performing Step 11 of this JPM (Procedure step 5.1.7). SAT JPM P-3 UNSAT Comment Number EVALUATOR CUE: When applicant requests each SRV indication, inform applicant that each has occurred.

Applicant verifies that torus water level is >5.5 ft. EVALUATOR CUE: When applicant verifies the torus water level, inform applicant that level is 13.9 ft. Applicant opens seven SRVs. EVALUATOR CUE: When applicant indicates the switch for opening an SRV, inform applicant that SRV has opened. Plant JPM P-3.doc 8 NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPMP-3 ELEMENT STANDARD SAT UNSAT Comment Number

12. IF any SRV was opened Applicant closes the door and Control from panel 02ADS-71, THEN room notified.

perform the Close and lock panel

EVALUATOR CUE: Acknowledge Notify Control Room.
when applicant informs the control
Do not perform subsection room. 5.2 until directed by the SM Subsection 5.2 is the restoration or CRS. section. EVALUATOR:

Terminate the task at this pOint. JPM Stop Time _____ Plant JPM P-3.doc 9 NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION JPMP-3 HANDOUT PAGE TASK CONDITIONS: Torus water level is 13.9 feet. The Shift Manager has identified the need to use the remote ADS cabinet 02ADS-71 to depressurize the RPV per EP-11. No SRVs have been opened from the Control Room. INITIATING CUE: You are the RO. The CRS has directed you to emergency depressurize the RPV per EP-11. Plant JPM P-3.doc Appendix Scenario Outline Form ES-D-1 Facility: Fitzpatrick Scenario No.: Op-Test No.: 1 Operators: Initial Conditions: Reactor startup is in progress with power at 90%. SWS pumps 46P-1A and 46P-1B are in service with 46P-1C in standby. Turnover: Continue power ascension to 100% lAW RAP-7.3.16. Maintenance is required on 46P-1A. Place 46P-1C in service. Event Malt. No. Event No. Type'"

1. N-SNO Swap SWS pumps. Place 46P-1C in service and remove 46P-1A. N/A R-SNO Raise power to 100% power using Rx 3. 'A' Recirc Flow unit failure. TS call4. RR19:S TS-CRS Upscale failure of 06L T -52S; FWLC level transmitter.

TS call R-ATC 5. Trip of'S' RFPT; Rx Recirc runbacks to 44% speed. C-SN02 RR15:A Coolant leakage inside primary containment. Defeat Auto Scram 6. M-ALL Loss of offsite AC power. Failure of 'A' and 'C' EDG output M-ALL breakers to close. 8. I AD07:A C-SN02 'A' ADS fails to open * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, {M)ajor NRC Scenario #1 -2010 Fitzpatrick Operating Page 1 of 29 Appendix 0 Required Operator Actions Form ES-O-2 SCENARIO

SUMMARY

Shift orders are to swap SWS pumps. Place 46P-1C in service and remove 46P-1A from service. As part of turnover the crew is directed to raise power to 100% using recirc flow. Initial condition. 90% Continue with startup. OP-65 Startup and Shutdown procedure; step 0.24.18. The 'A' Recirc flow unit will fail downscale. This instrument failure should result in a half scram condition. The SRO must assess Tech Spec for the failed flow unit TIS 3.3.1.1 for RPS and TIS SN02 will be required to bypass the 'A' Flow unit in order to reset the half scram. The FWLC level transmitter 06LT-52B will fail upscale. Reactor feedwater controls will respond as though vessel level has increased and immediately begin to reduce feedwater flow to the RPV. The SRO must assess Tech Spec for the failed transmitter. TIS 3.3.2.2 Feedwater and Main Turbine High Water Level Trip instrumentation 'B' RFPT will trip causing a recirc runback to 44% speed, power reduction and the ATC to insert cram rods to exit buffer zone. A medium size LOCA will begin and progress. Drywell temperature and pressure will be rising requiring a manual scram. The auto scram functions are defeated. Upon the scram a Loss of offsite AC power will occur and the 'A' and 'C' EDG output breakers will fail to close potentially causing a challenge to ECCS systems operability. As the LOCA size increases RPV water level will continue to lower requiring emergency depressurization. The ADS auto initiation function is defeated. When 7 ADS valves are open, the 'A' ADS valve will fail closed, requiring another SRV to be opened. The scenario will be terminated when reactor level is being controlled in band using Low pressure ECCS pumps. !\IRC Scenario #1 -2010 Fitzpatrick Operating Test Page 2 of 29 Appendix Required Operator Actions Form ES-D-2 INITIAL SIMULATOR SETUP ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION Reset simulator to Protected IC -43

Apply Information Tags on the following

-Take out of FREEZE and ensure the following: -46P-1A and 46P-1 B; SWS pumps are in service -Service Water Pump 46P-1C is powered from the 10700 bus and will not be available when Normal Station Service Transformer T-4 is de-energized -'A' EHC regulator is in control.

Ensure materials for applicants:

-OP-65; Startup and Shutdown procedure. Marked up to step D.24.18 -OP-42 : SWS; Marked up to step D.5 -OP-27; RWR system -RAP-7.3.16 plant power ascension with recirc -Reactivity maneuvering sheet

Ensure the following malfunctions are -RR23:A; 'A' Recirc Flow unit failure; trigger 1; severity -RR19:B; Upscale failure of 06L T-52B; FWLC level transmitter; trigger 2; severity 100%. -FW01 :B; 'B' RFPT trip; trigger 3 -RR15:A; Coolant leakage inside primary containment; trigger 4, initial severity at 2 % with ramp 20 min, final severity 40%. -RP01AA; 'A' RPS Auto scram failure; trigger 7 -RP01AB; 'B' RPS Auto scram failure; trigger 7 -ED43:A and B; Loss of offsite AC power; trigger 5; Manual trigger 4 minutes after DIW pressure of 2.7 psig. -DG03:A;failure of 'A' EDG output breaker to close: PRESET -DG03:C;failure of 'C' EDG output breaker to close: PRESET -AD07:A : PRESET -AD03:A,B,C,D,E,F,G:

PRESET

Ensure the following remote functions are -Ensure the following overrides are loaded: None -HPZDI23AS19-HPCI turbine trip trigger 6. Insert 60 seconds after restoring HPCI injection.

-Remove malfunction AD03:A,B,C,D,E,F and G when ADS is overridden. Ensure the following triggers are built: NRC Scenario #1 -2010 Fitzpatrick Operating Page 3 of 29 Appendix D Required Operator Actions Form ES-D*2 ./ ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION -trigger 1; RR23:A; 'A' Recirc Flow unit failure -trigger 2; RR19:B; Upscale failure of 06l T-52B; FWlC level transmitter -trigger 3; FW01 :B; 'B' RFPT trip. -trigger 4; RR15:A ; Severity initial 2% with ramp to 100% severity over 20 minutes, final severity 40%. -trigger 5; ED43:A and ED43:B. Manual trigger 4 minutes after Drywell pressure reaches 2.7 psig. -Trigger 7; RP01AA and RP01AB. 'A' and 'B' Auto scram failure.

Reset any annunciators that should not be present NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 4 of 29 Appendix 0 Required Operator Actions Form ES*D*2 INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1: Swap SWS pumps. Place 46P*1C in service and remove 46p*1A .;' MALFUNCTION I REMOTE FUNCTION I REPORT
Place 46P-1C in service and remove 46P-1A from service; per OP-42;step G.1 for Startup of third SWS pump. Changing SW8 pump lineup.
Respond as NPO during SWS pump swap EVENT 2: Raise power to 100% using Rx Recirc .;' MALFUNCTION I REMOTE FUNCTION I REPORT
Continue power ascension with Rx Recirc lAW RAP-7.3.16 , OP-27and 65
At the discretion of the Chief examiner after observing a rise in Reactor power, move to the next event.
Respond to request for assistance as appropriate.

EVENT 3: 'A' Recirc Flow unit failure .;' MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 1 after events 1 and 2 are completed
Respond to request for assistance as appropriate.

EVENT 4: Upscale failure of 06L T -528; FWLC level transmitter .;' MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 2 after T8 call has been made or at discretion of lead examiner.
Respond to request for assistance as appropriate.

EVENT 5: '8' RFPT trip ./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 3 after TS call has been made or at discretion of lead examiner.
Respond to request for assistance as appropriate.

NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 5 of 29 Appendix Required Operator Actions Form ES-D-2 EVENT 6: Coolant leakage inside primary containment ./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 4 and trigger 7 after actions are
Auto RPS scram failure on 'N and 'B'
Respond to request for assistance as EVENT Loss of Offsite AC power and failure of 'A' and 'c' EDG output breakers to close. MALFUNcnON I REMOTE FUNcnON I REPORT
Manually activate trigger 5 ; 4 minutes after Drywell pressure reaches 2.7 pSig.
PRESET malfunction, DG03:A and
Trigger 6; HPCI trip insert 60 seconds after restoring HPCI
Respond to request for assistance as EVENT 8: Emergency RPV Depressurization

./ MALFUNCTION I REMOTE FUNCTION I REPORT

When RPV level can not be maintained above -19 inches
Respond to request for assistance as appropriate.

EVENT 9: 'A' ADS fails to open ./ MALFUNcnON I REMOTE FUNcnON I REPORT

PRESET malfunction AD07:A
Delete PRESET malfunctions AD03:A,B,C,D,E,F,G after ADS has been inhibited.
Respond to request for assistance as appropriate.

NRC Scenario #1 -2010 Fitzpatrick Operating Page 6 of 29 Appendix Required Operator Actions Form ES-D-2 CRITICAL TASKS EOP-2: Scrams the reactor prior to 5 psig Drywell pressure with auto RPS scram defeated. Expected action to occur when Drywell pressure is > 2.3 psig lAW OPG-13; Transient Mitigation. Basis: The scram reduces the rate of energy production and thus the rate of drywell leakage. Basis from MIT-301.11C; EOP-2 basis 2. Perform Emergency RPV Depressurization. Before RPV water level reaches -19 inches; Emergency de-pressurizes per EOP-2, open 7 ADS valves. If an injection source is available but the decreasing RPV water level trend cannot be reversed before RPV water level drops to the Minimum Steam Cooling RPV Water Level, a blowdown is performed to permit injection from low head systems, maximize flow from available injection sources, and minimize the flow through any primary system break. Basis from MIT-301.11 C ; EOP-2 basis for Emergency RPV depressurization. SHIFT TURNOVER NRC Scenario #1 -2010 Fitzpatrick Operating Page 7 of 29 Appendix Required Operator Actions OFF GOING SHIFT D 0 N DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift. Control Panel Walkdown (all panels) (SM,CRS,STA,RO,SN02) PART II: To be reviewed by the oncoming Operator before assuming the shift. Shift Manager Log (SM,CRS,STA) RO Log (RO) Lit Control Room Annunciators (SM,CRS,STA,RO, SN02) Shift Turnover Checklist (ALL) LCO Status (SM,CRS,STA) Computer Alarm Summary (RO) Evolutions/General information/Equipment Status: Plant startup in progress from a refuel Plant is at approximately 90% PART III: Remarks/Planned Evolutions: Swap SWS pumps. Place 46P-1 C in service and remove 46P-1 A from service following pump swap. Continue power ascension to 100% power lAW RAP-7.3.16, OP-27 and OP-65 using Recirc. PART IV: To be reviewed/accomplished shortly after assuming the shift: Review new Clearances (SM) Shift Crew Composition (SM/CRS) Test Control Annunciators (SN02) TITLE NAME TITLE NAME SRO ATC SN02 NRC Scenario #1 -2010 Fitzpatrick Operating Page 8 of 29 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _1_ Event Event

Description:

Swap SWS pumps. Place 46P-1C in service and remove 46P-1A from Time Position Applicant's Actions or Behavior CRS Orders SN02 to start 46P-1 C per OP-42 and remove 46P-1 A from service. Note 1: OP-42; section G.1 Informs Chemistry that SWS pumps will be swapped to 46P-1 Band SN02 46P-1 C pumps in service. Coordinate with NPO to monitor SWS pump swap and screen wash SN02 booster pump alignment. SN02 Starts 46P-1C by placing pump to start Note 2: OP-42 contains tap changer steps for adjusting 12500 bus voltage. This may be done Sim Respond as NPO that 46P-1 C pump start is SAT. Booth Operator SN02 Remove 46P-1A from service by placing pump to stop. Note 3: Reduce voltage on 12500 Examiner Note: Proceed to the next event NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 9 of 29 I Appendix Required Operator Actions Form ES-D*2 Op-Test No.: Event Time Position CRS CRS SN02 ATC Scenario No.: _1_ Event No.: _2_ Raise Reactor Power with recirc lAW RAP-7.3.16; OP-27 and OP-65 Applicant's Actions or Behavior If not already performed, CRS conducts reactivity brief on raising Reactor Power with recirc lAW RAP-7.3.16; OP-27; and OP-65. Reviews Reactor Engineering RAP-7.3.16 and reactivity maneuvering guidance, if not previously performed. CRS Orders SN02 to raise reactor power with reactor recirc pumps to 100% power. Provides Reactivity CRS monitoring. lAW RAP-7.3.16 and OP-27; step E.2.1; Recirculation system commences raising Reactor Power: a. Guidance given in RAP-7.3.16 for adjusting reactor power, including maximum rate of power change. Maintain core flow less than or equal to 80.85 Mlb/hr. Control mismatch between recirculation loop jet pump flow as follows: 1) if operating at less than 70% of rated core flow, THEN maintain mismatch less than or equal to 10% of rated core flow. 2) if operating at greater than or equal to 70% of rated core flow, then maintain mismatch less than or equal to 5% of rated core flow d. Adjust speed in 1 to 3% increments. Monitors plant for correct response as is raised. Examiner Note: Proceed to next event when sufficient change in power level is observed. NRC Scenario #1 -2010 Fitzpatrick Operating Page 10 of 29 Appendix D Required Operator Actions Form ES*D*2 Op-Test No.: _1_ Scenario No.: _ 1_ Event No.: _3_ Event

Description:

'A' Recire Flow unit downscale failure me Position Applicant's Actions or Behavior Responds to alarms: 09-5-1-3 RPS A AUTO SCRAM 09-5-2-2 ROD WITHDRAW BLOCK 9-5-2-25 FLOW REF OFF NORM ALL 09-5-1-41 NEUTRON MON SYS TRIP 9-5-2-44 APRM UPSCALE 9-5-2-54 APRM TRIP SYS A INOP OR UPSCALE TRIP ATCI Determines 'A' Flow unit downscale failure. Indication in back panel 14.SN02 Enters AOP-59 for loss of RPS bus power and CRS orders ATC to CRS bypass 'A' flow unit. NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 11 of 29 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _3_ Event

Description:

'A' Recirc Flow unit downscale failure ____Bypasses 'A' Flow unit per OP-16. NOTE: The INOP, UPSCALE, and COMPARATOR indicating lights on panel 09-14 are unaffected by bypass switch. E.21.1 Place RWR FLOW UNIT BYP switch in (A). E.21.2 Verify the following FLOW UNIT indications:

Associated BYPASS indicating light is on
Associated UPSC OR INOP light is off
Associated COMPAR light is off E.21.3 Verify BYPASS light is off for other flow unit channel on the ATCI same side. E.21.4 Verify white BYP light in on at top of panel 09-14 for SN02 Flow Unit (A). NOTE: Refer to Tech Spec Bases 3.3.1.1.2.b and TRM Table T3.3.B-1.

E.21.5 IF the flow unit comparator function is the only function to be bypassed, THEN Steps E.21.6 and E.21.7 are not required. E.21.6 IF a flow unit is declared inoperable, THEN one of the two required APRM Neutron Flux-High (flow biased) Channels in the associated trip system must be declared inoperable. NOTE: The following step may cause a half-scram. E.21.7 Place switch S-1 on FLOW UNIT A to INT TEST at panel 09-14. A Resets half scram. Makes Tech Spec call for an inoperable APRM neutron flux -High; flow biased. TIS 3.3.1.1 Action A.A 1 place channel in the tripped condition in 12 hours RPS. Examiner Note: Actions to be entered when flow unit fails downscale. Once OP-16; step E.21.7 is completed. LeO can not be exited per basis 3.3.1.1. With a flow unit inoperable a loss of a single flow unit lose single failure criteria. (page 6.3.3.1.1-11.) Briefs crew on the event. Examiner Proceed to the next NRC Scenario #1 -2010 Fitzpatrick Operating Page 12 of 29 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _4_ Event

Description:

Upscale failure of 06l T -528; FWlC level transmitter Time Position Applicant's Actions or Behavior Responds to alarms: 09-5-1-28 RX WTR LVL ALARM HI OR LO ALL 09-5-2-29 FDWTR CH A or B or C RX WTR L VL HIGH TRIP CRS Enters AOP-42; Determines upscale failure of 06LT-52B. Orders SN02 to place feedwater controls in manual and attempt to maintain RPV water level between 196.5 inches and 206.5 inches. CRS Swap to other level channel and restore feedwater controls to automatic per OP-2A, G.30. Place feedwater in manual control to maintain RPV water level between 196.5 inches and 206.5 inches. Swap to other level channel per OP-2A. SN02 Verifies the following: Operating condensate and condensate booster and feedwater pumps lineup. Orders SN02 to place feedwater control back in automatic per OP-2A, CRS section G.7 NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 13 of 29 Appendix 0 Required Operator Actions Form ES-D*2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _4_ Event

Description:

Upscale failure of 06L T-52B; FWLC level transmitter Time Position Applicant's Actions or Behavior G.7.1 Stabilize RPV water level at 196.5 to 203 inches on 06L1-94A,B and C. G.7.2 Verify the following controllers are in MAN:

RFP A FLOW CONTROL 06-84A
RFP B FLOW CONTROL 06-84B G.7.3 Place RX WTR lVl CNTRl 06lC-83 in MAN. G.7.4 Slowly adjust RX WTR LVl CNTRl 06lC-83 manual control knob to balance RFP A FLOW CNTRL 06-84A. SN02 G.7.5 .Place RFP A FLOW CNTRl 06-84A in BAL. G.7.6 Line up RX WTR lVl CNTRl 06lC-83 as follows: a. Balance controller by adjusting setpoint tape. b. Place controller in BAL G.7.7 Line up RFP B CNTRl 06-84B as follows NOTE: Adjusting 06-84B manual control knob will result in RPV water level changes. a. Balance controller by adjusting manual control knob. b. Place controller in BAL CRS enters OP-27 A and makes Tech Spec call for failure of 06l T -52B. TIS 3.3.2.2. A. A 1 Feedwater and Main Turbine High Water level Trip CRS Instrumentation.

With 1 channel inoperable, place channel in the tripped condition within 7 days. CRS Briefs crew on the Examiner Note: At discretion of lead Proceed to the next NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 14 of 29 Appendix Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _ 1_ Event No.: _5_ Event

Description:

'8' RFPT trip and recirc runback to 44% speed. PositionATCI SN02 CRS SN02 ATC SN02 CRS Applicant's Actions or Behavior Responds to alarms: 09-5-1-28 RX WTR LVL ALARM HI OR LO 09-6-4-9 RX FEED PMP B TRIP Report observation of lowering RPV level to CRS CRS enters AOP-42; Feedwater malfunction lowering feedwater flow and AOP-8; Loss or reduction of reactor coolant flow. Directs ATC to monitor for onset of instabilities per OP-16 posted Directs SN02 to determines operating point on power to flow map and refers to attachment 1 Directs ATC to insert cram rods based on operating point on power to flow map Monitors feedwater discharge header pressure returns to normal. Determines operating point on power to flow map and refers to attachment

1. Monitor for onset of thermal-hydraulic instabilities per OP-16 posted attachment. Inserts cram rods to exit buffer zone. Resets recirc run back signal on Rx recirc. Briefs crew on the event Proceed to the next event NRC Scenario #1 -2010 Fitzpatrick Operating Page 15 of 29 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _ 1_ Event No.: _6Event

Description:

Coolant leakage inside primary Time Position Applicant's Actions or Behavior Annunciator 09-5-1-34 OW PRESS ALARM HI OR LO. Report of rising ALL drywell pressure. Enters AOP-39 for loss of coolant. Orders SN02 to attempt to detect CRS and locate leak per Attachment

1. Orders Torus CONTINUE TO NEXT NRC Scenario #1 -2010 Fitzpatrick Operating Page 16 of 29 i Appendix Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _6_ Event

Description:

Coolant leakage inside primary containment Position Applicant's Actions or Starts SBGT lAW 0.1 Train A Startup CAUTION Operating a standby gas treatment train with the charcoal filters installed to vent paint fuses, welding fumes, smoke from a fire, or chemical release could damage the charcoal filter. See precaution C.2.4. 0.1.1 Ensure open ABOVE EL369' SUCT 01-125MOV-11. 0.1.2 Ensure open TRAIN A INLET 01-125MOV-14A. 0.1.3. Verify the following: -White light for AIR HTR 01-125E-5A is on. Red lightfor AIR HTR 01-125E-5A is on. TRAIN A CLG VLV 01-125MOV-100A is closed. FN DISCH 01-125MOV-15A is open. TRAIN A FN 01-125FN-1A is Running. SN02 0.1.4 If SBGT is being placed in service to support any of the following: Tours venting Orywell venting HPCI operation Main steam leakage collection system operation Auxiliary Gas treatment system operation. Then ensure required SBGT suction valves are lined up per the applicable procedure prior to proceeding to step 0.1.5. 0.1.5 If SGT Train B is shutdown then perform the following:

a. Verify open TRAIN B CLG VLV 01-125MOV-100B

b. Verify flow rate on SGT FLOW 01-125FI-106A:

-RB un-isolated -approximately 6000 scfm -RB isolated -approximately 5600 to 5800 scfm 0.1.6 If RB OIFF PRESS 01-1250PI-100A or B indicates less negative than -0.25 inches water, then ensure SGT TRAIN B is in service per subsection 0.2. NRC Scenario #1 -2010 Fitzpatrick Operating Page 17 of 29 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _6_ Event

Description:

Coolant leakage inside primary containment Time Position Applicant's Actions or Behavior Starts SBGT lAW OP-20 0.2 Train B Startup CAUTION Operating a standby gas treatment train with the charcoal filters installed to vent paint fuses, welding fumes, smoke from a fire, or chemical release could damage the charcoal filter. See precaution C.2.4. 0.2.1 Ensure open ABOVE EL 369' SUCT 01-125MOV-12. 0.2.2 Ensure open TRAIN A INLET 01-125MOV-14B. 0.2.3. Verify the following: White light for AIR HTR 01-125E-5B is Red light for AIR HTR 01-125E-5B is TRAIN A CLG VLV 01-125MOV-100B is FN DISCH 01-125MOV-15B is TRAIN A FN 01-125FN-1B is 0.2.4 If SBGT is being placed in service to support any of the following: Tours venting Orywell venting HPCloperation Main steam leakage collection system operation Auxiliary Gas treatment system operation. Then ensure required SBGT suction valves are lined up per the applicable procedure prior to proceeding to step 0.2.5. 0.2.5 If SGT Train A is shutdown then perform the following:

a. Verify open TRAIN A CLG VLV 01-125MOV-100A

b. Verify flow rate on SGT FLOW

-RB un-isolated -approximately 6000 -RB isolated -approximately 5600 to 5800 0.2.6 If RB OIFF PRESS 01-1250PI-100A or B indicates less negative than -0.25 inches water, then ensure SGT TRAIN B is in service per subsection 0.2. I NRC Scenario #1 -2010 Fitzpatrick Operating Page 18 of 29 Appendix Required Operator Actions Op-Test No.: _1_ Scenario No.: _1_ Event No.: _6_ Event

Description:

Coolant leakage inside primary containment . Time Position SN02 CT CRS ATC CRS SN02 CRS Applicant's Actions or Behavior Performs Attachment 1 of AOP-39. Orders manual scram if drywell pressure> 2.3 psig. Enters AOP-1. NOTE: Auto RPS scram function are Inserts Manual Scram and perform AOP-1 Immediate Depress Manual Scram pushbuttons Reactor Mode Switch to Shutdown Fully Insert all SRM's and IRM's Verify all rods in Verify SDIV Vent and Drain valves closed Verify APRM's downscale

Verify RWR pumps running VerifylTrip Main Turbine Verify electrical distribution fast transfer Verify at least 1 Circ Water pump running Orders SN02 to control level with Feed/Condensate at 177-222.5 in. Trend level performance and manipulate GEMAC Master/Individual controllers, RFP discharge valves and RFP trip as necessary to control level. Enters EOP-2 and EOP-4 when drywell pressure exceeds 2.7 psig. Other EOP entry conditions EOP-2; RPV water level below 177 inches. EOP-4; Drywell temperature above 135°F. Examiner Note: Proceed to the next event NRC Scenario #1 -2010 Fitzpatrick Operating Page 19 of 29 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _7_ Event

Description:

Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close. P Applicant's Actions or Behavior Sim Trigger 5 for ED43: A and B; 4 minutes after Drywell pressure reaches Booth 2.7 pSig. Oper CRS References AOP-72; 115 KV Grid loss, AOP-16; Loss of 10300; 18; Loss of 10500; and AOP-69;CRD pump trouble but other EOPs. ATC Verifies all EDG starts. SN02 With no cire water pumps running, closes MSIVs. ATC Identifies and reports to eRS the failure of 'A' and 'C'EDG output breakers to close. CRS Directs ATC to shutdown 'A' and 'C' EDG lAW AOP-18; Loss of 10500. NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 20 of 29 I Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: Event Time Position ATC SN02 CRS SN02 Scenario No.: _1_ Event No.: Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close. Applicant's Actions or AOP-18: Step If EDG A is to be shutdown, then perform the

a. Ensure EDG A LOAD BKR 10502 is tripped and placed in pull to lock. b. Ensure EDG A & C TIE BKR 10504 is tripped. c. Place EDG A CONTROL SWITCH in MAINT at panel 93ECP-A. d. Place EDG A CNTRL control switch to STOP at panel 09-8. e. If EDG A fails to shutdown, then perform emergency EDG shutdown per section G of OP-22. f. If resumption of EDG A operation is desired, then place EDG A CONTROL SWITCH in STANDBY at panel 93ECP-A. Step If EDG C is to be shutdown, then perform the

a. Ensure EDG C LOAD BKR 10512 is tripped and placed in pull to lock. b. Ensure EDG A &C TIE BKR 10504 is tripped. c. Place EDG C CONTROL SWITCH in MAINT at panel 93ECP-C. d. Place EDG C CNTRL control switch to STOP at panel 09-8. e. If EDG C fails to shutdown, then perform emergency EDG shutdown per section G of OP-22. f. If resumption of EDG C operation is desired, then place EDG C CONTROL SWITCH in STANDBY at panel 93ECP-C. Verifies all available ECCS pumps start. Orders SN02 to prevent injection from those CS and RHR pumps not required for adequate core cooling per (EP-5) Prevents injection from CS and RHR pumps not required for adequate core cooling per (EP-5) NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 21 of 29 Appendix D Op-Test No.: _1_ Event

Description:

Time Position CRS SN02 SN02 Required Operator Form ES-D-2 Scenario No.: _ 1_ Event No.: _7_ Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close. Applicant's Actions or Behavior Orders SN02 to maintain RPV level between 177 and 222.5 inches using RCIC and HPCI align suctions from the CST. Defeat HPCI HI area temperature and High Torus water level suction transfer if necessary lAW EP-2. Defeat RCIC low RPV pressure and high area temperature isolations if necessary lAW EP-2. Maintains RPV level between 177 and 222.5 inches using RCIC and HPCI align suctions from the CST. Defeats HPCI Hi area temperature and High Torus water level suction transfer if necessary lAW EP-2. Defeats RCIC low RPV pressure and high area temperature isolations if necessary lAW EP-2. HPCI HI AREA TEMPERATURE DEFEAT 5.7.1 Verify one of the following conditions exist: A steam leak does not exist in HPCI steam piping outside the

Operation of both HPCI AND RCIC is required to maintain RPV water level. 5.7.2 For 23MOV-15, place HPCI STM LEAK AUTO ISOL DIV 12F-S6A keylock switch in TEST at panel 09-21. 5.7.3 For 23MOV-16 and 60, place HPCI STM LEAK AUTO ISOL DIV 11 2F-S68 keylock switch at panel 09-21. NRC Scenario #1 -2010 Fitzpatrick Operating Page 22 of 29 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: Event Position SN02 SN02 Scenario No.: _1_ Event No.: _7_ Loss of offsite AC power and failure of 'A' and fC' EDG output breakers to close. Applicant's Actions or Behavior HPCI HIGH TORUS WATER LEVEL SUCTION TRANSFER DEFEAT 5.13.1 Place HPCI TORUS SUCT BYPASS SW keylock switch in BYPASS at panel 09-3. 5.13.2 Verify white HPCI TORUS SUCT L T 23A-DS76 light is on at panel 09-3. 5.13.3 Perform one of the following:

A. IF HPCI not running, AND HPCI suction has swapped to torus, THEN restore HPCI to CST as follows: 1. Close the following valves:

23MOV-57
23MOV-58 2. Open 23MOV-17.

B. IF HPCI must remain running, AND HPCI suction has swapped to torus, THEN place in close the following valves:

23MOV-57
23MOV-58 When 23MOV-57 and 23MOV-58 have dual indication RCIC LOW RPV PRESSURE DEFEAT 5.17.1 For 13MOV-15, disconnect lead from one of the terminals in panel 09-33: AA-71 OR 5.17.2 For 13MOV-16, disconnect lead from one of the terminals in panel 09-30: AA-28 OR NRC Scenario #1 -2010 Fitzpatrick Operating Page 23 of 29 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _ 1_ Event No.: _7_ Event

Description:

Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close. Time Position Applicant's Actions or Behavior RCIC HIGH AREA TEMPERATURE DEFEAT 5.16.1 Verify one of the following conditions exist: A steam leak does not exist in RCIC steam piping outside the containment. OR SN02 Operation of both HPCI AND RCIC is required to maintain RPV water level. 5.16.2 For 13MOV-16, place RCIC STM LEAK AUTO ISOL DIV I 2F-S5A keylock switch in TEST at panel 09-21. 5.16.3 For 13MOV-15, place RCIC STM LEAK AUTO ISOL DIV 11 2F-S58 keylock switch in TEST at 09-21. Orders SN02 to spray the Torus before Torus pressure reaches 15 CRS psig using the posted instructions. NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 24 of 29 Appendix D Required Operator Actions Op-Test No.: _1_ Scenario No.: _1_ Event No.: Event

Description:

Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to Time Position SN02 CRS Applicant's Actions or Behavior Places RHR in Torus spray mode using the posted instructions. 1.Verifytorus pressure is GREATER THAN 2.7 psig. 2. IF RPV water level is LESS THAN 10 inches on fuel zone water level indication, and the EOPs permit diverting LPCI flow, THEN place DW &TORUS SPRAY VLV OVERRIDE OF FUEL ZONE LVL 10A-S18A (8) keylock switch in MANUAL OVERRD. 3. Place SPRAY CNTRL 10A-S17A (8) switch to MANUAL, spring return to normal. 4. Verify white SPRAY PERM 1 OA-DS-67 A(B) light is on. 5. Ensure available RHR pumps in RHR loop A(8) are running:

RHR PMP 10P-3A(B)
RHR PMP 10P-3C(D)

NOTE: 10MOV-3/A(B) may be throttled when 10MOV-39A(B) has dual position indication.

6. Open RHR TEST TORUS CLG & SPRAY 10MOV-39A(B).

7. Throttle TORUS SPRAY IN8D VLV 10MOV-38A(B) to desired torus spray flow 8. WHEN RHR Loop A(B) flow is GREATER THAN ensure closed MIN FLOW VLV IOMOV-16A(8).1500 gpm, 9. Throttle RHR TEST & TORUS CLG 10MOV-34A(8) to excess flow to the torus to maintain>

6,500 gpm RHR Loop flow with one RHR pump operating or> 13,000 gpm RHR A(B) flow with two RHR pumps NOTE: Procedure may be continued while condensate transfer is being isolated.

10. IF RHR Loop A(8) condensate transfer keep-full is in service, AND RHR Loop A(B) pressure is LESS THAN condensate transfer pressure, THEN close IORHR-274(IORHR-260).

11. Establish RHRSW flow and temperature control. Orders SN02 to place RHR in Drywell spray mode using the posted instructions.

NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 25 of 29 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: Event Time Position Scenario No.: _1_ Event No.: _7_ Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close. Applicant's Actions or Behavior Places RHR in Drywell Spray mode 1. ensure the following components are tripped: RWR Pumps Orywell Cooling Fans 2P-1A -68FN-2A,B,C, and D 02-2P-1B -68FN-4A,B,C, and D 2. Verify drywell temperature and pressure are within the Drywell Spray Initiation Limit. 3. If RPV water level is less than 10 inches on fuel zone water level indication, and the EOPs permit diverting LPCI flow, then place DW & TORUS SPRAY VLV OVERRIDE OF FUEL ZONE LVL 10A-S18A(b) keylock switch to MANUAL OVERRD. 4. Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, spring return to normal. 5. Verify white SPRAY PERM 10A-DS67A(B) light is on. CAUTION Starting an RHR pump loop that is not full could result in severe water hammer and equipment damage. RHR loop piping shall be full prior to manually starting an RHR pump in that loop. 6. Ensure available RHR pumps in RHR Loop A(B) are running: RHR PUMP 10P-3A(B) RHR PUMP 10P-3C(D)

7. Open DW SPRAY OUTBD VLV 10MOV-26A(B).

8. Throttle DW SPRAY INBD VLV 1 OMOV-31A(B) to establish desired drywell spray flow. 9. when RHR Loop A(B) flow is greater than 1500 gpm, ensure closed MIN FLOW 10MOV-16A(B).

NOTE Procedure maybe continued while condensate transfer is being isolated.

10. If RHR Loop A(B) condensate transfer keep-full is in service, and RHR Loop a(B) pressure is less than condensate transfer pressure, then close 10RHR-274(10RHR-260).

11. Establish RHRSW flow and temperature control. NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 26 of 29 Appendix D Required Operator Actions Form ES*D*2 Op-Test No.: _1_ Event

Description:

Time Position CRS SN02 Scenario No.: _1_ Event No.: _7_ Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close. Applicant's Actions or Behavior Orders SN02 to place RHR in Torus cooling mode using the posted instructions. Places RHR in Torus cooling mode using the posted instructions.

1. IF a LPCI auto-initiation signal is sealed in, THEN perform

a. IF RPV water level is LESS THAN 10 inches on fuel zone water level indication, and the EOPs permit diverting LPCI flow,THEN place DW &TORUS SPRAY VLV OVERRIDE OF FUEL ZONE LVL 10A-S18A(B) keylock switch in MANUAL OVERRD. b. Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, spring return to normal. c. Verify white SPRAY PERM 10A-DS-67A(B) light is on. 2. Ensure at least one of the following RHR pumps is running:

RHR PMP 10P-3A(8)
RHR PMP 10P-3C(D)

NOTE: 10MOV-3/A(B} may be throttled when 1 OMOV-39A(B) has dual position indication.

3. Open RHR TEST TORUS CLG & SPRAY 10MOV-39A(B).

4. Throttle RHR TEST & TORUS CLG 1 OMOV-34A(B) to establish desire flow. 5. WHEN RHR Loop A(8) flow is GREATER THAN 1500 ensure closed MIN FLOW VLV NOTE: Procedure may be continued while condensate transfer is being isolated.

6. IF RHR Loop A(B) condensate transfer keep-full is in service, AND RHR Loop A(B) pressure is LESS THAN condensate transfer pressure, close 1 ORHR-27 4(1 ORHR-260).

7. Establish RHRSW flow and temperature control. NOTE If Torus sprays have been initiated, terminate Torus sprays before Torus pressure drops below 0 psig. Terminates Torus sprays before Torus pressure drops below 0 psig. Examiner Note: Proceed to the next event NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 27 of 29 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: -1L Event

Description:

Emergency RPV depressurization; 'A' ADS valve fails to open Time Position Applicant's Actions or EXAMINER Monitor for annuciator 09-4-1-28 ADS TIMER ACTUATED recording time for the alarm. CRS Orders SN02 to line up CS and RHR for injection SN02 Lines up CS and RHR for injection. I CRS Orders ATC to override ADS. , ATC Overrides ADS and reports back to CRS. CT Before RPV water level reaches -19 inches; CRS enters CRS Emergency Depressurization and Orders opening 7 ADS Valves. I I ATC Opens 7 ADS valves and reports 'A' ADS valve has failed to CRS Orders ATC to open another ATC Opens another Orders SN02 to maintain RPV level above 177 inches with LPCI and ! CRS Core Spray. TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET: RPV level is controlled with band of 177 inches and 222.5 inches with LPCI and Core Spray. NRC Scenario #1 -2010 Fitzpatrick Operating Page 28 of 29 Appendix D Required Operator Actions Form ES-D-2 POST-SCENARIO: HAVE THE APPLICANT IN THE CRS POSITION IDENTIFY THE HIGHEST EAL CLASSIFICATION FOR THE COMBINATION OF EVENTS EXPERIENCED DURING THE SCENARIO. Alert: 3.1.1. due to Coolant leakage NRC Scenario #1 -2010 Fitzpatrick Operating Test Page 29 of 29 Appendix 0 Scenario Outline Form ES-O-1 Facility: Fitzpatrick Scenario No.: 2 Op-Test No.: 1 Examiners: Operators: Initial Conditions: Reactor is in Mode 1 with power at 80%. Power ascension on hold for CRD pump swap. Turnover: Swap CRD pumps. Place 'A' CRD pump in service and remove 'B' CRD pump from service. Event Malf. No. Event Event No. Type* Description 1 N/A N-SN02 Place 'A' CRD pump in service and remove 'B' CRD pump from service. TS-SRO 2 HP05 Inadvertent HPCI initiation C-SN02 : 3 FW13:A R-ATC 33E-6A Feedwater Heater Tube Leak. C-SN02 C-SN02 4 ED04:A Inverter failure 71-INV-3A failure TS-SRO 5 MC01 C-ATC Main condenser air In-leakage; Loss of condenser vacuum RP01A 6 RP01B RP09 M-ALL Failure to scram; RPS is still energized, ARI fails to actuate. 7 SL01:A or B SL03:A or B C-ATC Trip of the in service SLC pump with SLC pump 'A' or 'B' relief 11-RV-39A or 11-39B lifts * (N)ormal. (R)eactivity, (l)nstrument, (C)omponent. (M)ajor NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 1 of 26 Appendix 0 Required Operator Actions Form ES*D*2 SCENARIO

SUMMARY

Initial conditions are a reactor startup is in progress with power at 80%. Shift orders are to place 'A' CRO pump 03P-16A in service and remove 'B' CRO pump 03P-16B lAW OP-25 G.10. HPCI will inadvertently initiate, requiring crew actions to validate HPCI response and trip HPCI. Enters TS 3.5.1.0 and C, 14 day LCO, verify RCIC operable. 72 hours to restore HPCI or LPC!. 33E-6A FWH will develop a tube leak. CRS will enter AOP-62 and will need to order power reduction lAW AOP-62; Loss of Feedwater Heating guidance LPCI 'A' Inverter output breaker trips. TS call for the SRO. TIS 3.8.4.0. declares the associated LPCI subsystem inoperable immediately. There will be a main condenser in-leakage causing condenser vacuum to degrade. CRS enters 31 for loss of Condenser Vacuum. Eventually the main turbine will trip on loss of vacuum and the MSIV will need to be closed .. There will be a failure to scram when the scram is attempted. Entry into EOP-2 and then EOP-3 will be required. The first SLC pump when started will trip after about 1 minute and the second SLC pump will not inject. The operators will be required to vent the scram air header to insert control rods .. The scenario will be terminated when all control rods are inserted to or beyond position 02 and 2 has been entered. NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 2 of 26 Appendix D Required Operator Actions Form ES*D*2 INITIAL SIMULATOR SETUP -/ ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION -Reset simulator to: Protected IC -44

Apply Information Tags on the following components:

-None

Take out of FREEZE and ensure the Rx power is at 80% ready to swap CRD
Ensure materials for

-OP-65; Startup and shutdown procedure; step -OP-27; RWR -OP-25; Changing in-service CRD pumps; step G.1

Ensure the following malfunctions are loaded: -HP05; HPCI inadvertent initiation; trigger 1 -FW13:A; 33E-6A Feedwater Heater Tube Leak trigger 3; severity 100%; 5 min ramp -ED04:A; LPCI inverter 71-INV-3A; trigger -MC01; Main condenser in-leakage; trigger 5; severity 50%; 7 min -RP01 A; RP01 Band RP09; PRESET; Failure to -SL01 :A; 'A' SLC pump trip trigger 6 allow pump to run for 1 minute before inserting malfunction

-SL01 :B; 'B' SLC pump trip trigger 7 allow pump to run for 1 minute before inserting malfunction. -SL03: A; 'A' SLC pump relief 11-RV-39A lifts or SL03:B; 'B' SLC pump relief RV-39B lifts.; Preset Both

Ensure the following remote functions are loaded: -IA07 then a 5 minute delay before inserting IA01, 100% severity with 2 minute ramp. (trigger 9)
Ensure the following overrides are loaded: None
Ensure the following triggers are -trigger 1; HP05; HPCI inadventent

-trigger 3; FW13:A; 33E-6A Feedwater Heater Tube -trigger 4; ED04:A; LPCI inverter 71-INV-3A; trigger 4 -SIM BOOTH OPERA TOR Need to insert both R:ED24 and ED28 to close maint fdr bkrs to go to Alt feed trigger 8. -trigger 5; MC01; Main condenser in-leakage. -trigger 6; SL01:A insert after 1 minute of SLC pump running. -trigger 7; SL01:B insert after 1 minute of SLC pump running. NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 3 of 26 Appendix D Required Operator Actions Form ES-D-2 r.... ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION

Reset any annunciators that should not be present NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 4 of 26 Appendix D Required Operator Actions Form* ES-D-2 INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1: Swap in-service CRD pumps ./ MALFUNCTION I REMOTE FUNCTION I REPORT
Respond as NPO during the start of 'A' CRD pump EVENT 2: HPCI inadvertent initiation

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate Trigger 1 after CRD pumps are swapped
Respond to request for assistance as appropriate.

EVENT 3: 33E-6A Feedwater Heater Tube Leak AOP-62 ./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 3 after TS call has been made.
Respond to request for assistance as appropriate.

EVENT 4: Loss of LPCI inverter 71-INV-3A ./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 4 after event 4 is completed
SIM BOOTH OPERA TOR Need to insert both R:ED24 and ED28 to close maint fdr bkrs to go to Alt feed trigger 8.
Respond to request for assistance as appropriate.

EVENT 5: Main Condenser in-leakage Enter AOP-31 ./ MALFUNCTION I REMOTE FUNC1"ION I REPORT

Activate trigger 5 after TS call has been made.
Report a tear in the "A" RFPT Exhaust Boot
Respond to request for assistance as appropriate.

NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 5 of 26 I Appendix 0 Required Operator Actions Form ES*D*2 EVENT 6: Failure to scram v' MALFUNCTION I REMOTE FUNCTION I REPORT

PRESET RP01A; RP01B and RP09
Booth operator responds to de-energize scram solenoids by removing fuses states unable to open the doors to remove the fuses.
When requested by the control room to vent the scram air header insert trigger 9.
Respond to request for assistance as appropriate.

EVENT 7: Trip the in service SLC pump and SLC pump relief valve lifts 11*RV-39A or B v' MALFUNCTION I REMOTE FUNCTION I REPORT

Booth Operator insert malfunction SL01 :A; trigger 6 and SL01:B trigger 7 as appropriate.

Allow pumps to run for 1 minute before inserting and insert malfunction when operator has walked away from SLC.

Relief valve malfunctions are PRESET.
Respond to request for assistance as appropriate.

NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 6 of 26 Appendix Required Operator Actions Form CRITICAL TASKS EOP-3 Terminate and prevent all RPV injection sources except RCIC, CRD and SLC when BIIT is exceeded per EP-5. re-inject to maintain RPV water level-19 inches and either: the level to which RPV water level was lowered, if it was deliberately lowered or 222.5 inches, if RPV water level was not deliberately lowered. Standard: Terminate and prevent all RPV injection sources except RCIC, CRD and when BIIT is exceeded per EP-5. re-inject to maintain RPV water inches and the level to which RPV water level was lowered, if it was deliberately 222.5 inches, if RPV water level was not deliberately lowered. Basis: RPV water level is lowered to prevent thermal-hydraulic instabilities. Core instabilities may occur in a BWR when the reactor is operated at relatively high power-to-f1ow ratios and recirculation flow is reduced. The potential for instabilities is largely dependent upon core inlet subcooling. The greater the subcooling, the more likely that power oscillations will occur and increase in magnitude. Prompt level reduction is the most effective method of preventing or suppressing power oscillations.

2. EOP-3: Before Torus Temperature reaches the Boron Injection Initiation Temperature, Boron Injection is required.

Standard -Inject Boron using available systems. When pumps trip inject using alternate method per EP-4. In the absence of large irregular oscillations induced by hydraulic instabilities, fuel integrity and RPV integrity are not directly challenged even under failure-to-scram conditions as long as the core remains submerged (the preferred method of core cooling). A scram failure coupled with an MSIV isolation, however, results in rapid heatup of the torus water due to the steam discharged from the RPV via SRVs. The challenge to containment thus becomes the limiting factor which defines the second of the two possible conditions listed in this step requiring initiation of boron injection. If torus temperature and RPV pressure cannot be maintained below the Heat Capacity Temperature Limit, emergency RPV depressurization will be required. To avoid depressurizing the RPV with the reactor at power, it is desirable to shut down the reactor prior to reaching the Heat Capacity Temperature Limit. The Boron Injection Initiation Temperature is defined so as to achieve this goal when practicable. EOP-3: Vent the scram air header per EP-3 until all control rods are fully inserted Standard: With failure of RPS and ARI to actuate control rod insertion is required by venting the scram air header. Basis: EP-3 basis for backup control rod insertion methods. NRC Scenario #2 -2010 Fitzpatrick Operating Page 7 of 26 3 Appendix 0 Required Operator Actions Form ES-D-2 SHIFT TURNOVER INFORMATION OFF GOING SHIFT D 0 N I DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift.

Control Panel Walkdown (all panels) (SM,CRS,STA,RO,SN02)

PART II: To be reviewed by the oncoming Operator before assuming the shift.

Shift Manager Log (SM,CRS,STA)
RO Log (RO)
Lit Control Room Annunciators (SM,CRS,STA.RO, SN02)
Shift Turnover Checklist (ALL)
LCO Status (SM,CRS,STA)
Computer Alarm Summary (RO) Evolutions/General information/Equipment Status: Plant startup in progress from a refuel Plant is at approximately 80% PART III: Remarks/Planned Evolutions:

1. Swap in-service CRD pumps. Place 'A' CRD pump in service and remove '8' CRD pump 2. Continue power ascension to 85% power lAW RAP-7.3.16 by withdrawing control rods PART IV: To be reviewed/accomplished shortly after assuming the shift:

Review new Clearances (SM)
Shift Crew Composition (SM/CRS)
Test Control Annunciators (SN02) TITLE NAME TITLE NAME SRO ATC SN02 NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 8 of 26 Appendix Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _ 2_ Event No.: _1Event

Description:

Swap in-service CRD pumps. Place 03P-16A in service and Time Position CRS SN02 SN02 Sim Booth Operator SN02 Applicant's Actions or Behavior Orders SN02 to place 03P-16A; 'A' CRD pump in service and then remove 03P-16' 'B' CRD pump OP-25; section G.10 Note: Procedure marked up, "OP-25"; Changing in-service CRD pumps; steps completed up to step G.10.2 Coordinate with NPO to monitor 03P-16A start. Adjust CRD FLOW CNTRL 03FIC-301 to establish 20 to 30 on 03FIC-301 or Starts CRD PMP 03P-16A.

Respond as NPO that 03P-16A pump start is sat. Stop CRD PMP 03P-16B. Adjust CRD FLOW CNTRL 03FIC-301 to establish 59 to 61 on 03FI-31 0 or Verify normal operating values on the following indicators at -CHG WTR PRESS 03PI-302:

BETWEEN 1390 and 1580 not to exceed 1670 pSig -DRV WTR DIFF PRESS 03DPI-303: 260 to 270 psid -CLG WTR DIFF PRESS 03DPI-304: approximately 10 to 26 psid -DRV WTR FLOW 03FI-305: zero when no CRD is being driven -CLG WTR FLOW 03FI-306: 59 to 61 gpm Examiner Note: Proceed to the next event NRC Scenario #2 -2010 Fitzpatrick Operating Page 9 of 26 I Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: _2_ Event No.: _2_ Event

Description:

Inadvertent HPCI Initiation lune Applicant's Actions or Behavior ......All nize HPCI is starting Directs crew to verify the validity of the HPCI auto start using multiple CRS indications. Observes indications for Drywell pressure and reactor water level, SN02 determines HPCI start is not valid CRS Directs SN02 to trip HPCI SN02 Trips HPCI (OP-15 HPCI Section F Shutdown) The following alarms will annunciate: 9-3-3-15 HPCI PMP FLOW LO *

9-3-3-25 HPCI TRIP
9-3-3-28 HPCI TURB TRIP SOLENOID ENERGIZED
09-3-3-17 HPCI STM LINE DRN POT LVL HI (If HPCI injects and power changes), CRS enters AOP-32 CRS Unexplained/Unanticipated reactivity change Enters TS 3.5.1.C.1 and C.2, verify RCIC operable immediately and 14 CRS day LCO for HPCI inoperable.

SBGT started on HPCI start, secures SBGT or lineup flowpath by SN02 I uut::llina suction valve per OP-20 section F. NOTE: Shutdown of a SBT Train with a initiation signal present will prevent restart on a subsequent or different initiation signal. NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 10 of 26 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _2_ Event

Description:

Inadvertent HPCllnitiation Time Position SN02 SN02 Applicant's Actions or Behavior Performs shutdown of I A' SGT OP-20 F.1.1 ensure SGT Train A operation is not required F.1.3 Close TRAIN A INLET 01-125MOV-14A F.1.4 Close ABOVE EL 369' 01-125MOV-11 F.1.5 Verify the following:

White light for AIR HTR 01-125E-5A is on.
Red light for AIR HTR 01-125E-5A is off.
TRAIN A CLG VLV 01-125MOV-100A is open.
FN DISCH 01-125MOV-15A is closed.
TRAIN A FN 01-125FN-1A is stopped. NOTE: Shutdown of a SBT Train with a initiation signal present will prevent restart on a subsequent or different initiation signal. Performs shutdown of 'B' SGT OP-20 F.2.1 ensure SGT Train B operation is not required F.2.3 Close TRAIN A INLET 01-125MOV-14A F.2.4 Close ABOVE EL 369' 01-125MOV-11 F.2.5 Verify the following:
White light for AIR HTR 01-125E-5B is on.
Red light for AIR HTR 01-125E-5B is off.
TRAIN A CLG VLV 01-125MOV-100B is open.
FN DISCH 01-125MOV-15B is .* TRAIN B FN 01-125FN-1B is Examiner Proceed to next NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 11 of 26 Appendix D Required Operator Actions Form ES-D-2 Op*Test No.: _1_ Scenario No.: Event No.: _3_ Event

Description:

33E-6A Feedwater Heater Tube Leak Position Applicant's Actions or IF indications of thermal-hydraulic instability THEN insert a manual scram and exit this Lower feedwater temperature reduces the margin to the onset of core thermal-hydraulic instability. Respond to the following alarms: 09-6-3-36 FW HTR LEVEL 6A HI*

09-6-3-26 FW HTR LEVEL 6A HI HI
09-7-3-12 2 nd STAGE RHTR DR TNK 4A LEVEL HI A noticeable rise in core thermal power or APRM power in conjunction with a lowering RPV feedwater inlet temperature (EPIC Screen FDWTR) caused by the following:
Loss of feedwater heater level control ALL
Closure of reheat steam supply valve
Drag dump valve in mid-position
Isolation of extraction steam to the feedwater heater(s)
High level in first point feedwater heater ATC! Identifies 33E-6A Feedwater Heater Tube leak SN02 CRS Enters AOP-62 for a loss of feed water heating Orders ATC to monitor for indications of thermal-hydraulic instability per OP-16 posted attachment.

And monitors APRM power and RPV CRS feedwater inlet temperature changes on EPIC Screen FDWTR or EPIC points A-3411 and A-3412. Monitors for indications of thermal-hydraulic instability per OP-16 posted attachment. And monitors APRM power and RPV feedwater ATC inlet temperature changes on EPIC Screen FDWTR or EPIC points 3411 and A-3412. CONTINUE TO NEXT PAGE NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 12 of 26 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _ 2_ Event No.: _3_ Event

Description:

33E-6A Feedwater Heater Tube Leak Time Position CRS ATC SN02 CRS CRS Applicant's Actions or Behavior CRS orders if initial reactor power is LESS THAN OR EQUAL 90%, AND core flow is GREATER THAN THEN perform the Lower RWR flow to establish approximately 55% core flow. Insert cram groups per RAP-7.3.16 UNTIL reactor power BELOW 100% rod Maintain reactor power at least 20% below the pre-transient power level. Two CRAM groups of control rods need to be Lowers RWR flow to establish approximately 55% core flow. Inserts cram groups per RAP-7.3.16 UNTIL reactor power BELOW 100% rod Maintains reactor power at least 20% below the power NOTE Two CRAM groups of control rods need to be inserted Monitors secondary side of the plant and performs verifications for ATC. WHEN reactor power is stable demand an Official 3D Program and review core thermal-hydraulic parameters. If Feedwater Heater 33E-6A, 33E-6B, OR a Feedwater String isolates,THEN reduce power to less than 25%per and Orders SN02 when reactor power is stable demand an Official 3D Program and review core thermal-hydraulic parameters. Orders ATC If Feedwater Heater 33E-6A, 33E-6B, OR a Feedwater Heater String isolates, THEN reduce power to less than 25% per 62 and OP-3 CONTINUE TO NEXT PAGE NRC Scenario #2 -2010 Fitzpatrick Operating Page 13 of 26 Appendix 0 Required Operator Actions Form ES-D*2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _3_ Event

Description:

33E-6A Feedwater Heater Tube Leak Time Position Applicant's Actions or Behavior SN02 Demands an Official 3D program and reviews core thermal-hydraulic If Feedwater Heater 33E-6A, 33E-6B, OR a Feedwater Heater String ATC isolates, THEN reduce power to less than 25% per AOP-62 and OP-3 CRS Briefs crew on the event. Examiner Note: Proceed to the next event NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 14 of 26 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Event

Description:

Time Position All CRS SN02 CRS SIM BOOTH OPER SN02 Scenario No.: _ 2_ Event No.: _4_ Failure of LPCI inverter 71-INV-3A Applicant's Actions or Behavior

09-8-3-15 LPCI MOV IPS A 711NV-3A MINOR ALARM .09-8-3-2 LPCI MOV IPS A AC INPUT .09-8-3-7 LPCIIPS A BATT VOLTS LO OR BKR
09-8-3-8 LPCI MOV IPS A C OUTPUT VOL TS LO OR LOSS
09-8-3-10 LPCI MOV IPS A 71-INV-3A MAJOR ALARM .09-3-1-3 RHR A VLV OVERLOAD OR PWR .09-3-1-13 RHR A INJ VLV OVERLOAD OR PWR
09-4-0-8 RCIC PMP ENCL EXH FAN 13FN-2A .09-4-3-12 RWR LOOP A VLV OVERLOAD OR PWR (various power supply trouble Investigate the cause of the alarm. Sends a NPO to the LPCI inverter If the cause of the alarm is not readily apparent, then place LPCI MOV BUS A on alternate feed. CRS directs SN02 to place LPCI MOV BUS A on alternate feed per ARP 09-8-3-2.

Need to insert both R:ED24 and ED28 to close maint fdr bkrs to go to Alt feed Verifies L-15 is energized at panel 09-8 Places LPCI MOV A PWR SUPP switch in AL T PULL TO LOCK at panel 09-8. Step F .1.13.a.6 of OP-43C. When the cause of the alarm is known and corrected, LPCI MOV Bus A may be restored to normal per Section G.4 of OP-43C NRC Scenario #2 -2010 Fitzpatrick Operating Page 15 of 26 Appendix D Required Operator Actions Form ES*D*2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _4_ Event

Description:

Failure of LPGI inverter 71-INV-3A Time Position Applicant's Actions or Behavior Enters TIS 3.8.4.0.1 declares the associated LPGI 'A'subsystem CRS inoperable immediately. With HPGI enters TIS 3.5.10.1 and 0.2 Restore HPGI or LPGI within 72 hours with HPGI inoperable and Cond A entered for TIS 3.5.1.A. Examiner Proceed to the next NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 16 of 26 Appendix Required Operator Actions Form ES*D*2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _5_ Event

Description:

Main condenser in-leakage Time Position Applicant's Actions or Any of the following conditions Annunciator 09-3-1-28 OFFGAS RECOMBINER TROUBLE Annunciator 09-6-1-29 CNDSR VAC LO alarms Main Condenser vacuum is in Region 1 or 2 of Attachment 1 Main Condenser vacuum is less than expected for current plant conditions Enters AOP-31 for loss of Condenser Vacuum OVERRIDES

1. IF any of the following occur:

Turbine toad is LESS THAN 255 MWe AND vacuum is LESS THAN 25 inches Hg (Region 1 of Att 1) Condenser vacuum lowers to OR is rapidly approaching the main turbine trip setpoint.

THEN perform the following: IF reactor power is GREATER THAN 29%, THEN insert a Manual Scram. Trip the main turbine 2. As Main Condenser Vacuum lowers, Verify Automatic Actions of Section C. As condenser vacuum trends downward, the following occurs: 22.5 inches Hg -Main turbine trips 20 inches Hg -Reactor feed pump turbines trip 8 inches Hg -Turbine bypass valves close 8 inches Hg -MSIVs close (this isolation is bypassed if main turbine stop valves are closed AND the reactor mode switch is not in RUN) 3. Before main condenser vacuum lowers to 8 inches Hg, ensure MStVs are closed. Orders SN02 to perform the actions of AOP-31 for loss of condenser vacuum NRC Scenario #2 -2010 Fitzpatrick Operating Page 17 of 26 II Appendix Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _5_ Event

Description:

Main condenser in-leakage I Position Applicant's Actions or Behavior Set a manual scram benchmark for (Typically -23 Obtain AOP-31 for loss of condenser vacuum: SN02 At 09-6, Trip the Recombiner and verify The Hydrogen Addition

System trips i
Dispatch an NPO to verify valve positions at the Off Gas i System Recombiner Panel (01-1070GR) Dispatch NPO to place spare SJAE's in service At 09-6, Observe Off Gas Flow on 38FR-101 and determine that the source of condenser vacuum loss is air in leakage Dispatch NPO(s} to inspect for source of air in leakage. i At 09-7 monitor Turbine Steam Seal Pressure and SPE Vacuum Trend Condenser Vacuum and Orders SN02 to perform a power reduction with recirculation flow to combat trend. Limit the SN02 to maintain 55% Core Flow. Rapid rates may apply. Examiner Note: Expect power to be low due to earlier loss of feedwater heating. SN02 Obtain OP-27, Section E: I (Normal Rates at 200 Mwth/min)

ATC Obtain RAP-7.3.16, Attachment 1 (Posted at panel 09-5) At panel 09-5 Fully Insert CRAM RODS NRC Scenario #2 -2010 Fitzpatrick Operating Page 18 of 26 Appendix Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _5_ Event

Description:

Main condenser in-leakage Time Applicant's Actions or Behavior At 09-4, Simultaneously lower recirculation pump speeds while monitoring:

Jet Pump Loop Mismatch 5% (7.7 Mlbm/hr)
Core Flow> 55%
RPV Water Level < 222.5 inches Examiner Note: Expect power to be low due to earlier loss of feedwater heating. Trend condenser vacuum and Orders ATC to insert Control Rod Cram Groups to combat trend. Examiner Note: Proceed to the next event NRC Scenario #2 -2010 Fitzpatrick Operating Page 19 of 26 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _6_ Event

Description:

Turbine trip on loss of vacuum and Failure to scram Time Position CRS ATC CRS SN02 CRS CRS ATC CRS Applicant's Actions or Behavior Orders A TC to perform a manual scram and AOP-1 immediate actions. Note: If CRS does not order a manual scram before 22.5 inches HG the turbine will trip and automatic scram will occur. Insert Manual Scram and perform AOP-1 Immediate Actions

Depress Manual Scram push buttons
Reactor Mode Switch to Shutdown
Fully Insert all SRM's and IRM's
Verifies all rods did not scram
Verifies SDIV Vent and Drain valves are open
Verifies APRM's are not downscale
Verifies Main Turbine is still on line
Verifies at least 1 Circ Water pump running Orders SN02 to maintain RPV water band of 177 inches to 222.5 inches condensate and feed water. Trend level performance and manipulate GEMAC Masterllndividual controllers, RFP discharge valves and RFP trip as necessary to control level. Enters EOP-2 and then EOP-3; Failure to scram. Orders ATC to initiate ARI. Initiate ARI and recognizes all 5 valves did not de-energize.

Reports RPS and ARI failed to actuate to CRS. Orders ATC to reduce recirculation to minimum and trip Recirc Pumps NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 20 of 26 Appendix Required Operator Actions Form ES-D*2 Op-Test No.: _1_ Scenario No.: _ 2_ Event No.: _6Event

Description:

Turbine trip on loss of vacuum and Failure to Position SN02 SN02 CRS SN02 CRS CT SIM BOOTH OPER ATC SIM BOOTH OPER CRS ATC Applicant's Actions or Behavior Reduces Recirculation flow to minimum Trips Recirc Pumps Orders SN02 to control RPV pressure between 800-1000 psig with SRVs. Controls RPV pressure between 800-1000 psig with SRVs. Orders ATC to vent the scram air header per EP-3 section 5.3 If CRS determines to de-energize scram solenoids by removing fuses. Report unable to open the doors to remove the fuses. Determine EP-3 success path is to vent the scram air header Dispatches NPO to vent the scram air header per EP-3; section 5.3. Insert trigger 9 Orders ATC to Override ADS. A TC places both ADS Override switches to Override. NRC Scenario #2 -2010 Fitzpatrick Operating Page 21 of 26 Appendix Required Operator Actions Form ES-D*2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _6_ Event

Description:

Turbine trip on loss of vacuum and Failure to scram Time Position CRS CT SN02 Applicant's Actions or Behavior If Reactor power is above 2.5% or cannot be determined and RPV water level is above 110 in. Orders TIP all injection except SLC, CRD and RCIC per EP-5. Terminate high pressure sources first. Identify reinjection source as feedwater with a level band of 100" and caution against rapid level changes during reinjection. SN02 lowers RPV water level to below 110 inches by terminating and preventing all injections except for SLC, RCIC, and CRD (EP-5). At 09-3, Depress HPCI Turbine Trip Pushbutton At 09-5, Select both RFP GEMAC Controllers to Manual At 09-5, Reduce both RFP GEMAC Controllers to Minimum At 09-6, Ensure both RFP Min Flow Valves are Open At 09-6, As necessary, adjust RFP speed, Feedwater Startup Valve position and RFP Discharge Valve position to maintain level 80-100 inches. Exercise caution against rapid level rise. At 09-3, Place both 14MOV-11 A and B Auto Actuation Bypass switches in Bypass. At 09-3, Verify both white Auto Actuation Bypass lamps are lit. At 09-3, Ensure closed 14MOV-11 A and B At 09-3, Ensure both Core Spray pumps are stopped At 09-3, Place both 1 OMOV-27 A and B Auto Bypass switches in At 09-3, Verify both white Auto Control Bypass lamps are lit. At 09-3, Ensure closed 1 OMOV-27 A and B. At 09-3, Ensure RHR pumps not required to be running are stopped NRC Scenario #2 -2010 Fitzpatrick Operating Page 22 of 26 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: Event

Description:

Turbine trip on loss of vacuum and Failure to II Time Position Applicant's Actions or Behavior CRS Assign either operator to hang MSIV Low Water Level Jumpers per EP-2. EXAMINER NOTE: If MSIV Low Water Level jumpers are not installed per EP-2 then MSIVs will close. HPCI then maybe used to inject to the RPV. SN02 Dispatch NPO to hang MSIV Low Water Level Jumpers Examiner Proceed to the next NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 23 of 26 Appendix D Required Operator Actions Form ES*D*2 Op-Test No.: _1_ Event

Description:

me Po CRS SN02 CRS ATC SIM BOOTH OPER ATC Scenario No.: _2_ Event No.: Trip the in-service SLC pump and relief valve lift on the second SLC Applicant's Actions or Behavior Orders SN02 If a high Drywell pressure ECCS initiation signal exists (2.7 psig) THEN prevent injection from those CS and RHR pumps not required to assure adequate core cooling before depressurizing below their maximum injection pressures (EP-5) Prevents injection if a high Drywell pressure ECCS initiation exists (2.7 psig) THEN prevent injection from those CS and pumps not required to assure adequate core cooling depressurizing below their maximum injection pressures ATC to initiate SLC either SYS -A or Sys-B Initiates SLC either SYS -A or -Verifies white SQUIB VL VS READY lights are -Notes level on TK LVL -Places SLC pump keylock switch in START SYS-A or START -Verifies red SLC pump running light is -Verifies SLC pump discharge pressure on DISCH PRESS 11 PI-55 greater than or equal to RPV -Verifies the following: RWCU And the following valves are

CLN UP SUCT 12MOV-18
CLN UP RETURN ISOL VALVE 12MOV-69 Insert malfunction SL01:A or malfunction SL01:B 1 minute after the respective SLC pump is started. Recognizes the trip of the in-service SLC and reports this to the CRS. Orders ATC to start the other SLC system and to Orders an NPO to the CRS tripped SLC pump. NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 24 of 26 Appendix 0 Required Operator Actions Form ES*D*2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _7_ Event

Description:

Trip the in-service SLC pump and relief valve lift on the second SLC pump. Time .Position Actions or Behavior Initiates SLC the other SYS -A or Sys-B -Verifies white SQUIB VLVS READY lights are on .

Notes level on TK LVL 1IL1-66. ATC -Places SLC pump keylock switch in START SYS-A or START SYS-B. -Verifies red SLC pump running light is on. -Verifies SLC pump discharge pressure on DISCH PRESS 11 PI-65 is greater than or equal to RPV pressure.

SIM Insert malfunction SL03:A or malfunction SL03:B; When the BOOTH respective SLC pump is started. OPER A TC recognizes that the in service SLC pump discharge pressure is ATC i not greater than or equal to RPV pressure and reports this to the CRS. CT Enters EP-4; Boron injection using CRD and executes it concurrently CRS with this procedure ATC Dispatches NPO to commence EP-4 field actions. SIM Report back to A TC that the first SLC pump started has a tripped BOOTH breaker and the motor is hot to the touch and acknowledge A TC OPER report to commence Ep*4 field actions. Examiner Note: Proceed to the next event NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 25 of 26 Appendix 0 Required Operator Actions Form ES*D*2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: Event

Description:

Trip of the in-servicw SLC pump and relief valve lift on the second SLC pump Ilfntt Position Applicant's Actions or Behavior If BIIT exceeded while power is > 2.5%: Order TIP all injection except SLC, CRD and RCIC per EP-5. Terminate high pressure sources first. Identify reinjection source as CRS feedwater or HPCI with a level band of -19" to the level at which injection may recommence. Caution against rapid level changes during reinjection. SN02 At 09-3, confirm all other terminate and prevent actions are complete. When Rx Power <2.5%, or RPV level at TAF (0") or SRV's will remain CRS closed order injection with feedwater at a level band of current RPV level to -19". At 09-6. As necessary, adjust RFP speed, Feedwater Startup Valve position and RFP Discharge Valve position to maintain level 80-100 SN02 inches. Exercise caution against rapid level rise. CT ATC When scram air header is vented and verifies reactor is shutdown. TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET:

When all control rods are inserted to or beyond postion 02
EOP-3 has been exited and EOp*2 has been enteredPOST*SCENARIO:

HAVE THE APPLICANT IN THE CRS POSITION IDENTIFY THE HIGHEST EAL CLASSIFICATION FOR THE COMBINATION OF EVENTS EXPERIENCED DURING THE SCENARIO. SAE 2.2.2 Any RPS setpoint has been exceeded and automatic and manual scrams fail to result in a control rod pattern which assures reactor shutdown under all conditions without boron and either: Reactor power> Torus Temperature> Boron Injection Initiation NRC Scenario #2 -2010 Fitzpatrick Operating Test Page 26 of 26 II Appendix 0 Scenario Outline Form ES*D*1 Facility: Fitzpatrick Scenario No.: 4 Op-Test No.: 1 Examiners: Operators: Initial Conditions: Reactor power is 60%. ST-3PA, 'A Core Spray Valve 1ST' is marked as complete up to step 8.2. Turnover: Power was lowered to 60% power to perform a rod pattern adjustment. Perform section 8.2 of ST-3PA for Core Spray Loop A Quarterly Operability Test (1ST), and then perform rod pattern adjustment. " I **.*'" No. 1 OVR 1 2 RD11 :18: 15 3 RD03:B 4 RR22:A RP01AA 5 ED10 ED03:C 6 RX01 7 MS05 8 MS08B:C MS08B:G Perform ST -3PA Sect 8.2 only. A Core Spray Valve 1ST Perform Rod Pattern adjustment and uncoupled control rod 18 : B CRD Flow control valve fails partially closed. Swap to A Reactor Level Transmitter 02-3LT-101A fails low with failure half UPS Bus Failure causes loss of L 15, L25 and Fuel failure leads to High Rad. MSL break. Enter Radioactivity Release Control EOP-6 and Emergency Depressurization. Initiate Manual MSL isolation. One MSL fails to isolate ,.... (R)eactivity, (I)nstru NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 1 of 26 Scenario Summary and Administration Instructions SCENARIO Perform section 8.2 of ST-3PA for Core Spray Loop A Quarterly Operability Test (1ST). One valve will stroke longer than technical specifications allow. TS call for SRO. A minor rod pattern adjustment will be performed at 60% reactor power using control rods. During the rod pattern adjustment control rod 18: 15 will become uncoupled at position 48. At the end of the rod pattern adjustment, the in service flow control valve for CRD will fail partially closed. Operators will have to diagnose the failure and swap to the other flow control valve. Reactor Level Transmitter 02-3LT-101A fails low with failure to half scram. Operators will have to diagnose and make TS call. Can manually put trip in on RPS system A. UPS Bus Failure causes loss of L 15, L25 and UPS. When a fault occurs on the UPS bus the normal feeder breaker for the UPS MG set trips resulting in a trip of the UPS MG set and a momentary loss of power to the UPS bus as it auto transfers to the Alternate supply breaker. The Alternate feeder breaker will then trip on overcurrent, resulting in a complete loss of the UPS bus. Transformer T15 overloads causing a loss of L 15 and L25. The fault for T15 will be removed and L 15 and L25 can be recovered. Loss of UPS causes a RWR runback and the turbine driven feed pumps need to be manually adjusted to maintain reactor level. Possible that CRS determines to manually scram the reactor per AOP override statement. Fuel failure leads to High Radiation MSL. MSL break. Enter Radioactivity Release Control EOP-6 when above the alert level. Radiation levels approach the GE level and the operators then enter RPV control and Emergency Depressurization prior to GE. Initiate Manual Isolation of Main steam Lines. One MSL fails to isolate. NRC Scenario #4 -2010 Fitzpatrick Operating Page 2 of 26 Scenario Summary and Administration Instructions INITIAL SIMULATOR SETUP ./ ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION Reset simulator to a IC-45 with power at 60%.

Apply Information Tags on the following components:

NA

Take out of FREEZE and ensure the B CRO flow control valve in A CRO Pump in
Ensure materials for applicants:

-Stopwatch and a copy of ST-3PA marked up to step B.2. -Copy of ST-23B; Control rod coupling integrity test. (Simulator Booth operator is to keep the copy of ST-23B until requested.)

Ensure the following malfunctions are RP01AA-Failure to auto half scram MSOBB:C-MSOBB:G-* Ensure the following remote functions are ROOB for event 3. 3-6BA, 3-69A, FCV-19A ISOL R012; 3-FCV-19A on 3-FCV-19B select. Initial-A ED 12 and ED-39C for event 5. BKR 10660 LO RELAY -RESET (trigger 10) ED13 -trigger 11.
Ensure the following overrides are Override 1: 14MOV-11A takes 15 seconds to
Ensure the following triggers are built: Trigger 1: OVR CSZL014AS1A(2)

Core Spray OTBD Valve (ST malf) Trigger 2: RD03:B CRD FCV B FAIL set to 25% Trigger 9: RD11:: 18: 15 control rod uncoupled Trigger 4 RR22:A Set to Trigger 5: ED10 which triggers Trigger 6: RX01 Set to 15% Ramp 10 Trigger 7: MS05; Severity 30% ramp 30 seconds delay 1BO

RM01:15 PRM 17-RM-434A, 27% severity, 9:20 delay,6:40 ramp. NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 3 of 26 Scenario Summary and Administration Instructions

-/ ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION

RM01: 16 PRM 17 -RM-434B, 27% severity, 9:20 delay" 6:40 ramp
RM01 :23 PRM 17 -RIS-431,99%

severity,3:00 delay, 10:00 ramp

RM01:24 PRM 17-RES-432,99%

severity, 3:00 delay, 10:00 ramp

Reset any annunciators that should not be present NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 4 of 26 Scenario Summary and Administration Instructions INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1: Perform ST*3PA Sect 8.2 only. A Core Spray Valve 1ST ./ MALFUNCTION I REMOTE FUNCTION I REPORT
Insert override to make 14MOV-11A closing time slow
Respond to request for assistance as appropriate.
Delete override after 15 seconds CSlL014AS2A(2)

Core Spray OTB Valve EVENT 2: Perform Control Rod pattern adjustment at 60% power and uncoupled control rod 18-15 ./ MALFUNCTION I REMOTE FUNCTION I REPORT i

Withdraw 3 control rods to position 48. Control rods 26-07; 26-31; and 26-23. On fourth control rod 18-15 the rod will uncouple.
Insert trigger 9 when control rod 18-15 coupling check is performed.
Simulator Booth Operator is to keep a copy of ST -23B until requested
Respond to request for assistance as appropriate.

EVENT 3: B CRD Flow control valve fails partially closed ./ MALFUNCTION I REMOTE FUNCTION I REPORT

Insert trigger 2 when directed by chief examiner
When requested use remote function R008 to permit the standby (A) flow I control valve to be valved in. R:R008-open (trigger3)

R:R012

Respond to request for assistance as appropriate.

EVENT 4: Reactor Level Transmitter 02-3LT*101A fails low with failure to half scram. ./ MALFUNCnON/REMOTEFUNCnON/REPORT

Insert trigger 4 when directed by chief examiner
Failure to auto half scram is PRESET.
Respond to request for assistance as appropriate NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 5 of 26 Scenario Summary and Administration Instructions EVENT 5: UPS Bus Failure causes loss of L 15, L25 and UPS. ./ MALFUNCTION I REMOTE FUNCTION I REPORT
Insert trigger 5 when directed by chief examiner
Role play that the trip was an overload on T15 caused by the UPS bus failure and tripped breaker 10560 which has an 86 lockout. Inform CRS that 86 can be reset and 10560 re-energized.
Remove malfunction ED03C and reset using RF ED 13 and ED-12 to reset lockout when req uested.
Respond to request for assistance as appropriate EVENT 6: Fuel failure leads to High Rad. MSL. ./ MALFUNCTION I REMOTE FUNCTION I REPORT
Insert trigger 6 when directed by chief examiner
At Chief Examiner direction, Sim Booth Operator to raise severity of fuel failure if radiation levels do not approach GE levels.
Respond to request for assistance as appropriate EVENT 7: MSL break. Enter Rad Control EOP-6 ./ MALFUNCTION I REMOTE FUNcnON I REPORT
Insert trigger 7 when directed by chief examiner or when Rx mode switch is taken to shutdown.
Once Turbine Low Range Monitor is high, report to CRS that site dose projection is 450 mREM and rising.
10 minutes after reporting above dose, if ED has not been performed, report to CRS that site dose projection is 1100 mREM and rising.
Respond to request for assistance as appropriate EVENT 8: Initiate Manual MSL Isolation.

One MSL fails to isolate* ./ MALFUNCTION I REMOTE FUNCTION I REPORT

PRESET Malfunctions MS08B:C and MS08B:G
Respond to request for assistance as appropriate NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 6 of 26 Scenario Summary and Administration Instructions CRITICAL 1. EOP-6 Scram the reactor Standard:

1. Expected when Offgas timer times out, then manually scrams the reactor per AOP-3. Due to the loss of the UPS, the timer will not time out. 2. Failure criteria, before the offsite release rate reaches the E-Plan General Emergency Level, Verify Reactor Scram. Basis: The scram reduces the rate of energy production and thus the rate of radioactivity release. EOP-6 Basis. 2. EOP-6 Standard:

Perform emergency depressurization Before the offsite release rate reaches the Emergency Plan "General Emergency" level: perform Emergency RPV Depressurization per EOP-6 , open 7 ADS valves. Note: 1000 mRem TEDE is the GE criteria. Basis: An offsite release rate above the General Emergency level is an indication of Degrading conditions and presents a more immediate threat to the health and safety of the public. If a primary system is discharging outside the primary and secondary containments, a blowdown is performed before the release reaches the General Emergency level to reduce the discharge rate. EOP-6 Basis. NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 7 of 26 Appendix 0 Required Operator Actions Form ES*D*4 Op-Test No.: _1_ Scenario No.: Event No.: _1_ Event

Description:

Perform ST-3PA Sect 8.2 only. A Core Spray Valve 1ST e Position Applicant's Actions or Behavior Perform brief for performing ST-3PA, "CORE SPRAY LOOP A CRS QUARTERLY OPERABILITY TEST (1ST)" .Declare Core Spray Loop A inoperable. NOTE: A Core Spray Loop A Keep-full alarm could occur while testing core spray loop valves. The keep-full alarm is cleared in Subsection 8.3. Close and time MIN FLOW VLV 14MOV-5A. Closing time secs (1ST: 15.2 to 20.5) Open and time MIN FLOW VLV 14MOV-5A. Opening time secs (1ST: 15.2 to 20.4) Ensure closed INBD INJ VLV Close and time OUTBD INJ VLV 14MOV-11A. Closing time secs (1ST: 7.2 to 11.9) NOTE: (Actual time will be 15 seconds) Open and time OUTBD INJ VLV 14MOV-11A. Opening time secs (1ST: 6.9 to 11.3) CAUTION Failure to minimize time that 14MOV-7 A is closed will cause a loss of suction to the core spray holding pump. SN02 SN02 reports to CRS that 14MOV-11A closing time is out of band. CRS Stops ST-3PA, Core Spray Loop A Quarterly Operability Test Review surveillance. Determine 14MOV-11A is inoperable. TS CRS 3.6.1.3.A; 4 hours to isolate and de-activate 14MOV-11 A and TS 3.5.1.A.A1 7 day LCO. Examiner Note: Proceed to the next event NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 8 of 26 Appendix 0 Required Operator Actions Form ES-O-4 Op-Test No.: _1_ Scenario No.: _ 4_ Event No.: _2_ Event

Description:

Perform Control Rod pattern adjustment at 60% power and uncoupled control rod 18:15. e Position Applicant's Actions or Behavior If not already performed, CRS conducts reactivity brief on performing control rod pattern adjustment lAW RAP-7.3.16. CRS Reviews Reactor Engineering RAP-7.3.16, if not previously performed. CRS directs A TC to perform control rod pattern adjustment. CRS Provides Reactivity CRS monitoring lAW RAP-7.3.16 and OP-26; Control rod drive manual control system step E.1; Notch withdrawal; commences rod withdrawal to perform control rod pattern adjustment. ATC SN02 Monitors plant for correct response as control rods are manipulated. When control rod 18: 15 is withdrawn to position 48, the following annuciators will alarm: CREW

09-5-2-3; ROD DRIFT
09-5-2-4 ROD OVERTRA VEL CRS Enters AOP-27; Control rod drift and AOP-25; Uncoupled Control rod CRS Directs ATC to perform AOP-25 for uncoupled control rod. NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 9 of 26 Appendix Required Operator Actions Form ES*D*4 Op-Test No.: _1_ Scenario No.: _4_ Event No.: _2_ Event

Description:

Perform Control Rod pattern adjustment at 60% power and uncoupled control rod 18: 15. Time Position ATC Applicant's Actions or Behavior E.2 Perform the following steps several times, to attempt to couple the control rod: E.2.1 Insert the control rod to position 44 using notch insert per section E of OP-26; RMCS. OP-26; section E.3 Control rod insertion one notch E.3.1 Review Reactor Engineer's instructions concerning control rod positioning. E.3.2 WHILE inserting control rod perform the following:

a. Monitor the following:

-Nuclear instrumentation; To include SRM/IRM meters/recorders, reactor period meters and APRM recorders as -Control rod position indication on four rod b. IF control rod inserts two notches, AND is not in the rod final intended position, THEN perform the

1) Withdraw control rod to its intended

2) Notify SM. SM is not required to take any c. I F control rod inserts GREATER THAN two notches, THEN the

1) Notify 2) Position control rod per E.3.3 Ensure ROD SEL PWR switch is in E.3.4 Ensure control rod to be moved is selected by depressing select pushbutton on ROD SEL matrix, if E.3.5 Verify the Select pushbutton is brightly backlit Control rod indicating light is on (light with coordinates on FULL CORE DISPLAY) Annunciator 09-5-2-1 RWM ROD BLOCK RPIS INOP is clear. E.3.6 Momentarily place ROD MOVEMENT CNTRL switch to IN, spring return to OFF. E.3.7 Verify control rod latches in the expected even numbered position before ROD SETTLE light goes off. E.3.8 Verify ROD SETTLE light is off. E.3.9 IF additional notch insertion is desired, THEN return to Step .3.4. E.3.10 IF control rod movement is no longer required, THEN perform the following to prevent overheating rod select matrix pushbuttons:

a. Place ROD SEL PWR switch in OFF. b. Place ROD SEL PWR switch in ON. NRC Scenario #4 -2010 Fitzpatrick Operating Page 10 of 26 Appendix Required Operator Actions Op-Test No.: _1_ Scenario No.: Event No.: Event

Description:

Perform Control Rod pattern adjustment at 60% power and control rod 18: 15. Time Position ATC Applicant's Actions or Behavior E.2.2 Withdraw control rod to position 48 using notch withdrawal per section E.1 of OP-26; RMCS. E.LI Review Reactor Engineer's instructions concerning control rod positioning. E.1.2 IF reactor is in Mode 5. THEN perform ST-23F. E.1.3 WHILE withdrawing control rod, perform the following:

a. Monitor the following: Nuclear instrumentation; To include SRM/IRM meters/recorders, reactor period meters and APRM recorders as appropriate Control rod position indication on four rod display b. IF control rod withdraws GREATER THAN two notches, perform the

1) Notify Shift

2) Position control rod per

c. IF control rod double notches, and is not in the rod sequence intended position.

THEN perform the

1) Insert control rod one 2) Notify Shift

3) Stop all further control rod withdrawals until Shift Manager event and approves continued rod E.1.4 Ensure ROD SEL PWR switch is in E.1.5 Ensure control rod to be moved is selected by depressing select pushbutton on ROD SEL matrix, if E.1.6 Verify the Select pushbutton is brightly backlit Control rod indicating light is on (light with coordinates on FULL CORE DISPLAY) ROD OUT PERM light is on E.1.7 Perform one of the

a. IF control rod at position 46. THEN rod may be withdrawn to 48 with coupling test per b. Single notch as 1.) Place ROD MOVEMENT CNTRL switch to OUT NOTCH. return to 2.) Verify control rod latches in the expected even numbered BEFORE ROD SETTLE light goes 3) Verify ROD SETTLE light is UCOMA.

<::,..""n:>ri .... :I:M _ ?n1f to position P::InF'! 11 of?f Appendix 0 Required Operator Actions Form Op-Test No.: _1_ Scenario No.: _ 4_ Event No.: _2_ Event

Description:

Perform Control Rod pattern adjustment at 60% power and uncoupled control rod 18:15. Time Position Applicant's Actions or Behavior 4.) If control rod is withdrawn to position 48, THEN ensure control rod coupling integrity test is completed per ST-23B. E.1.8 if additional control rod notch withdrawal is desired, THEN return to step E.1.5. ATC E.1.9. If control rod movement is no longer required, THEN perform the following to prevent overheating rod select matrix pushbuttons:

a. Place ROD SEL PWR switch in OFF. b. Place ROD SEL PWR switch in ON. Examiner Note: When chief examiner has seen enough of the reactivity manipulations, and prior to completion of rod manipulations move on to the next event. The next malfunction is based on control rod manipulations.

Proceed to the next event NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 12 of 26 Appendix 0 Required Operator Actions Form ES-O-4 No.: _1_ Scenario No.: _4_ Event Event

Description:

B CRD Flow control valve fails partially Time Position ATC Crew CRS SN02 Applicant's Actions or Behavior NOTE: When the CRD flow control valve is in service and failed close (0%), the effect is a decrease in CRD system flow, indicated on 310; an increase in charging water header pressure as indicated on 302; drive water header differential

pressure, and Cooling water differential pressure, (03DPI-304), will decrease to low values. Subsequent movement of control rods by normal operation is impossible since the differential pressure developed across the piston in the CRD mechanism is too low. Prolonged operation without adequate cooling water will result in higher CRD temperatures than normal. This is indicated on temperature recorder 03TR-244, on panel and may result in actuating Alarm CRD HI TEMP, on panel 5, depending on the duration of reduced flow. The in service CRD flow control valve will be partially closed and therefore the affects will be less severe than noted above. EXAMINER NOTE Crew may take manual control of flow controller OP-25.G.15 Determines that Control Rod will not move. Diagnose that CRD flow is low and the cause of Control Rods not being able to move. Brief crew on swapping to the A CRD flow control valve per G.14 of OP-25.

Establish communications NPO and Control room
Ensures controller is in auto
Adjust controller setpoint to zero gpm
Verify open 03CRD-68A
Slowly open outlet isolation valve 03CRD69A
Close 03CRD-69B NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 13 of 26 Appendix Required Operator Actions Form ES-D-4 Op-Test No.: _1_ Scenario No.: _ 4_ Event No.: _3_ Event

Description:

B CRD Flow control valve fails partially closed ..Applicant's Actions or Behavior Have EO at Flow Control Hand Select Station place AUTO-MAN select knob for 03HSS-245A in AUTO Have EO at Flow Control Hand Select Station place AUTO-MAN select knob for 03HSS-245B in MAN Slowly raise setpoint on CRD FLOW CNTRL 03FIC-301 to establish 59 SN02 to 61 gpm on 03FIC-301 Verify normal operating values on the following indicators:

CHG WATER PRESS 03PI-302 Between 1390 and 1580 psig
DRV WTR DIFF PRESS 03DPI-303:

260-270 psid SN02

CLG WTR DIFF PRESS 03DPI-304 approx. 10 to 26 psid
DRV WTR FLOW 03FI-305 zero with no CRD is being driven
CLG WTR FLOW 03FI-306 59 to 61 gpm May continue with rod pattern adjustment after CRD flow control is re-CRS established.

Examiner Proceed to the next NRC Scenario #4 -2010 Fitzpatrick Operating Page 14 of 26 Appendix D Required Operator Actions Form ES*D*4 Op-Test No.: _1_ Scenario No.: Event No.: _4_ Event

Description:

Reactor Level Transmitter 02-3L T-1 01A fails low with failure to half scram Position I Applicant's Actions or Behavior NOTE: The following alarms will come in

09-5-1-31 RPS RX VESSEL LO LVL TRIP
EPIC Point A #963 & D 1207 will respond Responds to alarm. Determines that 02-3LT-101A is reading approx. 170.488".CREW Determines that half scram on RPS CH A1 did not occur as expected.

1.)Determines TS call 3.3.1.1-1 Condition A, One or more required channels inoperable. Required Action A.1: Place channel in Trip or A.2 Place associated trip system in trip. 12 hour completion time. Condition C, One or more functions with RPS Trip capability not maintained. Required Action C.1: Restore RPS Trip Capability. (Place associated trip system in trip.) 1 hour completion time. 2.) Determines TS call 3.3.6.1-1 Functions 2a,2g and 5e CRS Condition A, One or more required channels inoperable Required Action A.1: Place channel in Trip. 12 hour completion time. 3.) Determines TS call 3.3.6.2-1 Function 1 Condition A. One or more required channels inoperable Required Action A.1: Place channel in Trip. 12 hour completion time. Note: Since Lo L VL Trip alarm came in and half scram did not occur, the trip function is not operable and also requires entry into C.1 which requires restoring trip capability within 1 hour. CRS Briefs crew on placing a trip in the A RPS resulting in a half scram. ATC Places a manual scram in RPS channel A. NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 15 of 26 Appendix 0 Required Operator Actions Form ES-O-4 Op-Test No.: _1_ Scenario No.: _4_ Event No.: 4 Event

Description:

Reactor Level Transmitter 02-3LT-101A fails low with failure to half scram lime I Position I Applicant's Actions or Examiner Proceed to the next NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 16 of 26 Appendix D Required Operator Actions Form ES-D-4 Op-Test No.: _1_ Scenario No.: _4_ Event No.: _5_ Event

Description:

UPS Bus Failure causes loss of L 15, L25 and UPS. Time Position Applicant's Actions or Behavior Note: Large amount of alarms are going to come in. L 15 and L25 4KV SUPP FDR TRIP OR CNTRL PWR LOSS is the cause of the loss of L 15, L25 and UPS. Automatic Actions from a Complete Loss of UPS 15 seconds after loss of UPS, RWR MG sets run back to min-speed. RFP MGUs lose power and remain at the pre-power loss position. If RWR pumps run back, RPV water level rises rapidly due to steam flow -feed flow mismatch. RWCU isolates due to loss of power to demin inlet temperature switch. Automatic Actions from loss of L25 Loss of RPS Bus A PCIS Group I Half Isolation (Alarm only) PCIS Group II half Isolation Loss of IIA" Drywell Cams Loss of "A" Hydrogen/Oxygen Monitor 27PCX-101A Loss of Reactor Building Vent Rad Monitor 17RM-452A Numerous FPP Alarms due to loss of MPX Power Automatic Actions from loss of L 15 Loss of "A" CRD Drive Water Pump Loss of "A" STBY Gas Treatment Train Loss of "A" SLC Pump and SLC suction heat trace Loss of Drywell Cooling Assemblies 68FN-2Af 2C, 4A, 4C NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 17 of 26 Appendix Required Operator Actions Form ES-O-4 Op-Test No.: _1_ Scenario No.: _4_ Event Event

Description:

UPS Bus Failure causes loss of L 15, L25 and I Time Position Applicant's Actions or Behavior Crew Responds to alarms and runback. Recognizes loss of UPS. If recognizes prior to runback starting (15 seconds) immediate action is to lock scoop tubes by taking RWR A & B Scoop Tube to Trip Note: Override in AOP-21 Loss of UPS states IF plant shutdown is required as determined byeRS, Then shutdown shall be completed by inserting manual scram. CRS Directs operator to trip one feed pump and take manual control of feed pump speed. May trip one RFP if recirc runback starts .. Take manual control of one RFP as follows: a. Lower MSC until speed reduction is observed SN02 b. Place the associated RFPT A(B) MGU HYD JACK switch in High Speed Stop c . Control RPV water level with MSC. WHEN RWR MG set runback is complete, perform the following:

a. Place the following control switches to spring return to RWR A SCOOP RWR B SCOOP b. Verify the following annunciators in 09-4-3-11 RWR MG A SCOOP TUBE LOCK 09-4-3-20 RWR MG B SCOOP TUBE LOCK c. Place the following control switches in ON: SCOOP TUBE A AUTO UNLOCK SCOOP TUBE B AUTO UNLOCK NOTE: Cram groups can not be inserted due to loss of power to rod select relays and RPIS. NRC Scenario #4 -2010 Fitzpatrick Operating Page 18 of 26 Appendix Required Operator Actions Form ES-D-4 Op-Test No.: _1_ Scenario No.: _4_ Event No.: Event

Description:

UPS Bus Failure causes loss of L 15, L25 and UPS. Time Applicant's Actions or Behavior Directs entry into AOP-69 CRD Pump Trouble To restore CRD Directs execution of the following actions: Execute AOP-8 Loss or reduction of RWR flow. Verify cleanup auto isolation per section G of OP-28 Execute AOP-59 Loss of A RPS Execute AOP-18A Loss of L 15 Execute AOP-18B Loss of L25 Places CRD flow controller to manual. Rotates flow control fully counter clockwise. ATC Starts the B CRD Pump. Adjusts for 60 gpm and places back in manual. Note: fault is recoverable. Investigates cause of loss of UPS. Is told from field that the trip was an overload on T15 caused by the UPS bus failure and tripped breaker 10560 which has an 86 lockout. Informed that 86 can be reset and 10560 re-energized. Directs Reset of 86 and close breaker Examiner Proceed to the next NRC Scenario #4 -2010 Fitzpatrick Operating Page 19 of 26 Appendix 0 Required Operator Actions Form ES-D-4 Op-Test No.: _1_ Scenario No.: _ 4_ Event No.: _6_ Event

Description:

Fuel failure leads to High Rad. MSL. " .. Applicant's Actions or Behavior Entry conditions for AOP-3;: 09-3-2-27 OFF GAS RAD MON HI is in alarm and is not an expected condition. Any of the following annunciators are in alarm: 3-2-10 OFF GAS TIMER INITIATED 3-2-38 OFF GAS RAD MON HI-HI 3-3-1 MAIN STM RAD MON HI 09-5-1-32 MAIN STM LINE RADIATION HI-HI Responds to increasing radiation levels. Enter AOP-3 High Activity in Crew Reactor coolant or Off-Gas. Directs Chemistry to sample reactor coolant an off-gas. Directs Rad Pro to survey for changing rad levels. CRS When 2 or more main steam line rad monitors are tripped on hi-hi radiation then ensure condenser air removal pumps are tripped. Ensure closed the following valves: Main Steam drain 29MOV-74 SN02 *

Main Steam drain 29MOV-77
RWR Loop B Sample Isol VL V 02-2AOV-39

& 40

Air Removal PMP Suct VL V 38AOV-111

& 112 Enter EOP-5 Secondary Containment Control Consider inserting manual scram and closing MSIV's to minimize CRS release. NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 20 of 26 Appendix D Required Operator Actions Form ES-D-4 Op-Test No.: _1_ Scenario No.: _ 4_ Event No.: _6_ Event

Description:

Fuel failure leads to High Rad. MSL. Time Position Applicant's Actions or Behavior CT CRS When off-gas rad timer 17-157 times out directs a manual scram. Note: Use attachment 2 of AOP-21 Loss of UPS to assist in performance of AOP-1 actions if UPS is de-energized. Insert Manual Scram and perform AOP-1: Reactor Scram Immediate Actions

Depress Manual Scram push buttons
Reactor Mode Switch to Shutdown
Fully Insert all SRM's and ATC
Verify all rods
Verify SDiV Vent and Drain valves closed
Verify APRM's downscale
VerifylTrip Main Turbine
Verify electrical distribution fast transfer Enters EOP-2 and then EOP-3 (Unable to verify all control rods are in) CRS ARMs are in alarm for Reactor Building.

CRS enters EOP-5 CRS Directs SN02 to close MSIVs SN02 Manually closes MSIV's Determines that MSL C failed to isolate. MSIV 29AOV-86C & 29AOV-80C Examiner Proceed to the next NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 21 of 26 Appendix 0 Required Operator Actions Form ES-O-4 Op-Test No.: _1_ Scenario No.: Event No.: _7_ Event

Description:

MSL break. Enter Rad Control EOP Time Position Applicant's Actions or Behavior Note: the following alarms will come in during this event, 1) TURB BLDG ARM RAD HI 2) DIV I AMBIENT TEMP HI 3) DIV " AMBIENT TEMP HI Crew Responds to temperature alarms. CRS Enters AOP-40; Main steam Line Break. Determines that Turb Building exhaust is above 9.9E5 cpm (Alert level) and enters EOP-6 CRS Isolates Control Room and Relay Room ventilation within 30 minutes Continue to next page NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 22 of 26 Appendix D Required Operator Actions Form ES-D-4 Op-Test No.: Scenario No.: Event No.: _7_ Event

Description:

MSL break. Enter Rad Control EOP Applicant's Actions or Behavior CRS directs SN02 to isolate Control Room Ventilation per section G of OP-55Bat panel 09-75. G.I.I Place Control Room Ventilation ISOL & PURGE CNTRL switch in ISOL. G.1.2 Verify closed the following dampers and valves:

EXH 70MOD-109
INLET 70MOD-105
EXH ISOL 70MOV-107
INLET ISOL 70MOV-10S G.1.3 Verify open the following dampers:
RECIRC A 70MOD-110A
RECIRC B 70MOD-11 OB G.1.4 Verify one of the following control room emergency air supply fans is running with its discharge damper open: Supply Fan Discharge Damper
FRESH AIR SUPP 70FN-6A DISCH 70MOD-1I2A SN02
FRESH AIR SUPP 70FN-6B DISCH 70MOD-112B G.1.5 Close 70DMPR-1 05 (control room vent supply isolation 70Mod 105 manual bypass damper) ( located near 70MOV-10S)

G.1.6 Ensure closed all access doors to Control Room. G.1.7 IF differential pressure is LESS THAN +0.125 inches water gauge on CNTRL RM DIFF PRESS 70DPI-063, THEN ensure Office Area Ventilation is in normal operation or shutdown per OP-59B. NOTE: Step G.1.S and G.1.9 may be performed after Step G.LlO. G.1.S WHILE control room ventilation is operating in isolate mode, perform the following:

a. Record control room dP in the narrative log once per shift. b. Notify system engineer if LESS THAN +0.2 inches Continue to next page. NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 23 of 26 II Appendix 0 Required Operator Actions Form ES*D*4 Op-Test No'.: _1_ Scenario No.: _4_ Event No.: Event

Description:

MSL break. Enter Rad Control Time Position SN02 CRS Applicant's Actions or Behavior CRS directs SN02 to isolates Relay Room Ventilation per section G of OP-56 at panel 09-75. G.1.10 IF Control Room Ventilation is being isolated as a result of high radiation in the air supply header, THEN isolate Relay Room ventilation as follows: a. Place the following Relay Room Ventilation control switches in ISOL:

ISOL &PURGE CNTRL A
ISOL &PURGE CNTRL B b. Verify closed the following dampers and valves:
EXH ISOL 70MOV-105
INLET ISOL 70MOV-106
RR VENT DAMPER 70MOD-115

c. IF either 70MOV-105 or 70MOV-106 failed to close, THEN perform the following:

1) De-energize valve by opening associated circuit breaker: Valve Circuit Breaker 70MOV-105 71 MCC-253-0A2 70MOV-106 7IMCC-263-0A2 NOTE: Electric brakes need to be disengaged for manual operation.

2) Manually close valve. d.IF RR VENT DAMPER 70MOD-115 is not closed, THEN unlock and close 70DMPR-115 (relay room vent manual isol damper). e. Verify open the following dampers:

RECIRC A 70MOD-104A
RECIRC B 70MOD-104B

f. Ensure closed all access doors t a Relay Room. TSC filtered ventilation system is activated within 60 minutes and dispatches a team to check turbine building integrity EXAMINER NOTE: AT Chief Examiner direction.

Sim Booth Operator is to raise severity of fuel failure to GE radiation levels Examiner Note: Proceed to the next event NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 24 of 26 Appendix D Required Operator Actions Form ES-D-4 Op-Test No.: 1 Scenario No.: 4 Event No.: 8 Event

Description:

Initiate MSL Manual Isolation. One MSL fails to isolate and Enter RPV control and Emergency Depressurization prior to GE . . ..," Applicant's Actions or Behavior EXAMINER NOTE: Crew may have performed MSIV isolation early based on MSL High radiation. CRS Directs SN02 to close MSIVs Manually closes MSIV's Determines that MSL C failed to MSIV 29AOV-86C & Note: >12mRlhr on Turbine Building Exhaust Monitor for> 15 minutes is the GE criteria. However power is lost to the high range monitor. The booth will call in to the CRS and inform him that TEDE dose at the site boundary is 450mr/hr and rising (which is above the SAE setpoint of 100mRem). 10 minutes later if have not entered emergency depressurization steps, the booth will call with a TEDE dose of 11 OOmRem and rising (which is above the GE setpoint of 1000mRem.) CT Trends Turbine Building exhaust High Range Monitor. Prior to GE (Note: 1000 mRem TEDE is the GE criteria) enters EOP-2 CRS (scrams if not already done) and performs an Emergency RPV Depressurization. Performs Emergency RPV Depressurization by opening all 7 ADS ATC valves. NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 25 of 26 Appendix 0 Required Operator Actions Form ES*D*4 SN02 Maintains reactor level with feedwater in manual. TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET: Blowdown has been complete and reactor level is being controlled in the normal range. POST *SCENARIO

HAVE THE APPLICANT IN THE CRS POSITION IDENTIFY THE HIGHEST EAL CLASSIFICATION FOR THE COMBINATION OF EVENTS EXPERIENCED DURING THE SCENARIO.

General Emergency 5.2 Dose Projections. NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 26 of 26}}

ML101740486

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