ML101750146

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: 15 minutes Actual Time Used: _ _minutes

References:

RAP.7.3.03, CORE THERMAL POWER EVALUATION, Rev 13 RAP*7.3.16, PLANT POWER CHANGES, Rev. 44 ST*5D, APRM CALIBRATION, REV. 3 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 ,,'PM, and has been determined to be: 0 Satisfactory Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

RO ADMIN JPM A-1-1.doc 5

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. (*) Applicant calculates average Correctly calculates feedwater feedwater temperature and compensated flow.

compensated feed flow. Records 16. 392 data on Attachment 1 items 16 17. 391.9 through 23. 18. -28

19. -28.1

20. 1.01031

21. 1.01034

22. A=3.99 (~j.96-4.02)

23. 8=4.04 (4.01-4.07)

2. (*) Applicant uses the ASME steam Correctly determines enthalpy tables to calculate Items 24 through from steam tables.

30 on attachment 1.

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)

3. (*) Applicant calculates items 31 Correctly calculates Q to through 34 on attachment 1. feedwater.

31. 8.03 (7.97-8.09)

32. 367.4 (363.9-370.9) 33.1191.9 (1191.2-1192.6)

34. 1940.4 (1935.4-1945.4)

RO ADMIN JPM A-1-1.doc 6

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON ELEMENT STANDARD SAT UNSAT Comment Number

4. (*) Applicant calculates items 35 Correctly calculates Q to CRD through 36 on attachment 1. flow.

35..037 (.036-.038) 36.12.2 (11.9-12.5)

5. (*) Applicant calculates items 37 Correctly calculates Q to through 39 on attachment 1. i Cleanup system.

37.. 156 {.154-.158}

38. 92.5 (90.5-94.5) 39.4.24 (4.04-4.44)

6. (*) Applicant calculates items 41 on Correctly calculates QPUMP attachment 1. 41.1.58 (1.38-1.78)

7. (*) Applicant calculates items 42 Correctly determines core thermal power.

through 43 on attachment 1.

42.1956.3 (1947.5-1965.1)

43. 77.1 (76.8-77.5)

Task is complete.

JPM Stop Time _ _ _ __

RO ADMIN JPM A-1-1.doc 7

NRC JAMES A. FITZPATRICK INITIAL EXAMINATION l? XA-tI\ (. '-i HEAT BALANCE CALCULATION JHEET Page 1 of 1 PERFORMED BY: _ _ _ _ _ _ _ _ _ _ __ DATErnME: _ _ _ _ _ _ __

PURPOSE:

PANEL 9-4 9-4 9-4 A 9-4 r B 9-4 9-5 I 1

\

16.

17. OF

° HI. of

'19. OF

'20.

21.

22.

28.

24. HS

= '25.- HFG'

'26, HFWA

, *27. HFWB

28. HCUI

29. HCUO

30. HeR PARAMETER 31.

32.

33.

34.

36.

31.

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: _ _ _ _ _ _ _ _ _ _ _ __ Dateffime:_ _ _ _ _ _ _ _ __

Reviewed By: _ _ _-=----:--::--:---:---:=----:---:~--- Dateffime: _ _ _ _-'-_ _ _ __

Reactor Engineering $upertl:ltendent

- This IS a Quality . ,

Reeord RAP-'7.3.03 CORE THERMAL POWER EVALUATION ATTACHMENT 1.

Rev. No. 13

~~ftrM \(;E'f pag-e g of 16 .

NRC JAMES A. FITZPATRICK 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-1-1.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION HEAT BALANCE CALCULATION SHEET Page 1 of 1 PERFORMED BY: _ _ _ _ _ _ _ _ _ _ _ _ _--,.- DATEITIME: _ _ _ _ _ _ __

PURPOSE' "EM PARAMETER PANEL INSTRUMENT VALUE IJNfTS

1. Cleanup 'rnet Temp 9-4 12TSS*142 POS 1 ~Oa 'F

2. Clltenup Outlet Tamp. 9-4 12TSS*142POS 4 '-l~O 'F

3. Cleanup Flow ,A 9-4 I .<;' q GPM 4.

6.

1.

8.

Cleanup Row B

~to ReGirc. Pump A to Recire. PumP B Total Core Flow Reactor PrellSure jpsig + 14.71 9-4 9-4 94 9*5 9*5 R RW M BGENPWR 02*3DPRIfR.95 06PRlFR*9B ENPWR 6

I "

(},~('"

as-4'7 ULd...c;.

GPM MW MW Mlbihr PSlA

9. CROFlowto~ 9-5 03FI-310 s;-q OPM 91l RWR& RWCU wa Constant 15 GPM

10. CRD Svstam Temp Constant 95 Of

11. Gross~ 9-1 MAIN OEN MW G~< GMWE

'12. Feedwate 9*5 06FI-B9A .'1LQ' MLB/HR

'13. Feedwater Flow 1.000 B 9-5 06R-69B 4 . ..,.., MLBJHR

14. TANA use PTIO 407/410 or 9*21 02TT*168A1C 'b <j ~ I aq;" OF Hi. TFWB, use PTIO 408'411 or 9*21 02TT*16881O ~ql.q /J'lJ.<t"F FEEDWA TER now CAtcULA170NS

'16. Aver_ lANA {407+410)12 Of (1a8A+ ISBCl/l OF

'17. Average TANB (408'+411Jf2 or {1688+1680)/2 OF

'18. Delta T Loop A (OTA) - TANA

420 OF

'111. Delta T loop B IDTB) '" TANB - 420 °F

'ZO. C.F. '" 1.0 + {OTA'I-3,B064£-4 + (OTA '-4.4310E*7JJ)

"21. C.F, .. 1.0 + {DTB*t-3.8064E-4 + IPTB*-4.4310E-7lJl "22. Compensated Flow A 1112

120) MlBIHR

'23. ComDensllted Flow S' (#13

821) MLBIHR PARAMETER ITEM DATA USED VALUE IJNIT$

24, HS 118. BTU/LB II

- .. .. ble

'B,*

r _~,

"25. llFG BTUfLB

'26, HANA 118 816, BTUILB

27.. HFWS #8 #17 BTU/LS

28. HCUI #8 #1 ASME,Table STU/La

29. HCUO 8B, 1!1. ASMETable BTOILS

30. HCR #8 #10. 'ASMETable BTU/lB PARAMETER EQUATION ffTEM tI"'SI VALUE IJNfTS

31. Total Felldflow (#22 + 823) MlBIHfl

32. Faedwatllf EnthalllV 1(#26*#221 + (627"12311'631 BTU/LB

~

33. Steam Enthalpy BTU/LB

34. Q to fe.dwattr (OAN) *(#3 3

35. CRO flow (WeRI

36. Q to CRD flow (Q'CRl

37. Total CV flow IWCUJ

O.

]!r35 *(133' 630 113.413 (83 + #4) *(0.498E-3)

(#9a

0.49BE*311

~

38. HCUI ~HCUO

31. a to Cleanup 5Y$

40. Veesel ambient kl$s

('28 - 829)

(#38' 837113.413 ~

1.1 MWt

41. OPUMP IS)* 0.93 MWt

42. Core Thermal Power 38 + 839 + '40* #411 MWt 43 CTPIZ536 1#4 3~' 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: _ _ _ _ _ _ _ _ _ _ __ Datemme!_ _ _ _ _ _ _ _ __

Reviewed By: _ _ _-::---:--=--:---:--:::---:--_~:__:'--- Datemme: _ _ _ _..:-.._ _ __

Reactor Engineering Superintendent

- This ~ a Quality Record RAP-7.3.03 CORE THERMAL POWER EVALUATION ATTACEMENT 1 Rev. No. 13 page 11 of 16 .

ROAr.

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON RO ADMIN JPM A-1-1.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION 512010 JAMES A. FITZPATRICK Job Performance Measure Work Hour Restrictions JPM Number: RO A-1-2 Revision Number: 0 Date: 03/11/2010 Developed By: B. Litkett 3/1112010 Author Date Validated By:

Facility Technical Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date RO ADMIN JPM A-1-2.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION 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.

1. Task description and number, ..IPM 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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date

9. 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:

1. Not Applicable RO ADMIN JPM A-1-2.doc 2

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 REVISION RECORD (Summary):

1. This . .'PM is the original revision O.

..IPM Setup Instructions:

Provide applicant with the following:

JPM handout sheet TASK STANDARD:

Determine any work hour restrictions RO ADMIN JPM A-1-2.doc 3

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 TASK CONDITIONS:

A Reactor Operator has called out sick for Thursday, May 6th Day Shift.

The following is the recent work hour history of 4 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 T T T Week of April 12 Week of April 19 T

l-I D D Week of April 26 D 0 N N Week of May 3 N N D D D Week of May 10 N N N I 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 [) N N N Week of May 10 D D D Week of May 17 N N N N RO - Jane Riley M T W T F S S Week of April 26 T T T T T Week of May 3 D D D D D Week of May 10 D N N N Week of May 17 I D D D D N Week of May 24 N I N N RO ADMIN JPM A-1-2.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 4 Reactor Operators. Determine which operators can take the scheduled watch for a full dayshift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 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.

RO ADMIN JPM A-1-2.doc 5

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

Title:

Work Hour restrictions JPM Number: RO A-1-2 Revision Number: 0 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.O; Fatigue Management program 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: Satisfactory Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

RO ADMIN JPM A-1-2.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON 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 The applicant obtains a procedure EN-OM-123 Rev.O; Fatigue controlled copy of EN-OM-123 Management program Rev.O; 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. AP 11.03 no longer applies to operators on shift.

RO ADMIN JPM A-1-2.doc 7

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 ELEMENT STANDARD SAT UNSAT Comment Number

2. Step 5.2. Working hour limits for Applicant evaluates each covered individuals. listed operator against limitations of EN-OM-123.

A. Work hour limits for individuals performing Covered work consist of three concurrent components; maximum ceilings, minimum breaks and Minimum Days Off (MDO)

(1 ) The maximum ceilings which apply at all times are a maximum of:

16 work hours in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period,

26 work hours in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, and

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period.

(2) The minimum break times which apply at all times are a minimum of:

(a) 10-hour break between successive work periods, except that an 8-hour break is allowed when necessary to accommodate a crew's scheduled transition between work schedules or shifts, and (b) 34-hour break in any 9 day period.

(3) EN-OM-123; step 5.2.4 describes MDO:

(a) For Operators working a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift, the requirement is to average a minimum of 2.5 days off per week.

The average days off per week is averaged over a shift cycle of up to 6 weeks in duration.

~O ADMIN JPM A-1-2.doc 8

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 ELEMENT STANDARD SAT UNSAT Comment Number

3. Evaluate John Smith for overtime. Applicant determines John Smith can NOT take the watch because he would not have a 34 hour3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months uninterrupted break in the nine days from May 1 to MayS.

4. Evaluate Bill Waters for overtime. Applicant determines Bill Waters can NOT take the shift because he would exceed the 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period requirement. The night shift of May 5 will end at 7 am and Day shift May 6 starts at 7 am.

So with no time off between shifts, will end up working 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months straight.

5. Evaluate Mike Hill for overtime. Mike Hill can work the shift.

He would have a 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months break from May 4 to May 6 and for the week he will have 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months which is allowed, and for the cycle he will have 13 days off. The MOO, when working a five week cycle requires 12.5 days off, which rounded up is 13 days off.

Therefore he meets the MOO req uirement.

6. Evaluate Jane Riley for overtime. Jane Riley can NOT take the shift because she would exceed the MOO of 2.5 days off per week. For a 5-week cycle she needs 12.5 days off over the entire cycle to average 2.5 per week. She currently has 13 days off, but working one additional day will take her to 12 days off which is below the required minimum amount of days off.

Examiner: Terminate the task at this point RO ADMIN JPM A-1-2.doc 9

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-1-2 JPM Stop Time _ _ __

RO ADMIN JPM A-1-2.doc 10

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Handout Page TASK CONDITIONS:

A Reactor Operator has called out sick for Thursday, May 6th Oay Shift.

The following is the recent work hour history of 4 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.

WI~

RO - John Smith M T F Week of April 12 T T T So Week of April 19 o 0 Week of April 26 0 0 N N Week of May 3 N N 0 0 0 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 0 0 0 0 Week of April 19 0 N N N Week of April 26 0 0 0 0 N Week of May 3 N N[]J RO - Mike Hill M T T S S Week of A ril19 T T T Week of A ril 26 Week of Ma 3 0 0 Week of Ma 10 Week of Ma 17 N N i RO - Jane Riley M T W T F S S Week of April 26 T T T T T Week of May 3 0 0 0 0 0 Week of May 10 0 N N N Week of May 17 0 0 0 10 N!

Week of May 24 N N N

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION Handout Page INITIATING CUE:

Evaluate the work hour history for each of the 4 Reactor Operators. Determine which operators can take the scheduled watch for a full dayshift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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. FITZPATRICK Job Performance Measure Initiate a manual tagout for 'B' RHR pump discharge check valve replacement

,JPM Number: RO A-2 Revision Number: 1 Date: 03/09/2010 Developed By: B. Litkett 03/09/10 Author Date Validated By:

Facility Technical Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date RO ADMIN JPM A-2.doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - - - - -

9. 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:

1. Not Applicable RO ADMIN JPM A-2.doc

REVISION RECORD (Summary):

1. This JPM is the original revision 01

2. REFERENCES

a. EN-OP-102Rev.12

b. EN-OP-102-01 Rev.6

c. OP-13 Rev. 94

d. FM- 208 Rev. 68

3. TOOLS AND EQUIPMENT

a. Current copies of OP index and references.

4. SET UP REQUIREMENTS

a. Applicant has been assigned to prepare a tagout.

5. EVALUATOR NOTES

a. Examiner's copy of component positions (Answer Key) is provided.

b. The Applicant should demonstrate proper use of all HU tools during the performance of the procedure.

c. 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".

d. If Applicant asks for a copy of the work order state this was reviewed and no additional information was obtained.

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.

RO ADMIN JPM A-2.doc

The time clock starts when the Applicant acknowledges the initiating cue.

Operator's Name:

Job

Title:

Title:

Initiate a manual tagout for '8' RHR pump discharge check valve replacement JPM Number: RO A-2 Revision Number: 1 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: 15 minutes Actual Time Used: _ _minutes

References:

EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? DYes 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: D Satisfactory D Unsatisfactory Comments:

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: ____________________________(Print)

Evaluator's Signature: Date: _ _ _ __

RO ADMIN JPM A-2.doc

TASK CONDITIONS:

Currently all systems are operable INITIATING CUE:

A tagout is required on the "8" RHR system to conduct repairs on 10RHR-428; discharge check valve. Work scope is to replace valve internals per WR 123456789. eSOMs is out of service and the SM has directed the use of a manual tagout required 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 tag out RO ADMIN JPM A-2.doc

PERFORMANCE CHECKLIST:

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-102-01; attachment 9.2 blank copy of EN-OP-102-01; 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 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 -10P PUMP CONTROL SWITCH; STOP; 2B; RHR B KEEPFULL PUMP sequence 1. CONTROL SWITCH; STOP; sequence 1.

5. (*)1-71-71 MCC-163-0E1; 10P-2B; Applicant selects 1-71 RHR B KEEPFULL PUMP BREAKER; 71 MCC-163-0E1; 10P-2B; OFF/REMOVED, sequence 2. RHR B KEEPFULL PUMP BREAKER; OFF/REMOVED, sequence 2.

6. (*) 1 -71-10540 BKR CLOSE Applicant selects 1 -71 FUSE; Fuses removed; sequence 2. 10540 BKR CLOSE FUSE; Fuses removed; sequence 2.

7. (*) 1 CKTBKR-71-10540 racked Applicant selects 1 out/removed; sequence 3. CKTBKR-71-10540 racked out/removed; sequence 3.

8. (*) 1 -71-10540 BKR TRIP Applicant selects 1 -71 FUSES; fuses removed; sequence 4. 10540 BKR TRIP FUSES; fuses removed; sequence 4.

RO ADMIN JPM A-2.doc

ELEMENT STANDARD SAT UNSAT Comment Number 9.(*) 1-10 -VALVE 10RHR-45B; 'B' RHR Applicant selects 1-10 discharge isolation valve, CLOSED, VALVE 10RHR-45B; 'B' RHR sequence 5. discharge isolation valve, CLOSED, sequence 5.

10.(*) 1 -10MOV-13B [KEYLOCK Applicant selects 1 SW] TORUS SUCT VALVE; CLOSED; 10MOV-13B [KEYLOCK SW]

sequence 6. TORUS SUCT VALVE; CLOSED; sequence 6. I

11. (*) 1-10 -10MOV-15B (SW); Applicant selects 1-10 SHUTDOWN CLG VLV; CLOSED; 10MOV-15B (SW);

sequence 6. SHUTDOWN CLG VLV; CLOSED; sequence 6.

12. (*)1 71 MCC-163-0J4; 10MOV Applicant selects 1 71 13B RHR PUMP B SUCT FROM MCC-163-0J4; 10MOV-13B SUPPRESSION POOL ISOL RHRPUMP BSUCT FROM VALVE;OFF/REMOVED; sequence 7. SUPPRESSION POOL ISOL i VALVE; OFF/REMOVED;

sequence 7.

13. (*) 1 71 MMC-163-0D1; 10MOV Applicant selects 1-71 15B RHR PUMP SUCT SHUTDOWN 71MMC-163-0D1; 10MOV COOLING ISOL VALVE; 15B RHR PUMP SUCT OFF/REMOVED; sequence 7. SHUTDOWN COOLING ISOL !

VALVE; OFF/REMOVED; i sequence 7.

14. (*) 1 VALVE- 10MOV-15B; RHR Applicant selects 1-10 PUMP B SUCT Shutdown Cooling ISOL, VALVE- 10MOV-15B; RHR CLOSED, sequence 8. PUMP B SUCT Shutdown i

Cooling ISOL, CLOSED, sequence 8.

15. (*) 1-10-VALVE- 10MOV-13B; RHR

Applicant selects 1-10-VALVE PUMP B SUCT TORUS ISOL VALVE;

10MOV-13B; RHR PUMP B I CLOSED, sequence 8. SUCT TORUS ISOL VALVE; CLOSED, sequence 8.

16. (*) 1-10-VALVE-10RHR-251B; RHR Applicant selects 1-10-VALVE PUMP B SUCT DRAIN VALVE; 1ORHR-251 B; RHR PUMP B I CLOSED; sequence 9. SUCT DRAIN VALVE;

CLOSED; sequence 9.

17. (*) 1-10 -VALVE-10RHR-28B; RHR Applicant selects 1-10 PUMP B MIN FLOW ISOL VALVE; VALVE-10RHR-28B; RHR CLOSED; sequence 9. PUMP B MIN FLOW ISOL VALVE; CLOSED; sequence i i

9. I I RO ADMIN JPM A-2.doc

ELEMENT STANDARD SAT UNSAT Comment Number 18.(*) 1-10-VALVE-10RHR-91B; RHR Applicant selects 1-10-VALVE KEEP-FULL PUMP B SUCT ISOL 1ORHR-91 B; RHR KEEP VALVE;CLOSED; sequence 9. FULL PUMP B SUCT ISOL VALVE; CLOSED; sequence 9.

19.(*) 1-10-VALVE-10RHR-250D; RHR Applicant selects 1-10-VALVE Pump D DISCH DRAIN VALVE, 10RHR-250D; RHR Pump D CLOSED, sequence 9. DISCH DRAIN VALVE, CLOSED, sequence 9.

20. (*) 1-10-VALVE-10RHR-250B; RHR Applicant selects 1-10-VALVE PUMP B DISCH DRAIN VALVE; OPEN; 10RHR-250B; RHR PUMP B sequence 10. DISCH DRAIN VALVE; OPEN; sequence 10.

21.(*) 1-10-VALVE-10RHR-253; RHR Applicant selects 1-10-VALVE Pumps B & D DISCH DRAINS TO EQUIP 10RHR-253; RHR Pumps B &

~UMP ISOL VALVE; OPEN; sequence 10. D DISCH DRAINS TO EQUIP SUMP ISOL VALVE; OPEN; sequence 10.

22.(*) 1-10-VALVE-10RHR-682; RHR Applicant selects 1-10-VALVE PUMP B DISCH DRAIN VALVE; 10RHR-682; RHR PUMP B UNCAPPED & OPEN; sequence 10. DISCH DRAIN VALVE; UNCAPPED & OPEN; sequence 10.

23.1-10-VALVE-10RHR-698: RHR PUMP Applicant selects 1-10-VALVE B DISCH SPARE INSTRUMENTATION 10RHR-698: RHR PUMP B ISOLATION VALVE: UNCAPPED & DISCH SPARE OPEN; sequence 10. INSTRUMENTATION ISOLATION VALVE; UNCAPPED & OPEN; sequence 10.

Task is complete.

RO ADMIN JPM A-2.doc

ANSWER KEY Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.2 TAGOUT COVER SHEET Clearance: Manual Tagout: 10-RHR-42B-MAN Component to be worked: 'B' RHR pump discharge check valve

==

Description:==

Repair 10RHR- 42B - replace valve internals Placement Inst:

1.) Ensure MOVs are CLOSED prior to tagging open breakers.

2.) Ensure condensate transfer is for keepfull for '0' RHR 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 Description Attribute Value LCO N Work Order Number 123456789 Status Descri ption User Verification I Date Prepared Prepared Technical Reviewed Reviewed Approved Approved Tags Verified Hung Tags Verified Hung Removal Approved Removal Approved I Tags Verified Removed Tags Verified Removed RO ADMIN JPM A-2.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON 512010 nnmmm]

ATTACHMENT 9.3 ANSWER KEY TAGOUTTAGS SHEET Cl MANUAL T ~~~~ ..

Tag Equipment Place. Place. Rest Restoration 51

~st.2na PlacemenUl, ierial Tag Equipment Description Place. Placement 1st Verif 2nd Verif .Seq Configuratio Rest. 1 Verif Verif Removal I No. Tvpe Equipment Location Seq. Configuration DatelTime DatelTime n DatelTime DatelTime TaQ Notes i D 10P-3B; 'B' RHR pump control 1 Auto after Stop switch D 10P-2B; 'B' RHR Keep full pump 1 Stop control switch D 1-71-71 MCC-163-0E1 2 OFFI REMOVED :

D 1 -71-10540 BKR CLOSE 2 Fuses FUSE removed D 1-71 CKTBKR-71-10540 3 Racked ouURemoved D 1 -71-10540 BKR TRIP 4 Fuses FUSES removed D 1-10 -VALVE 10RHR-45B; 'B' 5 CLOSED RHR DISCHARGE ISOLATION VALVE.

D 1-10 --10MOV-13B [KEYLOCK 6 CLOSED SWj TORUS SUCT VALVE.

D 1-10 10MOV-15B (SW); 6 CLOSED SHUTDOWN CLG VLV D 1-71-71 MCC-163-0J4; 10MOV 7 OFFI 13B breaker REMOVED D 1-71-71MCC-163-0D1 ;10MOV 7 OFFI 15B breaker REMOVED D 1 VALVE-10MOV-15B; RHR 8 CLOSED PUMP B SUCT Shutdown Cooling ISOL D 1-10-VALVE-10MOV-13B; RHR 8 CLOSED PUMP B SUCT TORUS ISOL VALVE D 1-10-VALVE-10RHR-251B; RHR 9 CLOSED PUMP B SUCT DRAIN VALVE D 1-10-VALVE-10RHR-28B; RHR 9 CLOSED PUMP B MIN FLOW ISOL VALVE RO ADMIN JPM A-2.doc

I NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-2 ATTACHMENT 9.3 ANSWER KEY TAGOUT TAGS SHEET D 1-10-VALVE-10RHR-91B; RHR 9 CLOSED KEEP-FULL PUMP B SUCT ISOL VALVE

0 1-10-VALVE-10RHR-250D; RHR 9 CLOSED Pump D DISCH DRAIN VALVE D 1-10-VALVE-10RHR-250B; RHR 10 OPEN PUMP B DISCH DRAIN VALVE D 10RHR-253; 'B' and '0' RHR B & 0 10 OPEN

!DISCH DRAINS TO EQUIP SUMP ISOL VALVE 0 1-10-VALVE-10RHR-682; RHR 10 UNCAPPED PUMP B DISCH DRAIN VALVE and OPEN D 1-10-VALVE-10RHR-698: RHR 10 UNCAPPED PUMP B DISCH SPARE and OPEN INSTRUMENTATION ISOLATION VALVE JPM Stop Time _ _ __

RO ADMIN JPM A-2.doc 11

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION ADMIN RO JPM #A-2 HANDOUT PAGE TASK CONDITIONS:

Currently all systems are operable INITIATING CUE:

A tagout is required on the "8" RHR system to conduct repairs on 10RHR-428; discharge check valve.

Work scope is to replace valve internals per WR 123456789. eSOMs is out of service and the 8M has directed the use of a manual tagout required 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-2.doc

JAMES A. FITZPATRICK Job Performance Measure Liquid Radwaste Potentiometer Settings JPM Number: RO A-3 Revision Number: 0 Date: 03/04/2010 Developed By: 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 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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _ _ _ _ __

9. 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:

1. 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 CONDITIONS:

Current plant conditions are as follows:

The plant is at 70% power

2 Circulating water pumps (36P-1A1B) running

2 Service water pumps (46P-1A1C) 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 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%

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:

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: _ _m,inutes

References:

1. SP-01.05, Wastewater Sampling and Analysis, Rev. 10

2. SP-03.07, Liquid Process Radiation Monitors, Rev. 6 EVALUATION

SUMMARY

1. Were all the Critical Elements, performed satisfactorily? 0 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 0 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 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 I

3. APPLICANT CALCULATES Canal APPLICANT CALCULATES Dilution Factor (CDF) Canal Dilution Factor (CDF)

ATTACHMENT 1 #11.

11.7.25E-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 (BCA) ATTACHMENT 1 #13.

! 13.1.638 E-6

6. APPLICANT CALCULATES Hi/Hi APPLICANT CALCULATES setpoint value ATTACHMENT 1 Hi/Hi setpoint value

14.

14.1.58 E-3

7. APPLICANT CALCULATES Hi APPLICANT CALCULATES Hi setpoint value ATTACHMENT 1 setpoint value

15.

15.7.91 E-4 RO ADMIN JPM A-3.doc

ELEMENT STANDARD SAT UNSAT Comment Number

8. (*}Obtain 17RM-350 potentiometer Applicant determines and setting for Hi-Hi setpoint from records 17RM-350 Sample Activity vs. Alarm Pot potentiometer setting for Hi-Hi Setting graph setpoint from Sample Activity vs. Alarm Pot Setting graph 16.7.3 turns (7.2-7.4)

9. (*) Obtain 17RM-350 potentiometer Applicant determines and setting for Hi setpoint from Sample records 17RM-350 Activity VS. Alarm Pot Setting graph potentiometer setting for Hi setpoint from Sample Activity VS. Alarm Pot Setting graph

17. 7.4 turns (7.3-7.5)

Task is complete.

JPM Stop Time _ _ _ __

RO ADMIN JPM A-3.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION ADMIN RO JPM #A-3

!?.lIGB 1 OF 2 W'A cm.ya:r:nw

1. Ii'WIIber of -:In; <Ii.1:cu1'lting

2. Nud>er o~ J:\IIming service water

_r ~

pwIIlI.

f"61>-lAIBlC'l' 46li'-lA/e/Cl,

?.-OD _

). 'J'I1rIk D~ Flow};late C~_ I (l)II'l!),

- 'flIIn'I¢ 1\I:1:1v1t1' I~h 2. ,'2.1 e ~ 1iCi/lltl

!>. li!eQII4r.s DihJti.,.. ,..,tor (Drl \.0

6. <:u:n:ct Ll.quld IIadIIute I!IImitor l1'1'l1Jt.lSO) r<Md:I.lIQ IlA'IC-A.UO'I.

_. Bac~ MQul4 be . .~ ..... ftIiIJ 1000 <:pt.

7. Liquid IIaIh1uI:<t MQII.itol: (17l1K-l501 poooteC ~l

8. U<;\\lld ~tA _J.~Ql:' C17lUf-3$O) !c*'A\:\,;or,

,. 'I'~dlllif gate Uow (ane..",-3"')

10'. OInal 1'1_ RAta Cent) '!lilia' en. H' Cin ~ X 121).{100) + It nrri..,. _tor J>lIIIPII X J.8.000H X [1 - It ~111'1 I 100))

en .. Ull X 1:10.001.1) .. ttl! lI: 18,OOfIlJ X [1 - I" I 10ll1}

CPR

II '2- II llO,OllI)) + I 1,. X 18,000)1 x (l - <_......Q......._ f lOOll CPR- '}"')ls,ooO _

11.. ~ 1)1~ Factor tCDPl cor

fl'tIM: Di~ now _,,) I (~l Flaw Rat",

cor

Inl I (ftOJ cor .. ( 1 cD I kl~ obQ

aw- "1,1.)" o(o-f I

_ . 11'.. _.t.

U. Il'ftceion of AllOW01ld OUuUm IF$)

be , . . .... 1.0 for ti~e..

v... tOlnal OU,.timl :n.ct:e) It {1lequiEed 1)11,.\,;1<111 Plit.Ol:CI¥,

V, .. (fl.l' :x (t51 _ 'f 1".'" ].4f'X(O x _ _ _ _ _ _ __

..... 7,2.$ X(O-'"f I SIt-Ol.OS Rw. 19 0%

RO ADMIN JPM A-3.doc

/"(U AVM1N J1"'M A-~.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON ADMIN RO JPM #A-3 PAGE 2 OF 2 CALcrJLATIQl!!S (Cont)

u. ~W14 Correction lIoctivit;y llICAl in ;<Ciflll I!CA" (~t 17!IH-3!lO re...unq - 17l'mJ1-lS0 background) x 17RK-350 X*I'_r BCA ~ (If; - *') X (t8)

IICh ( 1.-9 , ~

1lCA. It ~ :S"'2> )( (u

14. ClilCIIllite aillti Htpo1n't vlOlue in ;<Cilml, Hi/iii .a'tpc>int value " [TanI< Mtivity I 12 X 1'.11 ~ [BCA)

Hi/Hi IOtII;pOlnt value - ['4 I III X ft2ll + {lU) -4 HiJli1 .etpo1t1t v;r.lue M 11.;'1.3 )('/0-" I <<_ X 7,]. $"?C /1>1) +

!ll/ai ""'tpc>int veL".. " IS t f! 0- 1 SlCi/llll

15. calculate Hi ...'tpc>int value in SlCllllll' 111 seepoint value" 1'l'arIk lIoctivity I (4 'It It.) l + BCA Hi ..et:point v.llMl .. ttl I (4 X '12) J .. IU3) _. " _(,.

at Q\:t>Olnt vallie. I '2..2. 11 Ng-'" I 14 l'. 7, Z) (fO ) I ... _ f, C, 3'i 'f (0 Hi ."t'i)(lint Val"'e ~ 1 *(II X Ii) -It uClllJll

15. Obl:<\in 1711M-3S0 1I1.1H1 alam potenti<l!l1liOtttt :setting, u.d"ll HifHi _point value "C1;l.vlty, fron current t.l<l11.id l!adwut:oa lI(mJ,tor *~l.. Act!.vity v~ lUlll:'III Pot SIIn1M' gro,p~.

lIi/Hi Alano pot""tiOlMter "tting 7. "3 (..,. ~ -') (:1)

17. Obtain 17_350 111 IIlU1II potentiOGlltter _tiM. "sing 111 1U.tpoint value "(lelvhy, frCIII curren" Liquid ....,.,..."t.. ""'n1t"" "San\ple Ml:ivity v.:** Al~ Pot li<iIttin!'l' g;raph.

!iii AlM1ll J,'IOtcU_".. satt.i1ll1 7, tf b, ~ - 7,_'l)

Performed b;t. A f f \ ~ c. <zy>+Sign+/-'t ; l \":>

Plo'int. I Pate (tV Independent ver1ficat100 ,

Print I Bi'iIU I Data l8. Gnl:<!r Hi .....s lIiJIii ,u0J:l'l potClti-.. .~t~ on ni.ociw:ge permit lAl:t:MbIIIenI: 2) ,

~ ~ 10 lJJ M"l'.IiCIfBIJ '10 J)J:1iK'lIII.lV;lB HIllIn' I Sp..Ol.05 Rev * ...lA..

A~ACHMIi!iN'P POlga; of f5 l{) I RO ADMIN JPM A-3.doc I'

0 s:

c....

liquid Radwaste Effluent Monitor Sample Activity vs. Alarm Pot Setting 1J 9 s:

R.*-. --rLL\-t ttj----L-l~. . -.H~.!!--llFff-+l~j-l

_ ,-- ~~~,~ . H~l::~-~l=-:~--_='-. -~

r:l;'~5~rf':-ir ';I;02L",~~1- ~ ...~ ..~ itt~=~..i~_f

t>

, ,. i.-. I--- - -

~

c..

0 1-..

()

8 --1 SoIveforaJarmpotseltil'lg(y)

. ~ :r--F q--:;:1ftF:~ ::'::l--

r- -.. --,' m- -j I 1- -,

~--

r-I--

~-~

~ I ___ ......b..l""'~-1H-l

~~.'--~--

II!

c::

1- __ ._L *t- t' ,-1 t' ~-- "-

II

- ---1 '--, r ! 1- --- -----rj ,I I I i1' t- t.- -.. -!::lliIh Alarm Curve--+---__

! I

,----1----

.j--

j....~

I __

~l----+

j....o 1 ..

L.,..-"'"

~- r~t 'j ,-r d.1---- r--- t l' i

.--1-- ~~

-f

l

t!'~

i ' _

tl:!

c 7

+ 1 I 1 H-, : i - ---, 11- 1 ~---

)1 :. . -~? '. _ - -

il._ - t--jLtt-1'i-----t'--l I !~ - ..- It... t-*

- T t* t'l11 i-- !i

\'I) :>. I i I: : I .;"',....

1-- _.. - - I-+t ~ ",,::_+j....o'-'--+"'F-l-H+---*--l-- I--*--*-\---**!--*I--- ...-- 1-

.--- r-- t ii ; l -i t--

(f';-

'5 +~ :..~~ ? t~ c-- - ++-H-------I-----l--Il- 1+1-+++--- ---+. *f a.. -t j -'! . - - --y ~i-- - .... -r:-" - __ ___ '] f -- -+

E 6 - -~I .-j - + -I k1,..1- ~

L...--'" - +._"

. - 1H' h H' hAl

_~ t 19 - 19 r- .. _,~ !--

arm vum::1

. -*---f-*_* f--j--- t ...*..*- ~.- ++",+-1-1 t~~~"'p -~ -.-- ~J~~JJ-prlr- ~=: ,- ~:~+

<<Ii

~ - i-+----c--

=~!-=...+ . . . . -..... - .....

I-I - t Trt-=-~~t-~' -~-. -

-h'.~.2ln(x) +8.6,---f.---...

f-

~---':.=~~+-+++++I 1-5 !--

---*r* .-j-. ,.... -"'fT I-----t~ -f-. 1- t--+ ...+-.

'.~: =1.. 1____ '- ".-. ~= --tit -~ -.---t=~r 1-- ! t ~--~- .-...j--l.+.l-+i~

-r--"'" f--**

i'

, ---. +!'-T'-I- - I J.1 1\ '

1+"--'-'-\-,-1-. ++-++.H II 4

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)

Cal Date 7/1512009 NOTE: ---q----->> INCREASING ACTIVITY ----_._**__ >>

HIGH ALARM POT .. HIGH-HIGH ALARM POT 00 Not Use After I I I 6 J0 ? 711512009 Prepared By'. * %4.r:----...1?- £

PAGE 1 OF 2

2. Numb..r af remninq &ervice ..acer PUllIpfl 46P-1AfB!C):

3 _ 'rank llisch..u".. Flow Rate (MaximlUl'l) (llFR): -----qpnl

_______ ,iJ:Cifml

____________ cps

i. Liquid Rad_lIt.., Monitor (11HX-HOI posted backllTound,

____________ cpa Il. Liquid !!adw.tste Monitor Il"IRM*)I}(li K-FaClor: __________ !SCl/mlle.,,.

9. 'T'_dnQ l1<1te flo... 1l1.I"1(;--A-15.'11 CALCULATIONS CFR ~ rr41 X 120. (lOll)

it2 X 16.0001 J X 11 - {f9 ;' 1(0):

erR !{ _ _ _ _ _ l( 120,\lOOI * (_ _ _ _ _ _ _ _ _ x :S.OOO)) x 11 - {_ _ _ _ _ ! 1(0)J CPR ~

~

It. Canal Oilu~iQ" Pactar (CDF)

COP 12 Y,acU,,'1 of Allowed OduUon (1'\)

lIonh F :ruB t be Lll88 'l'lIaR 1 _{! for dbcharge.

_ _ _ _ _ _ _ _ x _ _ _ _ _ _ _ __

WAS'['EWATER SAM.PLINO AND ANALYSIS RO ADMIN JPM A-3.doc

LIQUID BAOWASTE EfFLUENT MONUQR ALARM POT SETTING DETERMINATION WORKSHEgT PAGE 2 OF 2 CAI,c!JLbTIONS (Con t )

3. hclt;:tround Correction Activity (BeA) in .i.lCi/ml BeA (Current 17RM-350 readinq - 17RM-JSO background) X l1RM-3S0 X-Factor BCA = ) X _ _ _ _ _ __

ElCA " I"C !lml 14 CalculAt@ HilHi setpoint value in I<'Cilml:

HilHi setpoint val1le [Tank Activity I (2 x F.l] + (SeAl Hi/Hi setpoint vatu .. [.4 I (2X f12) J + (liB)

Hi/Hi ~etpoint value (2 x _ _ __ IJ + _ _ _ _ __

Hi/Hi setpoint vnlc.., _ _ _ _ _ _ _ lIei/ml

15. Calculate Hi "etpoint valUE! in ..Ci/ml; Hi setpoint value [Tetnk Actlvil:y ! (4 X F,,lj . ElCA Hi set);)oint value ff4 (4 X t121! . ItL))

IU seq,oint value ~ (4 X ): ..

Hi setpoint value

- I<'ci /ml

16. Obtain 17RM-350 Hillli alarm pocentiOllleter setting, using Hi/Hi setpoint value activitv, from current Liquid Radwaste MOnitor 'Sample Activity vrs. Alarm Pot Setting' graph.

Hi/Hi Alarm potentiome~er setting

17. Obtain 1?RM*3S0 Hi alarm potentjorr~ter setting. using Hi setpoint value activity, from current Liquid Radwaste Monitor 'Sample Activity VI'S, Alarm Pot Setting' graph.

Hi Alarm potentiomet~er ..aU.ing Performed by:

18. Independently verity calculations AID alarm potentiometer settings.

independent verification :

Print ! Sign I Date

18. Ent.er Hi and HilHi alam potentiometer settings on Di5charqe permit (ALtachment 2).

SP-Ol.05 WASTEWATER SAMPLING AND Rev * .-l..IL ANALYSIS Pa RO ADMIN JPM A-3.doc

LIQUID RADWASTE EFFLUENT MONITOR ALARM POT SETTING DETERMINATION WORKSHEET (CANDIDATE HANDOUn DATA COLLECTION

1. Number of running circulating water pumps (36P-1A1B/C):

2. Number of running service water pumps (46P-1A1B/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/mllcps

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 1100)]

=

CFR [(#1 x 120,000 + (#2 x 18,000)] x [1 (#9/100)]

CFR = [( x 120,000) + ( x i8,000)] x [1 -- ( 1100)]

CFR = gpm

11. Canal Dilution Factor (CDF)

CDF = (Tank Discharge Flow Rate) I (Canal Flow Rate)

CDF = (#3) I (#10)

CDF =( ) I(

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) x (#5)

FL ( )x( _ _ _ _ _ _ _ __

FL RO ADMIN JPM A-3.doc

LIQUID RADWASTE EFFLUENT MONITOR ALARM POT SETTING DETERMINATION WORKSHEET (CANDIDATE HANDOUT)

CALCULATIONS (Cont.)

13. Background Correction Activity (BCA) in uCi/ml BCA [(Current 17RM-350 reading) - (17RM-350 background)] x (17RM-350 K-Factor)

BCA =(#6 - #7) x (#8)

BCA =( ) x BCA uCi/ml

14. Calculate Hi/Hi setpoint value in uCilml:

Hi/Hi setpoint value =[Tank Activity I (2 x FL) ] + (SCA)

Hi/Hi setpoint value =[#41 (2 x #12) 1+ (#13)

Hi/Hi setpoint value [ / (2 x -=-:-.,...--:-_ _ _ _ ) ] + _ _ _ _ _ _ __

Hi/Hi setpoint value = uCi/ml

15. Calculate Hi setpoint value in uCi/ml:

Hi setpoint value = [Tank Activity / (4 x Fd 1+ (BCA)

Hi setpoint value [ #41 (4 x #12) 1+ (#13)

Hi setpoint value =[ 1 (4 x ) J + _ _ _ _ _ _ __

Hi setpoint value = uCi/ml

16. Obtain 17RM-350 Hi/Hi alarm potentiometer setting, using Hi/Hi setpoint value activity, from current liquid Radwaste Monitor "Sample Activity vs. Alarm Pot Setting" graph.

HilHi Alarm Potentiometer setting _ _ _ _ _ _ _ _ _ _ _.

17. Obtain 17RM-350 Hi alarm potentiometer setting, using Hi setpoint value activity, from current liquid Radwaste Monitor "Sample Activity vs. Alarm Pot Setting" graph.

Hi Alarm Potentiometer setting _ _ _ _ _ _ _ _ _ _ __

Performed by:

Print I Sign I Date

18. Independently verify calculations AND alarm potentiometer settings.

Independent Verification:

Print I Sign I Date

19. Enter Hi and Hi/Hi alarm potentiometer settings on Discharge permit (Attachment 2).

RO ADMIN JPM A-3.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON 512010 JAMES A. FITZPATRICK Job Performance Measure Core Thermal Power Calculated Manually JPM Number: SRO A-1-1 Revision Number: 0 Date: 03/04/2010 Developed By: T. Hedigan 03/04/10 Author Date Validated By:

Facility Technical Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date SRO ADMIN JPM A-1-1.doc

NRC JAMES A. FITZPA TRICK 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.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KJA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identifiecl.

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 an asterisk {*}.

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - _ . _ - -

9. 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:

1. Not Applicable SRO ADMIN JPM A-1-1.doc 2

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION 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 action, if any, is required.

SRO ADMIN JPM A-1-1.doc 3

NRC JAMES A. FITZPA TRICK 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 Llsed 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-1-1.doc 4

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

Job

Title:

Title:

Core Thermal Power Calculated Manually JPM Number: SRO A-1-1 Revision Number: 0 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: 15 minutes Actual Time Used: _ _minutes

References:

RAP*7.3.03, CORE THERMAL POWER EVALUATION, Rev 13 RAP*7.3.16, PLANT POWER CHANGES, Rev. 44 ST-5D, APRM CALIBRATION, REV. 3 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: Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _._ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

SRO ADMIN JPM A-1-1.doc 5

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. (*) Applicant calculates reactor Applicant calculates reactor power using first stage turbine

power using first stage turbine pressure.

pressure. !

100.2

2. (*) Applicant calculates average Correctly calculates feedwater feedwater temperature and compensated flow.

compensated feed flow. Records 16. 423.6 data on Attachment 1 items 16 17. 423.6 through 23. 18. 3.6

19. 3.6

20. 0.99862

21. 0.99862

22. A=5.43 (5.40-5.46)

23. 8=5.54 (5.51-5.57) i

3. (*) Applicant uses the ASME steam Correctly determines enthalpy from steam tables.

tables to calculate Items 24 through 30 on attachment 1.

24.1190.7 (1190-1191.4)

25. 639.6 (638-641.2)

26. 401.5 (398-405)

27. 401.5 (398-405)

28. 502.0 (498-506)

29. 403.0 (399-407)

30. 65.9 (61.9-69.9)

SRO ADMIN JPM A-1-1.doc 6

NRC JAMES A. FITZPATRICK INITIAL EXAMINATION ELEMENT

STANDARD SAT UNSAT Comment Number

4. (*) Applicant calculates items 31 Correctly calculates Q to through 34 on attachment 1. feedwater.

31. 10.97 (10.91-11.03)

32. 401.5 (398-405) i 33. 1190.7 (1190-1191.4) 34.2537.9 (2532.9-2542.9)

5. (*) Applicant calculates items 35 Correctly calculates Q to CRD through 36 on attachment 1. flow.

i 35..037 (.0:~6-.038) 36.12.2 (11.9-12.5) i

5. (*) Applicant calculates items 37 Correctly calculates Q to through 39 on attachment 1. Cleanup system.

37.. 157 (.155-.159) 38.98.98 (96.98-100.98)

39. 4.55 (4.~~5-4.75)

I

6. (*) Applicant calculates items 41 on ! Correctly calculates QPUMP attachment 1. 41. 6.88 (6.68-7.08)

7. (*) Applicant calculates items 42 Correctly determines core through 43 on attachment 1. thermal power.

42.2548.8 (2540-2557.6)

. 43. 100.5 (100.1-100.9)

8. (*) Applicant compares the two Applicant compares the two methods and determines that they methods and determines that are within 5%. No further action I they are within 5%. No further required per attachment 2. action required per attachment

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

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ELEMENT STANDARD SAT UNSAT Comment Number

9. (*) Applicant states that current RAP-7.3.16 step 7.1.1 reactor power is above license limit requires power to be lowered if and would lower power to ensure the 12 minute average below 100% License Limit, 2536 exceeds the Licensed Power Mwth. Level.

Applicant may also state that would adjust APRM's per ST 5d APRM Calibration.

Task is complete.

JPM Stop Time _ _ _ __

SRO ADMIN JPM A-1-1.doc 8

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON

\'" cc. 'II VERIFICATION OF CORE THERMAL HEAT BALANCE Page 1 of 1 DATE/TIME:

A. First stage pressure from EPIC 1299: &&?, ~ psig

[(0.1362

1 st stg pr) + 9.3] = 100. ~ % power B. Reactor power calcula ted from heat balance = L 0 o. !: % power

(/00,1-IOO,9J C. The two methods are within 5% of rated power of each other. 19 YES o NO D. If Not within 5%, investigation initiated. [] YES o NO E. If GRBATBR THAN 5%, and unexplained, General Manager Plant Operations notified. [] YES o NO Print Sign Date I I

Performed By: 1-\ ?P\: C~ ~ ~ t\ S:=--'=..:;0...>:;.,......; _ __

-I I

I I.'

. £)fA.M r

-'-' ~ ......-...

RAP-7.3.03 CORE THERMAL POWER EVALUATION

. Rev. No. 13 ATTACHMENT 2 Page 12 of .!§.

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON

)<J AM K<C' Y I HEAT BALANCE CALCULATION ~HEET page 1 of 1 r PERFORMED BV

_ _ _ _ _ _ _ _ _ _ __

PURPOSE' DATEfTlME: _ _ _ _ _ _ __

I ITEM PARAMETER PANEL INSTRUMENT VALUE tJNfTS

1. Cloanup Ihllit Tomp 9-4 12TSS*142 POS 1 <:"1:;), of 2.

3.

4.

6.

Cleanup Outlet Temp.

ClllllnU!! Flow A Cleanup Row 8 Power to Recire. Pump A Power to Recirc. PumJl fl 94 94 9*4 9-4 94 12TSS* 142POS 4 12FI*126A 12A*126B RWR MG A GEN PWR Rwa MG B GEN PWR

"'1':1'::-

/.hO is'S-j

.l,SS' Ss'"

of GPM GPM MW MW II

7. Total Core Flow 9-5 02*3DPRlFR-96 ~q Mlblhr

8. Reactor Pres$ureJpsfg + 14.7) 9*6 OSPRIFR*98 * ~.sJ PSIA

9. CRD Flow to RNctor 9*6 03FI*310 S'<t GPM f 9a RWR & RWCU Pump Seal Flows Constant 15 GPM

10. . CRO SySlem Temp Coostant 95 OF

11. Gross MW Electric

12. Feedw8ter Flow LoQl! A "13. Fae<1wllter Flow Loop B

. 14. TFWA, use PTIO 407/410 or 9*7 9*5 9*5 9-21 MAINGENMW 06FI-89A 06F1-69S 02TT*168AfC

~ '1 ()

...!/<+

S" ,.c: S ta3 ,(,.[I/.2J.(,Of' m:

GMWC \

16. TFWB usll PTIO 408/411 or 9-21 Om*168B1O 1./..:;J. , I'r'.:UJ':F FEEDWATER R.OW CALCULATIONS "IS. Average TFWA (407 +410)12 or (l6SA + 168CI/Z 0/::.1'3.(" OF

17. Average TFWEI 1408+4111{2 or (168E1+16801/2 ~~ I~ OF "18. Deltll T Loop A (OTA) .. TFWA* 420 ~.i, OF "19. Dellll T Loop ElIOTS) .. TFWB* 420 ?t. OF "ZO. C.F. : 1.0 + {DTA"I-3.0064E4 + (DTA"4.4310E*7111 o.G(n?,,~

"21. C.F.... 1.0 + /OTS",-3.8064E*4 + (OTa o*4.4310E-7Ul o ~'1 'AI.;;),

22. Compensated Flow A (#12

120) 5.'13 (s.)'o<Y('J MLB/HR "23. Compjm8sted Flow B (#13

121) ~CS~ r.<::'>1 -.<::'.>'}) MLB/HR PARAMETER ITEM DATA USED VALUE tJNfTS

24. HS #8 \I ql:l,,,) (H90-Il'IUJrrU/LB II "26." l1FG IS,.* ,~~ 'I. (. It* .,, ~ - (,<11..).) 8TUII.B "26. HFWA - #8.116. I{OJ.5"" (3 (U;* "16") BTU/lS

27.. HFWB 18,'17 ~().1.s( ?'l 13 os-J BTU/LB

28. HCUl #8 '1 <\o~ <> { '-/49. - 5'<1 ",\ BTUIL9

29. HCUO '8 n, able '10),0 ( ., 9 9 -1,1",..,) BTUILS

30. HCR 18 11O, ASME Table '"'S 9 ('-1, <J-L 9.<J\ STU/lS PARAMETER EOUA TlON ,ITEM '-S) VAL~ UNITS

31. Totel fesdflow ,'2Z + '2S1 10 q., III 91- II. OJ) MLBfHR

32. FeBdwater Enthalpy U'2S*1221 -+ 1127"'23)11#31 <lo/.S' .., U - .;I"..) STUILS 3$. Stllam EnthlllQY 11124 *10.000*,21111 I .94,) 1\<10 -h'lI.'f)BTU/lS r

-

.u. a to fee<1wllteir (OFW) 1131"(#33 - #32lJl3.413 ~<':l"'."i ~~.U ..'i'*.;l.><l.UJMWt

~. (1#9

0.49SE-31 + (I9a 0 0.4981:-3)1 .0)') dl.H. -,OJR' MLBtHR 36.. w IOCRI 1'35 *1133 - 83011/3.413 ':l :0\ ( 1\ q -I;J ""~'\ MWt

37. lotal CU flow IWCU) (#3 + '4) "IO.498E-3) d n ( I$".,;'"-I-;£~'S 38.

39.

HCUI :HCUO a to Cleanup Svs 1128* '29) 1#38 * .371(3.413

'tf/ .f3 {Q('.9k-/tJtJ n' 11..'-" ( q,jf - Sf. '}S") MWt 4(J. Vessel ombient loss 1.1 MWt

41. apUMP (#6 + #61

0.93 (",'i>~ {G.(.f-)coir)MWt

42. Core Thermal Power f,34.+ #36 oj. '39 + '40*1411 ~ S'fl\. "C(;J5;,/O -~ ...... ,)MWt 43 CTP/2536 ('42/2636)

100 LOO.~ (100 /-/ddfll%

11 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: ~ _ _ _ _ _ _ _ _ _ __ DatelTime:_ _ _ _ _ _ _ _ __

Reviewed By: ----;:---::--=---:----:--::--"":'"':~~-__c_ DatelTime: _ _~_""--_ _ __

Reactor Engillllsring $uPGriCltaooenl

- This IS a Quality .

Record RAP-7.3.03 CORE THERMAL POWER EVALUATION ATTACHMENT 1.

Rev. No. ...:!,;L

.t;;; X ".~f1.t\ k. '/ Page 11 of 16

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION 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 action, if any, is required.

SRO ADMIN JPM A-1-1.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON VERIFICATION OF CORE THERMAL HEAT BALANCE Page 1 of 1 DATE/TIME: --------_/------,

A. First stage pressure from EPIC 1299: ~ (p 7. i psig

[(0.1362

1 st stg pr) + 9.3]

_ _ _ _ _% power B. Reactor power calculated from heat balance

_ _ _ _ _% power C. The two methods are within 5% of rated power of each other. DYES D NO D. I f Not within 5%, investigation initiated. DYES D NO E. I f GREATER THAl'iJ 5%, and unexplained, General Manager Plant Operations notified. DYES o NO

'Print Sign Date Perfonned By:

Revi ewe(i By:'

,'~,---'.'--'----,--,--'"-----, '-===REA;::;::;;;;:;C:;;:'l;;;'OK:;:;::;='-;;m~G:::;:IN"""E""'E':;;:;R~I"N;;;G-='=;;S~Uffip:;';E~R¥-INTi'ii'~END~,~'EN;;:;:';;';T;-"',-...,.".,.....

_ _ ** _ .. _~r~' __ ___ '"'. _._ *

_._- ._- * * . * * ', ** -. - . - ***. - - - - . - -

=--'i'his IS _QUality Record RAP~T.3 .03 CORE THERMAL POWER EV~UATION ATTACHMENT 2 Rev. No,, , - 13 Page 12 of 16 SROA

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON HEAT BALANCE CALCULATION SHEET Page 1 of 1 PERFORMED BY: _ _ _ _ _ _ _ _ _ _ _ __ DATEfTlME: _ _ _ _ _ _ __

PURPOSE:

PANEL NT 9-4 OF 9-4 9-4 GPM 9*4 GPM 9-4 MW 9-4 MW

.9*6 Mlbfhr 14.11 9-5 PSIA 9*6 GPM 15 GPM 96 OF 9-1 GMWE 9*6 MlBIHR 9-6 MLB/HR 9-21 "16, OF

17. OF

lB. 'F

19.

"20.

"21.

22.

'23.

24. HS IB, 25." HFG ' #8,'

'26. HFWA 118 "6.

21.. HFWB 118,#17

28. HCUI 18 111

29. HCUO IB 112,

30. HeR 118 ',0 PARAMETER

(#6 + 116) .. 0.93 1#34 + 136 + #39 + #40 -11411

(#42/26361* 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: ~ _ _ _ _ _ _ _ _ _ _ __ Daternme:_ _~_ _ _ _ _ __

Reviewed By: _ _ _-=-_~~_~~.....,.---

Reactor Engineering !;juperil)tendent

____ Datemme: _ _ _ _--'-_ _ _ __

- This ~ a QUality Record RAl?-?3.03 CORE THERMAL POWER EVALUATION ATTACHMENT 1.

Rev. No.

,-13 Pag'! 11 of 16 SROA

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-1-1.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON 512010 CONTAINS SENSITIVE INFORMATION -- NOT FOR PUBLIC DISCLOSURE JAMES A. FITZPATRICK Job Performance Measure Determine Required Event Followup JPM Number: SRO A-1-2 Revision Number: 0 Date: 03/05/2010 Developed By: ,:..P.:...,:,P;.....:r=e=sb::::.iVL...-_ _ _ _ _ _ __ 03/05/10 Author Date Validated By:

Facility Technical Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date SRO ADMIN JPM A-1-2.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON CONTAINS SENSITIVE INFORMATION - NOT FOR PUBLIC DISCLOSURE 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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date

9. 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 "IPM 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:

1. Not Applicable SRO ADMIN JPM A-1-2.doc 2

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION CONTAINS SENSITIVE INFORMATION - NOT FOR PUBLIC DISCLOSURE REVISION RECORD (Summary):

1. This JPM is the original revision O.

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 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-1-2.doc 3

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON CONTAINS SENSITIVE INFORMATION - NOT FOR PUBLIC DISCLOSURE 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

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 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-1-2.doc 4

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION CONTAINS SENSITIVE INFORMATION - NOT FOR PUBLIC DISCLOSURE Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

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:

AP*03.04, Information Reporting Requirements, Rev 13 EOP*2, RPV Control, Rev 9 AOP-1, Reactor Scram, Rev 43 AOP-70, Security Threat, Rev AOP-17, Loss of 10400 Bus, Rev 17 IAP-2, Classification of Emergency Conditions, Rev 28 EAP*1.1, Offsite Notifications, Rev 64 IAP*1, Emergency Plan Implementation Checklist AP-12.11, Notifications and Response to Operational Concerns EAP-3; Fire 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: [J Satisfactory Unsatisfactory Comments:

SRO ADMIN JPM A-1-2.doc 5

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION CONTAINS SENSITIVE INFORMATION - NOT FOR PUBLIC DISCLOSURE 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 CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

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

entered to mitigate the event conditions.

EOP-2 (low RPV level, normal for a scram)

AOP-1 (for the scram)

AOP-17 (for the 10400 Bus loss)

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 SRO ADMIN JPM A-1-2.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION CONTAINS SENSITIVE INFORMA TION - NOT FOR PUBLIC DISCLOSURE ELEMENT STANDARD SAT UNSAT Comment Number

2. (*) Applicant determines NRC Applicant identifies NRC notification requirement per AP prompt notification required 03.04. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by ENS phone per AP-03.04 Attachment 2, Item 138, based on 50.72(a)(3) after declaration of an Emergency Class (Alert under IAP-2, Category 8.1.4.)

3. (*) Applicant determines E-Plan Applicant identifies E-Plan ERO callout required. ERO callout required.

4. (*) Applicant determines off-site Applicant identifies personnel!

agency notification requirements agencies that must be under E-Plan. contacted

1) under EAP-1.1 Offsite Notifications:

New York State

Oswego County

NinE3 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.

2) under IAP-1, Emergency Plan Implementation Checklist Item B:

NRC via ENS phone within 15 minutes of recognition of security-based emergency.

Task is complete.

JPM Stop Time _ _ _ __

SRO ADMIN JPM A-1-2.doc 7

NRC JAMES A. FITZPA TRICK 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.

AtT= 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 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 m.in

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

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. FITZPATRICK INITIAL EXAMINA TlON 512010 JAMES A. FITZPATRICK Job Performance Measure 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.::,by"'--_ _ _ _ _ _ __ 03/10/10 Author Date Validated By:

Facility Technical Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date SRO ADMIN JPM A-2.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON 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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _______

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is aCGurate.

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:

1. Not Applicable SRO ADMIN JPM A-2.doc 2

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

1. This JPM is the original revision O.

JPM Setup Instructions:

1. 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:

1. 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.

2. Determine HPCI Torus Suction Isolation Valves 23-57 and 23-58 will not automatically re-position on the failure.

3. 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).

4. 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.)

5. Identify required Tech Spec actions as follows:

Per 3.3.5.1 Action D, place affected low level channels in trip -DR align HPCI pump suction to the suppression pool within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SRO ADMIN JPM A-2.doc 3

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON 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 23 K51 at Terminal Point 9-39/CC-14.

NO other damage is apparent.

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 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-2.doc 4

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

Job

Title:

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 1.61 148, also referenced as Vendor Dwgs 791 E471 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 No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this ~IPM, 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: _ _ _ __

SRO ADMIN JPM A-2.doc 5

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON NOTE: Critical Element(s) indicated by 111 in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Applicants review the handout Applicants review initial sheet and ask any questions conditions and initiating cues.

regarding the initial conditions or initiating cues. Examiner Cue:

Hand the applicant HPCI Elementary Drawings (9 drawings, see references) and the cue handout sheet.

2. Review HPCI System Elementary Applicant determines 23-K51, Drawings. Determine how this normally energized, is de-failure impacts HPCI components. energized by the failure, 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 (LS23-74A or LS23-75A)

Examiner Note:

Sht 3 (H-9)

Sht 1 (A-2/3, K-6)

Sht 8 (H-5, H-6)

3. Determine system functionality. Applicant determines system remains functional as valves will reposition upon valid CST low level signal from the other CST (low level initiation is one out of two, taken twice, with one signal effectively actuated). A low level in CST

'A' will still perform the auto suction swap function. Valves I can still be operated manually. I SRO ADMIN JPM A-2.doc 6

NRC JAMES A. FITZPA TRICK 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 caeabilitv, which indicates the inoperability call is only 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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. FITZPATRICK INITIAL EXAMINA TlON 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 23 K51 at Terminal Point 9-39/CC-14.

NO other damage is apparent.

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 EXAMINA TION Job Performance Measure Determine Radiation Controls JPM Number: SRO A-3 Revision Number: 1 Date: 03/30/2010 Developed By: Bernard Litkett 03/30/2010 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date SRO ADMIN JPM A-3.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION SRO ADMIN JPM A-3 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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date

9. 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 . .IPM cannot be performed as written with proper responses, then revise the . .IPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

Review Questions and Comments:

SRO ADMIN JPM A-3.doc 2

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 REVISION RECORD (Summary):

1. New JPM.

JPM Setup Instructions:

Ensure the following documents are available in the exam area:

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;

1. Provide page 1 of handout sheet to applicant.

2. 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 STANDARD:

Determine which 2 workers must have Emergency exposure controls put in place due to anticipated dose during response to emergency conditions.

SRO ADMIN JPM A-3.doc 3

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 TASK CONDITIONS:

1. The plant is at 15% power.

2. A Site Area Emergency has been declared due to a steam line rupture with significant fuel damage.

3. Entry is required into the MSIV Room to close the outboard MSIVs to prevent event escalation.

4. 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 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months at the job site with both workers working the full time.

5. 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

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.

9. Emergency exposure controls have not been implemented.

INITIATING CUE:

1. Anticipate dose to be accumulated by each worker.

2. Select two (2) workers to complete the task.

3. Authorize work using the appropriate exposure limits to allow completion of the required task.

SRO ADMIN JPM A-3.doc 4

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION 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-3.doc 5

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

NLO ORO rzJ SRO STA SRO Cert JPM

Title:

Perform ED Functions JPM Number: SRO A-3 Revision 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, Rev.3, Dosimetry Administration

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

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

SRO ADMIN JPM A-3.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3

==

Description:==

This JPM is used to test generic knowledge in calculation of overall dose and control mechanisms to allow the selection of individuals to continue or perform work in high dose areas. This "IPM tests basic mathematics and understanding of stay times and the authorization of emergency radiation exposure.

This is a new JPM.

SRO ADMIN JPM A-3.doc 7

NRC JAMES A. FITZPATRICK 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 NOTE: EXAMINER NOTE:

Examiner to provide page 1 Examiner to provide page 1 of ofhandouf sheet to handout sheet to applicant.

applicant.

1. Determine dose to be received N/A for each worker

2. For each worker, the applicant:

2.a Determine anticipated Dose

Time = Task dose from task Rate Dose performance in the work 2000 mRlhr

1.5 hr = 3000 mR area.

2.b Determine anticipated Dose + Dose = Travel dose from transit to and To From Dose from the Main Steam Location Location chase 500mR + 500 mR = 1000 mR 2.c Determine anticipated Dose

Time = Transit dose from transit to the Rate Dose work area in the steam 800 mRlhr * (2 min/60) = 26 mR chase.

2.d Determine anticipated Dose

Time = Task dose from transit from Rate Dose the work area in the 800 mRl~lr * (2 min/60) = 26mR steam chase.

2.e Determine the total dose Task + Travel + Transit =Total for each worker from Dose Dose Dose Dose

@a through 2d.

3000 + 1000 + (26*2) =4052 mR

3. Determine that task

The applicant determines that total performance is not allowable dose is greater than the annual per normal controls. 4500 mR administrative limit for radiation exposure per EN-RP-201 and the 5000 mR federal limit SRO ADMIN JPM A-3.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION SRO ADMIN JPM A-3 ELEMENT STANDARD SAT UNSAT Comment Number

4. Determines that emergency *The applicant evaluates the total exposure controls are required expected dose and recognizes that per EAP-15. emergency exposure controls are required to raise the limit above 5 R for each individual per EAP-15 EXAMINER NOTE: EXAMINER NOTE:

Examiner should only Examiner should only provide provide EAP-15 and handout EAP-15 and handout sheet sheet page 2 if the applicant page 2 if the applicant determines emergency determines emergency radiation exposure radiation exposure authorization is required. authorization is required.

SRO ADMIN JPM A-3.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 ELEMENT STANDARD SAT UNSAT Comment Number

4.a Implements EAP-15; step The applicant Implements EAP 4.2.1 15;step 4.2.1 .. Selects a TEDE Limit of up to 10 Rem from dose limit 4.3 Selects personnel for Task The applicant using currently per Step 4.3 identified workers verifies workers:

- Personnel selected have volunteered

- are not declared pregnant workers

- Volunteers should be more than 45 years of age, if possible.

- have not received a previous emergency exposure

- 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 complete Attachment 4 for Technician 2 Attachment 4 for Technician 2 to to authorize the emergency authorize the emergency exposure.

exposure. Henry Work is the youngest of the five technicians.

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.

exposure. Jane Riley is the second youngest of the five technicians.

8. Completes Attachment 4 for

Completes Attachment 4 Section A Technician 4 to authorize the for Technician 4, Bill Smith per the I emergency exposure based on attached mark-up of attachment 4.

he has volunteered for the emergency exposure and his Note: The Employer / JAF Dept age. Although he is only 40 block is NOT a Critical years, procedure EAP-15 step component of this Step.

4.3.4 states, volunteers should be more than 45 years of age, if possible.

I SRO ADMIN JPM A-3.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 ELEMENT STANDARD SAT UNSAT Comment Number

9. Completes Attachment 4 for

Completes Attachment 4 Section A Technician 5 to authorize the for Technician 5, Mike Long per the emergency exposure based attached mark-up of attachment 4.

on his age and that he has volunteered for the emergency Note: The Employer I JAF Dept exposure. block is NOT a Critical component of this Step.

(Examiner Cue: "You may stop N/A here, you have met the termination criteria for this JPM")

..IPM Stop Time _ _ _ __

SRO ADMIN JPM A-3.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION SRO ADMIN JPM A-3

,I ATTACHMENT' 4 Page 1 of 2 EMERGENCY EXPoSURE 'AUTHORIZATION FORM SBCTION A Name of Individual to Receive Exposure: Bill Snit h SSN = S11 ~ 14 ~ 'lIlt' ~. ,",

TLP Badge No,; ~3~ Sa1 Employer/JAF Department: ~ IV+e£~ ,,' ~ Ma-ikJi-ew Nee Date of Authori~at:ion: -1oky's ~o..tt Authorized Exposure Limit: lD eG~

, Emergency Director; ______~¥~O~U~I--~5~1~~~~a~'}~o(~t~*______~~----------

(Signature)

XXXXXXXXXXXXXXXxxxxxxxxx:xxKXXxxxxxxxxxxxx.xxxxxxnxxxxXxxxxxxx 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.

Individual to Rec~

Exposure:

xL ~

-CJtU ~

(Signatur~). '

Date:

Individual Conducting Briefingt (Signature)

Date;

ct EAi?-lS Bl'4ERGENCY RADIATION EXPOSURE CRITERIA ATTACBMENT4 Rev. No . ...l.L AND CONTROL Page ~ of -1i

==

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION SRO ADMIN JPM A-3

,/'

!J~W£f<- Key ,ATTACHMENT 4 Page 1 of 2

!OOmGENC1 .EXPosTJRE .AUTHORIZATION FORM SECTION A Name of Individual 'to Receive ExPosure: BiKe baNS SSN: S 12 . 5:J-:l.1St*

'l'LtJ Badge No; L/2 I ¥t q Employer/JAF Department: & ttrgy~ tJ.felAholv S Date of Authorization; 'ivil&':/ S' Ji,/(

Authorized Exposure Limit: /Q itM Bmergency ,t Director: . XDv{ {rs l1all/.( ~

(Signature)

Date': -1VtitJv* \5 ~41e

,'- xxxxxxxx:xxxxxx~xxnxxxxxxxxxxxx~xxxxXxxx:xxxx.

SECTION B I bave 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.

Individual to Receive Exposure:

Mdt

~(

~'.

/ *

~"

(Signature. .

Date; , &

Z:dfY'$ If Individual Conducting Briefing:

(Signature)

Date:

EAP-15 EMERGENCY RADIATION ATTACHMENT 4 EXPOSURE CRITERIA Rev. No. 11 AND CONTROL Page ~ of -1i

NRC JAMES A. FITZPATRICK 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-3.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON SRO ADMIN JPM A-3 HANDOUT PAGE 1 TASK CONDITIONS:

1. The plant is at 15% power.

2. A Site Area Emergency has been declared due to a steam line rupture with significant fuel damage.

3. Entry is required into the MSIV Room to close the outboard MSIVs to prevent event escalation.

4. 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 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months at the job site with both workers working the full time.

5. Five workers are preparing to be briefed to complete the task.

6. 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 EleGtronic Dosimeter from his first entry, resulting in a total exposure of 1678 mR for the year.

7. The TSC has not been staffed yet.

8. Emergency exposure controls have not been implemented.

INITIATING CUE:

1. Anticipate dose to be accumulated by each worker.

2. Select two (2) workers to complete the task.

3. Authorize work using the appropriate exposure limits to allow completion of the required task.

SRO ADMIN JPM A-3.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON 512010 JAMES A. FITZPATRICK Job Performance Measure Determine Protective Action Recommendations and Complete Event Notification Form JPM Number: SRO A-4 Revision Number: 1 Date: 03/29/2010 Developed By: P. Presb~ 03/29/10 Author Date Validated By:

Facility Technical Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date SRO ADMIN JPM A-4.doc

NRC JAMES A. FITZPA TRICK 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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _ _ _ _ __

9. 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:

1. Not Applicable SRO ADMIN JPM A-4.doc 2

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

1. This JPM is the original revision O.

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 64

EAP-4, Dose Assessment Calculations, Rev 39 TASK STANDARD:

1. Complete the upgrade offsite notification message form, including correct PARs.

SRO ADMIN JPM A-4.doc 3

NRC JAMES A. FITZPATRICK 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).

Emergency and Plant Information Computer (EPIC) System is NOT available.

Emergency Dose Assessment Modeling System (EDAMS) is NOT available.

At 0412, (when you start the JPM) the following plant cond itions 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 high range effluent radiation monitor = 11,700 mr/hr.

Stack flow rate = 12,000 cfm, with 1 SGT train and 1 stack dilution fan operating.

Meteorological conditions are listed in the following table:

SRO ADMIN JPM A-4.doc 4

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Site Meteorological Conditions Parameter Data Avg Wind Direction egrees Avg Wind Direction 100 foot 263 degrees Avg Wind Direction 90 foot 261 degrees Avg Wind Speed - 200 foot 6.1 mph Wind Speed - 100 foot 4.5 mph Speed - 90 foot 4.7 mph Speed - 30 foot 3.8 mph es Delta T - 30 to 200 ) 1.49 degrees F T - 30 to 100 f 0.56 degrees F SRO ADMIN JPM A~4.doc 5

NRC JAMES A. FITZPATRICK 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 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-4.doc 6

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

Job

Title:

Title:

Determine Protective Action Recommendations and Complete Event Notification Form JPM Number: SRO A-4 Revision Number: 0 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 64

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? DYes [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: D Satisfactory D Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

SRO ADMIN JPM A-4.doc 7

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ __

SRO ADMIN JPM A-4.doc 8

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT I Comment i

Number

1. Applicants review the handout Applicants review initial I sheet and ask any questions conditions and initiating cues.

regarding the initial conditions or initiating cues.

2. Handout the references with the Start the JPM.

handout sheet and the initiating cue sheet.

Record START Time:

Examiner Cue: Remind applicant the task is time critical.

3. Obtains Notification Form Applicant completes (Attachment 1 of EAP-1.1, Offsite Notification Form Item #2, Notifications) . circling "B. Actual Event".

4. Record the correct event Applicant completes classification. Notification Form Item #3, circling "D. General Emergenc~" .

5. Record the correct declaration Applicant completes date and time. Notification Form Item #4, recording today's date (5/12/2010) and event declaration time (0412) I

6. Determine release rate using Applicant determines release 1

EAP-4 and EAP-4.1 (Step 4.1.2 or rate is 29,718 Ci/sec.

Attachment 2 from mr/hr

2.54 factor) I i

7. Record the radioactive release Applicant completes information based on EAP-4.1 Notification Form Item #5, Attachment 11.

circling "C. Release ABOVE federal limits Technical I Sgecification".

I SRO ADMIN JPM A-4.doc 9

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON ELEMENT STANDARD SAT UNSAT Comment Number

8. Determine and record the Applicant completes protective active Notification Form Item #6, recommendations using EAP-4 circling "B. EVACUATE and Attachment 1, Tables 4.1.1 and IMPLEMENT the KI PLAN for 4.1.2. 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 i

mile radius and 5 mile downwind ERPAs.

9. Record appropriate EAL number Applicant completes and brief description. Notification Form Item #7, i recording EAL # 5.1.4 and

brief description "high elevated rad release rate from main vent stack".

10. Record reactor status. Applicant completes Notification Form Item #8, i circling "B. Shutdown" and

date time of 5/12/10 at 0342.

11. Record appropriate wind speed i Records wind speed by filling

in Notification Form Item #9 as "A. 6.1 Miles/Hour at elevation 200 Feet (Elevated)".

12. Record meteorological stability Determines Stability Class "C",

class as determined using based on wind direction provided data per EAP-42. i variation and 30 to 200 foot

delta T. Records stability i

class by circling "C Neutral" in Notification Form Item #11.

13. Turn in notification form within Applicant turns in notification required time. form within 15 minutes of start of JPM.

Record Stop Time:

SRO ADMIN JPM A-4.doc 10

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SRO ADMIN JPM A-4.doc

NRC JAMES A. FITZPATRICK INITIAL EXAMINATION 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 noti'fication 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).

Emergency and Plant Information Computer (EPIC) System is NOT available.

Emergency Dose Assessment Modeling System (EDAMS) is NOT available.

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 high range effluent radiation monitor = 11,700 mr/hr.

Stack flow rate = 12,000 cfm, with 1 SGT train and 1 stack dilution fan operating.

Meteorological conditions are listed in the following table:

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON HANDOUT PAGE Site Meteorological Conditions I I

Parameter Data I

Avg Wind Direction 200 foot 271 degrees I

Avg Wind Direction 100 foot 263 degrees I Avg Wind Direction 90 foot 261 degrees I

Avg Wind Speed - 200 foot 6.1 mph i

Avg Wind Speed -100 foot 4.5 mph Avg Wind Speed - 90 foot 4.7 mph Avg Wind Speed - 30 foot 3.8 mph

Avg Wind Direction Variation 14 degrees Avg Delta T - 30 to 200 foot minus (-) 1.49 degrees F Avg Delta T - 30 to 100 foot minus (-) 0.56 degrees F

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.

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TION Job Performance Measure Changing In-service CRD Pump Suction Filters JPM Number: P-1 Revision Number: 1 Date: 1/15/10 Developed By: -=B::.:e::.:..r:.:;na=.::r:..:d~L:.:.it::.:k:.:e.:.:tt_ _ _ _ _ __ 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 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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - - - - -

9. 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. FITZPATRICK INITIAL EXAMINA TlON 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 ..'PM. 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 Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

NLO WSRO DSTA o SRO Cert 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 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 comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date:

Plant JPM P-1.doc 4

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION 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.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain a controlled copy of The applicant determines where to procedure OP-25; REV.79; obtain a controlled copy OP-25; Rev.

G.11, changing in-service 79;G.11, changing CRD suction filters CRD suction filter EVALUATORj Provide trainee a current copy of OP-25

2. Select the correct section to Selects section G.11 from OP-25; perform the task. REV.79.

EVALUATOR: Provide applicant with I copy of section G.11. I

3. Applicant notifies the Applicant notifies the control room that control room that CRD CRD suction filter will be changed.

suction filter will be changed.

4. Applicant notifies Radiation Applicant notifies Radiation Protection Protection that potentially that potentially radioactive water will be radioactive water will be vented from the CRD pump suction I

vented from the CRD pump filter.

suction filter. I

5. Perform the following for Applicant opens inlet isolation valve.

the filter to be placed in-

03CRD-151A (CRD water service. pump 'N Suct filter 'A' inlet a.) Verify open inlet isol valve) isolation valve or

03CRD-151A (CRD

03CRD-1518 (CRD water water pump 'A' Suct pump '8' Suct filter '8' inlet filter 'N inlet isol isol valve) valve)

Cue: After correct operation is or simulated, inform applicant that handwheel turns several rotations in

03CRD-1518 (CRD CCW direction, then hits a hard stop .

water pump '8' Suct filter '8' inlet isol valve)

I Plant JPM P-1.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION JPM P-1 ELEMENT STANDARD SAT UNSAT Comment Number

5b. Crack open vent valve: Applicant cracks open:

03CRD-400A (CRD water

03CRD-400A (CRD water pump 'A' suct filter 'A' pump 'A' suct filter 'A' vent vent valve valve or or

03CRD-400B (CRD water

03CRD-400B (CRD water pump 'B' suct filter 'B' pump 'B' suct filter 'B' vent vent valve valve EVALUATOR CUE: Valve is cracked open, water is flowing free of air from the vent.

5c. When water flowing Applicants closes the vent valve when from the vent is free of the water flowing is free of air.

air, close the vent valve. EVALUATOR CUE: Valve is closed.

I

5d. Slowly open outlet Applicant slowly opens outlet isolation isolation valve: valve.

03CRD-152A (CRD water

03CRD-152A (CRD water pump pump 'A' suct filter 'A' 'A' suct filter 'A' outlet isol valve) outlet isol valve) or or

03CRD-152B (CRD water pump

03CRD-152B (CRD water 'B' suct filter 'B' outlet isol valve) pump 'B' suct filter 'B' outlet isol valve) EVALUATOR CUE: After correct operation is simulated, inform applicant that handwheel turns several rotations in CCW direction, then hits a hard stop.

I 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 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.

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 By: Bernard Litkett 1/14/10 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date Plant JPM P-2.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPMP-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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _ _ _ _ __

9. 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):

1. None JPM Setup Instructions:

1. Performance of this JPM shall be simulated. Inadvertent manipulation of a component could result in unwanted system actuations.

2. When opening cabinets with energized equipment inside, ensure appropriate EN-IS-123 requirements are met.

3. Make a copy of EP-2; Section 5.8 for use by applicant.

4. 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:

1. Emergency depressurization has been ordered due to high secondary containment temperature (EOP-5), but only 3 SRV's can be opened.

2. 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.

INl"rlATING 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, Isolationllnterlock Overrides.

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.

Plant JPM P-2.doc 3

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION JPM P-2 Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

0 NLO IRO ISRO STA o 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 A2.10; 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 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: _ _ _ __

Plant JPM P-2.doc 4

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION JPMP-2 Descrigtion: 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 TlON JPM P-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 The applicant determines where to procedure EP-2, obtain a controlled copy of EP-2.

Isolation/Interlock Overrides (EOP supply cabinet, Control Room, Merlin)

EVALUATOR; Provide trainee a current copy of EP-2

2. Select the correct section to Selects section 5.8 from EP-2.

perform the task.

EVALUATOR: Provide applicant with copy of section 5.8.

3. For 23MOV-15, disconnect EVALUATOR: When the applicant lead from one of the following proceeds to panel 09-32 in the Relay terminals in panel 09-32: Room and locates and identifies C) TBC-5 terminals and states that he/she would Or disconnect a lead from either terminal TBC-5 or TBC-7, then inform the C) TBC-7 applicant "Lead disconnected".

4. Initials for lifting lead. Initials block for lifting lead from terminal.

5. For 23MOV-16 and 60, EVALUATOR: When the applicant disconnect lead from one of the proceeds to panel 09.,.39 in the Relay following terminals in panel 09 Room and locates and identifies 39: terminals and states that he/she would C) 00-17 disconnect a lead from either terminal Or 00-17 or 00-18, then inform the applicant "Lead disconnected".

C) 00-18

6. Initials step for lifting lead. Initials block for lifting lead from terminal.

7. Contact the Control Room EVALUATOR: Acknowledge the and inform them that the low communication as the CRS.

steam pressure isolation has been overridden per EP-2 EVALUATOR: Terminate the task at this point.

JPM Stop Time _ _ _ __

Plant JPM P-2.doc 6

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM P-2 HANDOUT PAGE TASK CONDITIONS:

1. Emergency depressurization has been ordered due to high secondary containment temperature (EOP-5). but only 3 SRV's can be opened.

2. 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.

Plant JPM P-2.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON Job Performance Measure Alternate Depressurization Using SRVs From Panel 02ADS-71 JPM Number: P-3 Revision Number: 1 Date: 1/19/10

, Developed By: Bernard Litkett 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 JPM P-3 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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date

9. 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. FITZPA TRICK INITIAL EXAMINA TlON JPM P-3 REVISION RECORD (Summary):

1. None JPM Setup Instructions:

1. EP-11 ;Rev.1 , Alternate depressurization using SRVs from 02ADS-71

2. Obtain Shift Manager's permission prior to performing this task.

3. Ensure Control Room is aware that the door to the remote ADS panel will be opened.

TOOLS AND EQUIPMENT:

1. Key for Remote ADS Cabinet 02ADS-71 is located in equipment cabinet near Remote Shutdown Panel 25RSP, RB 300 el., north.

2. 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:

1. Torus water level is 13.9 feet

2. The Shift Manager has identified the need to use the remote ADS cabinet 02ADS-71to depressurize the RPV,per EP-11; Rev,1.

3. 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 Use:

UNSAT requires written comments on respective step.

'It 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 P-3 Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

0 NLO IRO gSRO DSTA o 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 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 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

Plant JPM P-3.doc 4

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM P-3

==

Description:==

This JPM has the applicant perform an emergency depressurization lAW EP-11.

Plant JPM P-3.doc 5

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM P-3 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 Obtains a controlled copy of EP-11; procedure Rev.1.

2. Reviews precautions Applicant reviews applicable section associated with the of the procedure and verifies Torus procedure: water level is > 5.5 ft.

Torus water level shall be greater than or equal to 5.5 EVALUATOR CUE: When applicant feet to open an SRV.

requests information regarding Torus Opening an SRV with Torus water level, inform applicant level is water level less than 5.5 greater than 13.9 1't.

feet will cause direct pressurization of the containment and possible containment damage.

3. Reviews prerequisites Applicant reviews applicable sections associated with the of the procedure.

procedure:

Performance of this procedure has been directed by the EOPs or SAOGs.

4. Reviews special instructions Applicant reviews applicable section associated with the of the procedure.

procedure

Tools and materials for this procedure are located in the equipment cabinets near Remote Shutdown Panel 25RSP and panel 02ADS 71.

Notify RES prior to entering the RB due to potentially changing radiation conditions.

Plant JPM P-3.doc 6

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM P-3 ELEMENT STANDARD SAT UNSAT Comment Number

5. Establish communications Applicant proceeds to RB 300 el.

between the Control Room and establishes communications.

and ADS RELIEF VALVE CONTROL PANEL 02ADS EVALUATOR CUE: Inform applicant

71. that communications have been established and you will respond as control room operator.

6. Verify the following control Applicant verifies the control switches switches are in SOL are in SOL DEENG.

DEENG at panel 02ADS*

71 :

ADS & SRV 02RV-71C

SRV 02RV-71F

SRV 02RV-71J

SRV 02RV-71L

ADS & SRV 02RV-71B

ADS & SRV 02RV-71E EVALUATOR CUE: When applicant

ADS & SRV 02RV-71 H identifies the switches, inform applicant

SRV 02RV-71K that switches are in SOL DEENG.

ADS & SRV 02RV-71A

ADS & SRV 02RV-71 D

ADS & SRV 02RV-71G

7.Place CONTROL POWER Applicant places CONTROL POWER breaker in ON at panel breaker in ON.

02ADS-71.

EVALUATOR CUE: When applicant requests information regarding response, inform applicant that control power is ON.

8. Verify in the control room, Applicant verifies the alarm has annunciator 09-4-3-3 ADS actuated.

REMOTE CNTRL PNL BKR CLOSED is in alarm. EVALUATOR CUE: When applicant requests, inform applicant that alarm has actuated.

Plant JPM P-3.doc 7

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPMP-3 ELEMENT STANDARD SAT UNSAT Comment Number

9. WHILE performing Step Applicant verifies each of the 5.1.7, monitor the following indications while performing Step 11 of to verify SRV operation: this JPM (Procedure step 5.1.7).

Annunciator 09-4-2-6 SRV SONIC MON ALARM HI

ADS & SRV ACOUSTIC MONITOR 02VMR-071 at panel 09-4 .

EVALUATOR CUE: When applicant

White light at SRV control requests each SRV indication, inform switch at panel 09-4 applicant that each has occurred.

Red SOL ENGD and green SOL DEENG lights at panel 02ADS-71

10. IF torus water level is LESS Applicant verifies that torus water level THAN 5.5 feet, THEN is >5.5 ft.

perform the following:

Notify SM or CRS that SRVs cannot be opened.

Restore panel 02ADS-71 EVALUATOR CUE: When applicant per subsection 5.2. verifies the torus water level, inform applicant that level is 13.9 ft.

11.Place one or more of the Applicant opens seven SRVs.

following control switches in SOL ENGD at panel 02ADS 71, as necessary to establish seven SRVs open:

ADS & SRV 02RV-71C

SRV 02RV-71F

SRV 02RV-71 J EVALUATOR CUE: When applicant

SRV 02RV-71 L indicates the switch for opening an

ADS & SRV 02RV-71B SRV, inform applicant that SRV has

ADS & SRV 02RV-71E opened.

ADS & SRV 02RV-71H

SRV 02RV-71K

ADS & SRV 02RV-71A

ADS & SRV 02RV-71D

ADS & SRV 02RV-71G Plant JPM P-3.doc 8

NRC JAMES A. FITZPATRICK INITIAL EXAMINA TlON JPM P-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 following:

Close and lock panel door. 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 EXAMINA TION JPM P-3 HANDOUT PAGE TASK CONDITIONS:

1. Torus water level is 13.9 feet.

2. The Shift Manager has identified the need to use the remote ADS cabinet 02ADS-71 to depressurize the RPV per EP-11.

3. No SRVs have been opened from the Control Room.

INITIATING CUE:

You are the RD. The CRS has directed you to emergency depressurize the RPV per EP-11.

Plant JPM P-3.doc

James A. Fitzpatrick Generating Station Job Performance Measure Initiate RCIC in Pressure Control with Speed Control Failure JPM Number: 8-1 Revision Number: 1 Date: 1/13/10 Developed By: =B..;:;.e; . ; .rn=a;.;. rd;; ; . . .=L=it; . ; .;ke;;. ;t;.; . t_ _ _ _ _ __ 1/13/10 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date SIM JPM S-1.doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _ _ _ _ __

9. 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.

81M JPM 8-1.doc 2

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 between 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 TOOLS AND EQUIPMENT None TASK STANDARD:

Successfully initiate RCIC in the Pressure Control Mode re-establish control after a with 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.

INITIATING CUE:

You are the RO, 'The CRS directs you to start the RCIC System for RPV pressure control using OP-19; D.2. 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-1.doc 3

Operator's Name: _ _ _ _---._-----.__- - - - - - - - - - - -

Job

Title:

[J NLO I RO I SRO LJ STA 0 SRO Cert JPM

Title:

Initiate RCIC in the Pressure Control Mode re-establish control after a speed control failure.

JPM Number: S-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:

1. NUREG 1123. 217000; A4.07; 3.9; 3.8

2. OP-19; 0.2 Reactor Core Isolation Cooling System. Current Revision or or posted attachment at the 09-4 panel.

3. 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 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: _ _ _ __

SIM JPM S-1.doc 4

==

Description:==

This JPM has the applicant initiate RCIC in the Pressure Control Mode using OP-19. Maximize heat removal with RCIC to minimize SRV operations.

SIM JPM S-1.doc 5

NRC JAMES A. FITZPATRICK INITIAL EXAMINATION JPM S-1 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 posted The applicant locates and attachment, RCIC MANUAL START UP obtains from a controlled copy FOR RPV PRESSURE CONTROL; OP- of OP-19; 0.2.

19,0.2 or posted attachment at the 09-4 Applicant should verify that panel.

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. i I

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.

3. (Step 0.2.2) Verify Annunciator 09 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 VL V 13MOV

a. Ensure open CST SUCT VLV 18 red -- open 13MOV-18 indicating light is on.

b. Ensure closed the following valves: b. INSO TORUS SUCT 13MOV closed

INSO TORUS SUCT 13MOV-41

c. OUTSD TORUS SUCT

OUTSO TORUS SUCT 13MOV 13MOV closed 39 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. i SIM JPM S-1.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-1 ELEMENT i STANDARD SAT UNSAT Comment Number

5.(Step 0.2.4)Open HPCI and RCIC Applicant at Panel 09-3, opens TEST VLV TO CST 23MOV-24. 23MOV-24 by placing its control switch to the OPEN position. i

6. (Step 0.2.5) Start VAC PMP 13P-3. Applicant at Panel 09-4, starts i pump 13P-3 by placing its

control switch to the START position.

7.(Step 0.2.6) Open OIL CLR WTR Applicant at Panel 09-4 opens SUPP 13MOV-132. 13MOV-132 by placing its i

control switch to the OPEN position.

8. (Step 0.2.7) Open TEST VLV TO Applicant at Panel 09-4 opens CST 13MOV-30. 13MOV-30, by placing its i control switch to the OPEN i position.

9. (Step 0.2.8) Opens TURB STM Applicant at Panel 09-4, opens SUPP VLV 13MOV-131. 13MOV-131, by placing its control switch to the OPEN CAUTION: Operating RCIC at less than position.

2200 rpm could cause improper oil system operation and insufficient exhaust flow resulting in check valve banging or steam flow reversals.

I

10. (Step 0.2.9) Verify RCIC Flow rate Applicant adjusts RCIC flow i is approximately 400 gpm. rate is approximately 400 gpm on 13FI-91. I SIM JPM S-1.doc 7

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM $-1 ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR NOTE: Applicant should inform the CRS of the failure of automatic Applicant should recognize RCIC speed speed control of the RCIC as failed high. turbine; follow guidance of EN OP-115 to place the RCIC turbine speed controller in manual.

Examiner Note: The applicant may trip RCIC manually when speed fails high in order to protect the RCIC turbine.

Examiner: Role Playas CRS to direct the RO candidate to take manual control and establish pressure control with RCIC.

For SRO candidates ask them what they recommend for this situation.

11. Applicant places RCIC flow Applicant places RCIC flow controller in manual to control speed controller in manual to control speed

12. (Step D.2.10) Ensure closed the Applicant observes that the following valves: green - closed indicating light for:

MIN FLOW VLV 13MOV-27.

STM LINE DRN TO RADW

13MOV-27 is on.

13AOV-34

13AOV**34 is on.

STM LINE DRN TO RADW 13AOV-35

13AOV-35 is on.

NOTE NOTE As RPV pressure lowers, indicated level As RPV pressure lowers, on 02-3L1-283A may rise and result in indicated level on 02-3L1-283A an undesired trip at the red line high may rise and result in an level trip value. Posted attachment 3 will undesired trip at the red line give an equivalent trip level for 06L1 high level trip value. Posted 941AlB/C indicators on panel 09-5. I attachment 3 will give an

equivalent trip level for 06L1 I 941AlB/C indicators on panel 09-5.

SIM JPM S-1.doc 8

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-1 ELEMENT STANDARD SAT UNSAT Comment Number CAUTION CAUTION Operating RCIC at less than 2200 rpm Operating RCIC at less than could cause improper oil system 2200 rpm could cause operation and insufficient exhaust flow improper oil system operation resulting in check valve banging or and insufficient exhaust flow steam flow reversals. resulting in check valve banging or steam flow reversals. i

15.(Step 0.2.11) WHILE contrOlling At 09-4 Panel, monitors RCIC RPV pressure, maintain RCIC speed turbine speed on 13SPI-1 and GREATER THAN 2200 rpm by throttles closed 13MOV-30 to throttling closed TEST VL V TO CST ! ensure RCIC only runs below 13MOV-30.

2200 rpm during transient i

operation.

16. (Step 0.2.12) Throttle TEST VLV At Panel 09-4, throttles closed I TO CST 13MOV-30, to obtain the 13MOV-30 to begin the RPV desired RPV pressure control. depressurization by minimizing SRV operation .

17. (Step 0.2.13) Startup RHR Torus EVALUATOR: Inform the cooling per Section 0 of OP-138, as applicant that another operator soon as practicable. has been tasked with initiating Torus cooling.

18. (Step 0.2.14) Monitor Torus water Observes EPIC or 09-3 Panel temperature and level. indicators to monitor Torus water temperature and level.

19. (Step 0.2.15) WHEN time permits, Applicant verifies the following verify the following RCIC parameters: RCIC parameters:

Oil pump discharge pressure: 12

Oil pump discharge to 15 psig. pressure: 12 to 15 psig.

Oil temperature from cooler:

GREATER THAN 60 o F.

Oil temperature from cooler: GREATER

Oil temperature from the turbine THAN 60°F.

bearings: LESS THAN 160 0 F

Oil temperature from the turbine bearings:

LESS THAN 160 0 F I EVALUATOR: Terminate the task at this point.

JPM Stop Time _ _ _ __

S/M JPM S-1.doc 9

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION 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.

INITIATING CUE:

You are the RO, 'The CRS directs you to start the RCle System for RPV pressure control using OP 19; D.2. Maximize heat removal with RCIC to minimize SRV operations.

S/M JPM S-1.doc

James A. Fitzpatrick Generating Station Job Performance Measure HPCI Full Flow Test JPM Number: S-2 Revision Number: 1 Date: 02/04/2010 Developed By: =B;,:...=Li=tk=e:;.::;tt:...-_ _ _ _ _ _ __ 02/04/10 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date 81M JPM 8-2. doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _ _ _ _ __

9. 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-2.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

1. Reset simulator to IC-41.

2. Place RHR in torus cooling mode lAW OP-13B, Section D.

3. Start GLAND SEAL CNDSR BLOWER 23P-140.

4. Throttle open TEST VALVE TO CST 23MOV-21 for 5 seconds.

5. Simulator operator override RED light ON, GREEN light OFF for TEST VALVE TO CST 23MOV

24. ZL023A59-1, GREEN and ZL023A59-2, RED.

6. Simulator operator override TEST VALVE TO CST 23MOV-24 handswitch to CLOSE.

ZD123A59.

(Setup Steps #5 and #6 above simulate sheared valve stem. 23MOV-24 is closed, but indicates open.)

7. Simulator operator override MIN FLOW VALVE 23MOV-25 handswitch to CLOSE.

ZD123A58. (simulates switch problem which maintains min flow valve closed).

8. 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..

9. Initiate EPIC four-parameter plot TRHPCI.

TOOLS AND EQUIPMENT

Marked-up copy of ST-4N, HPCI QUICK-START, INSERVICE, AND TRANSIENT MONITORING TEST (1ST), completed through Section 8.3 and thru Step 8.4.6.

Stopwatch 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:

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. Venting Torus 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 S/M JPM S-2.doc 3

JPM

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:

1. NUREG 1123, Knowledge and Abilities Catalog for Nuclear Power Plant Operators - Boiling Water Reactors

2. 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? 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 comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date:

SIM JPM S-2.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-2.doc 5

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-2 NOTE: Critical Element( s) indicated by

in Performance Checklist PERFORMANCE CHECKLIST:

JPM Start Time _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtain procedure Applicant reviews completed sections of ST and begins implementation at Section 8.4

2. (Step 8.4.7) IF RPV pressure is Applicant opens 23MOV-16 GREATER THAN OR EQUAL TO 165 and records open stroke time psig. THEN open and time OUTBD within limits of 4.9 to 8.2 STM SUPP VLV 23MOV-16. seconds.

Opening time secs (1ST: 4.9 to 8.2)

3. (Step 8.4.8) Ensure open OUTBD Applicant verifies OUTBD STM SUPP VLV 23MOV-16. STM SUPP VLV 23MOV-16 is open.

4(Step 8.4.9) Verify the following: Applicant calls up EPIC points and verifies 0-457 OPEN and

EPIC-D-457 HPCI STM OUTB 0-458 NFC ISO-C indicates OPEN

EPIC-D-458 HPCI STM OUTB ISO-O indicates NFC Note: Loss of inventory to torus will cause hotwell level will trend down.

5. (Step 8.4.10) Automatic or manual No response required.

compensation may be required to maintain hotwell level.

SIM JPM S-2.doc 6

NRC JAMES A. FITZPA TRICK EXAMINA TION JPM S-2 ELEMENT STANDARD I SAT UNSAT Comment Number

6. (Step 8.4.11) Perform the following Evaluator Cue:I&C has in any order, just before turbine startup: started all installed transient recorders at the desired A. Initiate EPIC manual transient speed.

data capture per CDSO-3.600.

B. 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).

i

7. (Step 8.4.12) No response required.

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 ~135 psig.

i

8. * (Step 8.4.13) Applicant simultaneously Simultaneously perform the opens 23MOV-14 and starts following: 23P-150.

Open TURB STM SUPP VLV 23MOV-14. Evaluator Cue: 1

Start AUX OIL PMP 23P-150. Record time HPCI was !

IF RPV pressure is GREATER started.

THAN OR EQUAL TO 165 psig, THEN Start stopwatches. HPCI start time I

9. (Step 8.4.14) Evaluator Cue: I&C are recording voltage.

IF RPV pressure is GREATER THAN OR EQUAL TO 970 psig, THEN record null voltage for approximately 1 to 2 minutes during I turbine startup (cold condition).

i S/M JPM S-2.doc 7

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-2 ELEMENT STANDARD i SAT UNSAT Comment Number

10. *(Step 8.4.15) Applicant notes HPCI pump Verify the following: discharge flow rate does NOT

Turbine speed stabilized after stabilize at ~3400 gpm AND startup transient and remained Min Flow Valve 23MOV-25 is LESS THAN 4200 rpm during the closed.

startup transient (23SPI-161 or EPIC TRHPCI speed trace)

CUE: If applicant informs CRS

23HOV-1 opens smoothly by local that pump is running without observation.

adequate flow, then

Turbine vibration is LESS THAN acknowledge the report.

OR EQUAL TO limits (0.385 IPS)

Turbine accelerates smoothly (by observing TURB SPEED 23SPI EXAMINER NOTE: Applicant 161 OR EPIC TRHPCI speed may trip the HPCI pump at this trace). time. If so, terminate the

HPCI pump discharge flow rate JPM.

stabilizes at GREATER THAN OR EQUAL TO 3400 gpm on 23FI 108-1

MIN FLOW VLV 23MOV-25 is closed.

STM LINE oRN TO RAoW 23AOV-43 is closed.

STM LINE oRN TO RAoW 23AOV-42 is closed. I

11. Acknowledge alarms. Applicant acknowledges alarms and refers to 09-3-3-15 HPCI PMP FLOW LO

12. (ARP Step 1) Verify open MIN Applicant determines MOV-25 FLOW VLV 23MOV-25. . is not open.

13. (ARP Step 2) Verify expected Applicant determines speed is turbine speed and pump discharge normal and pump discharge pressure. pressure is high.

14. (ARP Step 3) No response required. HPCI initiate signal not present.

IF HPCI initiation signal is present, THEN ensure open:

INJ VLV 23MOV-19

PMP DISCH VLV 23MOV-20

15. * (ARP Step 4) Consider securing Applicant trips HPCI pump.

HPCI if flow can not be restored.

i I SIM JPM S-2.doc 8

NRC JAMES A. FITZPA TRICK EXAMINA TION JPM 8-2 ELEMENT STANDARD SAT UNSAT Comment Number NOTE TO EXAMINER:

1. IF applicant stops HPCI pump, THEN TERMINATE THE JPM.

2. 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.

16. (Step 8.4.16) EVALUATOR CUE: I&C has stopped recorders. Times are IF RPV pressure is GREATER as follows:

THAN OR EQUAL TO 165 psig, THEN perform the following in any

23HOV-1 response order or concurrently:

=

time 19.3 sec A. WHEN all parameters have

23HOV-1 opening time stabilized on EPIC plot = 17.4 sec TRHPCI, AND AT LEAST two

23MOV-14 opening minutes have elapsed, direct =

time 8.1 sec I&C to stop all installed transient recorder( s).

B. 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)

NOTE 1: TRHPCI printout is required within 15 minutes of turbine startup to ensure starting transient is included on plot.

NOTE 2: Test may be continued before the next step is complete.

81M JPM 8-2.doc 9

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-2 ELEMENT STANDARD SAT UNSAT Comment Number

17. (Step 8.4.17) EVALUATOR CUE: I&C is reviewing data.

IF RPV pressure is GREATER THAN OR EQUAL TO 165 psig, THEN I&C or Engineering review recorder trace and verify the following:

HPCI flow rate reached GREATER THAN OR EQUAL TO 3400 gpm within 60 seconds of initiation.

HPCI flow rate remained GREATER THAN OR EQUAL TO 3400 gpm after 60 seconds from initiation and through stabilization.

NOTE: HPCI response time is measured from Step 8.4.13 until flow rate reaches and remains GREATER THAN OR EQUAL TO 3400 gpm.

HPCI response time from recorder trace is LESS THAN 60 seconds.

18. (Step 8.4.18) No response required. RPV 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 reached GREATER THAN OR EQUAL TO 3400 gpm.

HPCI flow rate remained GREATER THAN OR EQUAL TO 3400 gpm through stabilization.

I SIM JPM S-2.doc 10

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM 8-2 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 discharge pressure as follows:

A. IF RPV pressure is GREATER THAN OR EQUAL TO 970 psig, THEN throttle TEST VL V TO CST 23MOV-21 to establish BOTH of the following conditions:

HPCI turbine speed GREATER THAN 2100 rpm on TURB SPEED 23SPI-161 AND

HPCI pump discharge pressure GREATER THAN OR EQUAL TO 1250 psig on DISCH PRESS 23PI-109

20. (Step 8.4.19 continued) Not applicable. RPV pressure is greater than 970 psig.

B. IF RPV pressure is LESS THAN 970 psig, ...

EXAMINER:

The pump has been running without flow for several minutes. Terminate the task at this point.

JPM Stop Time _ _ _ __

81M JPM 8-2.doc 11

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-2 HANDOUT PAGE TASK CONDITIONS:

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. Venting Torus 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-2.doc

James A. Fitzpatrick Generating Station Job Performance Measure Reactor Scram with a Control Rod Insertion Failure JPM Number: S-3 Revision Number: 1 Date: 1/13/10 Developed By: .;;;;;;B..=;.e.;:..;rn..;.;;a=r=d...::;L_.it_k=e..;;.;:tt:... _ _ _ _ __ 1/13/10 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date 81M JPM S-3.doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _ _ _ _ __

9. 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-3.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

Reset the simulator to appropriate IC-40, 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.

2. The Shift Manager has directed a manual scram and performance of AOP-1, Reactor Scram immediate actions.

INITIATING CUE:

You are the RD. 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-3.doc 3

Operator's Name: ______- - - -___- - - - - - - - - - - - -

Job

Title:

0 NLO. RO

SROO STA 0 SRO Cert JPM

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: 15 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 C 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 comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _{Print)

Evaluator's Signature: Date:

SIM JPM S-3.doc 4

==

Description:==

This JPM will require insertion o'f Manual Reactor Scram with a Control Rod insertion failure SIM JPM S-3.doc 5

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-3 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT CO~

NUll!

1.(Step E.1) If a manual scram is Applicant depresses the required, THEN depress the following manual scram pushbuttons.

pushbuttons:

MANUAL SCRAM A NOTE: The applicant should

MANUAL SCRAM B observe:

Annunciators 09-5-1-13, 14, RPS MAN SCRAM alarms.

i SCRAM GROUPS 1, 2, 3, 4 lights are off.

2. (Step E.2) Place RX MODE switch Applicant places RX MODE in SHUTDOWN. switch in the SHUTDOWN position.

NOTE: The immediate operator actions in Steps 3 through 7 may be performed concurrently.

3. (Step E.3) Fully insert the IRMs and Applicant select and drive in SRMs. fully all IRMs and SRMs.

NOTE:

I NOTE: Since low power IRMs are Since low power IRMs are already already inserted.

inserted.

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

responses:

APRM recorders

APRMs recorders or downscale indicate downscale indicating lights and/or observing that

Fully inserted IRMs trending the APRM downscale down (recorder selector switch lights are lit to IRM position)

Fully inserted IRMs

Fully inserted SRMs trending trending down for down those IRMs selected on the recorder

Fully inserted SRMs trending down on I recorder or meters SIM JPM S-3.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION JPM 8-3

~I ~"ENT

' STANDARD SAT UNSAT Comment Number

'* 5. (Step E5) Verify the reactor will Applicant using one or more of remain shutdown under all conditions the methods listed observes without boron using one or more of the that one control rod is full out, following methods: all others are full in and

Green FULL IN light on full core informs CRS that one rod is display (preferred method) full out.

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 E6) If multiple rods are Applicant observes that only 1 withdrawn, then initiate ARI. 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.

7. (Step E7) Ensure closed SDIV vent Applicant observes SDIV vent and drain valves. and drain valve position indicating lights. Verify that the green (closed) lights come on after the red (open) indicating lights go off. i 81M JPM S-3.doc 7

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-3 T STANDARD T UNSAT Comme Number

8. (Step E.8) WHEN APRM's are Applicant ensure main turbine downscale, THEN perform the is tripped by observing:

following: a.

Annunciator 09-5-2-9

a. Ensure Main Turbine is tripped. MAIN TURB TRIP is in alarm

Amber (tripped) light is on at EHC control on

b. Verify 4 KV loads transfer to reserve 09-5 Panel power.

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 KV on:

Bus 10500 volt meter on Panel 09-8.

Bus 10600 voltmeter on Panel 09-8.

9. (Step E.9) If circulating water pumps Applicant observes circulating are tripped, then ensure closed MSIV's. water pumps A and/or B running with red indicating light on.

10. (Step E.10) If both recirc pumps are Applicant observes Recirc tripped, then minimize RPV bottom pumps status by checking head cooldown per Attachment 6 of red/green light indication AOP-1. and/or pump flows.

EVALUATOR CUE: If recirc pumps EVALUATOR CUE: If recirc have tripped, inform applicant that pumps have tripped, inform Attachment 6 of AOP-1 will be applicant that Attachment 6 of performed by another operator AOP-1 will be performed by another operator.

11. (Step F.1.1) IF any control rod !§.. EVALUATOR CUE: When NOT full in, AND NO EOP-3 entry asked, CRS directs inserting condition is present, THEN perform control rod with RMCS.

attachment 4 or 5 as directed by the SM Applicant selects attachment or CRS. 4.

EVALUATOR CUE: When asked, CRS directs inserting control rod with RMCS applicant selects attachment 4. i SIM JPM S-3.doc 8

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-3 ENT STANDARD SAT UNSAT Com Numb......

12. (Attachment 4, step 2) Place Applicant places RWM keylock RWM keylock switch in BYPASS in switch in BYPASS.

RWM console.

13.(Attachment 4, step 3) Reset EVALUATOR CUE:

Reactor Scram as follows: ARI should not have actuated If ARI has actuated then reset ARI. during the scram, but if it did then reset it per Attachment 4, EVALUATOR CUE: step 3 ARI should n'ot have actuated during the scram, but if it did then reset it per Attachment 4, step 3

14. (Attachment 4, step 3.b) Verify Applicant verifies 09-5-1-33 is Annunciator 09-5-1-33 MODE SW IN in alarm.

SHUTDOWN TRIP BYPASSED is in alarm.

15. (Attachment 4, step 3.c) Applicant places SDIV HI LVL Place SDIV HI LVL TRIP keylock switch TRIP keylock switch in in BYPASS. BYPASS.

16. (Attachment 4, step 3.d) Applicant places RX SCRAM Place RX SCRAM RESET switch to RESET switch in group 2 & 3, group 2 & 3 then to 1 & 4, spring return then to group 1 & 4, spring to NORM. 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) Applicant verifies RPS A and Verify RPS A and B Scram Group 1, 2, B Scram Groups 1, 2, 3, and 4 3, and 4 lights are on. lights are on.

18. (Attachment 4,step 3.f) Applicant verifies all blue Verify closed all scram inlet and outlet SCRAM lights are out on valves using one or a combination of FULL CORE DISPLAY.

the following methods:

Blue SCRAM lights on FULL CORE DISPLAY

Local valve position indication

19. (Attachment 4,step 3.h) Applicant verifies red open Verify open SDIV vent and drain valves. lights are on and green closed lights are out for SDIV vent and drain valves at panel 09-5. i SIM JPM S-3.doc 9

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-3 ENT !STANDARD SAT UNSAT C....., "', ~

N 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.

I 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 NORMAL i in NORMAL I EVALUATOR CUE: The next step may be performed after rod insertion as there is only one rod out.

21. (Attachment 4,step 3.j) Goes to section G.2 for post Perform post scram reset control rod scram reset control rod position check per section G.2. as soon position check.

as practicable.

SIM JPM S-3. doc 10

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM 8-3 SAT UNSAT C

22. (Attachment 4, step 6) Applicant closes or throttles Raise CRD drive water closed 03MOV-20 without differential pressure using one exceeding 600 psid drive or more of the following water DIP to establish methods in the listed order of elevated drive water DIP.

priority:

EVALUATOR CUE: If asked, CAUTION: Drive water differential inform applicant to use the first pressure is limited to less than 600 psid priority option. Other options with reactor pressure below 650 psig to may be selected and utilized.

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:

o 03CRD-177A (CRD water pump A min flow isol valve) o 03CRD-177B (CRD water pump B min flow isol valve

23.(Attachment 4, step 7) Applicant selects stuck rod on Attempt to insert each withdrawn ROD SEL matrix.

control rod in the order specified in

Inserts rod to full in Attachments 1,2 and 4 as follows: using either the ROD

a. Select control rod on ROD SEL MOVEMENT CNTRL matrix. held in the IN position.

b. Insert control rod using one of the OR following switches:

Holding the ROD

ROD MOVEMENT CNTRL EMERG IN NOTCH

ROD EMERG IN NOTCH OVERRIDE IN EMERG OVERRIDE RODIN.

25. Re orts that all rods are full in. Re orts all rods are full in.

81M JPM 8-3.doc 11

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-3 ELEMENT STANDARD SAT UNs~mment umber

26. (Attachment 4,step G.2)

Verifies green FULL IN Applicant verifies all control rods have lights are on except for settled from the overtravel position back the rod stuck out.

to notch position (00) by observing one

Resets the ROD or more of the following: DRIFT and verifies the red DRIFT lights are

Green FULL IN lights are on and off at full core display iI red DRIFT lights are off at full OR core display.

Runs and verifies Full

Full core scram indicates 00. Core Scram indicates

Four rod display indicates 00. 00 for all rods except the one stuck out OR

Verifies four rod display indicates 00 for all rods except the one stuck out.

EVALUATOR: Terminate the task at this point.

JPM Stop Time _ _ _ __

SIM JPM S-3.doc 12

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-3 HANDOUT PAGE TASK CONDITIONS:

1. The reactor is operating near 5% reactor power and conditions exist that require a reactor scram.

2. The Shift Manager has directed a manual scram and performance of AOP-1. Reactor Scram immediate actions.

INITIATING CUE:

You are the RO. The eRS directs you to manually scram the reactor and carry out the actions of AOP-1.

SIM JPM S-3.doc

James A. Fitzpatrick Generating Station Job Performance Measure SPRAY THE DRYWELL WITH RHRSW (ALTERNATE PATH)

JPM Number: S-4 Revision Number: 2 Date: 1/20/10 Developed By: .;B,;,e;..:.rn=a:;.;rd::....=L.:.;.itk=e=t:,:...t_ _ _ _ _ __ 1/20/10 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date S/M JPM S-4.doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date

9. 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-4.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

1. Simulator should be reset to an IC-46 that has the following conditions:

Reactor level is at T AF

DW spray is required with temperature and pressure within DWSIL

RHR Pump 'A' and 'C' is not available for DW 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-RHZ1010151B(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:

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 per posted attachment for Drywell spray.

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.

81M JPM 8-4. 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 8-4.doc 4

Operator's Name: --------.....-------__r-----------------

Job

Title:

0 NLO I RO I SRO DSTA o SRO Cert JPM

Title:

SPRAY THE DRYWELL WITH RHRSW (ALTERNATE PATH)

JPM Number: S-4 Revision Number: 2 KIA Number and Importance: KA226001 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, Alternate Containment Sprays, Rev. 3 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: Satisfactory Unsatisfactory Comments:

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: ___________________(Print)

Evaluator's Signature: Date: _ _ _ __

SIM JPM S-4.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.

SIM JPM S-4.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM 8-4 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Applicant obtains posted instructions Applicant obtains posted I for Drywell Spray instructions for Drywell Spray

2. Ensure the following components are Applicant ensures the tripped: following components are tripped:

RWR Pumps

02-2P-1A RWR Pumps

02-2P-1 B

02-2P-1A

02-2P-1B Drywell Cooling Fans

68FN-2A. B, C, and D Drywell Cooling Fans

68FN-4A. B, C, and D

68FN-2A, B, C. and D

68FN-4A, B, C, and D

3. Applicant verifies drywell I Applicant verifies drywell temperature and. ~r~ssur~ ~re within the. temperature and pressure are Drywell Spray Imtiatlon Limit . within the Drywell Spray i Initiation Limit.

4. IF RPV water level is LESS THAN Applicant verifies IF RPV 10 inches on fuel zone water level water level is LESS THAN 10 indication, AND the EOPs permit inches on fuel zone water level diverting LPCI flow, THEN place DW & indication, AND the EOPs Torus Spray VLV OVERRIDE OFFUEL permit diverting LPCI flow, ZONE LVL 10A-S18A(B) keylock in THEN place DW & Torus MANUAL OVERRD Spray VL V OVERRIDE OFFUEL ZONE LVL 1OA S18A(B) keylock in MANUAL OVERRD

5. Place SPRAY CNTRL 10A-S17B Applicant places SPRAY switch to MANUAL, spring return to CNTRL 10A-S17B switch to !

normal. MANUAL, spring return to i

. normal.

6. Verify white SPRAY PERM 10A I Applicant verifies white DS67B light is on. i SPRAY PERM 10A-DS67B I light is on.

I 81M JPM 8-4.doc 7

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION JPM 8-4 ELEMENT STANDARD SAT UNSAT I 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 8 are running: RHR pumps in RHR Loop 8

RHR PMP 10P-38 are running:

RHR PMP 10P-30

RHR PMP 10P-38

RHR PMP 10P-30

8. Open DW SPRAY OUT80 VLV Applicant opens OW SPRAY 10MOV-268. OUT80 VLV 10MOV-268.

SIMULATOR BOOTH OPERATOR SIMULATOR BOOTH Insert RH12 TORUS OUTLET VLV OPERATOR (1518) TO RHR LOOP 8 to close valve Insert RH12 TORUS OUTLET and use override to have the valve VLV (1518) TO RHR LOOP 8 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 commenced.

9. Throttle OW SPRAY IN80 VLV Applicant throttles OW SPRAY 10MOV-318 to establish desired drywell IN80 VLV 10MOV-318 to spray flow rate. establish desired drywell spray flow rate.

10. WHEN RHR Loop 8 flow is Applicant ensures WHEN RHR GREATER THAN 1500 gpm, ensure Loop 8 flow is GREATER closed MIN FLOW VLV 10MOV-168 THAN 1500 gpm, ensure closed MIN FLOW VLV

, 10MOV-168

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 8-4.doc 8

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-4 ELEMENT STANDARD I SAT UNSAT Comment Number

12. Applicant ensures WHEN RHR Applicant ensures WHEN RHR Loop B flow is LESS THAN 1500 gpm, . Loop B flow is LESS THAN ensure open MIN FLOW VL V 10MOV ! 1500 gpm, ensure open MIN 16B FLOW VLV 10MOV-16B CAUTION CAUTION Blockage of ECCS pump suction Blockage of ECCS pump strainers could occur due to debris in suction strainers could occur the Torus. Within the latitude provided due to debris in the Torus.

by EOPs to restore and maintain Within the latitude provided by parameters within specified limits, EOPs to restore and maintain potential mitigative actions may include: parameters within specified

Minimizing ECCS flow or limits, potential mitigative removing affected ECCS pumps actions may include:

from service

Minimizing ECCS flow or

Alternating ECCS pumps from removing affected ECCS one division to another, if pumps from service available.

Alternating ECCS pumps

Shifting ECCS pump suction to from one division to another source,if available another, if available.

Operation of alternate injection

Shifting ECCS pump sources suction to another source,if I

available

Operation of alternate inlection sources

13. Ensure the following RHR pumps Applicant ensures pumps are are stopped: stopped.

RHR PMP 10P-3B

RHR PMP 10P-3D EVALUA TOR: Observe applicant identifies the pumps are stopped. I I

14. Applicant should recognize the Applicant should recognize the need to use Alternate Drywell Spray need to use Alternate Drywell EVALUA TOR CUE FOR SRO: Spray; EP-14 If necessary ask applicant to recommend a course of action.

EVALUA TOR NOTE:

EVALUATOR CUE FOR RO:

If necessary ask applicant What Applicant may perform step alternate methods are available for to F.B ofOP-13B; RHR Loop B spray the drywell? shutdown from Torus

1. RHRSW Cooling or Containment

2. FIRE PROTECTION Spray Mode before going to EP-14. I i I SIM JPM S-4.doc 9

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-4 ELEMENT STANDARD SAT UNSAT Comment Number

15. Obtain a controlled copy of Obtains a controlled copy of procedure and selects the correct EP-14 and selects section 5.2 section to perform. to perform.

16. Reviews precautions, prerequisites Reviews applicable section of and special instructions associated with the procedure and notes the procedure: requirements for Drywell spray

This procedure shall be used only flow rate.

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 B.

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.

17. Verify the following RHR pumps are Applicant verifies pumps are stopped: stopped.

RHR PMP 10P-3B

RHR PMP 10P-3D EVALUATOR:ObseNe applicant identifies the pumps are stopped.

18. Ensure closed at least one of the Applicant ensures at least one following valves: of the valves is closed.

OW SPRAY OUTBD VLV 10MOV EVALUA TOR: ObseNe 26B applicant identifies the

OW SPRAY INBD VLV 10MOV-31B valves are closed.

19. Ensure closed at least one of the Applicant ensures at least one following valves: of the valves is closed.

RHR TEST TORUS CLG & SPRAY 10MOV-39B

TORUS SPRAY INBD VLV 10MOV EVALUA TOR: ObseNe 38B applicant identifies the valves are closed.

SIM JPM S-4.doc 10

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION JPM S-4 ELEMENT STANDARD SAT UNSAT Comment Number

20. Ensure closed at least one of the Applicant ensures at least one following valves: of the valves is closed.

RHR TEST TORUS CLG & SPRAY 10MOV-39B EVALUA TOR: Observe

RHR TEST & TORUS CLG 10MOV applicant identifies the 34B valves are closed.

21. Ensure closed at least one of the Applicant ensures at least one following valves: of the valves is closed.

LPCI INBD INJ VLV 10MOV-25B EVALUA TOR: Observe

LPCI OUTBD INJ VLV 10MOV-27B applicant identifies the valves are closed.

22. Ensure available RHRSW pumps Applicant ensures pumps are in RHRSW Loop B are running: started.

RHRSW PMP 10P-1B

RHRSW PMP 10P-1D EVALUATOR: Observe applicant starts the pumps.

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

RHRSW pump.

EVALUATOR: Observe applicant throttles valve to required flow.

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 10MOV

Ensure open the following valves:

148B o RHRSW to RHR 10MOV-148B o RHRSW to RHR 10MOV-149B o RHRSW to RHR 10MOV 149B

=S='M==J~PM~S~-~4.~d~oc==================================================11

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-4 ELEMENT STANDARD SAT UNSAT Comment Number

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-1B them.

o DW CLG FN 68FN-2A o DW CLG FN 68FN-2B o DW CLG FN 68FN-2C EVALUATOR:

o DW CLG FN 68FN-2D This step was previously o DW CLG FN 68FN-4A performed.

o DW CLG FN 68FN-4B o DW CLG FN 68FN-4C o DW CLG FN 68FN-4D

27. Verify drywell temperature and Applicant verifies the DWSIL pressure are within the Drywell Spray within the curve.

Initiation Limit.

EVALUATOR: 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 LVL 10A-S18B keylock switch in MANUAL OVERRD. EVALUATOR:

This step was previously performed NOTE: Applicant reviews NOTE and The following step must be performed requirements for DW spray each time drywell spray is initiated or initiation.

re-initiated;

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 10A 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 VL V FROM HX A 10MOV-89B is closed.

~~~~========================================12 SIM JPM S-4.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION JPM 8-4 ELEMENT STANDARD SAT UNSAT Comment Number

32. Ensure open OW SPRAY OUTBO Applicant ensures OW SPRAY VLV 10MOV-26B. OUTBO VLV 10MOV-26B is open.

33. Throttle OW SPRAY INBO VLV Applicant throttles OW SPRAY 10MOV-31 B to establish desired flow INBO 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 _ _ _ __

====================================================13 SIM JPM S-4.doc

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON 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 'D' RHR pumps per posted attachment for Drywell spray.

S/M JPM S-4.doc

James A. Fitzpatrick Generating Station Job Performance Measure Manual Isolation and Verification of Reactor Building Ventilation System JPM Number: S-5 Revision Number: 0 Date: 1/13/10 Developed By: Bernard Litkett 1/13/10 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date 81M JPM 8-S.doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _ _ _ _ __

9. 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.

81M JPM 8-S.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:

1. Reactor Building Ventilation manual isolation is required to support a maintenance activity.

2. 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 Ventilation System per OP-51 A.

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-5.doc 3

Operator's Name: _ _ _ _-.......-______- - - - - - - - - - - -

Job

Title:

D NLO I RO I SRO DSTA DSRO Cert 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.47

3. Standby Gas Treatment System OP-20: section 0.1, 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: D Satisfactory Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

81M JPM S-S.doc 4

Descril2tion: This JPM has the applicant perform a manual isolation and verification of reactor building ventilation system SIM JPM S-5.doc 5

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-S NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT I Comment Number

1. Obtain a controlled copy of The applicant determines procedure OP-51A; Sections G.1 and where to obtain a controlled G.2 and OP-20. copy of OP-51A and OP-20. i i (Control Room, Merlin)

2. Review precautions associated with , Applicant review Section C of the procedure . the procedure and notes i precaution relating to changing building ventilation line-ups.

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

4. Ensure SBGT is running per OP-20. Applicant obtains a current I copy of OP-20 and reviews precautions associated with

. the operation of the SBGT System.

5. Selects the correct section to Applicant reviews the perform the task. procedure and selects Section D.1 for the "A" SBGT Train.

EVALUATOR CUE:

Act as the CRS/SNO and Act as the CRS/SNO and when asked, when asked order the "An order the "An SBGT Train started. If SBGT Train started. If asked, asked, inform operator that no painting, inform operator that no welding or smoke fumes have been in painting, welding or smoke the Reactor Building in the last 24 fumes have been in the hours.

Reactor Building in the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6. Ensure OPENS the following: Applicant at the 09-75 panel locates the control switch and ABOVE EL 369' SUCT.

I OPENS the following valve:

01-125MOV-11 I01-125MOV-11 S/M JPM S-S.doc 6

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

7.Ensure OPEN "An Inlet Valve: i Applicant locates and OPENS 01-125MOV-14A 01-125MOV-14A

8. Verify the following system response Applicant observes and on startup: verifies component operation during the startup of the "An SBGT Train

White light for AIR HTR 01

White light for AIR HTR 125E-5A is ON. 01-125E-5A is ON.

Red light for AIR HTR 01-125E 5A is ON.

Red light for AIR HTR 01 125E-5A is ON.

TRAIN A CLG VLV 01-125MOV 100A is CLOSED.

TRAIN A CLG VLV 01

FN DISCH 01-125MOV-15A is 125MOV-100A is OPEN. CLOSED.

TRAIN A FN 01-125FN-1A is running.

FN DISCH 01-125MOV 15A is OPEN.

TRAIN A FN 01-125FN-1A is running.

9. SBGT to Support: EVALUATOR CUE:

TORUS Venting SBGT "An is not being used to support any of these activities.

Drywell Venting

HPCI Operation

MSLCS Operation

AGT System Operation I i

10. IF SBGT "B" is shutdown" For the "B" SBGT train: !

Verify open 0 1-125MOV-1 OOB Applicant verifies open TRAIN "B" CLG VLV 01-125MOV Verify flowrate on SGT flow 01-125FI 100B 106A Applicant verifies flowrate on SGT flow 01-125FI-106A

RB un-isolated-Approximately 6000 SCFM

RB isolated Approximately 5600 to 5800 I S/M JPM S-5.doc 7

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION JPM 8-5 ELEMENT STANDARD SAT UNSAT I Comment Number

11. Applicant verifies Rx Building Applicant verifies Rx Building differential pressure DIFF Pressure 01-125DPI-100A is less i negative than -.25 inches

12. Depress pushbuttons: Applicant at the 09-75 panel, (OP-51A; G.1): locates the isolation pushbuttons and depresses

RB VENT ISOL A both isolation push buttons.

RB VENT ISOL B l i 81M JPM 8-5.doc 8

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-5 ELEMENT STANDARD I SAT UNSAT Comment i Number

13. Verifies the following to ensure Applicant at the 09-75 panel Reactor Building Ventilation Isolation verifies the isolation using the (OP-51A; G.2) posted attachment or OP-51A

INBD SUPP ISOL 66AOV

INBD SUPP ISOL 66AOV-100A 100A; CLOSED CLOSED

OUTBD EXH ISOL

OUTBD EXH ISOL 66AOV-101A 66AOV-101A; CLOSED CLOSED

BELOW EL 369' RECIRC

BELOW EL 369' RECIRC 66AOD 66AOD-'105; OPEN 105 OPEN

EL 369' RECIRC 66AOD 108; OPEN

EL 369' RECIRC 66AOD-1 08; OPEN

OUTBD SUPP ISOL

OUTBD SUPP ISOL 66AOV-100B; 66AOV-100B; CLOSED CLOSED

INBD EXH ISOL 66AOV

INBD EXH ISOL 66AOV-101B 101B; CLOSED CLOSED

SUPP FN 66FN-5A, 5B,

SUPP FN 66FN-5A, 5B, 5C (2 OF 5C (TWO OF 3); ON 3)ON

BELOW EL 369' EXH FN

BELOW EL 369' EXH FN 66FN-12A 66FN-12A OR 66FN-12B; OR 66FN-12B: ON ON

EL 369' EXH FN 66FN-13A

EL 369' EXH FN 66FN-13A AND 66FN-13B; OFF AND 13B; OFF

TK EXH FN 66FN-35; OFF

TK EXH FN 66FN-35; OFF

CRESC SUPP FN 66FN

CRESC SUPP FN 66FN-26A OR 26A OR 66FN-26B; ON 66FN-26B; ON

SBGT SYSTEM; RUN PER

SBGT SYSTEM; RUN PER OP-20 OP-20

!

RX BLDG DIP; -0.25 TO --2.5 in. WATER

RX BLDG DIP; -0.25 TO -2.5 in.

GAUGE WATER GAUGE I EVALUATOR: Terminate the task at this point.

JPM Stop Time _ _ __

SIM JPM S-5.doc 9

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TlON JPM S-5 HANDOUT PAGE TASK CONDITIONS:

1. Reactor Building Ventilation manual isolation is required to support a maintenance activity.

2. 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 Ventilation System per OP-51 A.

SIM JPM S-5.doc

James A. Fitzpatrick Generating Station Job Performance Measure PERFORM 5T-9BB, EDG B & D FULL LOAD TE5T AND E5W PUMP OPERABILITY TE5T JPM Number: S-6 Revision Number: 1 Date: 2/02/10 Developed By: .=B~er:..:.n::.:::a:.:..;:rd::;:....=Li:.::.:tk=e=tt:...-_ _ _ _ __ 2/02/10 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date S/M JPM S-6.doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - - - - -

9. 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-6.doc 2

REVISION RECORD (Summary):

1. Rev 1 JPM Setup Instructions:

1. Initialize the simulator to IC-39

2. Obtain a controlled copy of ST-9B8, EDG B & D FULL LOAD TEST AND ESW PUMP OPERA81L1TY TEST. Initial as complete Section 4.0, 5.0 and Steps 8.1 through and including Steps 8.12.

3. Copies of EDG Demand Log for EDG 8 & D forms from OP-22, DIESEL GENERATOR EMERGENCY POWER.

4. 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) 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 8 and D and place in MAINT.

TOOLS AND EQUIPMENT

1. Stopwatch

2. Synchronizing Switch TASK STANDARD:

Perform surveillance test ST-988 EDG 8 & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST. Determine EDGs have no cooling and shutdown prior to engine damage.

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-9B8, EDG 8 & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST, commencing at Step 8.13 for EDG 8 & 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.

S/M JPM S-6.doc 3

Operator's Name: _________- - -__- - - - - - - - - - - -

Job

Title:

D NLO I RO I SRO DSTA o SRO Cert JPM

Title:

Perform the Emergency Diesel Generator Load Test (StU 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: D Satisfactory D Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

S/M JPM S-6.doc 4

Description:

This JPM asks the applicant to perform ST-9BB; EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST.

SIM JPM S-6.doc 5

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM 8-6 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 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

2. Reviews the precautions Reviews the precautions, making note of any that are applicable

3. Select the correct section to perform Applicant selects step 8.13 of the task. ST-9BB EVALUATOR CUE: If asked, the other ROs will perform the stopwatch function.

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 stopwatch EVALUATOR CUE: If asked, the 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 81M JPM 8-6.doc 6

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-6 ELEMENT STANDARD I SAT: UNSAT Comment Number

6. EVALUATOR CUE: If asked, the EVALUA TOR CUE: If asked, other ROs perform the stopwatch the other ROs perform the function. stopwatch function.

Step 8.15 Operator 1 time: 6.92 sec

Step 8.15 Operator 1 time:

Step 8.16 Operator 2 time: 7.05 sec 6.92 sec

Step 8.17 Operator 3 time: 8.46 sec

Step 8.16 Operator 2 time:

Step 8.18 Operator 1 to record 7.05 sec frequency and voltage

Step 8.17 Operator 3 time:

8.46 sec

Step 8.18 Operator 1 to record frequency and voltage

7. Verify the following: Applicant verifies the following:

EDG B & 0 TIE BKR 10604 is

EDG B & 0 TIE BKR closed. 10604 is closed.

ESW Pump 46P-2B is running.

ESW Pump 46P-2B is i running. i

8. Trip EDG B & 0 TIE BKR 10604, Applicant trips EDG B & 0 TIE allow switch to spring return to AUTO BKR 10604, allow switch to and record time. . spring return to AUTO and i record time. i I

9. Applicant records frequency. Applicant records frequency. i

10. Verify EPIC-D-732 closed and open Applicant verifies EPIC-D-732 on alarm typer. closed and open on alarm typer.

i I I I I SIM JPM S-6.doc 7

NRC JAMES A. FITZPA TRICK EXAMINA TION JPM 8-6 ELEMENT STANDARD SAT UNSAT Comment Number

11. Place the following switches in Applicant places the following DROOP: switches in DROOP:

EVALUATOR NOTE:

EDG B GOV MODE (When placed in droop the following

EDG D GOV MODE i 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 Applicant reviews steps.

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.

EVALUATOR CUE: If asked, the other ROs will initiate a WR CAUTION CAUTION I Operation of the T -4 load tap changer Operation of the T -4 load tap during paralleling and loading of the changer during paralleling and EDG could cause the EDG to trip. . loading of the EDG could cause the EDG to trip.

13. While performing the next 2 steps While performing the next 2 do not operate the T -4 load tap steps do not operate the T-4 changer. load tap changer.

81M JPM 8-6.doc 8

NRC JAMES A. FITZPA TRICK EXAMINA TION JPM S-6 ELEMENT STANDARD SAT UNSAT Comment Number NOTE NOTE Steps 14 and 15 may be performed in Steps 14 and 15 may be i any order per SM direction. performed in any order per SM

direction. i

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

15. Place EDG B LOAD BKR SYNCH Applicant places EDG B LOAD I SW in ON. BKR SYNCH SW in ON.

16. Adjust EDG B VOL T REG to Applicant matches INCOMING match INCOMING and RUNNING (EDG) and RUNNING (bus voltages. 10600) voltages with EDG B

, VOL T REG adjustments.

17. Adjust EDG B GOV to rotate Applicant adjusts EDG B GOV synchroscope slowly in the FAST to rotate synchroscope slowly direction (clockwise). in fast direction.

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

18. When EDG B and the 10600 BUS Applicant places the control i I are in phase (synchroscope at 12 switch 10602, EDG B LOAD o'clock) close EDG B LOAD BKR BKR, to CLOSE when

10602. synchroscope is at 12:00.

19. Adjust EDG B GOV to raise EDG I Applicant places the EDG B !

B load between 100 to 300 kW. ! GOV switch to RAISE and loads EDG B between 100 to 300 kW.

20. Place EDG B LOAD BKR SYNCH

Applicant places the EDG B SW in OFF and removes sync switch i LOAD BKR SYNCH SW to handle. OFF removes sync switch handle.

21. IF EDG B is THEN the second IF EDG B is THEN the second diesel paralleled, balance EDG Band D diesel paralleled, balance EDG using voltage regulator( s) to establish Band D using voltage LESS THAN 100 KVAR difference

regulator( s) to establish LESS between EDG Band EDG D. THAN 100 KVAR difference l

I between EDG Band EDG D.

S/M JPM S-6.doc 9

NRC JAMES A. FITZPA TRICK EXAMINATION JPM S-6 ELEMENT STANDARD SAT UNSAT Comment Number

22. Adjust EDG B GOV to raise EDG Applicant adjusts EDG B GOV B load to 2600 kW over 3 to 5 minutes to raise EDG B load to 2600 in approximately 800 kW increments kW over 3 to 5 minutes in 800 kW increments

EVALUA TOR CUE: State, 3 minutes ft EVALUATOR CUE: State," 3 i have passed", after each load minutes have passed", after adjustment. each load adjustment.

23. Parallel EDG D with the 10600 Bus Parallel EDG D with the 10600 as follows Bus as follows

24. Place EDG D LOAD BKR SYNCH Applicant places EDG D SW in ON LOAD BKR SYNCH SW in ON

25. Adjust EDG D VOLT REG to Applicant matches INCOMING match INCOMING and RUNNING (EDG) and RUNNING (bus voltages 10600) voltages with EDG D VOLT REG adjustments

26. Adjust EDG D GOV to rotate Applicant adjusts EDG D GOV synchroscope slowly in the FAST to rotate synchroscope slowly direction (clockwise) in fast direction NOTE NOTE Steps 27 and 28 may be checked after Steps 27 and 28 may be step 28 is complete checked after step 28 is complete

27. When EDG D and the 10600 BUS Applicant places the control are in phase (synchroscope at 12 switch 10612, EDG D LOAD o'clock) close EDG D LOAD BKR BKR, to CL.OSE when 10612 synchroscope is at 12:00

28. Adjust EDG D GOV to raise EDG Applicant places the EDG D B load between 100 to 300 kW GOV switch to RAISE and loads EDG B between 100 to 300kW

29. Place EDG D LOAD BKR SYNCH Applicant places the EDG D SW in OFF and removes sync switch LOAD BKR SYNCH SW to handle. OFF and removes sync switch handle.

30. IF EDG D is THEN the second IF EDG D is THEN the second diesel paralleled, balance EDG Band D diesel paralleled, balance EDG using voltage regulator(s) to establish Band D using voltage LESS THAN 100 KVAR difference regulator(s) to establish LESS between EDG Band EDG D. THAN 100 KVAR difference between EDG Band EDG D.

SIM JPM S-6.doc 10

NRC JAMES A. FITZPA TRICK EXAMINA TION JPM S-6 ELEMENT STANDARD SAT UNSAT Comment Number

31. Adjust EDG D GOV to raise EDG Applicant adjusts EDG D GOV 8 load to 2600 kW over 3 to 5 minutes to raise EDG 8 load to 2600 in approximately 800 kW increments kW over 3 to 5 minutes in 800 kW increments EVALUA TOR CUE: State," 3 minutes EVALUATOR CUE: State," 3 have passed", after each load minutes have passed", after adjustment. each load adjustment.

Simulator booth operator simulate strainer clogging a.) Overriding ESW pump strainer dIp alarm on (O9~6-2-24)

32. Applicant responds to Annunciator: 09-6-2-24 for Log Time ARP 09-6~2-24 and recognizes ESW '8' ESW PMP A or 8 STRAINER pump strainer has HI DIP DIFF PRESS HI For annuciator Applicant responses to ARP Simulator booth operator simulate 09-6-2-24 09-6-2-24 and references strainer clogging EPIC point:

a.) Indications on control board should show pump running

EPIC -A-711: ESW 8 Loop flow EVALUATOR NOTE:

Evaluator is to log the time when

ESW flow is zero annuciator 09-06-2-24 alarms. EVALUA TOR CUE:

If applicant calls up ESW Pp B Strainer DIP. The cue is that DIP is the max value for the instrument

shift If applicant responds to strainer basket respond that the strainer baskets have been swapped. Strainer I

basket DIP is still high.

SIM JPM S-6.doc 11

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-6 ELEMENT STANDARD SAT UNSAT Comment Number SIMULATOR BOOTH OPERATOR: CRITICAL TASK simulate strainer clogging.

EVALUATOR NOTE:

a.) if after 10 minutes of operation If EDG destroyed, terminate and the applicant has not tripped 'B' this JPM, applicant critical task I and '0' EOG. The Booth Operator is to shutdown EDG within 10 to trip 'B' and '0' EOG. minutes not met.

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 Applicant may determine OP-22 G.17 while paralleled with 10600 Emergency EDG Shutdown is more bus, THEN applicant performs appropriate. the following:

OR Applicant may determine OP 22 G.17 Emergency EDG

Trip associated EDG load breaker.

Shutdown is more appropriate.

Shut down malfunctioning EDG per Section G of OP-22 (Single EDG OR Shutdown from Control Room).

Trip associated EDG load

Shut down other EDG per Section breaker.

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

Shut down malfunctioning EDG per Section G of OP

Initiate a WR to troubleshoot EDG.

22 (Single EDG Shutdown from Control Room).

EVALUA TOR CUE: If asked, the other ROs will initiate a WR

Shut down other EDG per Section G of OP-22 (Single EDG Shutdown from Control Room)

Initiate a WR to troubleshoot EDG.

EVALUATOR CUE: If asked, the other ROs will initiate a IWR

34. OP-22; G-17 EMERGENCY EDG OP-22; G-17 EMERGENCY SHUTDOWN. EDG SHUTDOWN.

SIM JPM S-6.doc 12

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-6 ELEMENT I STANDARD I SAT UNSAT Comment Number

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

EDG B; 71-10602 position.

EDG D; 71-10612

EDG B; 71-10602

!

EDG D; 71-10612

36. Ensure EDG tie breaker is tripped Applicant ensures EDG tie

EDG BID; 10604 breaker is tripped.

EDG BID; 10604 NOTE: NOTE:

The EDG BID; EDG FUEL CUTOFF The EDG BID; EDG FUEL OR CNTRLS OFF NORMAL CUTOFF OR CNTRLS OFF annunciator will alarm at panel 09-8 in NORMAL annunciator will the following step. (This alarm is alarm at panel 09-8 in the already in due the EDG being placed in following step. (This alarm is droop) already in due the EDG being placed in droop) I

37. Place EDG BID CONTROL Applicant contacts in plant SWITCH in MAINT at panel 93ECP- operator to place EDG BID BID. CONTROL SWITCH in MAINT SIMULATOR BOOTH OPERATOR: at panel 93ECP- BID.

Override MAINT switches for EDG B SIMULATOR BOOTH and D. Place in MAINT OPERATOR:

i Override MAINT switches for EDG Band D. Place in MAlNT.

38. Place EDG BID CNTRL switches Applicant places EDG BID to STOP at panel 09-8. CNTRL switches to STOP at panel 09-8.

EVALUATOR NOTE: EVALUATOR NOTE: I If the applicant chooses this method, If the applicant chooses this then the JPM is complete method, then the JPM is OR complete If the applicant chooses the single QB EOG shutdown method, then If the applicant chooses the continue the JPM. single EOG shutdown

. method, then continue the

. JPM. i SIMULATOR BOOTH OPERATOR: CRITICAL TASK simulate strainer clogging.

EVALUATOR NOTE:

a.) if after 10 minutes of operation If EDG destroyed, terminate and the applicant has not tripped 'B' this JPM, applicant critical task and '0' EOG. The Booth Operator is I to shutdown EDG within 10 to trip 'B' and '0' EOG. I minutes not met. i I SIM JPM S-6.doc 13

NRC JAMES A. FITZPA TRICK EXAMINA TION JPM S-6 ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR NOTE EVALUATOR NOTE The method for single EDG shutdown The method for single EDG takes a longer time to secure the shutdown takes a longer time EDGs. Without ESW flow, jacket water to secure the EDGs. Without and lube oil temperatures will rise and ESW flow, jacket water and cause the local EDG alarm panels to lube oil temperatures will rise annunciate which will cause 09-8-4-11; and cause the local EDG B EOG ENG TROUBLE OR alarm panels to annunciate SHUTDOWN and 09-8-4-14; 0 EOG which will cause 09-8-4-11; B ENG TROUBLE OR SHUTDOWN EOG ENG TROUBLE OR TROUBLE to alarm in the control room. SHUTDOWN and 09-8-4-14; The high jacket temperature alarm has o EOG ENG TROUBLE OR a setpoint of 200 0 F and the EOG trips SHUTDOWN TROUBLE to at 205 o F. The high lube oil temperature alarm in the control room. The alarm has a setpoint of 240 0 F but no high jacket temperature alarm trip function to the EDG. has a setpoint of 200 0 F and the EOG trips at 205 0 F. The high lube oil temperature alarm has a setpoint of 240 o F.

but no trip function to the EDG.

EVALUATOR CUE EVALUATOR CUE If applicant requests local temperature If applicant requests local indications, temperature indications, PRIOR to annunciators 09-8-4-11 or PRIOR to annunciators 09-8 09-8-4-14 alarming, provide the 4-11 or 09-8-4-14 alarming, following cue: Jacket water provide the following cue:

temperature is 190 0 F and rising. Jacket water temperature is Lube oil temperature is 1950 F and 1900 F and rising. Lube oil rising on 'B' and '0' EOG. temperature is 1950 F and

! rising on 'B' and '0' EOG.

EVALUATOR CUE EVALUATOR CUE If applicant requests local temperature If applicant requests local indications, temperature indications, AFTER annunciators 09-8-4-11 or 09- AFTER annunciators 09-8-4 8-4-14 alarming, provide the following 11 or 09-8-4-14 alarming, cue: Jacket water temperature is provide the following cue:

200 0 F and rising. Lube oil Jacket water temperature is temperature is 240 0 F and rising on 200 0 F and rising. Lube oil

'B' and '0' EOG.

temperature is 240 0 F and I

rising on 'B' and '0' EOG. !

Using OP-22; G.6. Single EDG Using OP-22; G.6. Single EDG Shutdown from Control Room Shutdown from Control Room S/M JPM S-6.doc 14

NRC JAMES A. FITZPA TRICK EXAMINATION JPM S-6 ELEMENT STANDARD SAT UNSAT Comment Number

39. IF EDG B is operating in parallel Applicant adjusts EDG B GOV with a 4.16 kV emergency bus, then to lower EDG B load to perform the following: approximately 50 kW over 3 to Adjust EDG B GOV to lower EDG B 5 minutes in approximately load to approximately 50 kW over 3 to 5 800 kW increments.

minutes in approximately 800 kW increments.

40. Trip EDG B load breaker. Applicant trips EDG B load

EDG B; 71-10602 breaker.

EDG B; 71-10602

41. Place EDG B GOV MODE switch Applicant places EDG B GOV in NORM. MODE switch in NORM.

42. Adjust EDG B GOV until Applicant adjusts EDG B GOV SYNCHROSCOPE is as close to being until SYNCHROSCOPE is as stopped as practical. close to being stopped as practical.

NOTE: NOTE:

EDG B VOL T REG may be adjusted to EDG B VOLT REG may be 4.3 kV when diesel shutdown is directed adjusted to 4.3 kV when diesel by a different procedure and voltage shutdown is directed by a was not noted at startup. different procedure and voltage was not noted at startup.

43. Adjust EDG B VOL T REG until Applicant adjusts EDG B voltage on EDG B kV meter is same as VOL T REG until voltage on noted in Step a. EDG B kV meter is same as noted in Step a.

44. Verify SYNCHROSCOPE is as Applicant verifies close to being stopped as practical. SYNCHROSCOPE is as close to being stopped as practical.

45. Place EDG B LOAD BKR SYNCH Applicant places EDG B LOAD SW in OFF and removes sync switch BKR SYNCH SW in OFF and handle. removes sync switch handle.

46. WAIT until EDG B has run Applicant WAIT until EDG B unloaded for AT LEAST 10 minutes to has run unloaded for AT cooldown cylinders. LEAST 10 minutes to cooldown cylinders.

47. Stop EDG B. Applicant stops EDG B.

48. Verify the following at panel Applicant contacts in plant 92W-9A or B: operator to verify:

92FN-1 B is stopped.

92FN-18 is stopped.

92FN-2B is running.

92FN-2B is running.

49. WHEN EDG B is stopped (at Applicant stops ESW PUMP B standstill), stop ESW PUMP B 46P-2B 46P-2B , when EDG B is at panel 09-6. stopped.

SIM JPM S-6.doc 15

NRC JAMES A. FITZPA TRICK EXAMINA TlON JPM S-6 ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR NOTE EVALUATOR NOTE At this point EDG D is still running At this point EDG D is still without ESW flow. If applicant stops running without ESW flow. If ESW PUMP B with EDG D still running, applicant stops ESW PUMP B terminate this JPM as unsat. with EDG D still running, terminate this JPM as unsat.

EVALUATOR: Terminate the task at this point.

JPM Stop Time _ _ _ __

SIM JPM S-6.doc 16

NRC JAMES A. FITZPA TRICK EXAMINA T/ON 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-6.doc

James A. Fitzpatrick Generating Station Job Performance Measure SRM SIGNAL TO NOISE RATIO DETERMINATION TEST (ST-5H)

JPM Number: 8-7 Revision Number: 1 Date: 2/3/10 Developed By: =B.:;er:..:.n::..:a~rd=-=Li:.::tk:.:.::e:..:;tt=--_ _ _ _ __ 2103110 Author Date Validated By:

Facility Representative Date Review By:

Examiner Date Approved By:

Chief Examiner Date SIM JPM S-7.doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - - - - -

9. 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-7.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

1. Initialize the simulator to an IC-39 with the plant in Mode 4.

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.

TASK STANDARD:

Applicant is to perform SRM Sjgnal to Noise Ratio Determination Test; ST-5H; Section 8.2 for SRM "A'.

TASK CONDITIONS:

1. The plant is in Mode 4.

2. The SM has directed that the SRM Signal to Noise Ratio Determination Test; ST-5H; Section 8.2 for SRM "A' must be completed.

3. Steps 8.2.1 thru 8.2.4 have been completed.

INITIATING CUE:

You are the RO. The CRS directs you to perform the SRM Signal to Noise Ratio Determination Test; ST-5H; Section 8.2 for SRM "A'.

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-7.doc 3

Operator's Name: - - - - - - . . . _ - - -__r - - - - - - - - - - - - - -

Job

Title:

[J NLO I RO I SRO DSTA D SRO Cert JPM

Title:

SRM Signal to Noise Ratio Determination Test; ST-5H JPM Number: 5-7 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: 15 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? DYes [] 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 comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _{Print)

Evaluator's Signature: Date: _ _ _ __

SIM JPM S-7.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'.

81M JPM 8-7. doc 5

NRC JAMES A. FITZPA TRICK ILOT EXAM/NAT/ON JPM S-7 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 Applicant obtains a controlled procedure, ST-5H. 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.

2. Reviews prerequisites, precautions, EVALUATOR CUE:

limitations and general test methods associated with the procedure. All prerequisites, precautions, limitations are satisfied.

3. Ensure SRM A may be fully Applicant ensures SRM A may withdrawn. be fully withdrawn.

4. Ensure SRM A is fully inserted. Applicant ensures SRM A is fully inserted.

5. Ensure POWER ON light is on. Applicant ensures POWER ON light is on.

6. Declare SRM A inoperable EVALUATOR CUE:

EVALUATOR CUE:

State as CRS 'A' SRM has State as CRS 'A' SRM has been been declarE~d inoperable declared inoperable

7. Select SRM A. Applicant selects SRM A.

8. Ensure SELECT lights are off for Applicant ensures SELECT SRM B, C, and D. lights are off for SRM B, C, and D.

9. Record SRM A initial count rate Applicant records SRM A initial count rate. cps.

10. Depress DRIVE OUT/DRIVING Applicant depresses DRIVE OUT pushbutton. OUT/DRIVING OUT pushbutton.

11. Verify DRIVE OUT light is on. Applicant verifies DRIVE OUT light is on.

12. Verify DRIVING OUT light comes Applicant verifies DRIVING on. OUT light is on.

SIM JPM S-7.doc 6

NRC JAMES A. FITZPATRICK ILOT EXAMINATION JPM 8-7 ELEMENT STANDARD SAT UNSAT Comment Number

13. When SRM OUT indicating light Applicant depresses DRIVE comes on, depress DRIVE OUT/DRIVING OUT OUT/DRIVING OUT pushbutton. pushbutton, when SRM OUT indicating light comes on .

. EVALUATOR NOTE EVALUATOR NOTE I Takes 3.5 minutes for SRM to drive out.

Takes 3.5 minutes for SRM to I

drive out.

I 14. Verify the following lights are off: Applicant verifies the following

DRIVE OUT lights are off:

DRIVING OUT

DRIVE OUT

DRIVING OUT

15. Record SRM A Full Out count Applicant records SRM A rate.

FULL OUT count rate cps

16. Depress DRIVE IN pushbutton Applicant depresses DRIVE IN pushbutton.

17. Verify top half of DRIVE IN light is Applicant verifies top half of on. DRIVE IN light is on.

18. Verify bottom half of DRIVE IN light Applicant verifies bottom half comes on. of DRIVE IN light comes on.

19. When SRM IN indicating light Applicant depresses DRIVE IN comes on, depress DRIVE IN pushbutton, When SRM IN pushbutton. indicating light comes on.

EVALUATOR NOTE EVALUATOR NOTE Takes 3.5 minutes for SRM to drive in.

Takes 3.5 minutes for SRM to drive in.

20. Verify DRIVE IN light is off Applicant verifies DRIVE IN light is off

21. Deselect SRM A Applicant deselects SRM A

22. Verify SRM A light is off. Applicant verifies SRM A light is off.

'" 23. Calculate signal to noise ratio for Applicant calculates signal to SRM A as follows: noise ratio for SRM A as follows:

( - ) I = (

- ) / =

8.2.11 8.2.17 8.2.17 TS > 2 8.2.11 8.2.17 8.2.17 TS> 2 81M JPM 8-7.doc 7

NRC JAMES A. FITZPATRICK ILOT EXAMINA TlON JPM S-7 ELEMENT STANDARD SAT UNSAT Comment I Number

24. Consider declaring SRM A operable.

EVALUATOR CUE:

Applicant should state the status of SRMA.

EVALUATOR: Terminate the task at this point.

JPM Stop Time _ _ __

SIM JPM S-7.doc 8

NRC JAMES A. FITZPA TRICK ILOT EXAMINA T/ON JPM S-7 HANDOUT PAGE TASK CONDITIONS:

1. The plant is in Mode 4.

2. The SM has directed that the SRM Signal to Noise Ratio Determination Test; ST-5HRev.2; Section 8.2 for SRM "A' must be completed.

3. Steps 8.2.1 thru 8.2.4 have been completed.

INITIATING CUE:

You are the RO. The CRS directs you to perform the SRM Signal to Noise Ratio Determination Test; ST 5H; Section 8.2 for SRM "A'.

S/M JPM S-7.doc

James A. Fitzpatrick Generating Station Job Performance Measure Perform RPV Isolation During Plant Fire ROONLY JPM Number: 8-8 Revision Number: 0 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 SIM JPM S-B.doc

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.

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 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date

9. 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.

S/M JPM S-8.doc 2

REVISION RECORD (Summary):

1. Rev 0 JPM Setup Instructions:

1. Initialize the simulator to IC~47. 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.

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.

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.

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.

81M JPM 8-B.doc 3

Operator's Name:

Job

Title:

0 NLO ISRO DSTA o 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: - - -minutes

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 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: _ _ _ __

SIM JPM S-8.doc 4

==

Description:==

This JPM has the operator perform RPV Isolation during Plant Fire SIM JPM S-8.doc 5

NRC JAMES A. FITZPA TRICK INITIAL EXAMINA TION JPM S-8 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 Obtains a controlled copy of procedure AOP-28, Operation During AOP-28.

Plant Fires.

2. Select the correct attachment to Applicant selects Attachment perform the task. 2, Step 1.1 of AOP-28.

3. Close CLN UP SUCT 12MOV-18. Applicant closes CLN UP SUCT 12MOV-18 by placing associated control switch on Panel 09-3 in the CLOSE position.

4.Close OUTBD STM SUPP VLV Applicant closes 23MOV-16 by 23MOV-16. placing associated control switch on panel 09-4 in the CLOSE position.

5. Close STM LINE WARMING VLV Applicant closes 23MOV-60 by 23MOV-60 placing associated control switch on panel 09-3 in the CLOSE position.

6. Close Outboard MSIVs Applicant closes outboard MSIVs by placing associated control switches (4) on panel 09-3 in the CLOSE position.

7. Ensure closed 13MOV-16 in drywell entrance.

EVALUATOR CUE: Role play

. as in-plant operator and report 13MOV-16 has been verified closed.

8. Attempt to trip TURB STOP VLV Applicant attempts to trip 13HOV-1 at panel 09-4. 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.. I S/M JPM S-8.doc 6

NRC JAMES A. FITZPA TRICK INITIAL EXAMfNA TlON JPM S-8 ELEMENT STANDARD SAT UNSAT Comment Number

9.0pen breaker DC MOTOR Contacts in-plant operator CONTROL CENTER 71 BCB-2A-B05, using Gaitronics or other (71 BMCC-1) at 71 BCB-2A in Station acceptable method and directs Battery Charger Room A. operator to open breaker 71 BCB-2A-B05, (71 BMCC-1) at 71 BCB-2A in Station EVALUATOR: INSERT Malfunction Battery Charger Room A.

RC03, Role playas in-plant operator EVALUATOR: INSERT and report 71 BCB-2A-B05, (71 BMCC Malfunction RC03, Role play

1) at 71 BCB-2A has been opened. as in-plant operator and report 71 BCB-2A-B05.

(71BMCC-1) at 71 BCB-2A has been opened.

10. Ensure closed, manually if Contacts in-plant operator required, 13MOV-16 in drywell using Gaitronics or other entrance. acceptable method and directs operator to ensure closed 13MOV-16. I EVALUATOR: Terminate the task at this point.

JPM Stop Time _ _ _ __

SIM JPM S-8.doc 7

NRC JAMES A. FITZPA TRICK INITIAL EXAMINATION 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.

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.

SIM JPM S-8.doc

AppendlxD Scenario Outline Fonn ES-D-1 Facility: Fitzpatrick Scenario No.: 1 Op-TestNo.: 1 Examiners: Operators:

Initial Conditions: Reactor startup is in progress with power at 90%. SWS pumps 46P-1A and 46P-1 B are in service with 46P-1C in standby.

Tumover: Continue power ascension to 100% lAW RAP-7.3.16. Maintenance is required on 46P-1A Place 46P-1C in service.

Event Malf. No. Event Event No. Type" Description 1 N/A N-SNO SwaltSWSpumps. Place 46P-1C in service and remove 46P-1A 2 N/A R-SNO Raise power to 100%power usina Rx recirc I-ATC 3 RR23:A T5-CRS 'A' Recirc Flow unit failure. TS call l<" b 1'-

4 ..RR1.9:B..

TC07:A RR15:A I-SN02 TS-CRS

\.;-/"\1 v Upscale failure of 06LT -52B; FWLC level transmitter. TS catl

....~ ".-.--

.,/

) ir-( ~ t,J Coolant leakage inside primary containment. Defeat Auto Scram 6 RP01AA M-ALL Function RP01AB ED43 :A 7 M-ALL Loss of offsite AC power ED43 :8 DG03:A 8 C-ATC Failure of 'A' and 'C' EDG output breakers to close

~ 0003:C

(: \.

~

./

,0:

) K\,;W:A AD07:A J-SN02 C-SN02 DI""'..... ... ' kil., ._ _ ..y restore feed to the reactor vessel.

'A' ADS fails to open

~\';Iv fntnil De operatea In ,_" . +"

I, (R .. * (I)nstrument, (C Ill, (M)ajor NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 1 of21

Appendix D Required Operator Actions Fonn 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 3.3.2.1 RBM. I&C assistance will be required to bypass the 'A' Flow unit in order to reset the half scram.

The FWlC level transmitter 06lT -52B win 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 EHC system regulator oscillations. CRS is to enter AOP- 6 and direct actions to place the 'B' EHC regulator in service.

A medium size lOCAwill begin and progress. Drywell temperature and pressure will be rising V~

requiring a manual scram. The auto scram functions are defeated. UPQ!!..the scram a loss offsite AC power will occur and the 'A' and 'c' EDG output breakers win fail to aosepotentiaR ~

off ~(

causing a challenge to ECCS systems operability. ___. ~

RCIC WI ave a governor fails high and RCIC mIlS operated in manual to restore feed ~~/

the reactor vessel. ____ 0-1', r As the lOCA size increases RPV water level will continue emergency

>0 depressurization. When 7 ADS valves are open, the 'A' ADS valve will fail closed, requiring f another SRV to be opened.

The scenario will be terminated when reactor level is being controlled in band using low

)/y ,

pressure ECCS pumps.

fY NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 2 of21

Appendix D Requlred Operator Actions Form ES-D*2 INITIAL SIMULATOR SETUP ITEM/MALFUNCTION / REMOTE FUNCnON / CONOmON

- Reset simulator to Protected rc -43

Apply tnfonnation Tags on the fottowing components:

- NlA

Take out of FREEZE and ensure the following:

- 46P-1A and 46P-1B; 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 appHcants:

- OP-65: Startup and Shutdown procedure. Marked up to step 0.24.18

- OP-42 : SWS; Marked up to step 0.5

- OP-27; RWR system

- RAP-7.3.16 plant power ascension with recirc

- Reactivity maneuvering sheet

Ensure the foHowing marfunctions are loaded:

- RR23:A; 'A' Recirc Flow unit failure; trigger 1; severity 0%

- RR19:B; Upscale failure of 06LT-52B; FWLC level transmitter; trigger 2; severity 0%.

- TC07:A; EHC system regulator oscillations; trigger 3

- RR15:A; Coolant leakage inside primary containment; trigger 4. initial severity at 2 % with ramp 25 min, finat severity 100%.

- RP01M; 'A' RPS Auto scram failure; PRESET

- RP01AB; 'B' RPS Auto scram failure; PRESET

- ED43:A and 8; Loss of offsite AC power; trigger 5; Manual trigger 4 minutes after ONV pressure of 2.7 psis.

--- --ix - OG03:A;failure of 'A' EDG output breaker to close: PRESET llG03:C;failure of 'C' EDG out~ut breaker to close: PRESET

..::.RC07:A* Relf" ruur'faifs high: PRESET

- AD07:A : PRESET

Ensure the following remote functions are loaded:

- TC02; 'B' EHC regulator in service. -10, trigger 3; 2 minute delay

Ensure the following overrides are loaded: None

Ensure the forrowing triggers are built:

- trigger 1; RR23:A; 'A' Recirc Flow unit failure NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 3 of21

Appendfx 0 Requrred Operator ActIons Fonn ES-D-2 ITEM I MALFUNCTION I REMOTE FUNCTION I CONDmON

- trigger 2; RR19:B; Upscale faifure of 06lT-52B; FWLC Ievet transmitter

- trigger 3; TC07:A; 'A' EHC system regulator oscillations

- trigger 4; RR15:A ; Severity initial 2% with ramp to 100% severity over 25 minutes

- trigger 5; ED43:A and ED43:B. Manual reaches 2.7 psig.

Reset any annunciators that should not be present NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 4 of21

Appendix D RequIred Operator Actions FORn ES-D-2 INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1: Swap SWS pumps, Place 46P-1 C In service and remove 46P-1 A

., 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 SWS pump lineup_

Respond as NPO during SWS pump swap EVENT 2: Raise power to 100% using Rx Recire

., MALFUNCnoN I REMOTE FUNCTION I REPORT

Continue power ascension with Rx Recifc lAW RAP-7.3.16 , OP-27and OP 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

./ IlALfUNCnON I REMOTE FUNCnON I REPORT

Activate trigger 1 after events 1 and 2 are completed

Respond to request for assistance as appropriate.

EVENT 4: Upscale failure of 06lT-528; FWLC level transmitter

., MALFUNCTION I REJIO'rE FUNCTION I REPORT

Activate trigger 2 after TS call has been made.

Respond to request for assistance as appropriate.

EVENT 5: EHC system regulator oscillations

., IlALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 3 after TS caD has been made.

Respond to request for assistance as appropriate.

NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 5 of 21

Appendfx 0 Requrred Operator Actions EVENT 6: Coolant leakage inside primary containment MALFUNCTION I REMOTE FUNCTION I REPORT EVENT 7 .. LossofOffs"lte AC power rS,.u.l- j\

./ MALFUNCTIOtyi ~.~ TE FUNCTION I REPORT S~.r-

M~nually PSIQ*

activate trigger ~es after Drywall pressure reaches 2.7

Respond to request for assistance as appropriate.

EVENT 8: Failure of 'A' and 'C' EDG output breakers to close

./ MALFUNCTION I REMOTE FUNCTION I REPORT

PRESET malfunction f-'""

-

Respond to request for assistance as apprvtnj,...

\re~

EVENT 9: RCIC governor fails high

\ ./ MAlFUNCTION I REIIOTE FUNCTION I REPORT J

'\.

PRESET malfunction

........ . to rAnllActt ft\f' EVENT 10: Emergency RPV Depressurization

......... c:a;:>> 0....,. vtn1ot.e.

/

./ MALFUNCTION I REMOTE FUNCTION I REPORT

When RPV level can not be maintained above -19 inches

Respond to request for assistance as appropriate.

EVENT 11: 'A' ADS fails to open

./ MALFUNCTION I REMOTE FUNCTION I REPORT

PRESET matfunction

Respond to request for assistance as appropriate.

NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 6 of21

Appendfx 0 Requrred Operator Actions Form ESwD-2 CRITICAL TASKS

1. EOP-2: Scrams the reactor prior to 2.7 psig Drywall pressure with auto RPS scram defeated.

Standard: Expected action to occur when Drywall pressure is > 2.3 psig lAW OPG-13; Transient Mitigation.

P Basis: The scram reduces the rate of energy production and thus the rate of drywall leakage. Basis from MIT-301.11C; EOP-2 baSis

2. EOP-2 Manual closure of 'A' and 'C' EDG output breakers J... (, f rT C/...I...~K

/o\\£> \

,~

Standard: Expected action to occur when auto closure of the breakers fail.

- ~

I

t~ J f"", \ L D{

t ) .

~ tLl-;/"

°/

- \ 1/

Basis: To maintain available Low Pressure ECCS injection required for atequate core cooling. Basis from MIT-301.11 C; EOP-2 basis for adequate core cooling

3. EOP-2 Perform Emergency RPV Depressurization.

Standard: Before RPV water level reaches - 19 inches; Emergency de-pressurizes per EOP-2, open 7 ADS valves.

Basis: 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-301.11C ; EOP-2 basis for Emergency RPV depressurization.

NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 7 of 21

Appendfx D Required Operator Actions Form ES*D*2 SHIFT TURNOVER lNFORMATtON I OFF GOING SHIFT D D 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 outage.

Plant is at approximately 90% power PART III: Remarks/Planned Evolutions:

1. Swap SWS pumps. Place 46P-1C in service and remove 46P-1A from service following pump swap.

2. Continue power ascension to 100% pgwer 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 Test Page 8 of 21

Appendix D RequIred Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _1_

Event

Description:

Swap SWS pumps. Place 46P-1C in service and remove 46P-1A from service Time Position A .... 's Actions or Behavior CRS Orders SN02 to start 46P-1C per OP-42 and remove 46P-1A from service.

Note 1: OP-42; section G.1 Informs Chemistry that SWS pumps will be swapped to 46P-1B and SN02 46P-1C NllTtnQ in service.

Coordinate with NPO to monitor SWS pump swap and screen wash SN02 booster pump alignment.

SN02 Starts 46P-1 C 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-1C pump start is SAT.

Booth Oper.tv, SN02 Remove 46P-1A from service by ~ny pump to stop.

Note 3: Reduce voltage on 12~

Examiner Note: \J Proceed to the next event NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 9 of21

Appendix 0 Required Operator Actions Form ES-D*2 Op-Test No.: _1_ Scenario No.: _ 1_ Event No.: _2_

Event

Description:

Raise Reactor Power with recire lAW RAP-7.3.16; OP-27 and OP-65 Tune f A, ... t'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.

CRS 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 CRS 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.

b. Maintain core flow tess than or equal to 80.85 Mfblhr.

SN02 c. 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.

ATC Monitors plant for correct I~R:M:J as power is raised.

examiner Note:

Proceed to next event when sufficient change in power level is observed.

NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 10 of21

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: _ 1_ Event No.: _3_

Event

Description:

'A' Recirc Flow unit downscale 'failure Time Position .. ... nt's Adlons or Behavior Responds to alanns: 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 'N Flow unit downscale failure. Indication in back panel 09 14.

SN02 Enters AOP-59 for loss of RPS bus power and CRS orders ATC to CRS bypass 'A' flow unit.

t\

ATe By~asses 'A' Frow unit ~r OP-16. /7j~) I

_/ ~O \ ~\/

ATCI SN02 Places S-1 switch for 'A' Flow Unit to tNT TEST.

I y,Vyt'tll

¥ '-v~ \.! .{r \V- el.......

V tt"i ~

\

ATe Resets half saam.

'tJ

\

IT

/ ,\

\

Mal<es Tech Spec call for an inope~ flow U~T/S 3.~ction eRS A.A 1 place channel in the tripped condition in hours RPS nd TRM 3.3.B.A.A1.1b, 7 days." ~

~w--lU. ~ ...L },

iOlJK Iof CRS Briefs crew on the event.

Examiner Note:

Proceed to the next event NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 11 of21

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.:-L Scenario No.: _1_ Event No.: _4_

Event

Description:

Upscale failure of 06lT-52B; FWLC level transmitter i Time Position A .It ofs Actions or Behavior Responds to alanns: 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 LVL HIGH TRIP CRS Enters AOP-42; Detennines upscale failure of 06LT -52B.

Orders SN02 to place feedwater contrors in manual and attempt to CRS maintain RPV water le\lel between 196.5 inches and 206.5 inches.

Swap to other level channel per OP-2A Place feedwater in manual contror to maintain RPV water level SNO between 196.5 inches and 206.5 inches. Swap to other level channel perOP-2A.

Verifies the following:

SN02

Operating condensate and condensate booster and feedwater ptJmps lineup.

CRS enters OP-27A and makes Tech Spec call for failure of 06LT -52B.

TIS 3.3.2.2. A. A 1 Feedwater and Main Turbine High Water Level Trip eRS Instrumentation. With 1 channel inoperable. place channel in the tripped condition within 7 da~s.

CRS Briefs crew on the event Examiner Note:

Proceed to the next event NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 12 of21

Appendix 0 Requfred Operator Actions Form ES~D~2 Op-Test No.:- Scenario No.: _ 1_ Event No.: _5_

Event

Description:

EHC System regulator oscillation Time Position A fa Actions or Behavior Observation of rising RPV pressure:

- RPV pressure rises approximately 3 psi.

- Backup EHC pressure regulator IN CONTROL light is on at EHC section of panel 09-5.

- smaU dip in RPV water level.

- Small u~scale spike in nuclear instrumentation.

ATCI Report observation of rising RPV,r~e to C~

SN02 ) \ pJ'.

, ;.JoJ /rJ OJ" CRS enters AOP-32/and AOPi..s for EHC Malfunction for rising pressure. Orders the following to ATC/SN02:

Verify backup EHC pressure regulator stabrtizes RPV pressure (approximately 3 psi greater than initial pressure).

Lower reactor power level by approximately 5 percent per RAP 7.3.16.

Verrty EHC hydraulic fluid system is operating normally per Section E of OP-8.

Demand an official 3D Monicore report and evaluate reactor power and thermal limits. Take corrective actions per RAP 7.3.16.

Establish communication between the Control Room and Bay "An of EHC Cabinet (EHP) in the Refay Room.

ATC verifies backup EHC pressure regulator stabilizes RPV ATCI pressure {approximately 3 psi greater than initial pressure}.

SN02

SN02 reduces reactor power fever by approximately 5 percent per RAP-7.3.16.

CRS Briefs crew on the event.

Examiner Note: After 5% power reduction move to next malfunction Proceed to the next event NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 13 of 21

Appendix D 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 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.

SN02 Performs Attachment 1 of AOP-39.

CT CRS Orders manual scram if d~1I pressure> 2.3 psig. Enters AOP-1.

NOTE: Auto RPS scram function are defeated.

Inserts Manual Scram and perform AOP-1 Immediate Actions

Depress Manual Scram pushbuttons

Reactor Mode Switch to Shutdown

Fully Insert all SRM's and IRM's

Verify all rods in ATC

Verify SDfV 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 CRS Orders SN02 to control level with Feed/Condensate at 177-222.5 in.

Trend level performance and manipulate GEMAC Masterllndividual SN02 controllers, RFP discharge valves and RFP trip as necessary to control level.

Enters EOP-2 and EOP-4 when drywall pressure exceeds 2.7 psig.

CRS Other EOP entry conditions EOP-2; RPV water level below 177 inches.

EOP-4; Drywall temperature above 135°F.

Examiner Note:

Proceed to the next event NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 14 of 21

Appendix D Required Operator Actions FOnn ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: 7and8 Event

Description:

Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close.

Time Position A ... *£*s Actions or Behavior Sim Trigger 5 for ED43: A and B; 4 minutes after Drywall pressure reaches Booth 2.7 psig.

OP!t, References AOP-72; 115 KV Grid loss but performs other AOPs and CRS EOPs.

ATC Verifies all EDG starts.

SN02 With no eire water rntn'U'~}lJnnirlg, closes MSIVs.

i ATC Identifies and reports to CRS the failure of 'A' and 'C'EOG output breakers to close.

ATC Croses 'A' and 'C' ED~ output breakers and verifies 'N and 'e' EDG load s e q u e n c i n g . C \ \..-.. J

""" ~~ w ~ '\\' 10~"~

rf L--- 11 SN02 Verifies all available ECCS pumps start. \ll:-r:r'

~D C~

Orders SN02 to maintain RPV level between 177 and 222.5 inches using RCtC and HPCf aUgn suctions from the CST. Defeat ~i CRS area temperature and High Torus water level suction transfer if O~ IA,W ~:-~Oeteat RCIC low RPV pressure1fifcfiiigh area te .

I

~-lSO

- 0 if~

.y lAW EP-2.

~~ ~::> ~\ -r NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 15 of21

AppendfxD Requrrecf Operator Actions Eonn ES-1)..2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: 7 and 8 Event

Description:

Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close.

Time Position AI .1:. -'a Actions or Behavior Maintains RPV level between 177 and 222.5 inches using RCIC and 1\

HPCI align suctions from the CST.

Oefeats HPCI Hi area temperature and High Torus water level SN02 suction transfer if necessary tAW 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 foltowing conditions exist

A steam leak does not exist in HPCI steam piping outside the containment.

OR

Operation of both HPCI AND RCIC is required to maintain RPV SN02 water level.

5.7.2 For 23MOV-15, place HPCI STM LEAK AUTO ISOL DIV 12F-86A keylock switch in TEST at panel 09-21.

5.7.3 For 23MOV-16 and 60, place HPCI STM LEAK AUTO ISOL DIV 112F-86B keylock switch at ~neI 09-21.

HPCI HIGH TORUS WATER LEVEL SUCTION TRANSFER DEFEAT 5.13.1 Place HPCI TORUS SUCT BYPASS SW 23A-S31 keylock switch in BYPASS at panef ()9..3.

5.13.2 Verify white HPCI TORUS SUCT BYPASS l T 23A-DS76 fight I

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 foltows:

SN02 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 forrowing varves:

23MOV-57 lO. "~

I

23MOV-58 When 23MOV-57 and 23MOV-58 have dual indication 23MOV-17.

YO

(" \ '

J \~\' '\\

~*tOr,rr NRC Scenario #1 - 2010 Fitzpatrick Operating Test ~Q'

Appendix 0 Required Operator Actions Form *ES..O-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: 7andS Event Oescription: Loss of offsite AC power and failure of 'A' and 'C' EOG output breakers to close.

Time Position A ... ....s Actions. or Behavior RCIC LOW RPV PRESSURE DEFEAT 5.17.1 For 13MOV-15, disconnect read from one of the fottowing SN02 terminals in panel 09-33: AA-71 OR AA-72 5.17.2 For 13MOV-16, disconnect lead from one of the following terminals in panel 09-30: AA-28 OR AA-29 RCIC HIGH AREA TEMPERATURE DEFEAT 5.16.1 Verify one of the folJowing conditions exist A steam leak does not exist in Rete steam piping outside the containment.

OR Operation of both HPCf AND RCfC is required to maintain RPV SN02 water level. \

5.16.2 For 13MOV-16, place Rete STM LEAK AUTO ISOL D1V I 2F-S5A keylock switch in TEST at panel 09-21.

5.16.3 For 13MOV-15. place RClC STM LEAK AUTO lSOL )

DIV r1 2F-S58 keyrock switch in TEST at panef 09-21. ./

/ ~~

CRS Orders SN02 to spray the Torus before Torus pressure reaches 15 psig USing the posted instructions.

NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 17 of21

Appendix 0 Required Operator Actions Fonn£S-o*2 Op-Test No.: _1_ Scenario No.: -L Event No.: 7 and 8 Event

Description:

Loss of offsite AC power and failure of 'A' and 'C' EDG output breakers to close.

Tame Position A*'" '5 Actions or Behavior Places RHR in Torus spray mode using the posted instructions.

1.Verify torus 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 OW & TORUS SPRAY VLV OVERRIDE OF FUEL ZONE LVL 10A-S18A(B) keylock switch in MANUAL OVERRD.

3. Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, spring retum to normal.

4. Verify white SPRAY PERM 10A-D8-67A(B) light is on.

5. Ensure avaUable RHR pumps in RHR loop A(S) are running:

RHR PMP 10P-3A(S}

RHR PMP 10P-3C(D)

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

SN02 6. Open RHR TEST TORUS eLG & SPRAY 10MOV-39A(B).

7. Throttle TORUS SPRAY fNBD VlV 10MOV-38A(B) to estabrish desired torus spray flow rate.

8. WHEN RHR Loop A(B) flow is GREATER THAN ensure closed MIN FLOWVlV IOMOV.*16A(B).1500 gpm,

9. Throttle RHR TEST &TORUS eLG 10MOV-34A(B) to divert excess flow to the torus to maintain> 6,500 gpm RHR Loop A(B) flow with one RHR pump operating or> 13,000 gpm RHR Loop A(B) flow with two RHR pumps operating.

NOTE: Procedure may be continued whire 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 IORHR-274{IORHR-260).

11. Establish RHRSW flow and temperature control.

Orders SN02 to place RHR in Torus cooling mode using the posted CRS instructions.

NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 18 of21

AppendfxD Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.: 7 and 8 Event

Description:

Loss of offsite AC power and failure of 'A' and 'C ' EDG output breakers to close.

Time Position Places RHR in Torus cooling mode using the posted instructions.

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

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 OW & TORUS SPRAY VLV OVERRfOE OF FUEL ZONE LVL 10A-518A(B) keylock switch in MANUAL OVERRD.

b. Place SPRAY CNTRL 1OA-S17A(B) switch to MANUAL, spring return to normal.

c. Verify white SPRAY PERM 10A-OS-67A(B) light is on.

2. Ensure at least one of the following RHR pumps is running:

RHR PMP 10P-3A(B)

RHR PMP 10P-3C(D)

SN02 NOTE: 10M0V-31A(B) may be throttled when 10M0V-39A(B) has dual position indication.

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

4. Throttle RHR TEST & TORUS CLG 10MOV*34A(B) to establish desire flow.

5. WHEN RHR Loop A(8) flow is GREATER THAN 1500 gpm.

ensure closed MIN FLOW VLV tOMOV-I6A(B).

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 10RHR-274(10RHR-260).

7. Establish RHRSW flow and temperature control.

NOTI; If Torus sprays have been initiated, terminate Torus sprays before Torus pressure drops below 0 psig.

SN02 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 19 of 21

Appendix 0 Required Operator Actions FonnES-D-2 Op-Test No.: _1_ Scenario No.: _1_ Event No.. _9_

Event

Description:

RCIC governor fails high _____________

~~'"

*n.-nt's Actions or BehaVio~

~

Time Position J A_

fai: ~

-~

/ /

~ Rec~nizes that RCtC governor has low ~PV water level and reports this info when RCtC starts on ation to the CRS. )

\ /

SN02 Placekclc in manual for govemofntrol to maintain RPV Le~

to 222. inches.

~ \ ...---

r SN02 Provides ~ate to CRS on Rffl/ water level trend.

\ I CRS Changes Rpv~~r I~~nd when RPV level is below 177 inches and enters Altern te R level Control. "

\/- \l)Y_f~ lED)

Estabiishes new ~'71 Band. Restore ~nd maintain RPV level CRS above 0 inches (l.i F). ay use 1 or more of Group 2 Water level Control System&!

/ \

CRS orderi!N02 to U~~I-A; LPCI-B; CS-A; CS-B; and 1 or more CRS

- of Group 2 ater level Cont I Sy:slt:ms for injection.

/ ~

}

SN02 Lines ~i~PC'-A; LPCI-B; CS-A; ~; and 1 or more of Group 2 Water I vel Control Systems for inje ion for injection.

I I '\

I'

/ Examiner Note:

Proceed to the next event NRC Scenario #1 - 2010 Fitzpatrick Operating Test Page 20 of 21

AppendixD Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _-_1_ Event No.: --12 Event

Description:

Emergency RPV depressurization; 'A' ADS valve fails to open Time Position .. .... t's Actions or Behavior 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.

ATC Opens 7 ADS valves and reports 'A' ADS varve has failed to open.

CRS Orders ATC to open another SRV.

ATC Opens another SRV.

Orders SN02 to maintain RPV level above 177 inches with LPGI and eRS 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.

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 21 of21

Appendix 0 Scenario Outline Form ES-O-1 Facility: Fitzpatrick Scenario No.: ~? 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 Place 'A' CRD pump in service and remove 'B' CRD pump from 1 N/A N-SNO service.

TS-SRO 2 HP05 Inadvertent HPCI initiation C-SNO TS-SRO Upscale failure of Drywell Pressure transmitter 10PT-101A .

3 1- PC05-14 TS call R-ATC 4 FW13:A 33E-6A Feedwater Heater Tube Leak.

C-SNO C-SNO 5 ED04:A Inverter failure 71-INV-3A failure TS-SRO C-ATC 6 MC01 . Main condenser In-leakage; Loss of condenser vacuum C-SNO RP01AA 7 RP01BA M-ALL Failure to scram; RPS is still energized, ARI fails to actuate.

RP09 SL01 :A 8 C-ATC Trip of the in service SLC pump or B SL03;A or 9 C-ATC SLC Pump 'A' or 'B' relief 11-RV-39A or 11-RV-39B lifts B

I 10 RC02 C-SNO RCIC failure to auto start

(N)ormal, (R}eactivity, (l)nstrument, (C}omponent, (M)ajor NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 1 of 24

Appendix D 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' CRD pump 03P-16A in service and remove'S' CRD pump 03P-16S lAW OP-25 G.10.

HPCI will inadvertently initiate, requiring crew actions to validate HPCI response and trip HPCI.

Enters TS 3.5.1. D and C, 14 day LCO, verify RCIC operable. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore HPCI or LPCI.

Drywell pressure transmitter 10PT-101A will fail upscale. The SRO must assess TS for the failure. And will determine that Tech Spec 3.3.5.1.A must be entered.

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. SNO transfer TS call for the SRO. TIS 3.8.4.D. declares the associated LPCI subsystem inoperable immediately.

There will b~ain condenser in-leakage causing condenser vacuum to degrade. CRS enters AOP-31 for loss of60ndenser Vacuum. Eventually the main turbine will trip on loss of vacuum.

There will be a failure to scram when the scram is attempted. Entry into EOP-2 and then EOP-3 will be required. The 'A' SLC pump when started will trip and'S' SLC is inoperable without L-1.§..

Requiring the use of de-energizing the scram solenoids or venting the scram air header.

When RPV water level is intentionally lowered, RCIC will have an auto start failure requiring a manual start.

The scenario will be terminated when all control rods are inserted to or beyond position 02 and EOP-2 has been entered.

NRC Scenario #2 2010 Fitzpatrick Operating Test Page 2 of 24

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

Apply Information Tags on the following components:

Take out of FREEZE and ensure the following:

Rx power is at 80% ready to swap CRD pumps

Ensure materials for applicants:

- OP-65; Startup and shutdown procedure; step D.21.4

- OP-25; Changing in-service CRD pumps; step G.1 0

Ensure the following malfunctions are loaded:

- HP05; HPCI inadventent initiation; trigger 1

- I-PC05-14; Failure of drywell pressure transmitter; trigger 2

- FW13A; 33E-6A Feedwater Heater Tube Leak trigger 3

- ED04; LPCI inverter 71-INV-3A; trigger 4

- MC01; Main condenser in-leakage; trigger 5.

- RP01AA; RP01 BA and RP09; PRESET; Failure to scram

- SL01 :A; 'A' SLC pump trip; trigger 6

- RC02; RCIC failure to auto start; PRESET

Ensure the following remote functions are loaded:

- RD03

- RD04

Ensure the following overrides are loaded: None

Ensure the following triggers are built:

- trigger 1; HP05; HPCI inadventent initiation

- trigger 2; I-PC05-14; Failure of drywell pressure transmitter

- trigger 3; I=W13A; 33E-6A Feedwater Heater Tube Leak

- trigger 4; ED04; LPCI inverter 71-INV-3A; trigger 4 trigger 5; MC01; Main condenser in-leakage.

- SL01 :A; trigger 6

Reset any annunciators that should not be present NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 3 of 24

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

Place 03P-16A in service and removed 03P-16B

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: Upscale failure of Drywell Pressure transmitter 10PT-101A

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate Trigger 2 after event 2 is completed.

Respond to request for assistance as appropriate.

EVENT 4: 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 5: Loss of LPCI inverter 71-INV-3A

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 4 after event 4 is completed

Respond to request for assistance as appropriate.

NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 4 of 24

Appendix 0 Required Operator Actions Form ES-D-2 EVENT 6: Main Condenser in-leakage Enter AOP-31

./ MALFUNCTION I REMOTE FUNCTION I REPORT

Activate trigger 5 after TS call has been made.

All valve in correct positions per AOP-14, Step C. 5

Report a tear in the"A" RFPT Exhaust Boot

Respond to request for assistance as appropriate.

EVENT 7: Failure to scram

./ MALFUNCTION I REMOTE FUNCTION I REPORT

PRESET RP01AA; RP01BA and RP09

Respond to request for assistance as appropriate.

EVENT 8: Trip the in service SLC pump i ./ MALFUNCTION I REMOTE FUNCTION I REPORT

Booth Operator insert malfunction SL01 :A; trigger 5 or SL01:B trigger 6 as appropriate.

Respond to request for assistance as appropriate.

EVENT 9: In service SLC pump relief valve lifts 11-RV-39A or B

./ MALFUNCTION I REMOTE FUNCTION I REPORT i

Booth Operator insert malfunction SL03:A; trigger 7 or SL03:B trigger 8 as appropriate.

Respond to request for assistance as appropriate.

EVENT 10: RCIC failure to auto start

./ MALFUNCTION I REMOTE FUNCTION I REPORT

PRESET RC02

Respond to request for assistance as appropriate.

NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 5 of 24

Appendix 0 Required Operator Actions Form ES*D*2 CRITICAL TASKS

1. EOP-3: De-energize scram solenoid fuses or vent the scram air header per EP-3 until all rods are fully inserted.

Standard: With failure of RPS and ARI to actuate pontrol rod insertion is required by removal of scram solenoid fuses or venting the scram air header.

Basis: EP-3 basis for backup control rod insertion methods

- 2. EOP-3: Terminate and Prevent injection sources per EP-5 with Reactor Power >2.5%

Re-inject to maintain RPV water level 0 - 100 inches> TAFI Standard - Terminate and Prevent with Reactor Power> 2.5% and all RPV injection except SLC, RCIC and CRD.

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-flow 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.

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.

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

~2.5 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-flow 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.

NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 6 of 24

Appendix 0 Required Operator Actions Form ES-O-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.SNO)

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, SNO)

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 outage.

Plant is at approximately 80% power PART III: Remarks/Planned Evolutions:

1. Swap in-service CRD pumps. Place 'A' CRD pump in service and remove 'B' 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 (SNO)

TITLE NAME TITLE NAME SRO ATC SNO NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 7 of 24

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _1_

Event

Description:

Swap in-service CRD pumps. Place 03P-16A in service and remove 03P-16B i Time Position Applicant's Actions or Behavior Orders SNO to place 03P-16A; 'A' CRD pump in service and then CRS remove 03P-16' 'B' CRD pump per OP-25; section G.10 Note: Procedure marked U~OP-25; Changing in-service CRD pumps; steps completed up to step G.10.2 I

SNO Coordinate with NPO to monitor 03P-16A pump start.

Adjust CRD FLOW CNTRL 03FIC-301 to establish 20 to 30 gpm on 03FIC-301 or 03FI-310.

Starts CRD PMP 03P-16A.

Stop CRD PMP 03P-16B.

Adjust CRD FLOW CNTRL 03FIC-301 to establish 59 to 61 gpm on 03FI-31 0 or 03FIC-301.

SNO

Verify normal operating values on the following indicators at panel 09-5:

- CHG WTR PRESS 03PI-302: BETWEEN 1390 and 1580 psig, 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 Sim Respond as NPO that 03P-16A pump start is sat.

Booth Operator Examiner Note:

Proceed to the next event NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 8 of 24

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: _ 2_ Event No.: _2_

Event

Description:

Inadvertent HPCllnitiation Time Position Applicant's Actions or Behavior All Recognize 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, SNO determines HPCI start is not valid CRS Directs SNO to trip HPCI SNO Secures HPCI (If HPCI injects and power changes), CRS enters AOP-32 CRS Unexplained/Unanticipated reactivity change Enters TS 3.S.1.D and C, 14 day LCO, verify RCIC operable. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months CRS to restore HPCI or LPCI SBGT started on HPCI start, secure SBGT or lineup flowpath by i SNO opening suction valve Examiner Note:

Proceed to next event NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 9 of 24

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: Event No.: _3_

Event

Description:

Upscale failure of Drywell Pressure Transmitter 10PT-101A Gme Position Applicant's Actions or Behavior ALL Respond to annunciator 09-3-1-24 RHR LOGIC OW PRESS HI Determines Drywell pressure transmitter 10PT-101A has failed SNO upscale.

I CRS Enters TIS 3.3.S.1.A. Chatel is already in the tripped condition CRS Briefs crew on this event Examiner Note:

Proceed to the next event NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 10 of 24

Appendix D Required Operator Actions Form ES*D-2 Op-Test No.: _1_ Scenario No.: _ 2_ Event No.: _4_

Event

Description:

33E-6A Feedwater Heater Tube Leak Time Position Applicant's Actions or Behavior OVERRIDES IF indications of thermal-hydraulic instability occur, THEN insert a manual scram and exit this procedure.

CAUTIONS Lower feedwater temperature reduces the margin to the onset of core thermal-hydraulic instability.

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:

ALL

Loss of feedwater heater level control

Closure of reheat steam supply valve

Isolation of extraction steam to the feedwater heater(s)

High level in first point feedwater heater ATCI Identifies 33E-6A Feedwater Heater Tube leak SNO CRS Enters AOP-62 for a loss of feed water heating Orders A TC 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 A 3411 and A-3412.

CONTINUE TO NEXT PAGE NRC Scenario #2 - 2010 Fitzpatrick Operating Test Page 11 of 24

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: _2_ Event No.: _4_

i Event

Description:

33E-6A Feedwater Heater Tube Leak I line Position Applicant's Actions or Behavior CRS orders if initial reactor power is LESS THAN OR EQUAL TO 90%,

AND core flow is GREATER THAN 80%,

THEN perform the following:

Lower RWR flow to establish approximately 55% core flow.

Insert cram groups per RAP-7.3.16 UNTIL reactor power is BELOW 100% rod line.

Maintain reactor power at least 20% below the pre-transient power level

Orders ATC to lower RWR flow to establish approximately 55%

core flow.

Orders ATC Insert cram groups per RAP-7.3.16 UNTIL reactor power is BELOW 100% rod line.

Orders ATC maintain reactor power at least 20% below the pre-transient power level.

Lowers RWR flow to establish approximately 55% core flow.

Inserts cram groups per RAP-7.3.16 UNTIL reactor power is ATC BELOW 100% rod line.

Maintains reactor power at least 20% below the pre-transient power level.

Monitors secondary side of the plant and performs verifications for SNO ATC.

WHEN reactor power is stable demand an Official 3D Program and review core thermal-hydraulic parameters.