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Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML14318A510
Person / Time
Site:	FitzPatrick
Issue date:	09/15/2014
From:	; Operations Branch I
To:	; FitzPatrick
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ENT~RGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 14-2 NRC RO TASK TITLE: Perform RHR Lineup Verification Per ST -2AN C001 APPL . TO JPM NUMBER REV : DATE: NRC KJA SYSTEM NUMBER: _.2:......1_.:.....31--'(._4_

.6i.-)- - - - -

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME :

- Minutes SUBMITTED:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location : Simulator DATE PERFORMED: TIME TO COMPLETE : Minutes

")ERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 14-2 NRC RO TASK TITLE: Perform RHR Lineup Verification Per ST-2AN C001 APPL. TO JPM NUMBER Current Update: By:.

Date lnt Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required C8] None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 8-

ENTERGY NU LEAR NORTHEAST JOB PERFO MANCE MEASURE RO 14-2 NRC RO TASK TliTLE: Perform RHR Lineup Verification Per ST-2AN C001 APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-2AN, RHR Loop A Monthly Operability Test Ill. TOOLS AND EQUIPMENT

None IV. SET UP REQUIREMENTS A. Provide a copy of ST-2AN complete up to step 8.1.

B. Reset the simulator to an IC (IC-66) ith RHR in a normal standby lineup, except for the following :

a. 10MOV-16A, MIN FLOWVLV, is closed .

b. 1OMOV-66A, HX A BYP VLV, is losed.

c. 10MOV-57, RHR DISCH TO RA W , is open.

d. 10MOV-18, SHUTDOWN CLG S CT, is open.

V. EVALUATOR NOTES A. The candidate should, at a minimum observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform th candidate that the conditions of each step need only be properly identified and not actually p rformed .

C. The candidate should demonstrate p oper use of HU tools such as procedure use, self checking , placekeeping and three-point communication .

D. Should Candidate inform CRS that ST cannot be continued due to the out of position valve or out of spec readings, etc .. . , inform Candidate the deviation has been noted and for them to continue with the ST.

VI. TASK CONDITIONS A. ST-2AN, RHR Loop A Monthly Oper bility Test, is in progress.

B. Other operators have prepared ST-2 N up to Section 8.1.

C. RHR Loop A level switches are operr ble.

D. RHR Loop A is in the standby LPCI I neup.

VII . INITIATING CUE t form the candidate, "Complete ST-2AN Sections e. 1 and 8.2. "

-3 of 8-

RO 14-2 NRC RO C001 TASK TITLE: Perform RHR Lineup Verific tion C -CRITICAL STEP STEP STANDARD EVALUATION I COMMENT

1. IF 10LS-100 (RHR loop A Co tacts Operator in Relay Room to SAT/UNSAT containment spray line level switch) ver fy lights for 10LS-100 and 10LS-and 10LS-101 (RHR loop' A LPCI 10 are OFF on alarm module 10-keep-full level switch) are operable, 74 1-44 inside panel AR-8 THEN perform the following:

EV ALUTOR ROLE PLAY:

~

Verify RHR Loop A keep-full level lnd rm the Candidate that the lights switch alarms are clear by one of the for 10LS-100 and 10LS-101 are following methods: OPF.

Verify lights for 1OLS-1 00 and -OR-10LS-101 are off on alarm module 10-7 4-1-44 inside panel AR-8 in relay room Uti izes any EPIC station and verifies poi pts EPIC-D-129 and EPIC-D-130

Verify associated EPIC points indicate NORMAL (EPIC-D-129 and EPIC-D-130) indicate NORMAL

, 2. Mark Steps 8.1 .2 through 8.1.10 N/A M rks Steps 8.1 .2 through 8.1.1 0 SAT/UNSAT N/

3. IF RHR Loop A is in standby LPCI Ve ifies the following lineup at panel CRITICAL STEP lineup per OP-13, Section E, THEN 09 3 and documents in ST-2AN: (bolded items only) perform the following: SAT I UNSAT Verify the following lineup at panel 09-3:

MAN INJ VLV 10RHR-81A-

MAN INJ VLV 10RHR-81A-Open Open

RHR HX A DISCH TO TORUS

RHR HX A DISCH TO TORUS OR RCIC 10AOV-71A- Closed OR RCIC 10AOV-71A- Closed

VLV CNTRL 10AOV-71A 10A-

VLV CNTRL 10AOV-71A 10A- S41A- CLOSE S41A- CLOSE

LPCI OUTBD INJ VLV 10MOV-

LPCI OUTBD INJ VLV 10MOV-27A- Open 27A- Open

-4 of 8-

RO 14-2 NRC RO C001 TASK TITLE: Perform RHR Lineup Verific~tion EVALUATION I STEP J STANDARD COMMENT

3. Verify the following lineup at panel ve~ifies the following lineup at panel CRITICAL STEP (cont.) 09-3 (cont.): 09 Ia and documents in ST-2AN (bolded items only)

(co t.): SAT I UNSAT I

LPCIINBO INJ VLV 10MOV-25A

-Closed

LPCIINBO INJ VLV 10MOV-25A

-Closed

MIN FLOWVLV 10MOV-16A-Open * *MIN FLOW VLV 10MOV-16A-Closed EV~LUATOR NOTE: The bolded iterps in this step are improperly ali ~ ned. Should the Candidate inform the CRS that the ST cannot be lbontinued due to the improperly ali~ ned item, inform the Candidate th~ deviation has been noted, continue with the ST, and the deyiation will be corrected by another Operator later.

OW SPRAY OUTBO VLV

OW SPRAY OUTBO VLV 1OMOV-26A- Closed 1OMOV-26A- Closed

OW SPRAY INBO VLV 10MOV-

OW SPRAY INBO VLV 10MOV-31A- Closed 31A- Closed

HX A INLET VLV 10MOV-65A-Open

HX A INLET VLV 10MOV-65A-Open

HX A OUTLET VLV 10MOV-12A

-Open

HX A OUTLET VLV 10MOV-12A

-Open

HX A BYP VLV 10MOV-66A-Open

*HX A BYP VLV 10MOV-66A-Closed

RHR TEST TORUS CLG &

RHR TEST TORUS CLG &

SPRAY 1OMOV-39A- Closed SPRAY 1OMOV-39A- Closed

TORUS SPRAY INBO VLV

TORUS SPRAY INBO VLV 1OMOV-38A - Closed 11 1OMOV-38A- Closed

!I

-5 of 8-

RO 14-2 NRC RO C001 TASK TITLE p e rform RHRL"me up ven"fiIC~ fIIOn II EVALUATION I STEP I STANDARD f COMMENT

3. Verify the following lineup at panel Ve ifies the following lineup at panel CRITICAL STEP (cont. ) 09-3 (cont.): 09J3 and documents in ST-2AN (bolded items only)

(co t.): SAT I UNSAT

RHR TEST & TORUS CLG 1OMOV-34A- Closed

RHR TEST & TORUS CLG 1OMOV-34A- Closed

RHRSW TO RHR 10MOV-148A

-Closed

RHRSW TO RHR 10MOV-148A

-Closed

TORUS SUCT VLV 10MOV-13A

-Open

TORUS SUCT VLV 10MOV-13A

-Open

SHUTDOWN CLG SUCT VLV 10MOV-15A- Closed

SHUTDOWN CLG SUCT VLV 10MOV-15A- Closed

TORUS SUCT VLV 10MOV-13C

-Open

TORUS SUCT VLV 10MOV-13C

-Open

SHUTDOWN CLG SUCT VLV 10MOV-15C- Close

SHUTDOWN CLG SUCT VLV 10MOV-15C- Close

RHRSW DISCH VLV FROM HX A 1OMOV-89A- Closed

RHRSW DISCH VLV FROM HX A 1OMOV-89A - Closed

HX A INBD VENT VLV 10MOV-166A - Closed

HX A INBD VENT VLV 10MOV-166A- Closed

HX A OUTBD VENT VLV 10MOV-167A- Closed

HX A OUTBD VENT VLV 10MOV-167A- Closed

RHRSW TO RHR 10MOV-149A

-Closed

RHRSW TO RHR 10MOV-149A

-Closed II

RHR DISCH TO RADW 1OMOV Closed

RHR DISCH TO RADW 1OMOV Closed

SHUTDOWN CLG SUCT 10MOV Closed

SHUTDOWN CLG SUCT I, 10MOV Closed I

-6 of 8-

RO 14-2 NRC RO C001 TASK TITLE Perform RHR Lineup Verification EVALUATION I STEP STANDARD COMMENT

4. Verify the following lineup at panel Ve ifies the following lineup at panel CRITICAL STEP 09-4: 09i 4 and documents in ST-2AN (balded items only)

(CO!lt. ): SAT/UNSAT

RHR DISCH TO RADW 1OMOV Closed * *RHR DISCH TO RADW 10MOV Open

SHUTDOWN CLG SUCT 10MOV Closed * *SHUTDOWN CLG SUCT 10MOV-18.:.... Open I

EVt LUATOR NOTE: The bolded ite I s above are improperly aligned.

Sh uld the Candidate inform the C~S that the ST cannot be co1tinued due to the improperly aligned item, inform the Candidate thel deviation has been noted, continue with the ST, and the deyiation will be corrected by

, anqther Operator later.

EVALUATOR: Terr ~ inate the task at this point.

Task Standard: RHR lineup verification performed Improper lineup of minimum flow valve, heat exchanger bypass valve, discharge valve to Radwaste, and sh utdown cooling isolation valve identified.

-7 of 8-

HA DOUT

ST-2AN, RHR Loop A Monthly Operability Test, is in progress.

Other operators have prepared ST -2AN up to Section 8.1.

RHR Loop A level swi ches are operable.

RHR Loop A is in the tandby LPCI lineup.

Complete ST-2AN Sections 8.1 a d 8.2.

I 8 of 8-

ENTERGY NUC EAR NORTHEAST I

JOB PERFOR ~ ANCE MEASURE RO NRC 14-2 RO TASK TIT~E: Re-activation of RO License C002 APPL . TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: .....:2:..:..

. 1.:...:...4..:.._(l.::.3:..::..3~..-)_ _ _ __

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME :

- Minute I

-z:;- ~ ----z_, _ .~ff)/,L_;;

SUBMITTED: .-

_,. r OPERATIONS REVIEW:

~~ (

APPROVED :

~ I CANDIDATE NAME:

JPM Completion Perform Classroom TE PERFORMED: Minutes PERFORMANCE EVALUATION : D Satisfact ry D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER I

JOB PERFOR ANCE MEASURE RECORD ~NO CHECKLIST RO NRC 14-2 RO TASK TIT E: Re-activation of RO License C002 APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Z1 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

- of 8-

JOB PERFORMANCE MEASURE REQUIRED T iSK INFORMATION RO NRC 14-2 RO TASK Tl E: Re-activation of RO License C002 APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ODS0-30, Maintenance of NRC Licenses ~ nd STA Qualifications Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. None EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the cand~date that the conditions of each step need only be properly identified and not actually perform d.

C. The candidate should demonstrate proper se of HU tools such as procedure use, self checking, place keeping and three-point communicat on.

VI. TASK CONDITIONS A. You are a Reactor Operator (RO) and your RO license became inactive on July 1, 2014.

B. You have been directed to re-activate your license during the 3rd quarter to stand an RO watch on October 4, 2014.

-3 of 8-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Complete the following worksheet regarding re-activation of your license. Consider each item separately and circle the correct response for each item as follows:

Yes- This IS required for license re-activation and it meets the standard.

No- This IS required for license re-activation, but it does NOT meet the standard.

N/R- This is NOT required for license re-activation."

EVALUATOR: Provide the candidate with the attached handout and worksheet. Provide ODS0-30 if requested .

STEP STANDARD EVALUATION I COMMENT

1. Evaluates worksheet step 1 Circles Yes for worksheet step 1. CRITICAL STEP regarding requalification SAT I UNSAT training .

EVALUATOR NOTE: This step meets the required standard of being current in requal, which includes passing all exams with at least an 80%.

2. Evaluates worksheet step 2 Circles No for worksheet step 2. CRITICAL STEP regarding a plant tour. SAT I UNSAT EVALUATOR NOTE: This step does not meet the required standard of the plant tour being supervised by an SRO.

3. Evaluates worksheet step 3 Circles No for worksheet step 3 Schedule A. CRITICAL STEP regarding proposed under- SAT I UNSAT instruction watch Schedule A.

EVALUATOR NOTE: The RB NPO position does not count towards the required 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months on-shift, leaving only 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

4. Evaluates worksheet step 3 Circles No for worksheet step 3 Schedule B. CRITICAL STEP regarding proposed under- SAT/UNSAT instruction watch Schedule B.

EVALUATOR NOTE: This step does not meet the required standard of the 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of on-shift time being performed in the same calendar quarter.

5. Evaluates worksheet step 3 Circles Yes for worksheet step 3 Schedule C. CRITICAL STEP regarding proposed under- SAT/UNSAT instruction watch Schedule C.

EVALUATOR NOTE: This step meets the required standard of 4 12-hour shifts during the same calendar quarter.

EVALUATOR: Terminate the task at this point.

-5 of 8-

EVALUATOR'S KEY

1. You have attended all requal training and passed all quizzes/exams. However your written grade average is 84% and you are on a PIP until it is greater than 85%. This is not expected until after Oct 4.

Does The Above Meet Re-activation Standard? N/R

2. On your own time, you and a friend (who has an active RO license) came in and took a complete tour of the plant. Neither the Shift Manager nor the Control Room Supervisor were aware of this.

Does The Above Meet Re-activation Standard? Yes N/R

3. Below are three proposed schedules for you to stand the watch under instruction.

Date Position Hours Attend All Turnovers?

Sept 12 SNO 12 Yes Schedule Sept 13 SNO 12 Yes A Sept 20 RBNPO 12 Yes Sept 21 SNO 12 Yes

Does The Above Meet Re-activation Standard? Yes G N/R Date Position Hours Attend All Turnovers?

Sept 28 SN02 12 Yes Schedule Sept 29 SNO 12 Yes B Sept 30 SNO 12 Yes Oct 01 SNO 12 Yes Oct02 SNO 12 Yes

Does The.Above Meet Re-activation Standard? Yes N/R Date Position Hours Attend All Turnovers?

Sept22 SNO 12 Yes Schedule Sept 23 SNO 12 Yes c Sept 24 RBNPO 8 No (last 4 hrs of shift in Work Control)

Sept 25 SNO 12 Yes Sept27 SNO 12 Yes

Does The Above Meet Re-activation Standard? G No N/R EVALUATOR'S KEY

-6 of 8-

HANDOUT

You are a Reactor Operator (RO) and your RO license became inactive on July 1, 2014 .

You have been directed to re-activate your license during the 3rd quarter to stand an RO watch on October 4, 2014.

Complete the following worksheet regarding re-activation of your license. Consider each item separately and circle the correct response for each item as follows:

Yes - This IS required for license re-activation and it meets the standard.

No- This IS required for license re-activation, but it does NOT meet the standard.

N/R- This is NOT required for license re-activation.

-7 of 8-

WORKSHEET I. You have attended all requal training and passed all quizzes/exams. However your written grade average is 84% and you are on a PIP until it is greater than 85%. This is not expected until after Oct 4.

Does The Above Meet Re-activation Standard? Yes No N/R

2. On your own time, you and a friend (who has an active RO license) came in and took a complete tour of the plant. Neither the Shift Manager nor the Control Room Supervisor were aware of this.

Does The Above Meet Re-activation Standard? Yes No N/R

3. Below are three proposed schedules for you to stand the watch under instruction.

Date Position Hours Attend All Turnovers?

Sept 12 SNO 12 Yes Schedule Sept 13 SNO 12 Yes A Sept 20 RBNPO 12 Yes Sept 21 SNO 12 Yes

Does The Above Meet Re-activation Standard? Yes No N/R Date Position Hours Attend All Turnovers?

Sept 28 SN02 12 Yes Schedule Sept 29 SNO 12 Yes B Sept 30 SNO 12 Yes Oct 01 SNO 12 Yes Oct02 SNO 12 Yes

Does The Above Meet Re-activation Standard? Yes No N/R Date Position Hours Attend All Turnovers?

Sept 22 SNO 12 Yes Schedule Sept 23 SNO 12 Yes c Sept 24 RBNPO 8 No (last 4 hrs of shift in Work Control)

Sept 25 SNO 12 Yes Sept 27 SNO 12 Yes

Does The Above Meet Re-activation Standard? Yes No N/R

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC 14-2 RO TASK TITLE : Perform ST-23C , Jet Pump Operability- Two Loop EC APPL . TO JPM NUMBER REV: DATE : NRC KJA SYSTEM NUMBER: _2_.2_._12_(,_3_

.7-'-)_ _ _ __

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME :

- Minutes SUBMITTED: OPERATIONS REVIEW: ~d z~

~ .s-;

APPROVED :

CANDIDATE NAME :

JPM Completion Perform Classroom ATE PERFORMED: TIME TO COMPLETE : Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST RO NRC 14-2 RO TASK TITLE: Perform ST-23C, Jet Pump Operability- Two Loop EC APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Z1 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 15-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION RO NRC 14-2 RO TASK TITLE: Perform ST-23C, Jet Pump Operability- Two Loop EC APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-23C, Jet Pump Operability Test for Two Loop Operation Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Prepare a copy of ST-23C filled out up to step 8.1.

EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking,

. place keeping and three-point communication .

VI. TASK CONDITIONS A. ST-23C, Jet Pump Operability Test for Two Loop Operation (EPIC Available), is in progress.

B. The required data for completing ST-23C is included on the provided handout.

C. Baseline data collection is complete and an "established pattern" exists.

-3 of 15-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Perform ST-23C steps 8.1 through 8.4. Then assess the results against the Level 1 Acceptance Criteria of section 10.1 .1 and 10.1 .2 by completing the provided worksheet. "

EVALUATOR: Provide the candidate with the attached handout, worksheet, and the prepared copy of ST-23C.

STEP STANDARD EVALUATION I COMMENT

1. Record data for ST-23C step Records data for ST-23C section 8.1 per the provided key. SAT I UNSAT 8.1.

EVALUATOR NOTE: It is acceptable for all values to be rounded to the nearest whole number.

2. Calculate the value for ST- Calculates and records a value of 6.5 Mlbmlhr per the SAT I UNSAT 23C step 8.2. provided key.

3. Record data for ST-23C step Records data for ST-23C step 8.3 on Attachment 5 per the SAT I UNSAT 8.3 on Attachment 5. provided key.

EVALUATOR NOTE: It is acceptable for all values to be rounded to the nearest whole number.

4. Record data for ST-23C step Record data for ST-23C step 8.4 on Attachment 2 per the SAT I UNSAT 8.4 on Attachment 2. provided key.

EVALUATOR NOTE: It is acceptable for all values to be rounded to the nearest whole number.

-4 of 15-

STEP STANDARD EVALUATION I COMMENT

5. Assess Level 1 Acceptance Determines Level1 Acceptance Criteria 10.1.1 is UNSAT CRITICAL STEP Criteria 10.1.1 . and provides brief description of why (see provided key). SAT I UNSAT EVALUATOR NOTE: Level1 Acceptance Criteria 10.1 .1 is NOT met because total core flow is greater than 70% and Recirculation loop jet pump flow mismatch is greater than 3.85 Mlbmlhr (5%).

6. Assess Level 1 Acceptance Determines Level1 Acceptance Criteria 10.1.2 is UNSAT CRITICAL STEP Criteria 10.1.2. and provides brief description of why (see provided key) . SAT I UNSAT EVALUATOR NOTE: Level 1 Acceptance Criteria 10.1.2 is NOT met because both:

Loop A flows are greater than 5% from predicted on Attachments 3 and 4 AND

Jet Pump 3 and 4 dPs are greater than 20% below established values .

EVALUATOR: Terminate the task at this point.

-5 of 15-

EVALUATOR'S KEY JET PUMP OPERABILITY TEST FOR TWO LOOP OPERATION (EPIC ST-23C AVAILABLE)

Init 8.0 PROCZD'URB 8.1 Record the following:

8.1.1 Total Core Flow 93.5 (% rated)

EPIC - A-3330 TH 8 .1. 2 Loop A Jet Pump Flow 32.5 Mlbm/hr 02-3FI-92A TH 8.1.3 Loop B Jet Pump Flow 39.0 Mlbm/hr 02-3FI-92B TH 8 .1. 4 A Pump Speed = 60 x 3 ~pump power - 1.3 =

60 3~ 2.63

- 1 .3 = 81.5 X

A- 399 TH 8 .1.5 B Pump Speed = 58.5 x 3~pump power + 1.9 =

58. 5 X 3 .J 2. 61 + 1.9 :; 82.4 A-400 ' TH 8.1.6 17.422 A Recirc Loop Flow Mlbm/hr EPIC-A-3317 TH 8.1. 7 B Recirc Loop Flow 16.602 Mlbm/hr EPIC-A-3318 TH 8.2 Calculate the absolute value of:

I <8.1.2> - (8.1.3) 1 = _ _6_*5_ _ _ _-J'-.lbm/hr TH EVALUATOR'S KEY

-6 of 15-

EVALUATOR'S KEY JET PUMP OPERABILITY TEST FOR TWO LOOP OPERATION (EPIC ST- 23C AVAILABLE}

ATTACHMENT 2 Page 1 of 1 ST 23C DATA FOR REACTOR ENGINEERING SUPPQRT Tod*y/0730 Date/Time A. Recirc Loop A flow (EPIC-A- 3317 ) __1_7._.4_22___ Ml bm/hr B. Recirc Loop B flow (EPIC-A- 3318) ---=1c..::.6.:..::60.=.:2=--- Mlbm/hr

c. Rx Total core Flow (EPIC- A- 04141 ___;.7...:.1*:....:4_ _ _ Mlbm/hr D. EPI C-A-6254 , ~"SUB __7_2._9___ Ml bm/hr E. Recirc Pump A Speed (02-184SI-16Al 82.46 at panel 09-4)

F. Recirc Pump B Speed (02-184SI -16Bl ,

at panel 09 - 4) 82.50 Q.

G. Recirc ~ A Speed A-399 Calc. ----"'8..;.;;

1*.5.;;._- - %

H. Recirc Pump B Speed A- 400 Calc

---82.4- - '

I. RWR Loop A Jet Pump Flow (02 - 3FI-92A at panel 09- 4 ) _3_2._5_ _ lbs/hr x 10' J. RWR Loop B Jet Pump Flow (02 - 3FI-92B at panel 09-4) _3_9._0_ _ lbs/hr x 10' K. Double Tapped JP 1 Fl ow (02-3FI-87A at panel 09-4) 3.45 lbs/hr x 10' L. Double Tapped JP 6 Flow (02-3FI -87C at panel 09-4) _ 3_.3_ _ lbs/hr x 10' M. Double Tapped JP l l Fl ow (02-3FI-87B at panel 09-4) _4_.o_ _ lbs/hr x 10' N. Double Tapped JP 16 Flow (02-3FI -87D at panel 09-4) 4.1 lbs/hr x 10'

0. EPIC-A- 3382 RECIRC LOOP A AVE JET PMP \PSID 31.01 %paid P. EPIC-A- 3381 RECI RC LOOP B AVE JET PMP %PSID 48.71 Q. EPIC- A- 405 RX CORE DIFF PRES 17.6 psid R. EPIC- A-3390 P6 10 MIN AVG CORE THERMAL POWER 2437.8 mwth EVALUATOR'S KEY

-7 of 15-

EVALUATOR'S KEY ATTACHMENT S Page 1 of 4 LOOP AVERAGE dP V" JET PUMP dP LOOI'AAYG JPI JPI

~1'110 -20% +211%

s 4.0 7.3 8 5.8 8.7 7 &.1 8.2 5.6 &A 5.1 7.7 s..a ... 8.7 10.1 I 7.8 11.5 9 7.8 11.7 7.2 10.1 u 9.11 7.3 11 .0 a.a 1u 10 e.1 13.o a.o 12.0 7A 11.0 a.1 12.2 9.!; 14.2 II 0.5 14.3 u 13.2 8.1 12.2 8.11 13.4 10.4 15.8 12 10.3 15.5 11.11 14.4 1.s 13.3 11.1 14.5 11,3 17.0 13 11.2 18.8 10.4 15.8 9.6 14.4 10.5 15.7 12.2 11A 14 12.0 18.0 11 .2 111.1 10.4 15.5 11.2 16.9 13.:Z 111.7 15 12.9 ID.3 12.0 1&0 11.1 18.7 12.0 18.0 14.1 21.1 16 13.7 20.5 12..8 11.2 11.0 17.1 12.8 18.2 15.0 22.5 17 14.5 21.8 13.8 2M 12.1 1U IU 20.3 18 15.3 23.0 14.4 21.0 13.4 20.0 14.3 21 .5 18.8 25.2 Ill 1e.2 24.3 15.2 22.1 14.1 21.2 15..1 22.8 17,7 28.5 20 17.0 26.15 18.0 24.0 14.8 22.3 15.8 2U 21 17.8 21.7 18.& 26.2 15.8 23.4 18.8 24.0 1'-5 28.2 22 18.6 21.0 17.8 21.4 18.4 24.6 17.4 2&1 20.4 30.8 23 19.5 28.2 18.4 27.8 17.1 25.7 11.1 27.2 21.3 31.9 24 20.3 30.4 111.2 2&7 17.9 28.8 1&11 28.S 22.2 33.3 25 21.1 31 .7 20.0 a-9 18.6 21.0 10.1 29.5 23.1 34.&

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.... 73.0 *** "1'0 .3 44.5 88.7 o66.0 87.4 53.0 7U 1!0 49.4 74.2

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47.1

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1312AYG -.IN 31.01 32.0 33.2 16.4 24.0 353 I ni t TH EVALUATOR'S KEY

-8 of 15-

EVALUATOR'S KEY ATTACHMENT S

. Par;re 2 of 4 LOOP AVERAG!!: dP vs JBT PUMP dP L~.,::vo JPI

~

-+81% ~

JP7 JP7 JPI JPI

-+81% ::

u JPt

.u

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-e 5.11 7.0 8.3 4.1 4.9 u

7.4

1.8 4.5 5.7 8.8 4.4 u

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7.9 !l.t u

7.7 u

lU u

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10.0 9.2 13.7 8.1 12.2 7.8 11.3 7.4 11.0 7.8 11 .7 13.4 u 11.0 12.0 13..0 10.1 10.11 11.8 16.1 us.*

17.8 8.8 9.7 10.5 14.8 15.7

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....u 8.1 12.2 1S.3 14.4 8.-4 10.2 1U._

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-9 of 15-

EVALUATOR'S KEY AT'l'ACHMENT 5 Page 3 of 4 I.OOP AVERAGE dP VB I JF.T PUMP dP av'o5.0o:'..:.0 ,

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7ti.G 4t.Z 4t. 7 Init TH EVALUATOR'S KEY

-10 of 15-

EVALUATOR'S KEY ATTACHMENT 5 Page 4 of 4 LOOP AVERAGE dP vs JET PUMP dP

.~~,.:., ~-11

~

JP11 JP17 JP11 JP11 JP1t

-~

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1().8 11..8 13.0 7.5

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_...7.11'-11 51.1 l 41.2

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41.4 Ini t _TH _ __

EVALUATOR'S KEY

-11 of 15-

EVALUATOR'S KEY Level 1 Status (circle one) If UNSAT, describe why below Acceptance Criteria Recirculation loop jet pump flow mismatch 10.1.1 SAT 8 exceeds 5% of rated core flow (3.85 Mlbm/hr).

(or similar)

Loop A and B flows are greater than 5% from predicted (Att. 3).

Loop A and B jet pump flows are greater than 5%

10. 1.2 SAT s from predicted (Att. 4).

Jet pump 3 and 4 dPs are greater than 20% below established values (Att 5).

(or similar, such as " Loop A does not meet any of the required criteria in 10.1.2.")

EVALUATOR'S KEY

-12 of 15-

HANDOUT

ST -23C, Jet Pump Operability Test for Two Loop Operation (EPIC Available), is in progress.

The required data for completing ST -23C is included on the provided handout.

Baseline data collection is complete and an "established pattern" exists.

Perform ST -23C section 8.0. Then assess the results against the Level 1 Acceptance Criteria of section 10.1.1 and 10.1.2 by completing the provided worksheet.

-13 of 15-

HANDOUT Parameter Instrument I EPIC Point Value Total Core Flow EPIC-A-3330 93.5% rated Loop A Jet Pump Flow 02-3FI-92A 32.5 Mlbm/hr Loop B Jet Pump Flow 02-3FI-92B 39.0 Mlbm/hr A Pump Power EPIC-A-399 2.63 MW B Pump Power EPIC-A-400 2.61 MW A Recirc Loop Flow EPIC-A-3317 17.422 Mlbm/hr B Recirc Loop Flow EPIC-A-3318 16.602 Mlbm/hr Rx Total Core Flow EPIC-A-0414 71.4 Mlbm/hr WTSUB EPIC-A-6254 72.9 Mlbm/hr Recirc Pump A Speed 02-184SI-16A1 82.46%

Recirc Pump B Speed 02-184SI-16B1 82 .50%

6 Double Tapped JP 1 Flow 02-3FI-87A 3.45 lbs/hr x 10 6

Double Tapped JP 6 Flow 02-3FI-87C 3.3 lbs/hr x 10 6

Double Tapped JP 11 Flow 02-3FI-87B 4.0 lbs/hr x 10 6

Double Tapped JP 16 Flow 02-3FI-87D 4.11bs/hr x 10 Recirc Loop A Ave Jet Pmp %PSID EPIC-A-3382 31.01% psid Recirc Loop B Ave Jet Pmp %PSID EPIC-A-3381 48.71% psid Rx Core Diff Press EPIC-A-405 17.6 psid P6 10 Min Avg Core Thermal Power EPIC-A-3390 2437.8 MWth Jet Pump 1 dP EPIC-A-942 32.0% psid Jet Pump 2 dP EPIC-A-944 33.2% psid Jet Pump 3 dP EPIC-A-946 16.4% psid Jet Pump 4 dP EPIC-A-948 24.0% psid Jet Pump 5 dP EPIC-A-950 35.3% psid Jet Pump 6 dP EPIC-A-952 30.3% psid Jet Pump 7 dP EPIC-A-954 35.1% psid Jet Pump 8 dP EPIC-A-956 34.8% psid Jet Pump 9 dP EPIC-A-958 34.0% psid Jet Pump 10 dP EPIC-A-960 35.0% psid Jet Pump 11 dP EPIC-A-943 51.2% psid Jet Pump 12 dP EPIC-A-945 43.7% psid Jet Pump 13 dP EPIC-A-947 50.1% psid Jet Pump 14 dP EPIC-A-949 49.2% psid Jet Pump 15 dP EPIC-A-951 49.7% psid Jet Pump 16 dP EPIC-A-953 51.1% psid Jet Pump 17 dP EPIC-A-955 46.1% psid Jet Pump 18 dP EPIC-A-957 51.8% psid Jet Pump 19 dP EPIC-A-959 48.2% psid Jet Pump 20 dP EPIC-A-961 46.4% psid

-14 of 15-

WORKSHEET Level 1 Status (circle one) If UNSAT, describe why below Acceptance Criteria 10.1 .1 SAT UNSAT 10.1 .2 SAT UNSAT

-15 of 15-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE

~....,_ ______

RO APPL. TO 14-2 NRC RO RC JPM NUMBER TASK TITLE : Determine Worker Exposure for Emergent Work REV: DATE : NRC KIA SYSTEM NUMBER: 2.3.4 (3 .2/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME : _ 20

____:..;_:__ Minutes SUBMITTED:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location : Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes n ERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

-1 of 10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 14-2 NRC RO RC TASK TITLE: Determine Worker Exposure for Emergent Work APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required 1:8] None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 14-2 NRC RO RC TASK TITLE: Determine Worker Exposure for Emergent Work APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EN-RP-201 , Dosimetry Administration Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Ensure adequate copies of the procedures referenced above are available.

V. EVALUATOR NOTES A. The candidate should , at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking , placekeeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. Two operators are required to enter a locked high radiation area to support an emergent job.

C. The job is expected to take 45 minutes D. The job site dose rate is 1500 mRem/hr.

E. Operator #1 has received 1147 mRem of dose so far this year.

F. Operator #2 has received 450 mRem of dose so far this year.

G. Neither operator has received any dose extensions so far this year.

H. Neither operator has any undocumented quarters for this year.

-3 of 10-

RO 14-2 NRC RO RC TASK TITLE: Determine Worker Exposure for Emergent Work

. - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Determine the expected dose that each operator will receive while performing this job.

Determine if each operator will need a dose extension in order to receive this dose. Report your results on the provided worksheet. "

EXAMINER: Provide the candidate with the first handout and worksheet.

EVALUATION STEP STANDARD

/COMMENT

1. Obtain required references. Obtains and utilizes required SAT I UNSAT references, which may include:

EN-RP-201 EXAMINER NOTE: See provided key for remaining steps.

2. Determine the expected dose that each Calculates that each operator will CRITICAL operator will receive while performing receive 1125 mRem while performing STEP this job this job. SAT I UNSAT (45 minutesl60 minutes per hour) x (1500 mRemlhour) = 1125 mRem

3. Determine if Operator #1 will need a Determines that Operator #1 will need CRITICAL dose extension in order to receive this dose extension in order to receive this STEP dose. dose. SAT I UNSAT 1147 mRem + 1125 mRem = 2272 mRem > 2000 mRem normal dose limit

4. Determine if Operator #2 will need a Determines that Operator #2 will NOT CRITICAL dose extension in order to receive this need dose extension in order to receive STEP dose. this dose. SAT I UNSAT 450 mRem + 1125 mRem = 1575 mRem < 2000 mRem normal dose limit c

-4 of 10-

RO 14-2 NRC RO RC TASK TITLE: Determine Worker Exposure for Emergent Work EVALUATION STEP STANDARD

/COMMENT EXAMINER: If the candidate correctly complete JPM steps 2-4, provide them with the extra handout, with the following information:

"Operator #1 has been granted a dose extension to 2500 mRem . Operator #2 has NOT been granted a dose extension.

Determine the maximum stay time allowed for both Operator #1 and for Operator #2, such that they do NOT exceed their dose limits. Document your results in the worksheet below."

5. Determine the maximum stay time Calculates the maximum stay time for CRITICAL allowed for Operator #1 such that dose Operator #1 is approximately 54 STEP limit is NOT exceeded . minutes. SAT I UNSAT (2500 mRem- 1147 mRem) 11500 mRemlhr =0.902 hours0.0104 days 0.251 hours 0.00149 weeks 3.43211e-4 months x (60 minutes

=

per hour) 54 .12 minutes

/ *6. Determine the maximum stay time Calculates the maximum stay time for CRITICAL allowed for Operator #2 such that dose Operator #2 is approximately 62 STEP limit is NOT exceeded . minutes. SAT I UNSAT (2000 mRem- 450 mRem) 11500

=

mRemlhr 1.033 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months (60 minutes per hour) = 62 minutes EVALUATOR: Terminate the task at this point.

-5 of 10-

EVALUATOR'S KEY

1. Expected dose that each operator will receive while performing this job:

1125 mRem

2. Will Operator #1 need a dose extension in order to receive the dose calculated above? (circle one) e No

3. Will Operator #2 need a dose extension in order to receive the dose calculated above? (circle one)

Yes G

-6 of 10-

EVALUATOR'S KEY

1. Maximum stay time allowed for Operator #1 (record final answer in minutes):

54 minutes

2. Maximum stay time allowed for Operator #2 (record final answer in minutes):

62 minutes EVALUATOR'S KEY

-7 of 10-

HANDOUT

The plant is operating at 100% power.

Two operators are required to enter a locked high radiation area to support an emergent job.

The job is expected to take 45 minutes.

The job site dose rate is 1500 mRem/hr.

Operator #1 has received 1147 mRem of dose so far this year.

Operator #2 has received 450 mRem of dose so far this year.

Neither operator has received any dose extensions so far this year.

Neither operator has any undocumented quarters for this year.

Determine the expected dose that each operator will receive while performing this job.

Determine if each operator will need a dose extension in order to receive this dose.

Report your results on the provided worksheet.

-8 of 10-

WORKSHEET

1. Expected dose that each operator will receive while performing this job:

2. Will Operator #1 need a dose extension in order to receive the dose calculated above? (circle one)

Yes No

3. Will Operator #2 need a dose extension in order to receive the dose calculated above? (circle one)

Yes No

-9 of 10-

EXTRA HANDOUT Operator #1 has been granted a dose extension to 2500 mRem.

Operator #2 has NOT been granted a dose extension.

Determine the maximum stay time allowed for both Operator #1 and for Operator #2, such that they do NOT exceed their dose limits.

Document your results in the worksheet below.

EXTRA WORKSHEET

1. Maximum stay time allowed for Operator #1 (record final answer in minutes):

2. Maximum stay time allowed for Operator #2 (record final answer in minutes):

-10 of 10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO NRC 14-2 SRO TASK TITLE : Verify Fuel Movement Sheets C001 APPL . TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: _2_.1_.3_5___.(3_.-'9)_ _ _ __

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME : 20 Minutes

- c:b-;zr=::::::->

SUBMITTED: OPERATIONS REVIEW: .~

/

APPROVED:

CANDIDATE NAME :

JPM Completion Perform Classroom ATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SRO NRC 14-2 SRO TASK TITLE: Verify Fuel Movement Sheets C001 APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required 1Zl None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2of12-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SRO NRC 14-2 SRO TASK TITLE: Verify Fuel Movement Sheets C001 APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A None II. REFERENCES A OSP-66.001 , Management of Refueling Activities Ill. TOOLS AND EQUIPMENT A None IV. SET UP REQUIREMENTS A None EVALUATOR NOTES A The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking ,

place keeping and three-point communication.

VI. TASK CONDITIONS A Today is October 2, 2014.

B. A refueling outage is underway.

C. A refueling error occurred last shift.

D. You are the oncoming Refuel Bridge SRO.

E. The prior shift's fuel moves into the Spent Fuel Pool have been verified correct by another SRO.

-3 of 12-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Verify the previous shift's in-core placement of components (steps 1, 2, 4, 5, 6, 7, 9, 10, 11, 12, 14, 15, 16, and 17 from the provided ICA Transfer Forms)."

EVALUATOR: Provide the candidate with the attached handouts (fuel movement-sheets and pictures of core cells). Provide OSP-66.001 if requested.

STEP STANDARD EVALUATION I COMMENT

1. Verify correct loading of Determines four Control Cell 38-35 bundles are in the SAT I UNSAT Control Cell 38-35. correct location and orientation (ICA Transfer Form steps 1-4):

JLV675

JLV682

JLK804

JLK817

2 . Determine the INCORRECT Determines two Control Cell 14-35 bundles are the correct CRITICAL STEP loading of Control Cell14-35. bundles but in the INCORRECT orientation (ICA Transfer SATIUNSAT Form steps 6 & 7):

JLV678

JLV670

3. Verify the correct loading of Determines two Control Cell 14-35 bundles are the correct SAT I UNSAT Control Cell 14-35. bundles and in the correct orientation (ICA Transfer Form steps 9 & 10) :

JLK805

JLK812

-4of12-

STEP STANDARD EVALUATION I COMMENT

4. Determine the INCORRECT Determines one Control Cell 38-15 bundle is in the correct CRITICAL STEP loading of Control Cell 38-15. orientation but is the INCORRECT bundle (ICA Transfer SAT/UNSAT Form step 11 ):

JLV668 (vs. JLV 698)

5. Verify the correct loading of Determines three Control Cell 38-15 bundles are the correct SAT/UNSAT Control Cell 38-15. bundles and in the correct orientation (ICA Transfer Form steps 12, 14, & 15):

JLV674

JLK807

JLK820

6. Determine the INCORRECT Determines that the two single blade guides in Control Cell CRITICAL STEP loading of Control Cell 14-15. 14-15 are in the wrong orientation (ICA Transfer Form steps SAT/UNSAT 16 & 17).

EVALUATOR: Terminate the task at this point.

-5 of 12-

HANDOUT

Today is October 2, 2014.

A refueling outage is underway.

A refueling error occurred last shift .

You are the oncoming Refuel Bridge SRO .

The prior shift's fuel moves into the Spent Fuel Pool have been verified correct by another SRO.

Verify the previous shift's in-core placement of components (steps 1, 2, 4, 5, 6, 7, 9, 10, 11, 12, 14, 15, 16, and 17 from the provided ICA Transfer Forms).

-6of12-

HANDOUT ATTACHMENT 9.1 ITEM CONTROL AREA (ICA) TRANSFER FORM (TYPICAL)

(1) Number: R21-0001 (2) Issued (Date): Oct I 2014 (3) Reason for Transfer: Cycle 21 Refueling Ouage (4) Prepared By: S. Carol in/ S. emw.fUt (4a) Reviewed By: B. Drews/ fJJ. 9)'1.(!(W (4b) Additional Approvals By: _N/A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(10) SNMC Approval: S. Carol in/ I S. emw.fUt Lines __l.:lL thru Date Oct 1, 2014 Line Description Serial No. I From To Performed Dateffime Verified No. of Material Equipment ID ICA Coord. ICA Coord. by Executed by (5) (5) (6) (7) (8) (9) (II) (12) (13)

I FUEL BUNDLE JLV675 SFP 26-BB-2 CORE 39-34 a9J 10/02/14 0300 e!J) 2 FUEL BUNDLE JLV682 SFP 26-CC-2 CORE 37-36 a9J 10/02/14 0310 e!J) 3 DOUBLE BLADE GUIDE N/A CORE 39-36 SFP 26-EE-2 a9J 10/02/14 0320 e!J) 37-34 26-DD-1 4 FUEL BUNDLE JLK804 SFP 26-DD-2 CORE 37-34 a9J 10/02/14 0330 e!J) 5 FUEL BUNDLE JLK817 SFP 26-EE-2 CORE 39-36 a9J 10/02/14 0340 e!J) 6 FUEL BUNDLE JLV678 SFP 26-FF-2 CORE 15-34 a9J 10/02/14 0350 e!J) 7 FUEL BUNDLE JLV670 SFP 26-W-3 CORE 13-36 a9J 10/02/14 0400 e!J) 8 DOUBLE BLADE GUIDE N/A CORE 15-36 SFP 26-DD-2 a9J 10/02/14 0410 e!J) 13-34 26-CC-1 c):o II FUEL BUNDLE FUEL BUNDLE FUEL BUNDLE JLK805 JLK812 JLV698 SFP SFP SFP 26-X-3 26-Y-3 26-Z-3 CORE CORE CORE 13-34 15-36 39-14 a9J a9J a9J 10/02/14 0420 10f02f14 0430 10/02/14 0440 e!J) e!J) e!J) 12 FUEL BUNDLE JLV674 SFP 26-AA-3 CORE 37-16 a9J 10/02/14 0450 e!J)

NOTES/COMMENTS Line#:

Line#:

(14) SNM Records Updated by: _ _ _ _ _ _ _ _ _ __ Lines Thru Date (15) Verified by: _ _ _ _ _ _ _ _ _ _ _ _ Lines Thru Date

-7 of 12-

HANDOUT ATTACHMENT 9.1 ITEM CONTROL AREA (ICA) TRANSFER FORM (TYPICAL)

(1) Number: R21-0001 (2) Issued (Date): Oct 1 2014 (3) Reason for Transfer: Cycle 21 Refueling Ouage (4) Prepared By: S. Carol in/ S. &mllin (4a) Reviewed By: B. Drews/ 91. ~

(4b) Additional Approvals By: _N/A._ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

(10) SNMC Approval: S. Carol in/ I S. &mllin Lines 13-19 thru __Date Oct 1, 2014 Line Description Serial No. I From To Performed Date/Time Verified No. of Material Equipment ID ICA Coord. ICA Coord. by Executed by (5) (5) (6) (7) (8) (9) (II) (12) (13) 13 DOUBLE BLADE GUIDE N/A CORE 39-16 SFP 26-CC-2 a9J 10/02/14 0500 e:J) 37-14 26-BB-1 14 FUEL BUNDLE JLK807 SFP 26-BB-1 CORE 37-14 a9J 10/02/14 0510 e:J) 15 FUEL BUNDLE JLK820 SFP 26-CC-1 CORE 39-16 a9J 10J02J14 0520 e:J) 16 SINGLE BLADE GUIDE N/A SFP 25-FF- CORE 13-16 a9J 10/02/14 0530 e:J)

II 17 SINGLE BLADE GUIDE N/A SFP 25-FF-1 CORE 15-14 a9J 10/02/14 0540 e:J) 18 FUEL BUNDLE JLV720 CORE 13-14 SFP 35-N-7 a9J 10/02/14 0550 e:J) 19 FUEL BUNDLE JLV725 CORE 15-16 SFP 35-N-6 a9J 10/02/14 0600 e:J)

NIA c

20 NIA 21 N/A

, 22 23 N/A 24 N/A NOTES/COMMENTS Line#:

Line#:

(14) SNM Records Updated by: _ _ _ _ _ _ _ _ _ __ Lines Thru Date (15) Verified by: _ __ _ __ _ _ _ _ _ _ Lines Thru Date

-8 of 12-

HANDOUT SOUTH NORTH Control Cell 38-35

-9 of 12-

HANDOUT SOUTH NORTH Control Cell 14-35

-10of12-

HANDOUT SOUTH NORTH Control Cell 38-15

-11of12-

HANDOUT SOUTH NORTH Control Cell14-15

-12 of 12-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO NRC 14-2 SRO TASK TITLE : Re-activation of SRO License C002 APPL. TO JPM NUMBER REV: DATE : NRC KIA SYSTEM NUMBER: _2_.1_.4__;(...._3._8).___ _ __

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

- Minutes SUBMITTED: OPERATIONS REVIEW~~?';*~

APPROVED :

CANDIDATE NAME :

JPM Completion Perform Classroom

'ATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SRO NRC 14-2 SRO TASK TITLE: Re-activation of SRO License C002 APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SRO NRC 14-2 SRO TASK TITLE: Re-activation of SRO License C002 APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ODS0-30, Maintenance of NRC Licenses and STA Qualifications Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. None EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking ,

place keeping and three-point communication.

VI. TASK CONDITIONS A. You are a Shift Manager and your SRO license became inactive on July 1, 2014.

B. You have been directed to re-activate your license during the 3rd quarter to stand the Shift Manager watch on October 4, 2014.

-3 of 8-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Complete the following worksheet regarding re-activation of your license. Consider each item separately and circle the correct response for each item as follows:

Yes- This IS required for license re-activation and it meets the standard.

No- This IS required for license re-activation , but it does NOT meet the standard.

N/R- This is NOT required for license re-activation ."

EVALUATOR: Provide the candidate with the attached handout and worksheet. Provide ODS0-30 if requested.

STEP STANDARD EVALUATION I COMMENT

1. Evaluates worksheet step 1 Circles Yes for worksheet step 1. CRITICAL STEP regarding requalification SAT I UNSAT training .

EVALUATOR NOTE: This step meets the required standard of being current in requal , which includes passing all exams with at least and 80%.

2. Evaluates worksheet step 2 Circles No for worksheet step 2. CRITICAL STEP regarding Emergency Director SAT I UNSAT qualification.

EVALUATOR NOTE: This step does not meet the required standard of being currently qualified Emergency Director.

3. Evaluates worksheet step 3 Circles NIR for worksheet step 3. SAT I UNSAT regarding Fire Brigade member qualification.

EVALUATOR NOTE: Fire Brigade qualification is not required for a Shift Manager.

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

4. Evaluates worksheet step 4 Circles No for worksheet step 4. CRITICAL STEP regarding a plant tour. SAT/UNSAT EVALUATOR NOTE: This step does not meet the required standard of the plant tour being supervised by an SRO.

5. Evaluates worksheet step 5 Circles No for worksheet step 5 Schedule A. CRITICAL STEP regarding proposed under- SAT/UNSAT instruction watch Schedule A.

EVALUATOR NOTE: The FSS position does not count towards the required 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months on-shift, leaving only 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

6. Evaluates worksheet step 5 Circles No for worksheet step 5 Schedule B. CRITICAL STEP regarding proposed under- SAT I UNSAT instruction watch Schedule B.

EVALUATOR NOTE: This step does not meet the required standard of the 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of on-shift time being performed in the same calendar quarter.

7. Evaluates worksheet step 5 Circles Yes for worksheet step 5 Schedule C. CRITICAL STEP regarding proposed under- SAT/UNSAT instruction watch Schedule C.

EVALUATOR NOTE: This step meets the required standard of 4 12-hour shifts during the same calendar quarter.

EVALUATOR: Terminate the task at this point.

-5 of 8-

EVALUATOR'S KEY

1. You have attended all requal training and passed all quizzes/exams. However your written grade average is 84% and you are on a PIP until it is greater than 85%. This is not expected until after Oct 4.

Does The Above Meet Re-activation Standard? <9 No NIR

2. You are no longer qualified as Emergency Director and you will notre-qualify until after Oct 4.

Does The Above Meet Re-activation Standard? Yes G NIR

3. You are no longer qualified as a Fire Brigade member and you will notre-qualify until after Oct 4.

Does The Above Meet Re-activation Standard? Yes No

4. On your own time, you and a friend (who has an active RO license) came in and took a complete tour of the plant. Neither the Shift Manager nor the Control Room Supervisor were aware of this.

Does The Above Meet Re-activation Standard? Yes NIR

5. Below are three proposed schedules for you to stand the watch under instruction.

Date Position Hours Attend All Turnovers?

Sept 12 SM 12 Yes Schedule Sept 13 SM 12 Yes A Sept 20 FSS 12 Yes Sept 21 CRS 12 Yes

Does The Above Meet Re-activation Standard? Yes G NIR Date Position Hours Attend All Turnovers?

Sept 28 CRS 12 Yes Schedule Sept 29 SM 12 Yes B Sept 30 SM 12 Yes Oct 01 SM 12 Yes Oct02 SM 12 Yes

Does The Above Meet Re-activation Standard? Yes NIR Date Position Hours Attend All Turnovers?

Sept 22 SM 12 Yes Schedule Sept 23 SM 12 Yes c Sept 24 STA 8 No (last 4 hrs of shift in Work Control)

Sept 25 SM 12 Yes Sept 27 SM 12 Yes

Does The Above Meet Re-activation Standard? e No NIR EVALUATOR'S KEY

-6 of 8-

HANDOUT

You are a Shift Manager and your SRO license became inactive on July 1, 2014 .

You have been directed to re-activate your license during the 3rd quarter to stand the Shift Manager watch on October 4, 2014.

Complete the following worksheet regarding re-activation of your license. Consider each item separately and circle the correct response for each item as follows:

Yes- This IS required for license re-activation and it meets the standard.

No- This IS required for license re-activation, but it does NOT meet the standard.

N/R- This is NOT required for license re-activation.

-7 of 8-

WORKSHEET

l. You have attended all requal training and passed all quizzes/exams. However your written grade average is 84% and you are on a PIP until it is greater than 85%. This is not expected until after Oct 4.

Does The Above Meet Re-activation Standard? Yes No NIR

2. You are no longer qualified as Emergency Director and you will notre-qualify until after Oct 4.

Does The Above Meet Re-activation Standard? Yes No NIR

3. You are no longer qualified as a Fire Brigade member and you will notre-qualify until after Oct 4.

Does The Above Meet Re-activation Standard? Yes No NIR

4. On your own time, you and a friend (who has an active RO license) came in and took a complete tour of the plant. Neither the Shift Manager nor the Control Room Supervisor were aware of this.

Does The Above Meet Re-activation Standard? Yes No NIR

5. Below are three proposed schedules for you to stand the watch under instruction.

Date Position Hours Attend All Turnovers?

Sept 12 SM 12 Yes Schedule Sept 13 SM 12 Yes A Sept 20 FSS 12 Yes Sept 21 CRS 12 Yes

Does The Above Meet Re-activation Standard? Yes No NIR Date Position Hours Attend All Turnovers?

Sept 28 CRS 12 Yes Schedule Sept 29 SM 12 Yes B Sept 30 SM 12 Yes Oct 01 SM 12 Yes Oct02 SM 12 Yes

Does The Above Meet Re-activation Standard? Yes No NIR Date Position Hours Attend All Turnovers?

Sept22 SM 12 Yes Schedule Sept 23 SM 12 Yes c Sept 24 STA 8 No (last 4 hrs of shift in Work Control)

Sept 25 SM 12 Yes Sept 27 SM 12 Yes

Does The Above Meet Re-activation Standard? Yes No NIR

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO NRC 14-2 SRO TASK TITLE: Review ST-23C , Jet Pump Operability- Two Loop EC APPL . TO JPM NUMBER REV: DATE: NRC KJA SYSTEM NUMBER: -=2:..:..:.2=-:....1.;. : 2:. . .J.(. .:. :..4. .;_{,)1_ _ _ __

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME : 20 Minutes

---=-.:......

SUBMITTED: OPERATIONS REVIEW: ~~cd')'~

APPROVED :

/

CANDIDATE NAME:

JPM Completion Perform Location : Classroom ATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SRO NRC 14-2 SRO TASK TITLE: Review ST-23C, Jet Pump Operability- Two Loop EC APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items 0 Technical Review 0 Additional Information 0 Questions and Answers 0 Validation 0 Procedural Change Required ['8] None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 6-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SRO NRC 14-2 SRO TASK TITLE: Review ST-23C, Jet Pump Operability- Two Loop EC APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-23C, Jet Pump Operability Test for Two Loop Operation Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Ensure a copy of the associated JPM handout is available for each candidate (ST-23C completed up to Management SRO Review- numbers based on failure of JP 4 at 100% power).

EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking ,

place keeping and three-point communication.

VI. TASK CONDITIONS A. ST-23C, Jet Pump Operability Test for Two Loop Operation (EPIC Available) , has been performed and is ready for the Management SRO Review.

-3 of 6-

-CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Perform the Management SRO Review of ST-23C per section 11 .2. Report your findings in the space below, including any required actions or restrictions (Tech Spec, TRM, ODCM , etc.), if applicable."

EVALUATOR: Provide the candidate with the attached handout and the prepared copy of ST-23C.

STEP STANDARD EVALUATION I COMMENT

1. Review data recorded in ST- Reviews data recorded in ST-23C . SAT I UNSAT 23C.

2. Identify calculation error in Identifies the calculation in step 8.2 should be recorded as CRITICAL STEP step 8.2. 6.5 Mlbmlhr. SAT I UNSAT

3. Identify Level 1 Acceptance Identifies Level 1 Acceptance Criteria 10.1.1 is NOT met CRITICAL STEP Criteria 10.1.1 is NOT met. due to Recirculation loop jet pump flow mismatch. SAT I UNSAT EVALATOR NOTE: Level1 Acceptance Criteria 10.1.1 is NOT met because total core flow is greater than 70% and Recirculation loop jet pump flow mismatch is greater than 3.85 Mlbmlhr.

-4 of 6-

STEP STANDARD EVALUATION I COMMENT

4. Identify Level1 Acceptance Identifies Level 1 Acceptance Criteria 10.1.2 is NOT met. CRITICAL STEP Criteria 10.1.2 is NOT met. SAT I UNSAT EVALUATOR NOTE: Level1 Acceptance Criteria 10.1.2 is NOT met because both:

Loop flow is greater than 5% from predicted on Attachments 3 and 4 AND

Jet pump 3 and 4 dPs are greater than 20% below established values .

5. Identify required notification. Identifies immediate notification of the Operations Manager SAT I UNSAT or alternate is required .

6. Identify required corrective Identifies Technical Specification LCO 3.4.1 Condition B CRITICAL STEP and compensatory actions. must be entered (restore mismatch within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ). SAT I UNSAT Identifies Technical Specification LCO 3.4.2 Condition A must be entered (be in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ).

EVALUATOR: Terminate the task at this point.

-5 of 6-

HANDOUT

ST -23C, Jet Pump Operability Test for Two Loop Operation {EPIC Available), has been performed and is ready for the Management SRO Review.

Perform the Management SRO Review of ST -23C per section 11.2. Report your findings in the space below, including any required actions or restrictions {Tech Spec, TRM, ODCM, etc.), if applicable.

-6 of 6-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO NRC 14-2 SRO TASK TITLE : Determine Visitor RCA Access Requirements RC APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: _2_.3_.4---'(.._3._7).___ _ __

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER :

ESTIMATED COMPLETION TIME :

- Minutes SUBMITTED:

APPROVED :

CANDIDATE NAME :

JPM Completion Perform Location : Classroom ATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SRO NRC 14-2 SRO TASK TITLE: Determine Visitor RCA Access Requirements RC APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required [2J None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SRO NRC 14-2 SRO TASK TITLE : Determine Visitor RCA Access Requirements RC APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EN-RP-201 , Dosimetry Administration B. EN-RP-202, Personnel Monitoring Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of EN-RP-201 and EN-RP-202.

V. EVALUATOR NOTES A. The candidate should , at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed .

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking ,

place keeping and three-point communication.

VI. TASK CONDITIONS A. A Technical Representative from the Viking Valve Corporation Engineering Department is arriving tomorrow to evaluate replacing the Main Condenser Pit Foam Fire Suppression System .

B. Dose rates in the associated work area range from 0 - 5 mr/hr.

C. The evaluation is expected to take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. The Operations Manager has designated you as the visitor sponsor and visitor escort.

E. Security arrangements have already been completed for visitor access.

F. The individual has never been exposed to or monitored for Occupational Radiation Exposure.

G. The individual will NOT be trained as a Radworker and will NOT perform any work.

-3 of 8-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Identify the in-processing requirements for allowing the individual to enter the RCA as a visitor/member of the public. Identify the individual's annual regulatory dose limit, maximum annual administrative dose guideline, and routine annual administrative dose guideline. Document your results on the provided worksheet."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of the Obtains a copy of EN-RP-201 and/or EN-RP-202, as SAT I UNSAT correct procedure. required.

2. Identify procedural Identifies requirements of EN-RP-202 section 5.3.[1] must CRITICAL STEP requirements for allowing the be met: SAT I UNSAT individual to enter the RCA as a visitor.

Perform an indoctrination briefing of Attachment 9.2 .

Escort briefed per page 2 of Attachment 9.1 .

Visitor and escort complete Attachment 9.9 when the briefing is completed.

Assign individual a DLR.

Assign TEDE limits per EN-RP-201 .

EVALUATOR NOTE: See attached key to assist in grading the candidate's completed worksheet. Each of these requirements may be written out or the appropriate procedure steps may be referenced.

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

3. Identify the individual's annual Identifies the individual's routine annual administrative dose CRITICAL STEP regulatory dose limit. guideline as 100 mrem/year. SAT/UNSAT

4. Identify the individual's Identifies the individual's maximum annual administrative CRITICAL STEP maximum annual dose guideline as 100 mrem/year. SAT/UNSAT administrative dose guideline.

5. Identify the individual's routine Identifies the individual's routine annual administrative dose CRITICAL STEP annual administrative dose guideline as 50 mrem/year. SAT/UNSAT guideline.

EVALUATOR: Terminate the task at this point.

-5 of 8-

EVALUATOR'S KEY

1. Identify the procedural requirements for allowing the individual to enter the RCA as a visitor:

Requirements of EN-RP-202 section 5.3.[1] must be met:

Perform an indoctrination briefing of Attachment 9.2.

Escort briefed per page 2 of Attachment 9.1.

Visitor and escort complete Attachment 9.9 when the briefing is completed.

Assign individual a DLR.

Assign TEDE limits per EN-RP-201.

EVALUATOR NOTE: Each of these requirements may be written out or the appropriate procedure steps may be referenced .

2. Identify the individual's annual regulatory dose limit:

100 mrem/year

3. Identify the individual's maximum annual administrative dose guideline:

100 mrem/year

4. Identify the individual's routine annual administrative dose guideline:

50 mrem/year EVALUATOR'S KEY

-6 of 8-

HANDOUT

A Technical Representative from the Viking Valve Corporation Engineering Department is arriving tomorrow to evaluate replacing the Main Condenser Pit Foam Fire Suppression System.

Dose rates in the associated work area range from 0 -

5 mr/hr.

The evaluation is expected to take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The Operations Manager has designated you as the visitor sponsor and visitor escort .

Security arrangements have already been completed for visitor access.

The individual has never been exposed to or monitored for Occupational Radiation Exposure.

The individual will NOT be trained as a Radworker and will NOT perform any work.

Identify the in-processing requirements for allowing the individual to enter the RCA as a visitor/member of the public.

Identify the individual's annual regulatory dose limit, maximum annual administrative dose guideline, and routine annual administrative dose guideline. Document your results on the provided worksheet.

-7 of 8-

WORKSHEET

1. Identify the in-processing requirements for allowing the individual to enter the RCA as a visitor:

2. Identify the individual's annual regulatory dose limit:

3. Identify the individual's maximum annual administrative dose guideline:

4. Identify the individual's routine annual administrative dose guideline:

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-2 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification REV: DATE: NRC KIA SYSTEM NUMBER: ....:2:..:..4..:..:.*_;_44.:_(~4.:_.4..t_)- - - - -

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME : --'--

30 Minutes SUBMITTED:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location : Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes ERFORMANCE EVALUATION : 0 Satisfactory 0 Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

-1 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-2 NRC SRO EP TASK TITLE : Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification Current Update: By:

Date lnt Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required [8:1 None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-2 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. IAP-1 B. IAP-2 C. EAP-1 .1 D. EAP-4 Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the referenced documents are available, including extra copies of the Part 1 notification form .

V. EVALUATOR NOTES A. The candidate should demonstrate proper use of HU tools such as procedure use, self checking , placekeeping and three-point communication .

-3 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-2 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification VI. TASK CONDITIONS A. The plant was initially operatin9 at 100% power with no equipment out of service.

B. An earthquake was felt in the Control Room and confirmed with both JAF and Nine Mile Point Unit 2 seismic instrumentation.

C. The Reactor was manually scrammed five minutes ago.

E. The following conditions exist now:

Reactor pressure is 200 psig and lowering.

Reactor water level is -5 inches and slowly lowering with all available injection sources maximized.

Drywell pressure is 15 psig and slowly rising .

A steam leak in the Reactor Building coming from the Reactor Water Cleanup system has been reported.

Reactor Water Cleanup isolation valves 12MOV-15 and 12MOV-18 have failed to close .

A team is being assembled to close 12MOV-18 in the field . Expected completion time for the team is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months from now.

Reactor Building differential pressure is -0.25" H2 0 .

No change has been seen in Stack or Reactor Building exhaust radiation levels.

200' elevation wind speed is 10 mph from 190°.

30' elevation wind speed is 5 mph from 190°.

Stability class is E.

-4 of 9-

SRO '-"" 14-2 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification VII. INITIATING CUE Inform the candidate of the following :

"1. Classify the event and inform the examiner of the classification. 2. Then, complete the Part 1 Notification per EAP-1.1, Offsite Notifications.

This is a time critical JPM. Your time clock starts once you acknowledge this task."

- CRITICAL STEP STEP STANDARD EVALUATION I COMMENT

1. Obtain applicable reference documents Obtains a copy of applicable reference documents, as SAT I UNSAT needed:

IAP-1

IAP-2

EAP-1.1 EVALUATOR: Ensure sufficient copies of these documents are available.

2. Classify the event Classifies the event as General Emergency FG1.1 CRITICAL STEP based on loss of RCS and Primary Containment barriers SAT I UNSAT and potential loss of Fuel Clad Barrier within 15 minutes of JPM start time.

JPM start time:

Time of classification :

Time difference:

-5 of 9-

SRO " 14-2 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification STEP STANDARD EVALUATION I COMMENT

3. Implement EAP-1 .1, Offsite Completes EAP-1 .1 Attachment 1, Part 1 notification CRITICAL STEP Notifications, in order to notify offsite form per attached key within 15 minutes of classification SAT I UNSAT agencies. time.

Time of classification :

Time of offsite notification:

Time difference:

EVALUATOR NOTE: Only item 3, 4 , 5, 6, 7, 9, and 10 of EAP-1 .1 Attachment 1 are deemed critical for this JPM. These items are individually graded in the JPM steps below. All other items are non-critical. See attached key.

4. Completes Part 1 Notification step 3. Indicates "GENERAL EMERGENCY" in Part 1 CRITICAL STEP Notification step 3 (see attached key) . SAT I UNSAT

5. Completes Part 1 Notification step 4. Records today's date and time of declaration in Part 1 CRITICAL STEP Notification step 4 (see attached key). SAT I UNSAT

6. Completes Part 1 Notification step 5. Indicates "No Release" in Part 1 Notification step 5 (see CRITICAL STEP attached key). SAT I UNSAT

-6 of 9-

SRO ....,.. 14-2 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification STEP STANDARD EVALUATION I COMMENT

6. Completes Part 1 Notification step 6. Indicates "EVACUATE and IMPLEMENT the Kl PLAN CRITICAL STEP for the following ERPA. .. : 1, 2, 3, 26, 27" in Part 1 SAT/UNSAT Notification step 6 (see attached key).

7. Completes Part 1 Notification step 7. Indicates EAL # "FG1.1 " in Part 1 Notification step 7 CRITICAL STEP (see attached key) . SAT/UNSAT

8. Completes Part 1 Notification step 9. Indicates elevated wind speed of 10 mph in Part 1 CRITICAL STEP Notification step 9 (see attached key) . SAT/UNSAT Indicates ground wind speed of 5 mph in Part 1 Notification step 9 (see attached key) .

9. Completes Part 1 Notification step 10. Indicates elevated wind direction of 190° in Part 1 CRITICAL STEP Notification step 10 (see attached key) . SAT/UNSAT Indicates ground wind direction of 190° in Part 1 Notification step 10 (see attached key).

EVALUATOR: Terminate the task at this point.

-7 of 9-

EVALUATOR'S KEY PART ONE GLNERAL INfORMATION Paqe 1 of 1 NEW YORK STATE UPSTAIR RADIOLOGICAL EMERGENCY DA.TA FORM PART l NOii(JCIIian II

'TillS iii tl) rlplli an inek!ent* 11e J*- A. Fllz.f'Ridl ~ Plri S.lllldbrlur ~.* (c-Ml rdll:lll to lndudlllllldloltolng t!Mienttl D ~~ewvor~~ ..... CJ o.w.go COUIIIIJ 0 t.IIN Mllil l'vlnt Ulllt ft 0 NIM llllllle f>tOinlt Unit n FIIOII: (Z.!&..I2£.. OTHER) ED Appi'OYilll: (Sifln~ture]

GE;Jti~ERAL tNFORMATION tNote: 0 When chldc.ed ll'dl'*- c:hiMe In statue, NOT for D1ace

- - u.u.ge1ranamllild an: (Oilflt lllltnm.t 24 HcNr Clodf v*: A. RECI ..~

[] o.-*

[] NY ..... ; 51848W2GO r;V201 Co.: $11.0150 QtJ111

[] . .,

i : 34N20t II[.Canlrllil *Roam HcllinB a NMP II 2: ~2&COrllrGI~ H~

02. lllis is : A. An AcNal Ema~ (a.) AD!:IIcn:ilo Ol. The Eme~ CLmir~e~tian il:

A. UNUSUAL EVE.'ff ~~E AREA EMERGI:NcY & il.MEROHNcY TERMINATED B. ALERT ENERAL EMERGENCY f . Otha-

04. Thi1 EmciJmqo ClusifiCIIiall de~:IIIRCran; trCNJan wreJ IJimel (daW) *' f1iml:>-24 br clock~

OS. I ~: of RadiD.:ti>-c Mftriai&!Nc wlbc diiNIIIicd even!;

Noltdease Rdaue BELOW £oderl.llimilll Ted111K.I Spel'ific.-.tion D Tb Aln>Oiiph~~~e g Ta W11et C. Ret-e ABO... £ ~rat limilt T<<blli~ll Specif.eati011 c To~ cToWIIer D. ~rel-ftlCIIIiriuewlllllillll

06. The fiJlllnwioll'rof<<<iYe ACdQDJ ate~ to be impletnetMd BICM:II upmctkla'ble:

A. NO NEED,_. Pll0Tt:C11VE ACTJOI'I"'S OII!Side 1he sile ~

lS o lS

{!)EVACtiATI! llld IMPLEMENT tM ICJ PUN for 1M follCPAing ERPAs and

~ rema.iJliq EIU'As MONITOR lbt EMERGENCY AURTSYSTIM 1 2 ~ S 6 7 I 9 10 II l:Z 13 14 IS 16 17 I I 19 ;zo

~*

2:z Zl 24 :z9 1'o'fl]L* Qff1lrE. d rJI((OIIITlfS.SHOuL/l. 'JH1.5J.llU ~EL T£R.JN.PY.'-£ + TM,j.lfJJ.f.&J'A'-f.!Al(QN IS.I:K!I.ad.~M C. SHI!LTER-I:N.rLACE N!CliMPUMIINT lllle Kl PLAN fGr the tollowlna EltPAs llld All mr.inio,a ell'~ )f()NJTOR till £MIJlG£NC'W AL£RT SYSTJtM I 2 l . ' s 7 ll 9 10 11 11 tl 14 IS 16 17 II l!l 20 21 l2 23 24 1S 2:6 27 za 29

07. tALl FGU Brief En:nc {~fiCHU/ desr:~fton henl* NOT Clftlr:lfj Dciaiption I; Oilier SiFi6CIIII lnf~icm Oil Jb!lol;tlot Sr.tlll8: A. OperatiOIIIII ~hllldown ffoa'llf'l Dire at tsllrlt me * ~ mmula)

(dille) (tilllC l4 t. dock) 10 100 I

09. W111d$pced: A. MiJWHour at dcv~on fM(EkYIII:IIl) 010.

Wind Di.ftu:tion: A. (Fnlm) 5 Jill Miletlllour ar el~

~-ll'~iQD 30 ZCJQ Feet: !Cii'OIIIIdl

: : (Eie\oaed)

B. (from) 1SD * ~- 111 ele~'MiCft .112 I_iOI'OWIIdl ou. SUblldy C11W Ele\IIIC!d: I.!DilllliSi - A B c ~ - D ~ *( E l F G t ekP"booe II Iilli Oil.

.INtmt! .dAnl!!;v), DQ kparud By- Ccmnnanicalol's nunc:;

~...,.. any quetliOIII&?"

0 N.wYorll.... D ~Coun11 D Nine ... Point Unllltt [] lllrw Mile Point Unttt:l

J.,..A. FbP8Itlck NUcle*POWifPianlcut81 ~

EVALUATOR'S KEY

-8 of 9-

HANDOUT

The plant was initially operating at 100% power with no equipment out of service.

An earthquake was felt in the Control Room and confirmed with both JAF and Nine Mile Point Unit 2 seismic instrumentation.

The Reactor was manually scrammed five minutes ago.

The following conditions exist now:

o Reactor pressure is 200 psig and lowering.

o Reactor water level is -5 inches and slowly lowering with all available injection sources maximized.

o Drywell pressure is 15 psig and slowly rising.

o A steam leak in the Reactor Building coming from the Reactor Water Cleanup system has been reported.

o Reactor Water Cleanup isolation valves 12MOV-15 and 12MOV-18 have failed to close.

o A team is being assembled to close 12MOV-18 in the field.

Expected completion time for the team is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months from now.

o Reactor Building differential pressure is -0.25" H20.

o No change has been seen in Stack or Reactor Building exhaust radiation levels.

o 200' elevation wind speed is 10 mph from 190°.

o 30' elevation wind speed is 5 mph from 190°.

o Stability class is E.

1. Classify the event and inform the examiner of the classification.

2. Then, complete the Part 1 Notification per EAP-1.1, Offsite Notifications.

This is a time critical JPM. Your time clock starts once you acknowledge this task.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-2 A TASK TITLE : Restore CRD to Normal Al ignment Following A TWS (Ait Path)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 201001 A2 .07 (3.2/3.1)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

- -15 - Minutes

. ?/')~*

SUBMITIED: OPERATIONS REVIEW: , -;<? ~L---~

/ ' (

APPROVED :

CANDIDATE NAME :

JPM Completion D Simulated C8J Performed Location : D Plant cgj Simulator TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 A TASK TITLE: Restore CRD to Normal Alignment Following ATWS (Ait Path)

APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1:8J None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 7-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 A TASK TITLE: Restore CRD to Normal Alignment Following ATWS (Ait Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A None II. REFERENCES A EP-3, Backup Control Rod Insertion B. OP-25, Control Rod Drive Hydraulic System Ill. TOOLS AND EQUIPMENT A None IV. SET UP REQUIREMENTS A Reset to an appropriate IC (IC-66).

B. Ensure the Reactor is scrammed, but RPS is reset.

C. Ensure both CRD pumps are running .

D. Ensure full open CRD Drive Water Pressure Control Valve 03MOV-20.

E. Ensure full closed CRD Cooling Water Pressure Control Valve 03MOV-22.

F. Ensure CRD Flow Control tapeset is run to maximum.

G. Ensure override RD ZAI3FC301 (2), CRD FLOW CONTROLLER- AUTO, is preset at a high value

(>95).

V. EVALUATOR NOTES A The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking ,

place keeping and three-point communication.

VI. TASK CONDITIONS A An ATWS has occurred.

B. Control rods were inserted by raising CRD drive water and cooling water differential pressure.

C. Another operator is assigned Reactor water level control.

-3 of 7-

-CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Perform EP-3 Section 5.15, CRD Hydraulic System Restoration. The procedure has been completed up to step 5.15.4. Secure CRD pump 8 and leave CRD pump A running ."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of EP-3. SAT I UNSAT EP-3.

2. Select the correct section to Selects Section 5.15. SAT I UNSAT perform the task.

Starts at step 5.15.4.

3. IF both CRD pumps are Stops CRD pump 8 by rotating control switch CRITICAL STEP running , THEN shut down one counterclockwise. SAT I UNSAT of the CRD pumps.

4. Establish normal CRD Obtains a controlled copy of OP-25 Section E. SAT I UNSAT Hydraulic System operating values per Section E of OP-25.

EVALUATOR NOTE: JPM steps 8-13 may be performed in any order, but each has the potential to affect CRD parameters established in other steps. JPM steps 11 and 12 should only be graded SAT if the associated parameter is ensured in band at the completion of the JPM. This may require the candidate to re-adjust the associated controls.

-4 of 7-

STEP STANDARD EVALUATION I COMMENT

5. Establish normal CRD system Attempts to adjust tapeset on CRD FLOW CNTRL 03FIC- CRITICAL STEP flow. 301 to lower CRD system flow. SATIUNSAT EVALUATOR NOTE: The tapeset on 03FIC-301 is failed ,

such that the controller will not respond to the operator's adjustments while in AUTO. EN-OP-115 provides guidance for the operator to take manual control of a controller that has failed in automatic.

6. Recognize I report CRD Flow Reports CRD Flow Control Valve failure. SATIUNSAT Control Valve failure.

EVALUATOR NOTE: If candidate asks how to proceed, direct them to make a recommendation and then carry out that recommendation.

7. Places CRD FLOW CNTRL Rotates CRD FLOW CNTRL 03FIC-301 selector clockwise CRITICAL STEP 03FIC-301 in MAN. to MAN. SAT I UNSAT

8. Establish normal CRD system Adjusts knob on CRD FLOW CNTRL 03FIC-301 to establish CRITICAL STEP flow. between 59 and 61 gpm . SAT I UNSAT

9. Establish normal CRD drive Throttles closed CRD Drive Water Motor Operated Pressure CRITICAL STEP water differential pressure. Control Valve 03MOV-20 by rotating control switch SATIUNSAT counterclockwise.

Adjusts 03MOV-20 as required to establish 260 to 270 psid drive water differential pressure.

-5 of 7-

STEP STANDARD EVALUATION I COMMENT

10. Establish normal CRD cooling Fully opens CRD Cooling Water Motor Operated Pressure SAT I UNSAT water valve alignment. Control Valve 03MOV-22 by rotating control switch clockwise.

EVALUATOR CUE: If necessary, report CRD stabilizing valve flow is 6 gpm.

EVALUATOR NOTE: The step below is the last step in EP-3 Section 5.15.

11 . Ensure reference leg backfill is Dispatches operator to ensure reference leg backfill is SAT I UNSAT restored by performing one of restored .

the following :

Slowly open 03CRD-300 EVALUATOR CUE: Report that backfill has been restored (reactor vessel wtr lvl as requested .

backfill sys CRD charging header tie in valve)

Place all Reference Leg Backfill Systems in service per Section D of OP-27A EVALUATOR: Terminate the task at this point.

Task Standard: The CRD system is restored to a normal alignment. The CRD flow controller is operated in manual due to failure of the automatic setpoint tape to respond to changes in operator demand.

-6 of 7-

HANDOUT

An ATWS has occurred.

Control rods were inserted by raising CRD drive water and cooling water differential pressure.

Another operator is assigned Reactor water level control.

Perform EP-3 Section 5.15, CRD Hydraulic System Restoration. The procedure has been completed up to step 5.15.4. Secure CRD pump B and leave CRD pump A running.

-7 of 7-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-2 B TASK TITLE: Restore ESW after injection into RBCLC APPL . TO JPM NUMBER REV: DATE : NRC KIA SYSTEM NUMBER: 400000 A4.01 (3 .1/3.0)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

- Minutes SUBMITTED: _;::z- /L 2 ~ OPERATIONS REVIEW: . ~ <~d::~~

~ 7 APPROVED: ~--"'-"-=----+-----------

CANDIDATE NAME :

JPM Completion 0 Simulated 1:8] Performed Location : 0 Plant 1:8] Simulator ATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : 0 Satisfactory 0 Unsatisfactory COMMENTS : (MANDA TORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 B TASK TITLE: Restore ESW after injection into RBCLC APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Zl None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 B TASK TITLE: Restore ESW after injection into RBCLC APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-21, Emergency Service Water B. OP-40, Reactor Building Closed Loop Cooling Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to IC-67.

B. Place RBCLC pump control switches in PTL.

C. Ensure remote SW22, LIFT LEADS LB-4/LA-6 PER OP-21, is inserted as LIFT.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking , place keeping and three-point communication.

VI. TASK CONDITIONS

1. The plant is shutdown.

2. All RBCLC pumps were placed in Pull to Lock.

3. ESW auto aligned to RBCLC .

4. RBCLC pumps are ready to be returned to service.

5. The implementation section of OP-21 Attachment 3, STATUS CONTROL FORM FOR ESW RESET FOLLOWING INJECTION TO RBCLC, has been performed.

-3 of 8-

- CRITICAL STEP

'NITIATING CUE Inform the candidate, "Restore the ESW system to normal per OP-21 Section F.3."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of OP-21 , Obtains a controlled copy of OP-21 . SAT I UNSAT ESW. Reviews Precautions.

Selects section F.3.

2. Perform Implementation section of Determines implementation section SAT I UNSAT Attachment 3. of Attachment 3 has been completed , per initial conditions.

3. Reset ESW Logic A by depressing Depresses ESW SYS A INJ SIG CRITICAL STEP ESW SYS A INJ SIG RESET RESET pushbutton. SAT I UNSAT pushbutton.

4. Verify white ESW SYS A INJ SIG Observes white ESW SYS A INJ SAT I UNSAT light is off. SIG light is off.

I *5. Reset ESW Logic 8 by depressing ESW SYS 8 INJ SIG RESET Depresses ESW SYS 8 INJ SIG RESET pushbutton.

CRITICAL STEP SAT I UNSAT pushbutton.

6. Verify white ESW SYS 8 INJ SIG Observes white ESW SYS 8 INJ SATIUNSAT light is off. SIG light is off.

-4 of 8-

STEP STANDARD EVALUATION I COMMENT EVALUATOR NOTE: The next 6 valves are throttleable, therefore the control switches must be held in the desired position while the valves re-position. Stroke times are each approximately 30-45 seconds.

7. Close ESW RETURN TO SERV Closes ESW RETURN TO SERV CRITICAL STEP WTR 15MOV-1758. WTR 15MOV-1758 by taking control SATIUNSAT switch CCW to Close.

8. Open ESW SYS 8 TEST VLV Opens ESW SYS 8 TEST VLV CRITICAL STEP 46MOV-1028. 46MOV-1028 by taking control SAT I UNSAT switch CW to Open.

9. Close ESW SYS 8 INJ VLV 46MOV- Closes ESW SYS 8 INJ VLV CRITICAL STEP 1018. 46MOV-1018 by taking control SAT I UNSAT switch CCW to Close.

/ *10. Close ESW RETURN TO SERV Closes ESW RETURN TO SERV CRITICAL STEP WTR 15MOV-175A. WTR 15MOV-175A by taking control SATIUNSAT switch CCW to Close.

11 . Open ESW SYS A TEST VLV Opens ESW SYS A TEST VLV CRITICAL STEP 46MOV-102A. 46MOV-102A by taking control SAT I UNSAT switch CW to Open.

12. Close ESW SYS A INJ VLV 46MOV- Closes ESW SYS A INJ VLV CRITICAL STEP 101A. 46MOV-1 01A by taking control SAT I UNSAT switch CCW to Close.

13. Ensure open 15R8C-41 R8CLC Dispatches operator to ensure open SAT I UNSAT Makeup Tank TK-4 Outlet 15R8C-41 R8CLC Makeup Tank TK-4 Outlet.

EVALUATOR CUE: 15R8C-41 R8CLC Makeup Tank TK-4 Outlet is open.

()

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

14. Start up RBCLC System per Section EVALUATOR CUE: Time SAT I UNSAT D of OP-40. compression will be invoked and another Operator will restore RBCLC.

SIMULATOR OPERATOR ACTION:

Start RBCLC pumps A & B.

Green flag RBCLC pump C.

Inform Candidate RBCLC discharge pressure is stable and > 80 psig.

15. Candidate reads OP-21 Steps EVALUATOR CUE: Inform SAT I UNSAT F.3.14, 15, & 16. Candidate no ESW valves were re-positioned during AOP-11 .

If asked about the position of Breaker 71MCC-152-0D4, report open .

16. WHEN RBCLC discharge header EVALUATOR CUE: OP-21 SAT I UNSAT pressure is stable at GREATER Attachment 3 Restoration section is THAN OR EQUAL TO 80 psig, complete.

perform Restoration section of Attachment 3.

17. Shut down ESW per Subsections Obtains Subsections F.1 and F.2. SAT I UNSAT F.1 and F.2.

18. Verify RBCLC System is in normal Determines RBCLC system is in SAT I UNSAT operation. normal operation.

EVALUATOR CUE: If needed , state that the RBCLC system is in normal operation .

19. Verify EDG A and C are shutdown. Determines EDG A and C are SATIUNSAT shutdown .

~

-6 of 8-

STEP STANDARD EVALUATION I COMMENT I 20. Verify ventilation loads downstream EVALUATOR CUE: Ventilation SAT/UNSAT of 46MOV-101A do not require loads downstream of 46MOV-101A ESW. do not require ESW.

21 . Ensure open ESW SYS A TEST Observes ESW SYS A TEST VLV SAT/UNSAT VLV 46MOV-102A. 46MOV-102A is open .

Red light on, Green light off

22. Ensure closed ESW SYS A INJ VL V Observes ESW SYS A INJ VLV SAT I UNSAT 46MOV-101A 46MOV-101A is closed.

Red light off, Green light on

23. Stop ESW PMP A 46P-2A. Stops ESW PMP A 46P-2A by taking CRITICAL STEP control switch CCW to Stop. SAT I UNSAT EVALUATOR CUE: Another operator will shutdown ESW loop B.

EVALUATOR: Terminate the task at this point.

Task Standard: The ESW logic is reset, ESW valves are aligned in a normal configuration , and ESW pump A is shutdown.

-7 of 8-

HANDOUT

The plant is shutdown.

All RBCLC pumps were placed in Pull to Lock.

ESW auto aligned to RBCLC.

RBCLC pumps are ready to be returned to service.

The implementation section of OP-21 Attachment 3, STATUS CONTROL FORM FOR ESW RESET FOLLOWING INJECTION TO RBCLC, has been performed.

Restore the ESW system to normal per OP-21 Section F.3.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-2 C TASK TITLE : Start First Feedwater Pump APPL . TO JPM NUMBER REV: DATE : NRC KIA-SYSTEM NUMBER: 259001 A4 .02 (3.9/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME :

- -20 - Minutes SUBMITTED : __;;:;c: /L ==:z OPERATIONS REVIEW: ~~:-L /'~

APPROVED : -~JL~~~~---------

CANDIDATE NAME :

JPM Completion D Simulated C8J Performed Location : D Plant C8J Simulator TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 C TASK TITLE: Start First Feedwater Pump APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required [8J None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 9-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 C TASK TITLE: Start First Feedwater Pump APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-2A, Feedwater System Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Plant in a startup condition near 500 psig (IC-68) .

B. Ensure both Feedwater pumps are secured.

C. Ensure 34MOV-100A and 34MOV-100B are closed .

D. Ensure Reactor water level is being maintained in the green band and controlled with 34FCV-137 in AUTO.

E. Place FDWTR screen on EPIC slave 1 monitor.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking ,

place keeping and three-point communication .

VI. TASK CONDITIONS A. A plant startup is in progress.

B. Reactor pressure is approaching 500 psig.

C. Reactor water level is being controlled with 34FCV-137 in AUTO.

-3 of 9-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Start Feedwater pump A per OP-2A Section D.2. The procedure is in progress up to step D.2.18."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-2A. SATIUNSAT OP-2A.

2. Select the correct section to Selects Section D.2 of OP-2A. SAT I UNSAT perform the task.

Proceeds to Step D.2.18.

3. Test RFPT A trip as follows at Depresses A MAN TRIP pushbutton. CRITICAL STEP panel 09-6:

SAT I UNSAT

Depress A MAN TRIP pushbutton.

4. Verify the following : Observes RFPT A LP Stop Valve green light on, red light SAT I UNSAT off.

RFPT A LP AND HP Stop Valves are closed .

Observes RFPT A HP Stop Valve green light on, red light off. I

Annunciator 09-6-4-2 RFPT A TRIP is in alarm.

Observes annunciator 09-6-4-2 is in alarm.

-4 of 9-

STEP STANDARD EVALUATION I COMMENT

5. Reset RFPT A trip as follows Depresses A MAN TRIP RESET pushbutton. CRITICAL STEP at panel 09-6: SAT I UNSAT

Depress AND hold A MAN EVALUATOR NOTE: The candidate should hold the TRIP RESET pushbutton. pushbutton while observing conditions in the next step, but it is only critical that the pushbutton is depressed long enough to reset the trip signal.

6. Verify the following: Observes RFPT A LP Stop Valve green light off, red light SAT/UNSAT on.

RFPT A LP AND HP Stop Valves are open.

Observes RFPT A HP Stop Valve green light off, red light

Annunciator 09-6-4-2 on.

RFPT A TRIP is clear.

Observes annunciator 09-6-4-2 is clear.

7. Release A MAN TRIP RESET Releases A MAN TRIP RESET pushbutton. CRITICAL STEP pushbutton. SAT/UNSAT EVALUATOR CUE: Time compression is in effect. The RFPT A local trip test and reset have been completed SAT per OP-2A steps D.2.20 and D.2.21.

8. Perform RFPT A local trip test Determines RFPT A local trip test has been completed SAT, SAT/UNSAT as follows ... per evaluator cue.

9. Perform RFPT A local trip Determines RFPT A local trip reset has been completed SAT/UNSAT reset as follows ... SAT, per evaluator cue.

-5 of 9-

STEP STANDARD EVALUATION I COMMENT

10. Open 34FWS-16A (rx fdwtr Dispatches operator to open 34FWS-16A. SAT I UNSAT pump A inlet to FCV-137 isol valve) .

EVALUATOR CUE: 34FWS-16A is open.

11 . WHILE performing the Acknowledges procedure step. SAT I UNSAT following steps, maintain RPV water level BETWEEN 197 and 203 inches on 06LI-94A, EVALUATOR CUE: Another operator will monitor Reactor 8, and C. water level and operation of 34FCV-137.

12. Place RFPT A MSC on high Slowly raises RFPT A MTR SPEED CHANGER until RFPT CRITICAL STEP speed stop as follows: A speed begins to rise. SAT I UNSAT IF 34FCV-137 is in automatic (BAL), THEN perform the following :

Slowly raise RFPT A MTR SPEED CHANGER to roll A RFPT.

13. Slowly raise RFPT A MTR Slowly raises RFPT A MTR SPEED CHANGER until high CRITICAL STEP SPEED CHANGER to high speed stop red light illuminates and green light SATIUNSAT speed stop. extinguishes.

14. Continue to raise MSC for at Raises RFPT A MTR SPEED CHANGER for at least 5 SAT I UNSAT least 5 seconds after reaching seconds after high speed stop red light first illuminates and high speed stop to ensure green light extinguishes.

MSC is fully on high speed stop.

-6 of 9-

STEP STANDARD EVALUATION I COMMENT

15. Take control of RFPT A speed Adjusts RFP A FLOW CNTRL 06-84A manual control knob SAT IUNSAT with MGU as follows: a small amount in both the clockwise and counterclockwise Raise and lower RFPT A directions.

speed a small amount by adjusting RFP A FLOW Observes RFPT A speed raises and lowers a small amount.

CNTRL 06-84A manual control knob.

16. IF 34FCV-137 is in automatic May adjust RFP A FLOW CNTRL 06-84A manual control SAT I UNSAT INA (BAL), THEN adjust RFP A knob to raise RFP A discharge pressure.

FLOW CNTRL 06-84A manual control knob to maintain RFP A discharge pressure EVALUATOR NOTE: RFP A discharge pressure will GREATER THAN RPV already be greater than Reactor pressure, therefore no pressure. adjustment is required .

17. Close the following valves: Closes 41 MOV-1 04A by depressing close pushbutton. SAT I UNSAT

RFPT A STOP VLV DRNS Closes 41 MOV-1 07A by depressing close pushbutton.

0 41MOV-104A 0 41MOV-107A Closes 41 MOV-1 08A by depressing close pushbutton.

RFPT A DRNS Closes 41MOV-112A2 by depressing close pushbutton.

0 41MOV-108A 0 41 MOV-112A2 I

-7 of 9-

STEP STANDARD EVALUATION I COMMENT EVALUATOR CUE: 31MOV-103A is NOT required to be open for Main Turbine warming.

18. IF 31MOV-103A is not Observes annunciator 09-6-4-33 is clear. SAT I UNSAT required to be open for main turbine warming, THEN perform the following :

Verify annunciator 09-6-4-33 RFPT A LP STM DRN POT LVL HI is clear.

19. Ensure closed RFPT A LP Closes 31 MOV-1 03A by depressing close pushbutton. SAT I UNSAT STM DRN 31MOV-103A.

EVALUATOR CUE: Another operator will continue with this procedure as actions become necessary.

EVALUATOR: Terminate the task at this point.

Task Standard: Feedwater pump A is running with discharge pressure greater than Reactor pressure.

-8 of 9-

HANDOUT

A plant startup is in progress.

Reactor pressure is approaching 500 psig.

Reactor water level is being controlled with 34FCV-137 in AUTO.

Start Feedwater pump A per OP-2A Section 0.2. The procedure is in progress up to step 0.2.18.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-2 D TASK TITLE: Start EDGs A and C Due to Hurricane Warning APPL. TO JPM NUMBER REV: DATE: NRC KJA SYSTEM NUMBER: 264000 A4 .04 (3.7/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 20 Minutes

--~

SUBMITTED: _::z:-~ '") 1c- OPERATIONS REVIEW: ... ~F::::e; ~

APPROVED: _ __.~-'-"~...:::::;;.___.,~:;..___ _ _ _ _ _ _ __

CANDIDATE NAME:

JPM Completion D Simulated C8] Performed Location: D Plant C8] Simulator TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS: (MANDA TORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 D TASK TITLE: Start EDGs A and C Due to Hurricane Warning APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required [8J None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2of12-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 D TASK TITLE: Start EDGs A and C Due to Hurricane Warning APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-22, Diesel Generator Emergency Power Ill. TOOLS AND EQUIPMENT A. Synch Key IV. SET UP REQUIREMENTS A. Plant in a power operating with Bus 10500 supplied from T-3 (IC-68).

EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly *identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking ,

place keeping and three-point communication .

VI. TASK CONDITIONS A. The National Weather Service has issued a Hurricane Warning for Oswego County.

B. AOP-13 , High Winds, Hurricanes, and Tornadoes, has been entered.

C. AOP-13 Step E.3.9.a requires starting and loading each pair of EDGs.

D. Pre-startup checks have been completed for all EDGs.

E. EDGs have been declared inoperable.

-3 of 12-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Start EDGs A and C per OP-22 Section D.1. Load each EDG to approximately 2600 KW."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-22. SATIUNSAT OP-22.

2. Select the correct section to Selects Section D.1 of OP-22. SAT I UNSAT perform the task.

3. Perform pre-startup checks for Determines pre-startup checks have been completed, per SATIUNSAT EDG A and C per Subsections initial conditions .

G.25 and G.26.

4. IF pre-startup checks are Determines pre-startup checks have NOT been omitted, per SAT I UNSAT omitted ... initial conditions.

5. Simultaneously place the Simultaneously rotates EDG A CONTROL and EDG C CRITICAL STEP following control switches to CONTROL switches clockwise to START. SATIUNSAT START:

EDGACNTRL

EDG C CNTRL

-4 of 12-

STEP STANDARD EVALUATION I COMMENT

6. IF frequency of either EDG Observes EDG A and C frequency stabilize between 58 and SAT I UNSAT does not stabilize BETWEEN 62Hz.

58 and 62 Hz AFTER reaching normal voltage, THEN immediately place the affected EDG CNTRL switch in STOP.

I

7. WHEN approximately 10 Observes EDG A speed is approximately 900 rpm . SAT I UNSAT seconds have elapsed , verify the following:

Observes EDG A frequency is approximately 60 Hz.

EDG A speed is approximately 900 rpm.

EDG A frequency is Observes EDG A voltage is approximately 4.3 KV. I approximately 60 Hz.

EDG A voltage is Observes EDG C speed is approximately 900 rpm.

approximately 4.3 kV.

EDG C speed is approximately 900 rpm . Observes EDG C frequency is approximately 60 Hz.

EDG C frequency is approximately 60 Hz.

EDG C voltage is Observes EDG C voltage is approximately 4 .3 KV.

approximately 4.3 kV.

EDG A & C TIE BKR Observes EDG A & C TIE BKR 10504 green light off, red 10504 is closed .

light on.

ESW Pump 46P-2A is running .

Observes ESW pump 46P-2A green light off, red light on.

-5 of 12-

STEP STANDARD

. EVALUATION I COMMENT

8. Verify the following at panel Dispatches operator to verify conditions at panel 92HV-9A. SAT I UNSAT 92HV-9A:

The following fans indicate EVALUATOR CUE: All verifications for OP-22 step 0 .1.6 running: have been completed SAT.

92FN-1A

92FN-1 C

The following fans indicate stopped:

92FN-2A

92FN-2C

The following annunciators are clear:

HV-9A-7 SUPPLY FAN FN-1A TROUBLE

HV-9A-9 SUPPLY FAN FN-IC TROUBLE

9 . Trip EDG A & C TIE BKR Trips EDG A & C TIE BKR 10504 by rotating control switch CRITICAL STEP 10504, allow switch to spring counterclockwise to TRIP, then releasing switch . SAT I UNSAT return to AUTO.

10. Verify EPIC-D-730 alarmed Observes EPIC-D-730 alarmed and cleared on alarm typer. SAT I UNSAT and cleared on alarm typer.

-6of12-

STEP STANDARD EVALUATION I COMMENT

11. IF 10500 bus is being supplied I Rotates AUTO MANUAL T-3 LTC CONTROL switch SAT I UNSAT by 71T-3, THEN ensure AUTO clockwise to MAN .

MANUAL T-3 LTC CONTROL switch is in MAN .

EVALUATOR ROLE PLAY: If contacted as Power Control, acknowledge T-3 LTC will be taken to manual.

12. Place the following switches in I Places EDG A GOV MODE switch in DROOP. CRITICAL STEP DROOP: SAT I UNSAT

EDG A GOV MODE Places EDG C GOV MODE switch in DROOP.

EDG C GOV MODE

13. Parallel EDG A with 10500 Inserts synch key and rotates EDG A LOAD BKR SYNCH CRITICAL STEP Bus as follows: SW clockwise to ON. SAT I UNSAT Place EDG A LOAD BKR SYNCH SW in ON.

14. Adjust EDG A VOLT REG to Adjusts EDG A VOLT REG to match INCOMING and SAT I UNSAT INA match INCOMING and RUNNING voltage, as necessary.

RUNNING voltage.

15. Adjust EDG A GOV to rotate Adjusts EDG A GOV to establish SYNCHROSCOPE CRITICAL STEP SYNCHRO.SCOPE slowly in rotation slowly in the FAST direction (clockwise). SAT I UNSAT INA the FAST direction (clockwise).

EVALUATOR NOTE: If initial conditions are such that an acceptable rotation is initially present, mark this step NA.

The step is then NOT critical.

-7 of 12-

STEP STANDARD EVALUATION I COMMENT

16. WHEN EDG A and 10500 Bus When SYNCHROSCOPE is at approximately 12 o'clock, CRITICAL STEP are in phase closes EDG A LOAD BKR 10502 by rotating control switch SAT I UNSAT (SYNCHROSCOPE at 12 clockwise.

o'clock), close EDG A LOAD BKR 10502.

17. Adjust EDG A GOV to raise Rotates EDG A GOV control switch clockwise to establish CRITICAL STEP EDG A load 100 to 300 kW. EDG A load 100 to 300 kW, as necessary. SAT I UNSAT INA EVALUATOR NOTE: If initial conditions are such that an acceptable loading is initially present, mark this step NA.

The step is then NOT critical.

18. Place EDG A LOAD BKR Rotates EDG A LOAD BKR SYNCH SW counterclockwise SAT I UNSAT SYNCH SW in OFF and to OFF and removes synch key.

remove synch switch handle.

19. IF A EDG has operated at Determines EDG A has NOT operated less than 520 kW for SAT I UNSAT LESS THAN 520 kW for greater than 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

GREATER THAN 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , THEN perform the following ...

EVALUATOR CUE: If asked, report that EDG A has NOT operated less than 520 kW for greater than 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

-8 of 12-

STEP STANDARD EVALUATION I COMMENT

20. Adjust EDG A GOV to raise Rotates EDG A GOV control switch clockwise to raise EDG CRITICAL STEP EDG A load to LESS THAN A load to approximately 2600 kW in approximately 800 kW SATIUNSAT OR EQUAL TO 2,600 kW over increments.

3 to 5 minutes in approximately 800 kW increments. EVALUATOR CUE: If desired, prompt the candidate that time compression is in effect and one minute has passed.

This cue can be repeated as necessary to complete loading of EDG A.

21 . Parallel EDG C with 10500 Inserts synch key and rotates EDG C LOAD BKR SYNCH CRITICAL STEP Bus as follows: SW clockwise to ON . SATIUNSAT Place EDG C LOAD BKR SYNCH SW in ON.

22. Adjust EDG C VOLT REG to Adjusts EDG C VOLT REG to match INCOMING and SAT I UNSAT INA match INCOMING and RUNNING voltage, as necessary.

RUNNING voltage.

23. Adjust EDG C GOV to rotate Adjusts EDG C GOV to establish SYNCHROSCOPE CRITICAL STEP SYNCHROSCOPE slowly in rotation slowly in the FAST direction (clockwise). SAT I UNSAT INA the FAST direction (clockwise).

EVALUATOR NOTE: If initial conditions are such that an acceptable rotation is initially present, mark this step NA.

The step is then NOT critical.

-9 of 12-

STEP STANDARD EVALUATION I COMMENT

24. WHEN EDG C and 10500 Bus When SYNCHROSCOPE is at approximately 12 o'clock, CRITICAL STEP are in phase closes EDG C LOAD BKR 10512 by rotating control switch SATIUNSAT (SYNCHROSCOPE at 12 clockwise .

o'clock), close EDG C LOAD BKR 10512.

25. Adjust EDG C GOV to raise Rotates EDG C GOV control switch clockwise to establish CRITICAL STEP EDG C load 100 to 300 kW. EDG C load 100 to 300 kW, as necessary. SAT I UNSAT INA EVALUATOR NOTE: If initial conditions are such that an acceptable loading is initially present, mark this step NA.

The step is then NOT critical.

26. Place EDG C LOAD BKR Rotates EDG C LOAD BKR SYNCH SW counterclockwise SATIUNSAT SYNCH SW in OFF and to OFF and removes synch key.

remove synch switch handle.

27. IF C EDG has operated at Determines EDG C has NOT operated less than 520 kW for SATIUNSAT LESS THAN 520 kW for greater than 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

GREATER THAN 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , THEN perform the following ...

EVALUATOR CUE: If asked, report that EDG C has NOT operated less than 520 kW for greater than 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

-10 of 12-

STEP STANDARD EVALUATION I COMMENT

28. Adjust EDG C GOV to raise Rotates EDG C GOV control switch clockwise to raise EDG CRITICAL STEP EDG C load to LESS THAN C load to approximately 2600 kW in approximately 800 kW SAT I UNSAT OR EQUAL TO 2,600 kW over increments.

3 to 5 minutes in approximately 800 kW increments. EVALUATOR CUE: If desired, prompt the candidate that time compression is in effect and one minute has passed.

This cue can be repeated as necessary to complete loading of EDG C.

EVALUATOR CUE: Another operator will complete the remaining portions of OP-22 for startup of EDGs A and C .

EVALUATOR: Terminate the task at this point.

Task Standard: EDGs A and C are running and loaded to approximately 2600 KW.

-11 of 12-

HANDOUT

The National Weather Service has issued a Hurricane Warning for Oswego County.

AOP-13, High Winds, Hurricanes, and Tornadoes, has been entered.

AOP-13 Step E.3.9.a requires starting and loading each pair of EDGs.

Pre-startup checks have been completed for all EDGs .

EDGs have been declared inoperable .

Start EDGs A and C per OP-22 Section 0.1. Load each EDG to approximately 2600 KW.

-12 of 12-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-2 E TASK TITLE : Restore Shutdown Cooling After Isolation , RHR Pump Trips APPL . T O JPM NUMBER REV: DATE : NRC KIA SYSTEM NUMBER: 205000 A4 .01 (3.7/3 .7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

- Minutes SUBMITTED : OPERATIONS REVIEW: -~ -~~c:d;>"' ,~

~ 7 APPROVED :

CANDIDATE NAME :

JPM Completion 0 Simulated ~ Performed Location : 0 Plant ~ Simulator

.TE PERFORMED : TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : 0 Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

\

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 E TASK TITLE: Restore Shutdown Cooling After Isolation, RHR Pump Trips APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1:8:1 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 9-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 E TASK TITLE: Restore Shutdown Cooling After Isolation, RHR Pump Trips APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-30, Loss of Shutdown Cooling Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to a low-power IC (IC-67).

B. Ensure RHR B was initially in Shutdown Cooling lineup with RHR pump B running , but is now isolated by closing valves 25B, 17, and 18.

C. Close 10MOV-12B.

D. Ensure Reactor coolant temperature is above 140°F.

E. Ensure Reactor water level is greater than 215".

F. Ensure EPIC screen RHRB is on a screen near the JPM location.

G. Ensure RHRSW pump B is in service and RHRSW pump D is in standby.

H. Ensure all actions of AOP-30 Attachment 1 are complete up to step 5.G.

I. Ensure the following simulator programming:

Malfunction RH01 :B, RHR Pump B Trip (Trigger 1)

Trigger 1- Event Command : zlo10as35b(2)==1 (code for 10MOV-12B red light on) , Action: None J. Ensure the following tags are hanging:

RHR KEEP-FULL PMP 1OP-2B control switch - in STOP with red tag

MIN FLOW VLV 10MOV-16B control switch- red tag

RHR TEST TORUS CLG & SPRAY 1OMOV-39B - red tag V. EVALUATOR NOTES A. The candidate should , at a minimum, observe the change in equipment status light indication when equipment is operated.

-3 of 9-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 E TASK TITLE : Restore Shutdown Cooling After Isolation, RHR Pump Trips APPL. TO JPM NUMBER B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication .

VI. TASK CONDITIONS A. RHR B was in Shutdown Cooling .

B. A spurious isolation signal caused Shutdown Cooling to isolate.

C. The cause of the isolation signal has been determined and corrected.

-4 of 9-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Restore Shutdown Cooling using RHR pump B per AOP-30 Attachment 1. The procedure has been complete up to step S.G."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of AOP-30 Attachment 1. SAT I UNSAT AOP-30 Attachment 1.

2. IF white HI DW PRESS OR Observes white HI DW PRESS OR LO LVL CLOSE OF SATIUNSAT LO LVL CLOSE OF 1OMOV- 10MOV-25B IN SHUTDOWN CLG 10A-DS85A(B) light is 25A(B) IN SHUTDOWN CLG not lit.

1OA-DS85A(B) light is on, THEN reset logic as follows:

3. Ensure open HX A( B) BYP Observes 1OMOV-668 green light off, red light on. SAT I UNSAT VLV 10MOV-66A(B).

4. Open SHUTDOWN CLG Opens 10MOV-18 by rotating control switch clockwise. CRITICAL STEP SUCT 10MOV-18. SAT I UNSAT

5. Open SHUTDOWN CLG Opens 10MOV-17 by rotating control switch clockwise. CRITICAL STEP SUCT 10MOV-17. SAT I UNSAT I

6. Ensure closed HX A( B) Observes 10MOV-12B green light on, red light off. SAT I UNSAT OUTLET VLV 10MOV-12A(B).

-5 of 9-

STEP STANDARD EVALUATION I COMMENT

7. Ensure RPV water level is Observes Reactor water level is above 215 inches. SATIUNSAT GREATER THAN 215 inches.

8. Start RHR pump that was in Starts RHR pump B by rotating control switch clockwise . CRITICAL STEP service prior to isolation. SAT I UNSAT

9 Open LPCIINBD INJ VLV Opens 1OMOV-258 by rotating control switch clockwise. CRITICAL STEP 1OMOV-25A(B). SAT I UNSAT EVALUATOR NOTE: RHR pump B amps will be just below the red line value. If the candidate identifies this and is looking for direction, report that RHR pump B operation is satisfactory as long current does not exceed red line amps.

EVALUATOR CUE: Direct the candidate to establish Reactor coolant temperature control in a band of 120-140°F using RHR heat exchanger inlet temperature.

10. Establish normal temperature Throttles open 10MOV-12B by rotating control switch CRITICAL STEP control per Section E of OP- clockwise. SAT I UNSAT 130.

EVALUATOR NOTE: When 10MOV-12B red light illuminates, an automatic trigger trips RHR pump B. This initiates an alternate path for the candidate to start RHR pump D to re-establish Shutdown Cooling flow.

-6 of 9-

STEP STANDARD EVALUATION I COMMENT

11. Recognize trip of RHR pump Recognizes trip of RHR pump B. SAT/UNSAT B.

EVALUATOR NOTE: This may include recognizing annunciator 09-3-2-5, RHR pump B indicating light, flow, and/or amps.

EVALUATOR ROLE PLAY: If asked to determine cause of RHR pump B trip, report RHR pump B tripped on overcurrent.

EVALUATOR CUE: If asked how to proceed, direct candidate to make a recommendation for restoring Shutdown Cooling and then carry out that recommendation.

EVALUATOR NOTE: The candidate may use guidance in AOP-30 Attachment 1 or OP-13D section D for starting RHR pump D. Depending on the exact procedural path taken ,

additional steps may be taken (such as re-positioning 10MOV-12B and/or closing 10MOV-15B), but the following two steps are the only critical steps.

-7 of 9-

STEP STANDARD EVALUATION I COMMENT

12. Open SHUTDOWN CLG Opens 10MOV-15D by rotating control switch clockwise to CRITICAL STEP SUCT VLV 10MOV-15D. open. SAT/UNSAT

13. Start RHR pump D. Starts RHR pump D by rotating control switch clockwise to CRITICAL STEP START. SAT I UNSAT EVALUATOR CUE: Another operator will continue actions in the procedure.

EVALUATOR: Terminate the task at this point.

Task Standard: Shutdown Cooling is placed in service on RHR B. RHR pump D is started in response to the trip of RHR pump B.

-8 of 9-

HANDOUT

RHR B was in Shutdown Cooling.

A spurious isolation signal caused Shutdown Cooling to isolate.

The cause of the isolation signal has been determined and corrected.

Restore Shutdown Cooling using RHR pump B per AOP-30 . The procedure has been complete up to step 5.G.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-2 F TASK TITLE : Manually Isolate Reactor Building Ventilation , Low Reactor Building D/P (Ait Path)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 261000 A4 .06 (3.3/3.6)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME : __ 15

__:__ Minutes SUBMITTED: OPERATIONS REVIEW~~

APPROVED :

CANDIDATE NAME:

JPM Completion 0 Simulated C8J Performed Location : 0 Plant C8J Simulator E PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 F TASK TITLE: Manually Isolate Reactor Building Ventilation , Low Reactor Building D/P (Ait Path)

APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items 0 Technical Review 0 Additionallnformation 0 Questions and Answers 0 Validation 0 Procedural Change Required 1:8] None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 11-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 F TASK TITLE: Manually Isolate Reactor Building Ventilation, Low Reactor Building D/P (Ait Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-51A, Reactor Building Ventilation and Cooling System B. OP-20, Standby Gas Treatment System Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to a power operating IC (IC-69).

B. Ensure the following simulator programming:

Malfunction HV03, Secondary Containment Leakage, 50%

Event Trigger 1: Event- zdi11 sgta04(3)==1 &zdi11 sgtb04(3)==1 , Command- imf hv03 10

Event Trigger 29: Event- zdi5as1 (1 )==1 , Command- set ypo:rp02:a=1

Event Trigger 30: Event- zdi5as1 (1 )==1 , Command- set ypo:rp02 :b=1 C. Insert a Reactor scram .

D. Restore Reactor water level above 177".

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication .

VI. TASK CONDITIONS A. A radioactive steam leak has developed in the Reactor Building.

-3 of 11-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Manually isolate the Reactor Building per OP-51A section G.1."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-51A. Refers to section SAT I UNSAT OP-51A. G.1.

2. Ensure SBGT is running per Obtains a controlled copy of OP-20. Refers to section 0 .1 SATIUNSAT OP-20. or 0 .2 or Posted Attachment 3.

EVALUATOR ROLE PLAY: If asked which train of SBGT to start, tell the candidate that either train is fine.

EVALUATOR NOTE: The subsequent JPM steps are written for use of OP-20 sections 0 .1 or 0.2. If the Posted Attachment is used, slightly different verifications will be performed, but there will be no impact on Critical Steps.

3. Ensure open Opens ABOVE(BELOW) EL 369' SUCT 01-125MOV-11(12) CRITICAL STEP ABOVE(BELOW) EL 369' by rotating control switch clockwise to open. SAT I UNSAT SUCT 01-125MOV-11 (12)

4. Ensure open TRAIN A(B) Opens TRAIN A(B) INLET 01-125MOV-14A(B) by rotating CRITICAL STEP INLET 01-125MOV-14A(B) control switch clockwise to open. SATIUNSAT

-4 of 11-

STEP STANDARD EVALUATION I COMMENT

5. Verify the following : Observes white light for AIR HTR 01-125E-5A(B) is on. SAT I UNSAT

White light for AIR HTR 01-125E-5A(B) is on

6.

Red light for AIR HTR 01- Observes red light for AIR HTR 01-125E-5A(B) is on. SAT I UNSAT 125E-5A(B) is on

7.

TRAIN A(B) CLG VLV 01- Observes TRAIN A(B) CLG VLV 01-125MOV-100A(B) SAT I UNSAT 125MOV-100A(B) is closed green light on, red light off.

8.

FN DISCH 01-125MOV- Observes FN DISCH 01-125MOV-15A(B) green light is off, SATIUNSAT 15A(B) is open red light is on .

9.

TRAIN A(B) FN 01-125FN- Observes TRAIN A(B) FN 01-125FN-1A(B) green light is off, SAT I UNSAT 1A(B) is running red light is on.

10. IF standby gas treatment is Determines step is NIA. SAT I UNSAT being placed in service to support any of the following ...

-5 of 11-

STEP STANDARD EVALUATION I COMMENT 11 . IF SGT Train B(A) is Observes TRAIN B(A) CLG VLV 01-125MOV-100B(A) SAT I UNSAT shutdown, THEN perform the green light off, red light on.

following :

Verify open TRAIN B(A)

CLG VLV 01-125MOV-100B(A).

12.

Verify flow rate is 6000 to Observes SGT flow rate. SATIUNSAT 5800 scfm on SGT FLOW 01-125FI-106A.

13. IF RB DIFF PRESS 01- Observes Reactor Building DIP is more negative than -0.25 SAT I UNSAT 125DPI-100A orB indicates inches water.

less negative than -0.25 inches water, THEN ensure SGT Train B is in service per EVALUATOR NOTE: Reactor Building DIP is SAT at this Subsection 0.2. point in the JPM because normal Reactor Building ventilation has not yet been isolated. Once the Reactor Building isolation is performed, Reactor Building DIP will be UNSAT.

EVALUATOR NOTE: The candidate will proceed back to OP-51A step G.1 .2.

-6 of 11-

STEP STANDARD EVALUATION I COMMENT

14. Depress the following Depresses RB VENT ISOL A pushbutton. CRITICAL STEP pushbuttons at panel 09-75: SAT I UNSAT

RB VENT ISOLA

RB VENT ISOL B Depresses RB VENT ISOL B pushbutton. CRITICAL STEP SATIUNSAT EVALUATOR NOTE: The verifications below may be done in any order.

15. Verify isolation per Subsection Proceeds to OP-51A section G.2. SATIUNSAT G.2.

16. Verify the following : Observes 66AOV-100A green light on, red light off. SATIUNSAT

INBD SUPP ISOL 66AOV-1OOA - Closed

17.

OUTBD EXH ISOL Observes 66AOV-101A green light on, red light off. SAT I UNSAT 66AOV-101A- Closed

18.

BELOW EL 369' RECIRC Observes 66AOD-105 green light off, red light on. SAT I UNSAT 66AOD-1 05 - Open

19.

EL 369' RECIRC 66AOD- Observes 66AOD-108 green light off, red light on. SATIUNSAT 108- Open

-7 of 11-

STEP STANDARD EVALUATION I COMMENT

20.

OUTBD SUPP ISOL Observes 66AOV-1008 green light on, red light off. SAT I UNSAT 66AOV-100B- Closed

21.

INBD EXH ISOL 66AOV- Observes 66AOV-101B green light on, red light off. SAT I UNSAT 101 B- Closed

22.

SUPP FN 66FN-5A, 58, Observes 2 of the following fans have green light off, red SAT I UNSAT SC (two of three)- On light on and 1 of the following fans has green light on, red light off:

66FN-5A

66FN-5B

66FN-5C

23.

BELOW EL 369' EXH FN Observes 1 of the following fans have green light off, red SAT I UNSAT 66FN-12A OR 66FN-12B light on and 1 of the following fans has green light on, red

-On light off:

66FN-12A

66FN-12B

24.

EL 369' EXH FN 66FN- Observes 66FN-13A green light on, red light off. SAT I UNSAT 13A AND 66FN-13B- Off Observes 66FN-13B green light on, red light off.

25.

TK EXH FN 66FN Off Observes 66FN-35 green light on, red light off. SAT I UNSAT

-8 of 11-

STEP STANDARD EVALUATION I COMMENT

26.

CRESC SUPP FN 66FN- Observes 1 of the following fans have green light off, red SAT I UNSAT 26A OR 66FN-26B - On light on and 1 of the following fans has green light on, red light off:

66FN-26A

66FN-26B

27.

Standby Gas Treatment- Determines SBGT is still running per OP-20. SAT I UNSAT Running per OP-20

28.

Reactor Building to Observes Reactor Building to atmosphere differential SAT I UNSAT atmosphere differential pressure is less negative than 0.25 in . water gauge.

pressure- (-)0.25 to(-)

2.50 in . water gauge EVALUATOR NOTE: The candidate will now proceed to OP-20 section 0 .1 or 0.2 to start the second train of SBGT.

-9 of 11-

STEP STANDARD EVALUATION I COMMENT

29. Ensure open Opens BELOW(ABOVE) EL 369' SUCT 01-125MOV-12(11) CRITICAL STEP BELOW(ABOVE) EL 369' by rotating control switch clockwise to open. SAT I UNSAT SUCT 01-125MOV-12(11).

30. Ensure open TRAIN B(A) Opens TRAIN B(A) INLET 01-125MOV-14B(A) by rotating CRITICAL STEP INLET 01-125MOV-14B(A). control switch clockwise to open. SAT I UNSAT EVALUATOR CUE: Another operator has verified proper response of Standby Gas Treatment Train B(A) .

EVALUATOR: Terminate the task at this point.

Task Standard: The Reactor Building is isolated and Reactor Building differential pressure is restored with two trains of Standby Gas Treatment in service.

-10 of 11-

HANDOUT

A radioactive steam leak has developed in the Reactor Building.

Manually isolate the Reactor Building per OP-51 A section G.1.

-11 of 11-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE

. S/RO NRC 14-2 G TASK TITLE: Reset Group 2 Isolation , Restore RWCU APPL . TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 223002 A4 .03 (3.6/3.5)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: __ 15

....;__ Minutes SUBMITTED: OPERATIONS REVIEW: ~~~ ~

rr -~7

/"V APPROVED :

CANDIDATE NAME:

JPM Completion D Simulated [gj Performed Location : D Plant [gj Simulator ifE PERFORMED: TIME TO COMPLETE : Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 G TASK TITLE: Reset Group 2 Isolation, Restore RWCU APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items 0 Technical Review 0 Additional Information 0 Questions and Answers 0 Validation 0 Procedural Change Required [gl None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 11-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 G TASK TITLE: Reset Group 2 Isolation, Restore RWCU APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-15 , Isolation Verification and Recovery B. OP-28, Reactor Water Clean-Up System Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to a power operating IC (IC-69).

B. Insert a Reactor scram.

C. Restore Reactor water level above 177".

D. Trip both Recirculation pumps.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. Both Recirculation pumps have tripped .

B. A Reactor scram has been inserted.

C. Reactor water level lowered to 140 inches.

D. Reactor water level has been recovered above 177 inches.

E. Other operators have completed isolation verifications per AOP-15 Attachments 1 & 2.

-3 of 11-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Reset the Group 2 isolation per AOP-15 section G.1 . Then , restore RWCU per OP-28 section G.4.

Establish gravity blowdown flow to the Main Condenser."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of AOP-15. Refers to section SAT I UNSAT AOP-15 . G.1.

2. WHEN it has been determined Continues with procedure. SAT I UNSAT that an undesired release will not occur when isolation is reset, continue with EVALUATOR CUE: If the candidate requests assistance procedure. determining an undesired release will not occur, then inform the candidate "An undesired release will not occur when isolation is reset".

3. Place control switch for OW Rotates control switch for OW FLOOR ORN 20AOV-83 to SAT I UNSAT FLOOR ORN 20AOV-83 in CLOSE.

CLOSE.

4. Place control switch for OW Rotates control switch for OW EQUIP ORN 20AOV-95 to SAT I UNSAT EQUIP ORN 20AOV-95 to CLOSE, then releases .

CLOSE, spring return to AUTO.

-4 of 11-

STEP STANDARD EVALUATION I COMMENT

5. Simultaneously rotate the Simultaneously rotates PCIS VLV RESET switches 16A- CRITICAL STEP following PCIS VLV RESET S32 and 16A-S33 to clockwise positions. SAT I UNSAT switches to both RESET positions, spring return to NORM :

16A-S32 Simultaneously rotates PCIS VLV RESET switches 16A- CRITICAL STEP

16A-S33 S32 and 16A-S33 to counterclockwise positions . SAT I UNSAT EVALUATOR NOTE: These switches may be rotated in either direction first.

6. Restore RWCU System , if Obtains a controlled copy of OP-28. Refers to section G.4 SATIUNSAT necessary, per Section G of per initiating cue.

OP-28.

7. IF boron was injected per the Determines no boron has been injected. SAT I UNSAT EOPs, THEN Subsection G.4 cannot be performed.

EVALUATOR CUE: If asked about boron injection, report that no boron has been injected. *

8. Ensure Subsection G.1 is Indicates need to ensure Subsection G .1 is complete . SATIUNSAT complete.

EVALUATOR CUE: OP-28 sections G .1 and G.2 have been completed by another operator.

-5 of 11-

STEP STANDARD EVALUATION I COMMENT

9. Ensure one of the following Determines RWCU pump A is the preferred pump to isolate. SAT I UNSAT RWCU pumps is isolated by performing one of the following : EVALUATOR NOTE: A note in OP-28 identifies RWCU pump A as the preferred pump to isolate.

EVALUATOR CUE: If asked about which pump to isolate, direct the candidate to isolate RWCU pump A.

10. IF RWCU Pump A will be the Directs operator to close valves to isolate RWCU pump A. SAT/UNSAT isolated pump, THEN ensure closed the following valves:

12RWC-19A (RWCU pump EVALUATOR CUE: OP-28 step G.4.3.a has been A suet inner isol valve) completed to isolate RWCU pump A.

12RWC-73A (RWCU pump A suet outer isol valve)

12RWC-29A (RWCU pump A disch isol valve)

12RWC-87A (outlet block valve 12FE-20A)

12RWC-38A (RWCU pump A disch check valve RWC-28A bypass valve) 11 . Reset isolation per AOP-15, if Determines isolation has been reset per AOP-15 . SAT/UNSAT necessary.

-6 of 11 -

STEP STANDARD EVALUATION I COMMENT

12. Ensure closed 12RWC-63 Directs operator to ensure closed 12RWC-63. SATIUNSAT (RWCU return line manual isol valve) .

EVALUATOR CUE: 12RWC-63 is closed.

13. Open CLN UP SUCT 12MOV- Opens 12MOV-15 by rotating control switch clockwise to CRITICAL STEP

15. OPEN . SATIUNSAT

14. Open CLN UP SUCT 12MOV- Opens 12MOV-18 by rotating control switch clockwise to CRITICAL STEP

18. OPEN . SAT I UNSAT

15. Ensure seal purge flow rate as Directs operator to establish seal purge flow for RWCU SATIUNSAT follows: pump A.

IF seal purge flow is for 12P-1B only, THEN throttle EVALUATOR CUE: RWCU pump seal purge is 2 gpm.

12RWC-88B as necessary (bypass regulating valve 12P-1B) to establish a flow rate BETWEEN 1.8 and 2.2 gpm as indicated on 12FI-20 (RWCU pumps mini purge flow indic).

16. Ensure ST-26J , Heatup and Acknowledges cue. SAT I UNSAT Cooldown Temperature Checks, is in progress prior to establishing blowdown flow. EVALUATOR CUE: Another operator is performing ST-26J .

-7 of 11 -

STEP STANDARD EVALUATION I COMMENT

17. Slowly establish a gravity Proceeds to OP-28 section G.5. SAT I UNSAT blowdown flow rate of LESS THAN OR EQUAL TO 30 gpm per Subsection G.5.

18. Direct RP to ensure posting Directs RP to ensure posting requirements are met to SAT I UNSAT requirements are met to support the blowdown operation.

support the blowdown operation.

EVALUATOR CUE: RP reports that posting requirements are met.

19. IF reactor coolant temperature Determines Reactor coolant temperature is greater than . SAT I UNSAT is LESS THAN 212°F, THEN 212°F.

ensure RPV is vented to prevent drawing a vacuum inside RPV.

20. At the discretion of the Shift Acknowledges cue. SAT I UNSAT Manager, contact the Reactor Analyst prior to commencing blowdown to turn off core EVALUATOR CUE: The Shift Manager directs continuing thermal monitoring. with the procedure prior to contacting the Reactor Analyst.

I 21 . IF RPV pressure is GREATER Observes 12MOV-53 green light on, red light off. SAT I UNSAT THAN 50 psig, THEN ensure closed SLOWDOWN ORIFICE BYP 12MOV-53.

-8 of 11-

STEP STANDARD EVALUATION I COMMENT

22. IF RPV pressure is LESS Determines RPV pressure is greater than 50 psig. SAT I UNSAT THAN 50 psig, THEN open SLOWDOWN ORIFICE SYP 12MOV-53. !

23. IF RWCU pumps trip during Acknowledges step. SATIUNSAT blowdown operation to the condenser, THEN perform the following ...

24. IF initiating a blowdown Determines blowdown flow will be to the Main Condenser, SAT I UNSAT following a RWCU pump trip not the WCT, per initiating cue.

and manual system isolation, THEN perform gravity blowdown to WCT starting at Step G.5.9 ...

25. IF blowdown is to be routed to Observes 12MOV-57 green light on, red light off. SAT I UNSAT the Main Condenser, THEN perform the following:

Ensure closed SLOWDOWN TO RADW 12MOV-57.

26. Open SLOWDOWN Opens 12MOV-56 by rotating control switch clockwise to CRITICAL STEP TO MAIN CNDSR 12MOV-56. OPEN. SAT I UNSAT

27. IF blowdown is to be routed to Determines blowdown flow will be to the Main Condenser, SATIUNSAT the Waste Collector Tank, not the WCT, per initiating cue.

THEN perform the following ...

-9 of 11-

STEP STANDARD EVALUATION I COMMENT

28. Establish blowdown flow as Directs operator to ensure closed 12RWC-63 or determines SAT I UNSAT II follows: it is closed from earlier cue.

IF gravity blowdown will be used, THEN perform the EVALUATOR CUE: If asked, report that 12RWC-63 is following: closed.

Ensure closed 12RWC-63 (RWCU return line manual isol valve) .

29. Throttle open FILTER DEMIN Throttles open 12MOV-74 by rotating control switch CRITICAL STEP BYP 12MOV-74 until red open clockwise to OPEN .

light comes on (dual position SAT I UNSAT indication).

30. Adjust CLN UP SLOWDOWN Throttles open 12FCV-55 by rotating potentiometer CRITICAL STEP FLOW CNTRL 12FCV-55 until clockwise. SAT I UNSAT desired blowdown flow rate is established.

EVALUATOR: Terminate the task at this point.

Task Standard: PC IS Group 2 isolation is reset. RWCU gravity blowdown flow to the Main Condenser is established.

-10 of 11-

HANDOUT

Both Recirculation pumps have tripped.

A Reactor scram has been inserted.

Reactor water level lowered to 140 inches.

Reactor water level has been recovered above 177 inches.

Other operators have completed isolation verifications per AOP-15 Attachments 1 & 2.

Reset the Group 2 isolation per AOP-15 section G.1. Then, restore RWCU per OP-28 section G.4. Establish gravity blowdown flow to the Main Condenser.

-11 of 11-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-2 H TASK TITLE: Perform Rod Worth Minimizer On-Line Diagnostic Test APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 201006 A4 .02 (2.9/2.9)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME :

- -10 - Minutes SUBMITTED: OPERATIONS REVIEW:~~~~

7~1 APPROVED :

CANDIDATE NAME:

JPM Completion D Simulated ~ Performed Location : D Plant ~ Simulator TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 H TASK TITLE: Perform Rod Worth Minimizer On-Line Diagnostic Test APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required r8l None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 7-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 H TASK TITLE: Perform Rod Worth Minimizer On-Line Diagnostic Test APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A None II. REFERENCES A ST-20A, Rod Worth Minimizer Functional Test Ill. TOOLS AND EQUIPMENT A None IV. SET UP REQUIREMENTS A Plant in cold shutdown condition (IC-70).

B. Ensure the Rod Worth Minimizer is initialized.

C. Insert malfunction RW01 .

D. Bypass the Rod Worth Minimizer E. Delete malfunction RW01 .

F. Prepare a copy of ST-20A marked up to step 8.2.

V. EVALUATOR NOTES A The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A The plant is in cold shutdown.

B. Preparations are underway for a Reactor startup.

C. ST-20A, Rod Worth Minimizer Functional Test, is in progress.

D. This is the first time initializing the Rod Worth Minimizer below the Low Power Alarm Point.

-3 of 7-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Perform the Rod Worth Minimizer on-line diagnostic test per ST-20A section 8.2."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of ST-20A from evaluator. Refers SAT I UNSAT ST-20A. to section 8.2.

EVALUATOR: Provide a working copy of ST-20A.

2. Ensure NORMAL BYPASS Rotates NORMAL BYPASS keylock switch clockwise to CRITICAL STEP keylock switch is in NORMAL. NORMAL. SAT I UNSAT

3. Verify MANUAL BYPASS light Observes MANUAL BYPASS light is off. SAT I UNSAT is off.

4. Perform Steps 8.2.4 through Acknowledges step. SAT I UNSAT 8.2.5A without delay.

5. Initialize RWM as follows: Depresses SYSTEM INITIALIZE PUSHBUTTON. CRITICAL STEP SAT I UNSAT Depress and hold SYSTEM EVALUATOR NOTE: This pushbutton is only required to INITIALIZE pushbutton. be held long enough to obtain successful system initialization for purposes of the critical step.

-4 of 7-

STEP STANDARD EVALUATION I COMMENT

6. Verify SYSTEM INITIALIZE Observes SYSTEM INITIALIZE light is on. SAT/UNSAT light is on .

7. IF RWM operator panel AUTO Acknowledges cue. SAT/UNSAT light is on, OR first time initializing RWM below Low Power Alarm Point, RWM EVALUATOR CUE: If asked, "RWM OPERABLE ON" has operator panel AUTO light Off, printed out on the alarm typer.

THEN verify "RWM OPERABLE ON" prints out on alarm typer.

8. Release SYSTEM INITIALIZE Releases SYSTEM INITIALIZE pushbutton. CRITICAL STEP pushbutton. SAT/UNSAT

9. Verify SYSTEM INITIALIZE Observes SYSTEM INITIALIZE light is off. SAT/UNSAT light is off.

10. IF INOP/RESET light is on, Depresses INOP/RESET pushbutton CRITICAL STEP THEN perform the following: SAT/UNSAT

Depress INOP/RESET pushbutton.

11 .

Verify all associated lights Observes INOP/RESET light is off. SAT/UNSAT go off.

-5 of 7-

STEP STANDARD EVALUATION I COMMENT

12. IF AUTO light on RWM Observes AUTO light is off on RWM operator panel. SAT I UNSAT operator panel is off THEN Perform on-line diagnostic test as follows:

13. Depress SYSTEM Depresses SYSTEM DIAGNOSTIC pushbutton. CRITICAL STEP DIAGNOSTIC pushbutton to SAT I UNSAT start diagnostic routine.

I

14. Verify WITHDRAW BLOCK Observes WITHDRAW BLOCK and INSERT BLOCK lights SAT I UNSAT and INSERT BLOCK lights go go on and off sequentially multiple times.

on and off sequentially at least five times.

15. Depress SYSTEM Depresses SYSTEM DIAGNOSTIC pushbutton. CRITICAL STEP DIAGNOSTIC pushbutton to SATIUNSAT stop diagnostic routine.

EVALUATOR: Terminate the task at this point.

Task Standard: The Rod Worth Minimizer is un-bypassed, initialized, and the system diagnostic test is performed.

-6 of 7-

HANDOUT

The plant is in cold shutdown.

Preparations are underway for a Reactor startup.

ST -20A, Rod Worth Minimizer Functional Test, is in progress.

This is the first time initializing the Rod Worth Minimizer below the Low Power Alarm Point.

Perform the Rod Worth Minimizer on-line diagnostic test per ST -20A section 8.2.

-7 of 7-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE

{~ S/RO 14-2 NRC I TASK TITLE: Vent Torus to Lower Primary Containment

. i APPL. TO JPM NUMBER Pressure REV: DATE: NRC KIA SYSTEM NUMBER: 295010 AA1 .05 (3.1/3.4)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

- Minutes SUBMITTED: OPERATIONS REVIEW~>~

APPROVED :

CANDIDATE NAME :

JPM Completion [8J Simulated D Performed Location : [8J Plant D Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : D Satisfactory D Unsatisfactory (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-2 NRC I TASK TITLE: Vent Torus to Lower Primary Containment APPL. TO JPM NUMBER Pressure Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update By:

Date lnt Previous Revision Date:

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-2 NRC I TASK TITLE: Vent Torus to Lower Primary Containment APPL. TO JPM NUMBER Pressure I. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed .

II. REFERENCES A. EP-6, POST ACCIDENT CONTAINMENT VENTING AND GAS CONTROL Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Current copy of EP-6 including Attachment 1.

V. EVALUATOR NOTES A. The candidate should, at a minimum , observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking , placekeeping and three-point communication .

VI . TASK CONDITIONS A. Conditions have occurred which require venting the containment.

B. The EOPs have been entered.

C. Action to preclude the failure of containment must be completed.

D. One train of SGT is in service. The other train of SGT is secured.

E. Containment purge is NOT in progress.

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Vent the Torus using EP-6, SectionS.? "Venting Containment" . Start at step 5.7.6."

NOTE: Unless otherwise noted, all controls are located on Panel 27PCP in the Relay Room .

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of procedure Obtains a controlled copy of procedure and proceeds to SAT/UNSAT EP-6. the PCP panel in the Relay Room.

EVALUATOR: A controlled copy of the procedure is available at the PCP panel. Evaluator to provide working copy.

2. Reviews prerequisites, precautions and Reviews applicable portions of procedure. SAT I UNSAT special instructions associated with the procedure.

3. Selects section 5.7, Venting Selects the correct section of the procedure to be SAT/UNSAT Containment. performed.

4. NOTE: Reviews Note and selects step 5.7.6 to perform as SAT/UNSAT Steps 5.7.6 and 5.7.7 may be directed.

performed and repeated in any order to alternate between torus and drywell venting . Torus venting is preferred.

STEP STANDARD EVALUATION I COMMENT

5. {Step 5.7.6) Verifies Torus pressure is less than PCPL and Torus SAT I UNSAT IF Torus will be vented THEN perform level is less than 29.5 ft.

the following:

Verify torus pressure is LESS THAN PCPL

Verify primary containment water EVALUATOR CUE: When candidate locates indication level is LESS THAN 29.5 feet. of pressure and level, inform the candidate that Torus Pressure is 50 psig and Primary Containment Water

While venting torus, frequently Level is 29.0 ft.

monitor torus pressure and primary containment water level.

IF primary containment water level reaches 29.5 feet while venting the torus, THEN vent drywell per Step 5.7.7.

{Step 5.7.6.D) Candidate places TORUS EXH INNER BYP VLV CRITICAL STEP

Open TORUS EXH INNER BYP 27MOV-117 control switch to the OPEN position.

SAT/UNSAT VLV 27MOV-117.

EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.

{Step 5.7.6.E) Candidate places TORUS EXH OUTER BYP VLV CRITICAL STEP

Open TORUS EXH OUTER BYP 27MOV-123 control switch to the OPEN position.

SAT/UNSAT VLV 27MOV-123.

EVALUATOR CUE: When candidate indicates placing the control switch to open , inform the candidate that the green light is off, red light is on .

STEP STANDARD EVALUATION I COMMENT

5. cont. (Step 5.7.6.F) For each valve, candidate locates its red/green position SAT I UNSAT

Ensure closed the following valves: lights and indicates it should be closed .

0 OW EXH OUTER BYP VLV 27MOV-113.

EVALUATOR CUE: When candidate inquires about 0 OW EXH INNER BYPASS VLV light status, inform the candidate the green light is on, 27MOV-122. red light is off.

0 OW EXH INNER ISOL VLV 27AOV-113.

0 OW EXH OUTER ISOL VLV 27AOV-114.

EVALUATOR CUE: After 27MOV-117 & 123 are open ,

inform the candidate that the control room has called to inform the candidate that Primary Containment Water Level is 30 ft.

6. (Step 5.7.6.C) Candidate refers to section 5.7.7 SAT I UNSAT IF primary containment water level reaches 29.5 feet while venting the torus, THEN vent drywell per Step EVALUATOR CUE: If candidate wants direction from 5.7.7. the control room , inform the candidate that for the purposes of this JPM, no further guidance can be given.

STEP STANDARD EVALUATION I COMMENT

7. (Step 5. 7. 7) Verifies Torus pressure is less than PCPL. SAT I UNSAT IF drywell will be vented , THEN perform the following :

Verify torus pressure is BELOW EVALUATOR CUE: When candidate locates indication PCPL of pressure and level, inform the candidate that Torus Pressure is 50 psig and Primary Containment Water

. Level is 30.0 ft

(Step 5.7.7.8) Candidate places DW EXH OUTER BYP VLV 27MOV- CRITICAL STEP

Open DW EXH OUTER BYP VLV 113 control switch to the OPEN position.

SAT I UNSAT 27MOV-113 EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.

(Step 5.7.7.C) Candidate places DW EXH INNER BYPASS VLV CRITICAL STEP

Open DW EXH INNER BYPASS 27MOV-122 control switch to the OPEN position.

SATIUNSAT VLV 27MOV-122.

EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.

L _ _ _ _ ___

STEP STANDARD EVALUATION I COMMENT 7 cont. (Step 5.7.7.D)

Ensure closed the following valves :

0 TORUS EXH INNER Candidate places TORUS EXH INNER BYP VLV CRITICAL STEP

BYP VLV 27MOV-117 27MOV-117 control switch to the CLOSE position.

SAT I UNSAT EVALUATOR CUE: When candidate indicates placing the control switch to close, inform the candidate that the green light is on , red light is off.

i 0 TORUS EXH OUTER Candidate places TORUS EXH OUTER BYP VLV CRITICAL STEP

BYP VLV 27MOV-123 27MOV-123 control switch to the CLOSE position.

SAT I UNSAT EVALUATOR CUE: When candidate indicates placing the control switch to close, inform the candidate that the green light is on, red light is off.

0 TORUS EXH INNER For each valve, candidate locates its red/green position SAT I UNSAT ISOL VLV 27AOV-117 lights and indicates it should be closed.

0 TORUS EXH OUTER ISOL VLV 27AOV-118 EVALUATOR CUE: When candidate inquires about light status, inform the candidate the green light is on, red light is off.

STEP STANDARD EVALUATION I COMMENT

8. (Step 5.7.7.E} Contacts control room and requests direction on vent SAT I UNSAT

IF it becomes necessary to raise rate .

vent rate, AND torus pressure is LESS THAN PCPL, THEN attempt EVALUATOR CUE: When candidate requests direction to open the following valves: for vent rate, respond that current rate of pressure 0 OW EXH INNER ISOL VLV reduction is acceptable.

27AOV-113 0 OW EXH OUTER ISOL VLV 27AOV-114

9. (Step 5.7.7.F} Contacts the control room on the status of containment SAT/UNSAT

IF containment purge is not in purge .

progress, THEN cycle one or more of the following valves as necessary to control drywell pressure. Verify EVALUATOR CUE: When candidate inquires as to the torus pressure is LESS THAN PCPL status of containment purge, inform the candidate that it before opening any valve: is NOT in progress.

0 OW EXH OUTER BYP VLV 27MOV-113 0 OW EXH INNER BYPASS VLV 27MOV-122 0 OW EXH INNER ISOL VLV 27AOV-113 0 OW EXH OUTER ISOL VLV 27AOV-114 EVALUATOR: Terminate the JPM at this point.

HANDOUT

Conditions have occurred which require venting the containment.

The EOPs have been entered.

Action to preclude the failure of containment must be completed .

One train of SGT is in service. The other train of SGT is secured.

Containment purge is NOT in progress.

Vent the Torus using EP-6, Section 5.7 "Venting Containment". Start at step 5.7.6.

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC14-2J TASK TITLE : Line-up SLC Test Tank for Injection APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 295031 EA1 .08 (3 .8/3 .9)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME : _ 15

____..;:....... Minutes SUBMITTED: ~ ~ ---~< ~ OPERATIONS REVIEW: . ~~ / ~ ~ 7~

CA"'

~ I APPROVED : -~db~~=-~-----------------

CANDIDATE NAME:

JPM Completion 1:8J Simulated 0 Performed Location : 1:8J Plant 0 Simulator ITE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC . COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-2 J TASK TITLE: Line-up SLC Test Tank for Injection APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Z1 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-2 J TASK TITLE: Line-up SLC Test Tank for Injection APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-8, Alternate Injection Systems Ill. TOOLS AND EQUIPMENT A. Flashlight.

IV. SET UP REQUIREMENTS A. Obtain Shift Managers/Control Room Supervisors permission prior to performing this task.

B. Obtain a controlled copy of EP-8 prior to performing this task.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication .

VI. TASK CONDITIONS A. Operation of Alternate Injection Systems is required due to a LOCA.

B. The SLC system is to be utilized as an injection source.

C. The SLC system is to be aligned to use the test tank with the Demineralized Water System and the Fire System as the source of injection water supply.

-3 of 8-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Align the SLC test tank for injection into the RPV using both the Demineralized Water and Fire Protection Systems as water sources per EP-8 Section 5.12."

STEP STANDARD EVALUATION I COMMENT

1. Obtains a controlled copy of The candidate determines where to obtain a controlled copy SAT I UNSAT the procedure EP-8 and of EP-8. (Control Room , Merlin , EOP cabinet) selects section 5.12.

EVALUATOR: Provide candidate a current copy of EP-8 section 5.12.

2. Proceeds to Reactor Building Proceeds to the Reactor Building 326' elevation to the SLC SAT I UNSAT 326' elevation to the SLC Skid.

Skid.

3. (Step 5.12.1.A} Simulates unlocking 11 SLC-11 . CRITICAL STEP Close 11 SLC-11 (SLC tank SAT I UNSAT TK-1 outlet isol valve).

EVALUATOR CUE: The indicated valve is unlocked.

Simulates closing 11 SLC-11 by rotating valve operator clockwise until motion stops.

EVALUATOR CUE: The indicated valve operator has rotated in the indicated direction and come to a stop.

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

4 . (Step 5.12.1.8) Simulates unlocking 11 SLC-41 . CRITICAL STEP Open 11 SLC-41 (SLC test SAT/UNSAT tank TK-3 outlet isol valve) . EVALUATOR CUE: The indicated valve is unlocked.

Simulates opening 11 SLC-41 by rotating valve operator counterclockwise.

EVALUATOR CUE: The indicated valve operator has rotated in the indicated direction.

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

5. (Step 5.12.1.C) Simulates opening 11 SLC-29 by rotating valve operator CRITICAL STEP Station an operator at 11 TK-3 counterclockwise. SAT I UNSAT (standby liquid control test tank) to establish and maintain EVALUTOR CUE: If the candidate attempts to station 11TK-3 at least 112 full using another operator for this step, direct them to perform the one or both of the following required manipulation(s) themselves.

sources of makeup water:

EVALUATOR CUE: The indicated valve operator has

Demin-water: By opening rotated in the indicated direction. If lineup has been 11 SLC-29 (SLC test tank performed correctly, report that water is flowing into the TK-3 demin water addition test tank and the tank is filling slowly.

isol valve)

Simulates uncoiling fire hose (located west of SLC tank) and CRITICAL STEP

Fire system water: Using a placing nozzle into the test tank. SAT I UNSAT fire hose EVALUATOR CUES: The hose is uncoiled. The hose nozzle is in the test tank.

Simulates opening hose rack isolation valve and using the bail handle to open the nozzle.

EVALUATOR CUES: Water is flowing from the hose nozzle. The test tank is filling more rapidly.

-6 of 8-

STEP STANDARD EVALUATION I COMMENT

6. (Step 5.12.1.D) Observes test tank water level. CRITICAL STEP WHEN 11TK-3 is at least 112 SAT I UNSAT full , place SLC pump switch in EVALUATOR CUE: After the fire hose is filling the tank, START SYS-A OR START inform the candidate that the tank is more than % full.

SYS-8 .

Simulates contacting the Control Room to start an SLC pump.

EVALUATOR CUE: The Control Room has started SLC pump A

7. Monitors SLC test tank water Continues to observe SLC test tank water level. SAT I UNSAT level while injecting.

EVALUATOR: Term inate the task at this point.

Task Standard: An SLC pump is running with suction from the SLC test tank. The SLC test tank is aligned for injection of both Demineralized water and Fire water to the RPV.

-7 of 8-

HANDOUT

Operation of Alternate Injection Systems is required due to a LOCA.

The SLC system is to be utilized as an injection source.

The SLC system is to be aligned to use the test tank with the Demineralized Water System and the Fire System as the sources of injection water supply.

Align the SLC test tank for injection into the RPV using both the Demineralized Water and Fire Protection Systems as water sources per EP-8 Section 5.12.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-2 NRC K TASK TITLE : Electrically Disarm a CRD HCU APPL . TO JPM NUMBER REV: DATE : NRC KIA SYSTEM NUMBER: 201003 A2 .02 (3.7/3.8)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

- -15 - Minutes SUBMITTED:

APPROVED :

CANDIDATE NAME:

JPM Completion 0 Simulated 0 Performed Location : 0 Plant 0 Simulator

.TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION : 0 Satisfactory 0 Unsatisfactory COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE :

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO 14-2 NRC K TASK TITLE: Electrically Disarm a CRD HCU APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items 0 Technical Review 0 Additionallnformation 0 Questions and Answers 0 Validation 0 Procedural Change Required 1:8:1 None Comments:

urrent Update: By:

Date Int.

Previous Revision Date:

-2 of 7-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO 14-2 NRC K TASK TITLE: Electrically Disarm a CRD HCU APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-25, Control Rod Drive Hydraulic System Ill. TOOLS AND EQUIPMENT A. Flashlight IV. SET UP REQUIREMENTS A. Provide a working copy of OP-25.

EVALUATOR NOTES A. The candidate should, at a minimum , observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking ,

place keeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. Control rod 22-19 was fully withdrawn , but would not couple.

C. The rod has been fully inserted and its HCU has been valved out.

D. The rod must be electrically disarmed.

-3 of 7-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Electrically disarm control rod 22-19 per OP-25 Section G.21."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of The candidate determines where to obtain a controlled copy SATIUNSAT OP-25. of OP-25. (Control Room, Merlin)

EVALUATOR: Provide candidate a current copy of OP-25.

2. Review precautions and Reviews precautions and selects section G.21. SAT I UNSAT selects correct section.

3. (Step G.21.1) Notifies Control Room that CRD 22-19 will be electrically SAT I UNSAT Notify Control Room that CRD disarmed .

22-19 will be electrically disarmed. EVALUATOR CUE: Acknowledge communication.

-4 of 7-

STEP STANDARD EVALUATION I COMMENT

4. (Step G.21.2) . Simulates unplugging amphenol connector from 03SOV-120 CRITICAL STEP Unplug amphenol connector at HCU 22-19. SAT I UNSAT from each of the following solenoid operated valves at HCU 22-19 and control per EVALUATOR CUE: The indicated connector has been AP-12 .06. unplugged.

03SOV-120(*) (withdraw settle solenoid operated valve)

5. (Step G.21.2) Simulates unplugging amphenol connector from 03SOV-121 CRITICAL STEP

03SOV-121 (*)(insert at HCU 22-19. SAT I UNSAT exhaust water solenoid operated valve)

EVALUATOR CUE: The indicated connector has been unplugged .

6. (Step G.21.2) Simulates unplugging am phenol connector from 03SOV-122 CRITICAL STEP

03SOV-122(*) (withdraw at HCU 22-19. SAT I UNSAT drive water solenoid operated valve)

EVALUATOR CUE: The indicated connector has been unplugged.

7. (Step G.21.2) Simulates unplugging amphenol connector from 03SOV-123 CRITICAL STEP at HCU 22-19.

03SOV-123(*) (insert drive SAT I UNSAT water solenoid operated valve) EVALUATOR CUE: The indicated connector has been I i I

I unplugged.

I

-5 of 7-

STEP STANDARD EVALUATION I COMMENT

8. (Step G.21.3) Notifies Control Room that CRD 22-19 has been electrically SAT/UNSAT disarmed.

Notify Control Room that CRD 22-19 has been electrically disarmed. EVALUATOR CUE: Acknowledge communication .

EVALUATOR: Terminate the task at this point.

Task Standard: Control rod 22-19 is electrically disarmed .

-6 of 7-

HANDOUT

The plant is operating at 100°/o power.

Control rod 22-19 was fully withdrawn, but would not couple.

The rod has been fully inserted and its HCU has been valved out.

The rod must be electrically disarmed.

Electrically disarm control rod 22-19 per OP-25 Section G.21.

-7 of 7-

Appendix D Scenario Outline Form ES-D-1 Facility: James A Fitzpatrick Scenario No. : NRC-1 Op-Test No.: 14-2 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 90% power. RCIC is out of service for maintenance. Torus cooling is in service on RHR loop A Turnover: Secure Torus cooling per OP-13B sections F.1 and F.7.

Event Malf. Event Event No. No. Type* Description N- Shutdown Torus Cooling 1 N/A BOP, SRO OP-13B RHRSW Pump A Trip 2 SW04:A C-SRO ARP 09-3-1-25, Technical Specifications 1-ATC, APRM B Fails Upscale 3 NM14:B SRO OP-16, ARP 09-5-1-4 I-BOP, HPCIInadvertent Initiation 4 HP05 SRO AOP-77, AOP-32, Technical Specifications C-BOP FW05:A Feedwater Pump A High Vibration and Pump Trip 5 R-ATC ,

FW01 :A SRO ARP 09-6-4-11, AOP-41 RR15:A Loss of Coolant Accident 6 M-All MS02:A EOP-2, EOP-4 FW01 :B Feedwater Pump B Trip, HPCI Trip 7 C-All HP02 EOP-2 ED43 :A Loss of Offsite Power 8 C-All ED43 :B AOP-72

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No. : NRC-1 Op-Test No.: 14-2

1. Total malfunctions (5-8) 7 Events 2, 3, 4, 5, 6, 7, 8

2. Malfunctions after EOP entry (1-2) 2 Events 7 & 8

3. Abnormal events (2-4) 3 Events 3, 4, 5

4. Major transients (1-2) 1 Event 6

5. EOPs entered/requiring substantive actions (1-2) 2 EOP-2, EOP-4

6. EOP contingencies requiring substantive actions (0-2) 2 EOP-2 Alt Level Leg, EOP-2 Emergency Depress Leg

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1 : Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4.

CT-2: Given a coolant leak, a loss of high pressure injection systems, and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization before Reactor water level lowers below -19", in accordance with EOP-2.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT

~~

LOI14-2 NRC EXAMINATION SCENARIO 1

~------------------------------------------------------------~

TITLE: LOI14-2 NRC EXAMINATION SCENARIO 1 SCENARIO NUMBER: NRC 1 PATH: STAND ALONE Validation: ...:z:-n :'"3

/1..-- Training: i&o/ Operations: ~~/

r I

~

,) CANDIDATES CRS ATC BOP LOI 14-2 NRC Examination Scenario 1 Page 1 of 23

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 5/1/14 LOI 14-2 NRC Exam New Scenario T. Hooper

\.

LOI 14-2 NRC Examination Scenario 1 Page 2 of 23

A. TITLE: LOI14-2 NRC EXAMINATION SCENARIO 1 B. SCENARIO SETUP:

1. IC-61

2. Special Instructions:

a. The Plant is operating at approximately 90% power.

b. RCIC is out of service for maintenance.

c. Torus cooling is in service on RHR loop A.

3. Preset Conditions:

a. Preset, M:RC03, RCIC System Turbine Trip

b. Trigger 1, M:SW04:A, RHR Service Water Pump A Trip

c. Trigger 2, NM14:B, APRM Channel B Failure, 100%

d. Trigger 3, M:HP05, HPCI Inadvertent Initiation

e. Trigger 16, M:HP02, HPCI Turbine Trip

f. Trigger 4, M:FW05:A, Rx Feedwtr Pmp A High Vibration

g. Trigger 17, M:FW01:A, Rx Feedwtr Pmp A Trip

h. Trigger 5, M:RR15:A, Coolant (A) Leakage Inside Primary Containment, ramp=3 minutes, initial=1.5%, final=5%

i. Trigger 6, M:FW01 :B, Rx Feedwtr Pmp B Trip

j. Trigger 6, M:ED43:A, LHH Line #3 Fault, delay=4 minutes

k. Trigger 6, M:ED43:B, NMP Line #4 Fault, delay=5 minutes I. Trigger 6, M:MS02:A, (MSL A) Stm Leakage Inside Prim, ramp=3 minutes, 50%

m. Preset, O:RC ZA013PI96, Pump Suction Pressure lndi, 0%

n. Preset, O:RC ZA013PI94, Turbine Steam Inlet Pressu, 0%

o. Preset, O:RC ZL01315(1), (Mimic) Inboard Stm Supply Is, Off

p. Preset, O:RC ZL01316(1), (Mimic) Outbd Stm Supply lsol, Off

q. Preset, O:RC ZL01339(1), (Mimic) Pump Suet From Supp C, Off

r. Preset, O:RC ZL01341 (1 ), (Mimic) Pump Suet From Supp C, Off

s. Preset, O:RC ZL013AS1(1), Inboard Steam Supply lsol, Off

t. Preset, O:RC ZL013AS10(1), Pump Suction From Supp C, Off

u. Preset, O:RC ZL013AS2(1), Outboard Steam Supply lso, Off

v. Preset, O:RC ZL013AS22(1), Pmp Suction From Supp C, Off

w. Preset, O:RC ZL013AS4(1), Pmp Suction From Cond Sto, Off

x. Preset, O:AN941 :34, RCIC Exh Press Hi (25 psig), Off

y. Event Trigger 1, Action: zlo1 034a(2)==0, Command: None

z. Event Trigger 6, Action: zdi5as1(1)==1, Command: imf rr15:a 22 20:00 5 aa. Event Trigger 16, Action: zdi23as19==1, Command: None bb. Event Trigger 17, Action: fwvrfpt(1)>8 , Command: None

4. Consumable Forms and Procedures:

+ AOP-1, AOP-8, AOP-41, AOP-72, AOP-77 LOI 14-2 NRC Examination Scenario 1 Page 3 of23

C. SCENARIO

SUMMARY

The scenario will begin at approximately 90% power with RCIC out of service for maintenance and Torus cooling in service on RHR loop A. The crew will begin the shift by securing the Torus cooling lineup.

While the crew is securing Torus cooling , RHRSW pump A will trip. The SRO will determine the Technical Specification impact. The crew will continue with the remaining steps to secure Torus cooling APRM B will fail upscale and cause a half scram on RPS B. The SRO will determine that Technical Specifications are satisfied with APRM B bypassed. The crew will bypass APRM Band reset the half scram.

HPCI will inadvertently start. The SRO will enter AOP-77 and direct securing HPCI. The crew will secure HPCI and one train of Standby Gas Treatment. The SRO will determine the Technical Specification impact.

With RCIC out of service, Technical Specifications will require a plant shutdown.

Feedwater pump A will develop a high vibration . The crew may lower Reactor power in anticipation of tripping the pump. When the vibration exceeds 6 mils, the crew will trip the pump. If the crew does not trip the pump by 8 mils, the pump will spuriously trip. A Recirculation run back is likely to occur following the pump trip. The crew will respond to stabilize the plant within the capacity of a single Feedwater pump.

A coolant leak will develop in the Drywell. The crew will scram the Reactor in anticipation of an automatic scram. Following the scram, Feedwater pump B will trip. With no remaining high pressure Feedwater, the crew may attempt to restore HPCI to service, but HPCI will trip. The crew will attempt to maintain Reactor water level with CRD and SLC, and may lower Reactor pressure to inject with Condensate Booster pumps.

Offsite power lines 3 and 4 will sequentially trip. The loss of offsite power will make all Condensate pumps unavailable. Only low pressure ECCS pumps will be available for high capacity injection to the Reactor.

Additionally, all Circulating Water pumps will trip, requiring the crew to close MSIVs and control Reactor pressure using SRVs.

The coolant leak will continue to get worse. The crew will place Torus spray in service. When Torus pressure exceeds 15 psig, the crew will also place Drywell spray in service. Drywell spray will lower Drywell pressure such that the Pressure Suppression Pressure curve is not challenged. The coolant leak rate will exceed the capacity of available high pressure injection . Reactor water level will lower to the top of active fuel. The crew will execute an Emergency RPV Depressurization and then control low pressure injection systems to restore Reactor water level.

The scenario will be terminated when all control rods are inserted, the Emergency RPV Depressurization is in progress, and Reactor water level is controlled above 0".

LOI 14-2 NRC Examination Scenario 1 Page 4 of 23

Shift Turnover The Plant is operating at approximately 90% power during a power reduction.

RCIC is out of service for maintenance.

Torus cooling is in service on RHR loop A When you take the shift, secure Torus cooling per OP-138 sections F.1 and F.7 LOI 14-2 NRC Examination Scenario 1 Page 5 of 23

Critical Tasks/Standards Critical Task #1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4.

Critical Task #2: Given a coolant leak, a loss of high pressure injection systems, and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization before Reactor water level lowers below

-19" , in accordance with EOP-2.

LOI 14-2 NRC Examination Scenario 1 Page 6 of 23

EVENT NO. EVENT SEQUENCE

1. Shutdown Torus Cooling (Normal: BOP, SRO)

RHRSW Pump A Trip (Component: SRO)

2. (Tech Spec: SRO)

3. APRM B Fails Upscale (Component: ATC, SRO)

HPCI Inadvertent Initiation (Instrument: BOP, SRO) 4.

(Tech Spec: SRO)

Feedwater Pump A High Vibration and Pump Trip (Component: BOP) 5.

(Reactivity: ATC, SRO)

6. Coolant Leak in Drywell (Major: All)

7. Feedwater Pump B Trip, HPCI Trip (Component: All)

(~ 8. Loss of Offsite Power (Component: All)

D. TERMINATION CUES:

All control rods are inserted

Emergency RPV Depressurization is in progress

Reactor water level is controlled above 0" LOI 14-2 NRC Examination Scenario 1 Page 7 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow All no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch I

Events 1 & 2 SRO SAT I UNSAT INA Secure Torus Cooling, RHRSW Pump A Trip

Perform Crew Brief

Direct BOP to secure Torus cooling per OP-13B sections F.1 and F.7.

Acknowledge trip of RHRSW pump A

Determine Technical Specification 3.7.1 Condition A must be entered (restore RHRSW pump A to operable within 30 days)

BOP SAT I UNSAT INA Note:

Close RHR TEST & TORUS CLG 1OMOV-34A Ensure Trigger 1 automatically

Recognize I report trip of RHRSW pump A goes active and trips RHRSW pump A when 1OMOV-34A red

IF RHR Loop A flow is LESS THAN 1500 gpm, THEN ensure light extinguishes. open MIN FLOWVLV 10MOV-16A

IF RHR Loop A operation is not required, THEN shut down RHR Loop A per Subsection F.7 LOI 14-2 NRC Examination Scenario 1 Page 8 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP cont. SAT I UNSAT INA

Ensure one of the RHR Loop A keep-full systems is in service Role Play: as follows:

If dispatched to investigate trip 0 RHR KEEP-FULL PMP 10P-2A is running, of RHRSW pump A , wait 2 minutes, then report that the OR pump breaker tripped on 0 10RHR-274 (RHR loop A containment spray keep-full cond overcurrent, but there is xfer connection valve) is throttled open nothing abnormal at the pump.

Ensure closed the following valves:

0 RHR TEST & TORUS CLG 1OMOV-34A 0 TORUS SPRAY INBD VLV 10MOV-38A 0 OW SPRAY INBD VLV 10MOV-31A

Ensure the following RHR pumps are stopped:

0 RHR PMP 1OP-3A 0 RHR PMP 1OP-3C

Ensure closed the following valves : I 0 RHR TEST TORUS CLG & SPRAY 1OMOV-39A I 0 DW SPRAY OUTBD VLV 1OMOV-26A

Ensure open MIN FLOWVLV 10MOV-16A

Ensure open HX A BYP VLV 1OMOV-66A

IF RHRSW Loop A operation is not required, THEN shut down RHRSW Loop A as follows:

0 Close RHRSW DISCH VLV FROM HX A 10MOV-89A 0 Ensure the following RHRSW pumps are stopped:

0 RHRSW PMP 10P-1A 0 RHRSW PMP 10P-1C LOI 14-2 NRC Examination Scenario 1 Page 9 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event3 ATC SAT I UNSAT INA On Lead Examiner Cue:

Recognize I report multiple annunciators, including:

ACTIVATE TRIGGER 2 0 09-5-2-44, APRM UPSCALE APRM B Fails Upscale 0 09-5-2-55, APRM TRIP SYS B INOP OR UPSCALE TRIP

Recognize I report APRM B indicates upscale

Recognize I report half scram SRO SATIUNSATINA

Acknowledge report

Direct ARP response

Determine Technical Specification Table 3.3.1.1-1 Functions 2b, c, and d are met with APRM B out of service

.Determines TRM Table T3.3.B-1 Functions 1a, b, and care met with APRM B out of service

Direct bypassing APRM B per OP-16

Direct reset of half scram ATC SAT I UNSAT INA

Bypass APRM B per OP-16 Section E.16:

0 Place APRM BYP switch in B 0 Verify APRM B is bypassed using one or both of the following:

APRM B BYPASS indicating light is on

APRM B EPIC alarm indicates bypassed 0 Verify the other two APRM channels associated with the same APRM BYP switch are in service using one or both of the following:

APRM BYPASS indicating lights are off for the other two APRMs

No EPIC bypassed alarms for the other two APRMs LOI 14-2 NRC Examination Scenario 1 Page 10 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC cont. SAT I UNSAT INA

Reset half scram per ARP:

0 Place RX SCRAM RESET switch to GROUP 2 & 3, then to GROUP 1 & 4, spring return to NORM 0 Verify RPS 8 SCRAM GROUPS 1, 2, 3, and 4 lights are on LOI 14-2 NRC Examination Scenario 1 Page 11 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event4 BOP/ATC SAT/UNSAT/NA On Lead Examiner Cue:

ACTIVATE TRIGGER 3

Recognize I report spurious HPCI initiation HPCI Inadvertent Initiation

Recognize I report Reactor power rise, if applicable

Recognize I report Reactor water level rise, if applicable SRO SAT/UNSAT/NA

Acknowledge report

Enter AOP-77 (Inadvertent Initiation of ECCS or RCIC)

Verify HPCI injection not required

Direct trip of HPCI I

May enter AOP-32 (Unexplained/Unanticipated Reactivity Change)

Declare HPCI inoperable but available

Determine Technical Specification 3.5.1 Condition C is NOT met with RCIC inoperable

Determine Technical Specification 3.5.1 Condition G requires being in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reducing Reactor pressure to :s; 150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Declare the secured train of Standby Gas Treatment inoperable

Determine Technical Specification 3.6.4.3 Condition A requires restoring Standby Gas Treatment to operable within 7 days LOI 14-2 NRC Examination Scenario 1 Page 12 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP SAT/UNSAT/NA Role Play:

Execute AOP-77 If dispatched to investigate HPCI, wait three minutes, then

Observe Reactor water level and Drywell pressure indications report there is no obvious to verify HPCI injection not required reason why HPCI started and

Trip HPCI there is no observable damage to the system.

AFTER turbine comes to a complete stop, place AUX OIL PMP 23P-150 control switch in PULL-TO-LOCK

Secure one train of Standby Gas

For the running Standby Gas train, open 02-125MOV-11(12)

May execute AOP-32 (Unexplained/Unanticipated Reactivity Change) 0 Determine HPCI initiation was only cause of reactivity change LOI 14-2 NRC Examination Scenario 1 Page 13 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 5 BOP I ATC SAT I UNSAT INA On Lead Examiner Cue:

Recognize I report EPIC alarms ACTIVATE TRIGGER 4

Recognize I report annunciator 09-6-4-11, RFPT A VIB HI Feedwater Pump A High Vibration and Pump Trip

Recognize I report rising Feedwater pump A vibrations SRO SAT I UNSAT INA Note:

Acknowledge report The ARP directs tripping

Direct ARP response Feedwater pump A if vibration reaches 6 mils. There is no

May direct emergency power reduction with Recirculation flow automatic trip on vibration, and/or CRAM rods however the pump will

Direct trip of Feedwater pump A spuriously trip in this scenario if vibration reaches -8 mils.

Enter AOP-41 (Feedwater Malfunction)

May enter AOP-8 (Unexpected Change in Core Flow)

BOP SAT I UNSAT INA Note:

Execute ARP 09-6-4-11 Recirculation pumps will likely 0 Monitor vibration level and trend runback to the 44% limiter due to only one Feedwater pump 0 When vibration approaches/exceeds 6 mils, trip Feedwater operating and Reactor water pump A level lowering to 196.5".

Coordinate with A TC to lower Reactor power with Recirculation flow, as required I directed Role Play:

If dispatched to investigate, wait 2 minutes, then report that Feedwater pump A is vibrating, but there is no obvious cause .

LOI 14-2 NRC Examination Scenario 1 Page 14 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC SAT I UNSAT INA Note:

Coordinate with BOP to lower Reactor power with CRAM rods, as required I directed Following the trip of

Monitor for thermal-hydraulic instabilities (THI)

Feedwater pump A, Reactor power will likely stabilize between 65-70% power. The crew may decide to lower Reactor power further by inserting CRAM rods, since during a startup the second Feedwater pump is started prior to exceeding 55% power.

However, there is no hard requirement to continue the power reduction.

Role Play:

If the crew is not taking action to lower Reactor power by inserting CRAM rods, when crew informs management or Reactor Engineering of event, direct crew to lower Reactor power to 50% using RAP-7.3.16.

LOI 14-2 NRC Examination Scenario 1 Page 15 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Events 6 1 7 1 & 8 BOP I ATC SAT I UNSAT INA On Lead Examiner Cue:

Recognize I report degrading Primary Containment conditions ACTIVATE TRIGGER 5 (leakage, temperature, pressure)

Loss of Coolant Accident, Feedwater Pump 8 Trip, HPCI

Recognize I report trip of Feedwater pump 8 (after scram)

Trip, Loss of Offsite Power

Recognize I report trip of HPCI (if re-start attempted)

Recognize I report loss of Lines 3 and 4 (approximately 4 and Note: 5 minutes after scram, respectively)

Ensure Trigger 6 automatically goes active when the Reactor scrams to cause the Feedwater pump trip and delayed loss of offsite power.

This trigger also re-inserts the coolant leak malfunction and ramps it to a higher value.

Critical Task #1 Given a coolant leak Inside the Containment, the crew will Pass/ Fail spray the Drywall, in accordance with EOP-4.

Drywall spray In service.

Critical Task t1 Standard:

Critical Task t2 . Given a coolant leak, a loss of high pi'8SSure Injection Pass/ Fall systems, and the Inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will Initiate actio* for an Emerge~~ey RPV Depressurization before RNctor wat.rlevellowtn below -1.8 ", In accordance wlthEOP..Z.

7 ADS valves open.

Critical Task t2 Standard:

LOI14-2 NRC Examination Scenario 1 Page 16 of 23

IINSTRUCTORACTIVITY I POSITION I OPERATORACTIONS/STANDARD I COMMENTS/EVALUATION I SRO SAT/UNSAT/NA

Acknowledge reports

Direct Reactor scram

Enter AOP-1 (Reactor Scram)

Enter EOP-2 (RPV Control) on low Reactor water level, high Drywell pressure, and high Drywell temperature (as they occur)

Enter EOP-4 (Primary Containment Control) on high Drywell pressure and high Drywell temperature (as they occur)

Acknowledge trip of Feedwater pump B

Direct Reactor water level controlled 180-220" using HPCI ,

Condensate, SLC, and/or CRD

Acknowledge trip of HPCI

Direct Reactor pressure controlled 800-1000# using Turbine Note: Bypass Valves A pressure band of 600-800#

May direct Reactor depressurization to inject with Condensate would allow injection with

Enter AOP-39 (Loss of Coolant)

Condensate Booster pumps, however these will become

Direct Control Room and Relay Room Ventilation isolated per unavailable due to the OP-55B Section G within 30 minutes eventual loss of offsite power.

Direct TSC filtered ventilation started per Section D of OP-59B within 60 minutes

May direct Core Spray and RHR injection prevented per EP-5 Role Play:

When directed to place

When Primary Containment pressure exceeds 2.7 psig and Control Room , Relay Room , before Torus pressure exceeds 15 psig, direct initiation of and/or TSC filtered ventilation Torus Spray in service, acknowledge direction.

LOI 14-2 NRC Examination Scenario 1 Page 17 of 23

[INSTRUCTOR ACTIVI"TY ImPOSITION I OPERATOR ACTIONS/STANDARD I COMMENTS/EVALUATION I SRO cont. SAT/UNSAT/NA

Acknowledge loss of Line 3

Acknowledge loss of Line 4

Enter AOP-72 (115 KV Grid Loss, Instability, or Degradation)

Note:

Acknowledge loss of all Condensate pumps and Circulating The MSIVs will be closed due Water pumps to loss of all Circulating Water pumps after the loss of 115

Direct closure of MSIVs KV.

Direct Reactor pressure control using SRVs

When Torus pressure exceeds 15 psig:

0 Verify Recirculation pumps tripped 0 Verify trip of Drywell cooling fans 0 Direct initiation of Drywell Spray

Determine Reactor water level cannot be maintained above 0"

Enter Alternate RPV Level Control leg of EOP-2

Direct override of ADS

Direct CRD maximized and SLC injection, if not done Note: previously As Reactor water level lowers,

When Reactor water level reaches 0", enter Emergency Critical Task #2 the crew will transition from RPV Depressurization leg of EOP-2 wide range to fuel zone level

Direct opening 7 ADS valves indicators. The determination of when to initiate Emergency

Direct Reactor water level restored and maintained 180-220" RPV Depressurization (CT-2) using Core Spray and/or LPCI will be made using Fuel Zone level indicators.

As time allows, directs re-start of Drywell spray LOI 14-2 NRC Examination Scenario 1 Page 18 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I ATC SAT I UNSAT INA

Enter AOP-1

Depress MANUAL SCRAM A and MANUAL SCRAM 8 pushbuttons

Place RX MODE switch in SHUTDOWN

Fully insert IRMs and SRMs

Observe Reactor power lowering

Ensure closed SDIV vent and drain valves

Ensure Main Turbine is tripped

Verify 4KV loads transfer to reserve power

May begin Reactor depressurization BOP SAT/UNSAT/NA

Enter AOP-1

Attempt to control Reactor water level 180-220" using HPCI, Condensate, SLC, and/or CRD

May attempt to manually re-start HPCI :

0 Ensure open 23MOV-16 0 Ensure running 23P-140 0 Ensure open 23MOV-14 0 If 09-3-3-28 is in alarm, then depress 23A-S17 0 Ensure running 23P-150 0 Recognize I report failure of HPCI to start LOI14-2 NRC Examination Scenario 1 Page 19 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC I BOP SAT I UNSAT INA

Attempt to maintain Reactor water level with SLC and/or CRD

Recognize I report leakage exceeds capacity of SLC and/or CRD

May lower Reactor pressure using Turbine Bypass Valves

May inject using Condensate Booster pumps

Initiate Torus spray: I I

0 Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, '

spring return to normal 0 Verify white SPRAY PERM 1OA-DS67A( B) light is on 0 Ensure available RHR pumps in RHR Loop A(B) are running (recognize/report failure to automatically start) 0 Open RHR TEST TORUS CLG & SPRAY 1OMOV-39A(B) 0 Throttle TORUS SPRAY INBD VLV 10MOV-38A(B) to establish desired torus spray flow rate 0 WHEN RHR Loop A(B) flow is GREATER THAN 1500 gpm, ensure closed MIN FLOW VLV 10MOV-16A(B) 0 Throttle RHR TEST & TORUS CLG 1OMOV-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 LOI 14-2 NRC Examination Scenario 1 Page 20 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC I BOP SAT I UNSAT INA cont.

0 Establish RHRSW flow and temperature control:

0 Start one of the RHRSW pumps 0 Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-89A(B) to establish 2500 to 4000 gpm 0 Start the second RHRSW pump if desired 0 Throttle RHRSW DISCH VLV FROM HX A( B) 1OMOV-89A(B) to establish 2500 to 4000 gpm per RHRSW pump 0 IF drywell or torus sprays are in service, THEN establish 4000 gpm per RHRSW pump 0 Close HX A( B) BYP VLV 1OMOV-66A(B)

Close MSIVs

Control Reactor pressure using SRVs Note:

Ensure Recirc pumps tripped When RPV water level lowers

Ensure Drywell Cooling fans tripped below 59.5", Torus and

Initiate Drywell spray: Critical Task #1 Drywell Spray are automatically secured as LPCI 0 Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, receives an initiation signal. spring return to normal The SRO will direct Torus and 0 Verify white SPRAY PERM 1OA-DS67A( B) light is on Drywell Spray re-established at a later time. 0 Ensure available RHR pumps in RHR Loop A(B) are running 0 Open OW SPRAY OUTBD VLV 1OMOV-26A(B) 0 Throttle OW SPRAY INBD VLV 10MOV-31A(B) to establish desired drywell spray flow rate LOI 14-2 NRC Examination Scenario 1 Page 21 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I ATC I BOP SAT I UNSAT INA cont.

Override ADS:

0 Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE 0 Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-S2B in OVERRIDE 0 Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm 0 Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on

Maximize CRD, if not done previously

Initiate SLC injection, if not done previously

Verify isolations per AOP-15 Critical Task #2

Open 7 ADS valves

Restore and maintain Reactor water level 180-220" using available injection systems

Control Core Spray injection:

0 Throttle 14MOV-12A(B)

Control LPCI injection:

0 Throttle 1OMOV-27A( B) 0 Secure RHR pumps if needed Termination Criteria:

All control rods are inserted

Emergency RPV Depressurization is in progress

Reactor water level is controlled above 0" LOI 14-2 NRC Examination Scenario 1 Page 22 of 23

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 90% power during a power reduction .

RCIC is out of service for maintenance.

Torus cooling is in service on RHR loop A.

When you take the shift, secure Torus cooling per OP-138 sections F.1 and F.7 LOI14-2 NRC Examination Scenario 1 Page 23 of 23

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 14-2 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 99% power. Air Compressor B is out of service for maintenance. Core Spray pump A is ready for full flow testing. Main Generator reactive load is at minimum per Power Control request.

Turnover: Perform Core Spray full flow testing per ST-3PA, starting at step 8.7.6.

Event Malf. Event Event No. No. Type* Description N- Perform Core Spray Full Flow Test 1 N/A BOP, SRO ST-3PA C- Core Spray Pump Overload 2 Override BOP, SRO ARP 09-3-1-31, Technical Specifications C- Control Rod Drive Pump Trip, One Control Rod Drive Accumulator RD06 3 ATC, Low Pressure RD09 SRO AOP-69, ARP-09-5-1-43, Technical Specifications R-ATC Main Turbine Bearing High Vibration; Loss of Main Condenser TU04 4 Vacuum C-ATC, MC01 SRO AOP-66, AOP-31, AOP-1 RP01AB Failure of RPS and ARI to Actuate 5 RP01BB M-All EOP-2, EOP-3 RP09 SL02 First SLC Squib Valve Fails to Fire, Second SLC Pump Trips, C-6 SL01 ATC, Recirculation Pumps Fail to Automatically Trip SRO EOP-3 RR13 EG01 C- Main Generator Trip, Two Turbine Bypass Valves Fail Closed 7 BOP, TC04 SRO EOP-3

(N)ormal, (R)eactivitv, (l)nstrument, (C)omponent (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 14-2

1. Total malfunctions (5-8) 6 Events 2, 3, 4, 5, 6, 7

2. Malfunctions after EOP entry (1-2) 2 Events 6 & 7

3. Abnonnal events (2-4) 2 Events 3 &4

4. Major transients (1-2) 1 Event 5

5. EOPs entered/requiring substantive actions (1-2) 1 EOP-2

6. EOP contingencies requiring substantive actions (0-2) 1 EOP-3

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT -1: Given a failure to scram with Reactor power above 2.5%, the crew will lower Reactor power by one or more of the following methods, in accordance with EOP-3:

Terminating and preventing all RPV injection except SLC, RCIC, and CRD

Tripping Recirculation pumps CT-2: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI14-2 NRC EXAMINATION SCENARIO 2 TITLE: LOI14-2 NRC EXAMINATION SCENARIO 2 SCENARIO NUMBER: NRC 2 PATH: STAND ALONE Validation: ..-=:-""' '} ~- Training: ,Jl~

) '

CANDIDATES CRS ATC BOP LOI 14-2 NRC Examination Scenario 2 Page 1 of 29

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 5/3/12 New New Scenario T. Hooper 5/14/14 LOI14-2 NRC Exam Modified for LOI14-2 NRC Exam T. Hooper LOI14-2 NRC Examination Scenario 2 Page 2 of 28

A. TITLE: LOI 14-2 NRC EXAMINATION SCENARIO 2 B. SCENARIO SETUP:

1. IC-62

2. Special Instructions:

a. The Plant is operating at approximately 99% power.

b. Air Compressor B is out of service for maintenance.

c. Ensure Generator reactive load is at minimum per OP-11A.

3. Preset Conditions:

a. Preset, R:IA15:B, Air Camp 39AC-2B Supply Breaker, Open (will not show in Instructor Station Summary after snap/reset)

b. Preset, O:AN962: 18, Air Compr 39AC-2B Trip, Off

c. TRIGGER 1, O:CS ZA014P1A, Core Spray Pump A Current, Ramp=20 seconds, 170

d. TRIGGER 1, O:AN931 :31, Core Spray Pmp 14P-1A Overload, Delay=15 seconds, ON

e. TRIGGER 2, M:RD06:A, CRD Hydraulic Pump Trip (A)

f. TRIGGER 2, M:RD09:22:31, Control Rod (22-31) Accumulator, Delay=30 seconds

g. TRIGGER 3, M:TU04E, Main Turbine High Bearing #5 Vibration, lnitial=21 %,

Final=27%, Ramp=5:00

h. TRIGGER 3, M:TU04F, Main Turbine High Bearing #6 Vibration, lnitial=21 %,

Final=28%, Ramp=5:00

i. TRIGGER 4, M:MC01, Main Condenser Air In Leakage, lnitial=12%, Final=25%,

Ramp=8 minutes

j. Preset, M:RP01 :AB, RPS Automatic Scram Failure B Side Only

k. Preset, M:RP01 :BB, RPS Manual Scram Failure B Side Only I. Preset, M:RP09, ARI Fails to Actuate

m. Preset, M:SL02:A, Standby Liquid Squib Valve Fails

n. Preset, M:SL02:B, Standby Liquid Squib Valve Fails

o. Preset, M:RR13:A, ATWS System Fails to Initiate

p. Preset, M:RR13:B, ATWS System Fails to Initiate

q. TRIGGER 5, M:EG01, Main Generator Trip

r. TRIGGER 6, M:TC04:A Turbine Bypass Valve Failure, 0%

s. TRIGGER 6, M:TC04:B Turbine Bypass Valve Failure, 0%

t. TRIGGER 20, R:IA07, Scram Air Hdr Man lso Vlv, CLOSE

u. TRIGGER 20, M:IA01 , Loss of Air Pressure to Scram Air Header, 100%, Ramp=30 seconds

v. TRIGGER 19, R:RH40:A, Relay 1OA-K45A Timer Grayboot, REMOVED

w. TRIGGER 19, R:RH40:B, Relay 10A-K45B Timer Grayboot, REMOVED

x. Event Trigger 1, Event: zdi14as4a(2)==1 , Command: None

y. Event Trigger 4, Event: ycx07nmaprmaf<95, Command : None

z. Event Trigger 5, Event: ycx07nmaprmaf<42, Command : None aa. Event Trigger 6, Event: ycx07nmaprmaf<24, Command: None bb. Event Trigger 16, Event: csipump(1)>50&&zdi14as5a(1)==1, Command: dor zao14p1a LOI 14-2 NRC Examination Scenario 2 Page 3 of 28

cc. Event Trigger 16, Event: csipump(1)>50&&zdi14as5a(1)==1, Command: dor an931 :31 dd. Event Trigger 21, Event: ycx07nmaprmaf<95, Command: imf tu04:e 14 60 ee. Event Trigger 22, Event: ycx07nmaprmaf<95, Command: imf tu04:f 14 60 ff. Event Trigger 23, Event: ycx07nmaprmaf<85, Command: imf mc01 30 1:00 gg. Event Trigger 24, Event: ycx07nmaprmaf<60, Command: imf mc01 35 1:00 hh. Event Trigger 25, Event: zdi11 s1 (2)==1, Command: dmf sl02:b ii. Event Trigger 26, Event: zdi11 s1 (2)==1, Command: trgr 28 jj. EventTrigger27, Event: zdi11s1(2)==1, Command: imfsl01:b (30 5) kk. Event Trigger 28, Event: zdi11s1(1)==1, Command: dmf sl02:a II. Event Trigger 29, Event: zdi11s1(1)==1, Command: trgr 25 mm. Event Trigger 30, Event: zdi11s1(1)==1, Command: imf sl01 :a (27 5)

4. Consumable Forms and Procedures:

+ AOP-1, AOP-31, AOP-66, AOP-69, ST-3PA LOI 14-2 NRC Examination Scenario 2 Page 4 of 28

C. SCENARIO

SUMMARY

The scenario will begin with the plant operating at approximately 99% power. The crew will begin by performing Core Spray pump testing per ST-3PA. When the Core Spray test valve is opened , an overload condition will develop on Core Spray pump A The crew will perform ARP actions to lower pump flow and then stop the pump. The SRO will determine the Technical Specification impact.

The running Control Rod Drive pump will trip. The crew will enter AOP-69, start the standby pump, and restore normal Control Rod Drive parameters. During this evolution, one Control Rod Drive accumulator will develop a low pressure. The SRO will determine the Technical Specification impact.

Main Turbine vibrations will develop. The crew will enter AOP-66 to address the vibrations. The vibrations will subside as Reactor power is lowered, however the vibrations will have caused damage resulting in Main Condenser air in-leakage. Main Condenser vacuum will degrade. The crew will enter AOP-31 and eventually insert a manual Reactor scram .

RPS B will fail to process the scram and ARI will also fail to insert control rods. The crew will enter EOP-2 and EOP-3. The ATWS system will fail to automatically trip the Recirculation pumps when required . The crew will lower Recirculation flow to minimum and then trip the Recirculation pumps. The crew will terminate and prevent injection except CRD, SLC, and RCIC. The crew will attempt to inject boron using SLC, however the squib valves will fail to fire when the first SLC pump is started. The second SLC pump will successfully start and inject, but then trip after a time delay. The Main Turbine will be available until power lowers to approximately 40%, when a spurious turbine trip occurs. As power lowers, two Turbine Bypass alves will fail closed, challenging Reactor pressure control and Primary Containment control. The crew will be able to manually insert control rods. Either pulling RPS fuses or venting the scram air header will result in all rods inserting .

The scenario will be terminated when control rods are being inserted or are all inserted and Reactor water level is controlled above 0".

LOI14-2 NRC Examination Scenario 2 Page 5 of 28

Shift Turnover The Plant is operating at approximately 99% power.

Air Compressor B is out of service for maintenance.

Main Generator reactive load is at minimum per Power Control request.

When you take the shift, perform Core Spray A pump testing per ST-3PA, starting at step 8.7.6 .

LOI 14-2 NRC Examination Scenario 2 Page 6 of 28

Critical Tasks/Standards Critical Task #1 : Given a failure to scram with Reactor power above 2.5%, the crew will lower Reactor power by one or more of the following methods, in accordance with EOP-3:

Terminating and preventing all RPV injection except SLC, RCIC, and CRD

Tripping Recirculation pumps Critical Task #2: Given a failure to scram , the crew will initiate Control Rod insertion, in accordance with EOP-3.

LOI14-2 NRC Examination Scenario 2 Page 7 of 28

EVENT NO. EVENT SEQUENCE

1. Perform Core Spray Full Flow Test (Normal: BOP, SRO}

2. Core Spray Pump Overload (Component: BOP, SRO}

Control Rod Drive Pump Trip, One Control (Component: ATC, SRO}

3.

Rod Drive Accumulator Low Pressure Main Turbine Bearing High Vibration, Loss of (Reactivity: ATC}

4.

Main Condenser Vacuum (C: ATC, SRO}

5. Failure of RPS and ARI to Actuate (Major: All}

First SLC Squib Valve Fails to Fire, Second SLC (Component: ATC, SRO}

6. Pump Trips, Recirculation Pumps Fail to Automatically Trip Main Generator Trip and Two Turbine (Component: BOP, SRO}

7.

Bypass Valves Fails Closed D. TERMINATION CUES:

Control rods are being inserted or are all inserted.

Reactor water level is being controlled above 0".

LOI 14-2 NRC Examination Scenario 2 Page 8 of 28

INSTklJCTOR ACTIVITY POSITION OPERA fOR ACTIONS/STANDARD COMMENTS I EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow All no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch Event 1 SRO SAT I UNSAT INA Perform Core Spray Full Flow Test

Perform Crew Brief

Direct BOP to perform Core Spray testing per ST-3PA BOP SAT I UNSAT INA

Start PMP 14P-1A

Throttle TEST VL V 14MOV-26A to momentarily establish Core Spray Loop A flow rate at GREATER THAN OR EQUAL TO Note:

5150 gpm on EPIC display CS As 14MOV-26A is being opened, ensure Trigger 1

Throttle TEST VLV 14MOV-26A to establish GREATER THAN automatically activates. This OR EQUAL TO 4610 LESS THAN OR EQUAL TO 4790 gpm will lead immediately into the on EPIC display TRCS (as time permits) next event.

Verify closed MIN FLOW VLV 14MOV-5A (as time permits)

LOI 14-2 NRC Examination Scenario 2 Page 9 of 28

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Event2 BOP SAT I UNSAT INA Core Spray Pump Overload

Recognize I report high current on Core Spray pump A

Recognize I report annunciator 09-3-1-31 , Core Spray Pmp 14P-1A Overload SRO SAT I UNSAT INA

Acknowledge report

Direct execution of ARP

Declare Core Spray pump A inoperable

Determine Technical Specification 3.5.1 Condition A requires restoring Core Spray pump to operable within 7 days BOP SAT I UNSAT INA Role Play:

Executes ARP 09-3-1-31 :

If contacted as NPO about Core Spray pump A while it is

IF either of the following conditions exist:

still running, immediately 0 Pump flow rate is > 4700 gpm, OR Pump amps are > 160, report that the pump is running very loudly and there is some

THEN reduce pump flow rate until:

light smoke coming from the 0 Pump flow rate is s 4700 gpm, AND Pump amps are s 160 motor.

If contacted as NPO about

IF the annunciator remains in alarm , AND core spray is not Core Spray pump A after it required to assure adequate core cooling , THEN perform the has been stopped, following :

immediately report that it has

Ensure closed INBD INJ VLV 14MOV-12A stopped and the smoke is dissipating .

Ensure closed TEST VLV 14MOV-26A

Ensure open MIN FLOW VLV 14MOV-5A

Stop PMP 14P-1A LOI 14-2 NRC Examination Scenario 2 Page 10 of 28

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Event 3 ATC SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 2

Recognize I report annunciators:

Control Rod Drive Pump Trip, 0 09-5-1-9, CRD CHARGING WTR PRESS LO One Control Rod Drive 0 09-5-1-39, CRD PMP 3P-16A OVERLOAD Accumulator Low Pressure 0 09-5-1-49, CRD PMP 3P-16A TRIP 0 09-5-1-43, CRD ACCUM PRESS LO OR LVL HI (delayed)

Recognize I report trip of CRD pump A

Recognize I report accumulator alarm on control rod 22-31 (delayed)

Role Play: SRO SAT I UNSAT INA If contacted about control rod scram times, report that all

Acknowledge reports control rod scram times were

Enter AOP-69 (Control Rod Drive Pump Trouble) within limits during last surveillance.

Direct start of CRD pump B

Determine Technical Specification 3.1.5 Condition A requires declaring control rod 22-31 scram time "slow" or declaring control rod 22-31 inoperable within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Role Play: ATC SAT I UNSAT INA If dispatched to investigate pump trip, wait 2 minutes, then

Execute AOP-69 report CRD pump A breaker is

Note override conditions for RPV pressure above 900 psig and tripped and there are no required scram abnormal indications at the pump.

Monitor ACCUM alarm lights on full core display

Ensure CRD FLOW CNTRL 03FIC-301 is in MAN

Rotate manual control knob on CRD FLOW CNTRL 03FIC-301 fully counterclockwise LOI 14-2 NRC Examination Scenario 2 Page 11 of 28

INSTRuCTOR ACTIVITY POSITION

. OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION ATC cont. SAT I UNSAT INA Role Play:

Verify in-service CRD flow control valve (03FCV-19A or B) is If dispatched to investigate closed accumulator alarm, wait 2 minutes, then report that the

Start CRD PMP 03P-16B accumulator pressure for

Slowly adjust manual control knob on CRD FLOW CNTRL control rod 22-31 is 850 psig 03FIC-301 to establish 59 to 61 gpm on 03-FI-310 or 03FIC-and slowly lowering. 301

Place CRD FLOW CNTRL 03FIC-301 in automatic as follows:

0 Balance controller by adjusting setpoint tape 0 Place controller in AUTO 0 Adjust setpoint to BETWEEN 59 and 61 gpm I

I LOI14-2 NRC Examination Scenario 2 Page 12 of 28

INSTklJCTOR ACTIVITY POSITION OPERAlOR ACTIONS/STANDARD COMMENTS I EVALUATION Event 4 ATC I BOP SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 3

Recognize I report high Turbine vibrations Main Turbine Vibration

Monitor Turbine vibrations

Report vibrations on bearing 5 & 6 are greater than 9 mils but less than 12 mils I

Note: SRO SAT I UNSAT INA A Reactor scram is required if vibrations exceeded 12 mils or

Acknowledge report if vibrations exceeded 9 mils

Enter AOP-66 (Main Turbine High Vibration) for more than 15 minutes.

Neither of these conditions are expected in this scenario.

BOP SAT I UNSAT INA Role Play:

If dispatched to investigate

Execute AOP-66 vibrations; wait 2 minutes,

Notifiy crew of Reactor scram criteria then report you can feel vibrations on the Turbine Deck

Ensure Main Turbine system engineer is notified but do not see any obvious

Determine MVARs already lowered to minimum cause.

Coordinate with A TC to lower Recirc flow with RWR MG A(B)

SPEED CNTRL

Monitor Turbine vibrations

Report Turbine vibrations are less than 9 mils LOI 14-2 NRC Examination Scenario 2 Page 13 of 28

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Note: ATC SAT I UNSAT INA Once Reactor power is reduced to approximately

Lower Recirc flow with RWR MG A(B) SPEED CNTRL 95% , Triggers 21 and 22

Monitor APRMs, CTP, Recirc flow, Reactor water level activate to lower the Turbine vibrations. Trigger 4 activates to initiate the next part of event 4.

LOI 14-2 NRC Examination Scenario 2 Page 14 of 28

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Event 4 Continued BOP/ATC SAT I UNSAT INA Loss of Main Condenser vacuum

Recognize I report annunciator 09-3-1-28 Offgas Recombiner Trouble Note:

Recognize I report lowering Main Condenser vacuum This part of event 4 is automatically initiated when Reactor power is lowered <

-95% in the previous part of the event.

SRO SATIUNSAT/NA Note:

Acknowledge reports A typical benchmark for directing a Reactor scram is a

Enter AOP-31 (Loss of Condenser Vacuum) vacuum of 24.0" Hg.

Direct power reduction per RAP-7.3.16 to maintain Main Condenser vacuum within Normal Operating Region I

Direct Reactor scram Note: BOP SAT I UNSAT INA If desired by lead examiner to

Execute AOP-31 expedite the vacuum loss in this event, Triggers 23 and/or

Monitor Main Condenser vacuum 24 may be manually inserted

Trip Recombiner once the previous severity of malfunction MC01 is fully

Trip H2 addition ramped in.

Close 20LCV-958

Attempt to determine cause of vacuum degradation Role Play:

If dispatched to investigate

Coordinate with ATC to lower Recirc flow with RWR MG A(B)

Recombiner trouble alarm, SPEED CNTRL if Core Flow is >55%

wait 2 minutes, then report that the alarm is caused by high Recombiner flow.

LOI14-2 NRC Examination Scenario 2 Page 15 of 28

INSTklJCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Note: ATC SAT/UNSAT/NA Once a Reactor scram is

Lower Recirc flow with RWR MG A(B) SPEED CNTRL if Core attempted, a failure to scram Flow is >55%1nsert CRAM rods will occur. This is scripted in the next event.

Depress manual Scram pushbuttons

Place Mode Switch to Shutdown LOI 14-2 NRC Examination Scenario 2 Page 16 of 28

INSTklJCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION I Events 61 71 & 8 ATC SAT I UNSAT INA Failure of RPS and ARI to Actuate, First SLC Squib

Recognize I report failure to scram Valve Fails to Fire, Second

Manually initiate ARI SLC Pump Trips, Recirculation Pumps Fail to Automatically Trip, Main Generator Trip, Two Turbine Bypass Valves Fail Closed Critical Task #1 Given a failure to scram with Reactor power above 2.5%, the Pass I Fail crew will lower Reactor power by one or more of the following methods, in accordance with EOP-3:

Terminating and preventing all RPV injection except SLC, RCIC, and CRD

Tripping Recirculation pumps Critical Task #1 Standard: Terminate and prevent all injection except SLC, RCIC and CRD per EP-5 And/or Trip Recirculation pumps

_, -- -~----- .. ------

Critical Task #2 Given a failure to scram, the crew will initiate Control Rod Pass I Fail insertion, in accordance with EOP-3.

Critical Task #2 Standard: Perform EP-3 Backup Control Rod Insertion Actions to insert control rods.

LOI 14-2 NRC Examination Scenario 2 Page 17 of 28

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION SRO SAT/UNSAT/NA

Acknowledge report Note:

Malfunctions will:

Enter EOP-2 (RPV Control) on Reactor power above 2.5% or unknown when a scram is required 0 Trip the Main Generator when Reactor power

Determine the Reactor will NOT remain shutdown under all lowers to approximately conditions without boron 42% I

Exit EOP-2 0 Fail closed two Turbine Bypass Valves when

Enter EOP-3 (Failure to Scram)

Reactor power lowers to Critical Tasks #1 and #2

Direct EP-3 Failure to Scram Actions approximately 24%

Direct bypassing MSIV low RPV water level isolation interlocks per EP-2 Critical Task #1

Direct terminate and prevent all injection except SLC, RCIC and CRD per EP-5

Direct RPV water level controlled between -19" and 11 0" with only Group 1 Water Level Control Systems (Condensate/Feedwater, CRD, HPCI, RCIC, LPCI)

Direct Reactor pressure controlled 800-1000 psig with Turbine Bypass Valves and SRVs, as required LOI 14-2 NRC Examination Scenario 2 Page 18 of 28

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION ATC SAT/UNSAT/NA

Perform EP-3 Failure to Scram Actions 0 Ensure Rx Mode Switch in SHUTDOWN 0 Ensure ARI initiated 0 Run Recirc flow to minimum 0 Determine Rx power greater than 2.5%

0 Ensure Recirc pumps tripped Critical Task #1 0 Override ADS 0 Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE 0 Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-S2B in OVERRIDE 0 Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm 0 Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on 0 Obtain CRS concurrence to inject SLC 0 Attempt to inject SLC 0 Verify white SQUIB VLVS READY lights are on Note:

Due to failure of the SLC squib 0 Note level on TK LVL 11 Ll-66 valves to fire, pump discharge 0 Place SLC pup keylock switch in START SYS-A or pressure will be high (near START SYS-B 1500 psig) and tank level will NOT lower. 0 Verify red SLC pump running light is on 0 Verify SLC pump discharge pressure on DISCH PRESS 11 Pl-65 is greater than or equal to RPV pressure LOI 14-2 NRC Examination Scenario 2 Page 19 of 28

INSTRuCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION ATC cont. SAT/UNSAT/NA 0 Verify the following :

0 CLN UP SUCT 12MOV-18 is closed 0 CLN UP RETURN ISOL VALVE 12MOV-69 is closed 0 Recognize I report failure of SLC pump to inject 0 Attempt to inject with other SLC pump 0 Recognize I report trip of second SLC pump

Insert IRMs and SRMs

Range IRMs as necessary LOI14-2 NRC Examination Scenario 2 Page 20 of 28

INSTkLICTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD I COMMENTS I EVALUATION Booth Operator: BOP SAT I UNSAT INA When directed to install MSIV low water level jumpers, wait 2

Direct NPO to bypass MSIV low RPV water level isolation minutes and run interlocks per EP-2 Section 5.1 MSIVLEVEL.cae.

Terminate and prevent all injection except SLC, RCIC, and Critical Task #1 CRD per EP-5 0 Feedwater 0 If RFP A is running:

0 Ensure RFP A FLOW CNTRL 06-84A is in MAN 0 Lower RFP A FLOW CNTRL 06-84A to minimum 0 Ensure open RFP A MIN FLOW 34FCV-135A 0 If RFP B is running:

0 Ensure RFP B FLOW CNTRL 06-848 is in MAN 0 Lower RFP BFLOW CNTRL 06-848 to minimum 0 Ensure open RFP B MIN FLOW 34FCV-135B 0 Ensure closed:

0 RFP A DISCH 34MOV-100A 0 RFP B DISCH 34MOV-100B 0 Ensure FDWTR STARTUP VLV 34FCV-137 in MANUAL 0 Ensure closed FDWTR STARTUP VLV 34FCV-137 0 HPCI 0 Trip HPCI by depressing TURB TRIP 23A-S19 pushbutton LOI 14-2 NRC Examination Scenario 2 Page 21 of 28

INSTRUCTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD I COMMENTS I EVA~UATION BOP cont.

0 Core Spray Loop A SAT I UNSAT INA 0 Place 14MOV-11A AUTO ACTUATION BYPASS SW Note: 14A-S 16A switch in bypass RCIC is out of service as part of the scenario setup, so RCIC 0 Verify white 14MOV-11A AUTO ACTUATION BYPASS actions may not be taken. LT 14A-DS35A light is on 0 Ensure closed OUTBD INJ VLV 14MOV-11A 0 Ensure PMP 14P-1A is stopped 0 Core Spray Loop B 0 Place 14MOV-11 B AUTO ACTUATION BYPASS SW 14A-S16B switch in bypass 0 Verify white 14MOV-11B AUTO ACTUATION BYPASS LT 14A-DS35B light is on 0 Ensure closed OUTBD INJ VLV 14MOV-118 0 Ensure PMP 14P-1 B is stopped LOI 14-2 NRC Examination Scenario 2 Page 22 of 28

INSTRUCTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD I COMMENTS I EVALUATION BOP cont. SAT/UNSAT/NA 0 RHR Loop A Booth Operator:

0 Place 10MOV-27A AUTO CONTROL BYPASS 10A-If requested to disconnect S23A RHR timers, wait 2 minutes, then activate Trigger 19 and 0 Verify white light above 1OMOV-27A AUTO CONTROL report task completion . BYPASS 1OA-S23A is on 0 Ensure closed LPCI OUTBD INJ VLV 10MOV-27A 0 Ensure RHR Loop A pumps which are not required to be running are stopped 0 RHR Loop B 0 Place 10MOV-27B AUTO CONTROL BYPASS 10A-S23B 0 Verify white light above 1OMOV-27B AUTO CONTROL BYPASS 1OA-S23B is on 0 Ensure closed LPCI OUTBD INJ VLV 10MOV-27B 0 Ensure RHR Loop B pumps which are not required to be running are stopped

Report RPV water level is less than 11 0" to CRS LOI 14-2 NRC Examination Scenario 2 Page 23 of 28

INSTklJCTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD I COMMENTS , *EVALUATION BOP cont. SAT I UNSAT INA

Control RPV water level between -19" and 11 0" with only Group 1 Water Level Control Systems (Condensate/Feedwater, CRD, HPCI, RCIC, LPCI) 0 Feedwater 0 If any Reactor feed pump is running:

0 Ensure feedwater pump discharge pressure is less than RPV pressure by adjusting reactor feed pump speed 0 Lineup injection flow path by performing on or both of the following:

0 Adjusting FDWTR STARTUP VLV 34FCV-137 0 Ensure open or throttled open Reactor feed pump discharge valve for running pump (34MOV-100A or B) 0 Control feed flow to RPV by performing any of the

_following:

0 Adjust RFP speed 0 Adjust FDWTR STARTUP VLV 34FCV-137 0 Close feed pump discharge valves 0 If both Reactor feed pumps are shutdown, and feedwater discharge header pressure is greater than RPV pressure, then control feed flow to RPV by performing one or both of the following :

0 Throttling FDWTR STARTUP VLV 34FCV-137 0 Throttling one or both of the following valves, only if APRMs are on scale:

0 RFP A DISCH 34MOV-100A 0 RFP B DISCH 34MOV-100B LOI 14-2 NRC Examination Scenario 2 Page 24 of 28

INSTklJCTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD I COMMENTS , *EVALUATION BOP cont. SAT I UNSAT INA 0 HPCI 0 Preparation for injection:

0 Ensure SGT is running per OP-20 0 Ensure open one of the following valves:

0 HPCI GLAND SEAL SUCT 01-125MOV-13A 0 HPCI GLAND SEAL SUCT 01-125MOV-13B 0 Ensure HPCI FLOW CNTRL 23FIC-108-1 setpoint is adjusted to minimum 0 Ensure HPCI FLOW CNTRL 23FIC-108-1 is in AUTO 0 Injection with initiation signal:

0 Depress INITIATION SIG/MAN TURB TRIP RESET 23A-S 17 pushbutton 0 Verify annunciator 09-3-3-28 HPCI TURB TRIP SOLENOID ENERGIZED is clear 0 Verify HPCI auto-initiation 0 Control HPCI turbine speed in manual or automatic 0 Periodically verify HPCI turbine speed is greater than 21 00 rpm 0 Injection without initiation signal:

0 Depress INITIATION SIG/MAN TURB TRIP RESET 23A-S 17 pushbutton 0 Verify annunciator 09-3-3-28 HPCI TURB TRIP SOLENOID ENERGIZED is clear 0 Ensure open OUTBD STM SUPP VLV 23MOV-16 0 Ensure GLAND SEAL CNDSR BLOWER 23P-140 is running LOI14-2 NRC Examination Scenario 2 Page 25 of 28

INSTRUCTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD I COMMENTS I EVALUATION BOP cont. SAT I UNSAT INA 0 HPCI cont.

0 Injection without initiation signal cont.

0 Ensure open TURB STM SUPP VLV 23MOV-14 0 Ensure AUX 01 L PMP 23P-150 is running 0 Open INJ VLV 23MOV-19 0 Ensure closed the following valves:

o STM LINE DRAIN TO RADW 23AOV-42 o STM LINE DRAIN TO RADW 23AOV-43 o TEST VLV TO CST 23MOV-21 o HPCI & RCIC TEST VLV TO CST 23MOV-24 0 Control HPCI turbine speed in manual or automatic 0 Periodically verify HPCI turbine speed is greater than 21 00 rpm ATC SAT I UNSAT INA Booth Operator:

Perform EP-3 Backup Control Rod Insertion Actions If requested to pull RPS fuses, Critical Task #2 wait 30 seconds and for lead 0 May de-energize scram solenoids per Subsection 5.2 examiner concurrence, then 0 Determine fuses to be pulled based on lit RPS Scram run SCRAMFUSEOUTB.cae Group lights and report task completion.

0 Direct NPO to pull fuses 5A-F18B, 5A-F18F, 5A-F18D, and 5A-F18H If directed to vent Scram Air Header, wait 2 minutes and for 0 May direct NPO to vent scram air header per Subsection lead examiner concurrence, 5.3 then activate Trigger 20 and report task completion .

Report all control rods are inserted LOI 14-2 NRC Examination Scenario 2 Page 26 of 28

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION SRO SAT I UNSAT INA

Acknowledge report

Exit EOP-3

Enter EOP-2

Direct Reactor water level restored and maintained 177-222 .5" BOP SAT I UNSAT INA

Begin restoring Reactor water level 177-222 .5" Termination Criteria:

Control rods are being inserted or are all inserted.

Reactor water level is being controlled above 0".

LOI 14-2 NRC Examination Scenario 2 Page 27 of 28

IIVIENT 1 Shift Turnover The Plant is operating at approximately 100% power.

Air Compressor B is out of service for maintenance.

Main Generator reactive load is at minimum per Power Control request.

When you take the shift, perform Core Spray A pump testing per ST-3PA, starting at step 8.7.6.

LOI 14-2 NRC Examination Scenario 2 Page 28 of 28

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-3 Op-Test No.: 14-2 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 100% power. Air Compressor B is out of service for maintenance.

Turnover: Swap RBCLC pumps per OP-40 section G.1. Then lower Reactor power to 95% using Recirculation flow.

Event Malf. Event Event No. No. Type* Description N- Swap RBCLC Pumps 1 N/A BOP, SRO OP-40 R- Lower Reactor Power to 95% Using Recirculation Flow 2 N/A ATC, SRO OP-27 Recirc Flow Unit Failure 3 RR23:B I-AII OP-16, Technical Specifications C- Electrical Fault on Bus L-15 4 ED21 :A BOP, SRO AOP-18A, Technical Specifications C- SRV C Inadvertently Opens 5 AD06 :C BOP, SRO AOP-36 AD06 :C SRV C Re-Opens , SRV Tailpipe Break Into Torus Airspace 6 M-All MS16:G AOP-36 , AOP-1 EOP-2 , EOP-4 I

1-ATC, Main Turbine Fails to Trip 7 TC11 SRO AOP-1 RH01 RHR Pump Trip, RHR Pump Suction Valve Fails Closed, RHRSW C-8 Remotes BOP, Crossties Fail Closed SRO EOP-4, EOP-2 Overrides

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-3 Op-Test No.: 14-2

1. Total malfunctions (5-8) 6 Events 3, 4, 5, 6, 7, 8

2. Malfunctions after EOP entry (1-2) 2 Events 7 & 8

3. Abnormal events (2-4) 2 Events 4 & 5

4. Major transients (1-2) 1 EventS

5. EOPs entered/requiring substantive actions (1-2) 2 EOP-2, EOP-4

6. EOP contingencies requiring substantive actions (0-2) 1 EOP-2 Emergency Depress Leg

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1: Given a stuck open SRV, the crew will scram the Reactor before Torus water temperature exceeds the Boron Injection Initiation Temperature, in accordance with AOP-36 and EOP-4.

CT-2: Given the inability to maintain Primary Containment conditions inside the Pressure Suppression Pressure, the crew will perform an Emergency RPV Depressurization, in accordance with EOP-4.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI14-2 NRC EXAMINATION SCENARIO 3 TITLE: L0114-2 NRC EXAMINATION SCENARIO 3 SCENARIO NUMBER: NRC 3 PATH: STAND ALONE Validation: .--Z~,te ') ~ Training: tfl~ Operatlon~4~',z£/

CANDIDATES CRS ATC BOP LOI 14-2 NRC Examination Scenario 3 Page 1 of 25

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 5/15/14 LOI 14-2 NRC Exam New Scenario T. Hooper

()

LOI 14-2 NRC Examination Scenario 3 Page 2 of 25

A. TITLE: LOI14-2 NRC EXAMINATION SCENARIO 3 B. SCENARIO SETUP:

1. IC-63

2. Special Instructions:

a. The Plant is operating at approximately 100% power.

b. Air Compressor B is out of service for maintenance.

3. Preset Conditions:

a. Trigger 1, M:RR23:B, Recirculation Flow Unit B Fails, 0%

b. Trigger 2, M:ED21 :A, 600VAC Emerg Bus 11500 Failure

c. Trigger 3, M:AD06:C, Rx Press Relief Valve (C- Inadvertently Opens)

d. Trigger 4, O:AN941 :08, ADS CNTRL PWR FAIL, on

e. Trigger 4, O:AD ZL0271C(1), SRV C Green Light, off

f. Trigger 4, O:AD ZL0271 C(2), SRV C White Light, off

g. Trigger 4, O:AD ZL0271 C(3), SRV C Red Light, off

h. Preset, M:TC11, Main Turbine Auto Trip Failure

i. Trigger 6, M:RH01 :B, RHR Pump B Trip, Delay=90 seconds

j. Trigger 6, M:RH01 :D, RHR Pump D Trip, Delay=1 05 seconds

k. Trigger 6, M:MS16:C, ADS Discharge Line (2E-RV2-71C), Delay=1 minute, Ramp=5 minutes, 100%

I. Trigger 25, R:AD07:C, 'C' SRV Isolation Switch at Remote Panel, Local

m. Trigger 26, R:AD02:C, 'C' SRV Fuse Pull Out, Out

n. Trigger27, O:AN941:18, REMOTE SHUTDOWN PNL DOOR OPEN, on

o. Trigger 22, R:SW46A, Manual Operation of 10MOV148A, 0%

p. Trigger 23, R:SW46D, Manual Operation of 10MOV149B, 0%

q. Trigger 22, O:SW ZL010AS49A(1), Service Wtr Crosstie Valve, Off

r. Trigger 22, O:SW ZL01 OAS49A(2), Service Wtr Crosstie Valve, Off

s. Trigger 23, O:SW ZL010AS50B(1), Service Wtr Crosstie Valve, Off

t. Trigger 23, O:SW ZL010AS50B(2), Service Wtr Crosstie Valve, Off

u. Preset, O:AN962: 18, Air Compr 39AC-2B Trip, Off

v. Event Trigger 4, Action: None, Command: mrf ad02:c in

w. Event Trigger 6, Action: (zlo5ads8a == 0) && (zlo5ads8b == 0), Command: None

x. Event Trigger 16, Action: zlo10as4b(2)==0, Command: dmf rh10:b

y. Event Trigger 17, Action: zlo10as4d(2)==0, Command: dmf rh10:b

z. Event Trigger 22, Action: zdi1 Oas49a==1, Command: None aa. Event Trigger 23, Action: zdi1 Oas50b==1, Command: None

4. Consumable Forms and Procedures:

+ AOP-1

+ AOP-18A

+ AOP-36 LOI14-2 NRC Examination Scenario 3 Page 3 of 25

C. SCENARIO

SUMMARY

The scenario will begin at approximately 100% power with Air Compressor B out of service for maintenance.

The crew will begin the shift by starting RBCLC pump A and securing RBCLC pump C for normal equipment rotation . Next the crew will lower Reactor power to approximately 95% using Recirculation flow.

Recirculation flow unit B will fail downscale. This will result in a rod block and half scram. The SRO will determine the Technical Specification impact. The crew will bypass Recirculation flow unit Band reset the half scram.

An electrical fault will develop on Bus L-15. The crew will execute AOP-18A, Loss of Switchgear L 15. The crew will start Standby Gas Treatment train B and isolate normal Reactor Building Ventilation. Multiple important loads will be lost, including RHR A Containment spray/cooling valves, Core Spray A injection valves, and SLC pump A. The SRO will determine the Technical Specification impact.

SRV C will inadvertently open. The crew will execute AOP-36, Stuck Open Relief Valve(s) . The crew will take actions to close SRV C. The valve will close when the isolation switch in the field is manipulated. The crew will place Torus cooling in service on RHR loop B. RHR loop A will be unavailable from the earlier loss of Bus L 15.

SRV C will re-open due to mechanical failure . The crew will execute AOP-36, Stuck Open Relief Valve(s) .

The crew will take actions to close SRV C, but the valve will not close . The crew may lower Reactor power in anticipation of a Reactor scram . The crew will execute EOP-4, Primary Containment Control, and EOP-2, RPV Control. The crew will manually scram the Reactor per AOP-1, Reactor Scram, before Torus water temperature reaches 11 0°F. Following the scram, the Main Turbine will fail to automatically trip. The crew "will execute guidance in AOP-1 to manually trip the Main Turbine.

The SRV C tailpipe will develop a break in the Torus airspace. This will result in rising Containment pressures and temperatures. The crew will attempt to control Containment conditions by initiating Torus and Drywell spray. RHR loop A will be unavailable for sprays due to the earlier loss of L-15. RHR pumps B and D will trip, resulting in loss of the ability to spray with RHR. The crew will attempt to spray using RHR Service Water. Loop A will be unavailable due to the earlier loss of Bus L 15. Loop B will be unavailable due to failure of one of the crosstie valves to open. With no Torus and Drywell spray capability, Containment conditions will exceed the Pressure Suppression Pressure. The crew will execute and Emergency RPV Depressurization .

The scenario will be terminated when all control rods are inserted, the Emergency RPV Depressurization is in progress, and Reactor water level is controlled above 0".

LOI 14-2 NRC Examination Scenario 3 Page 4 of 25

Shift Turnover The Plant is operating at approximately 100% power.

Air Compressor B is out of service for maintenance.

When you take the shift:

1. Start RBCLC pump A and secure RBCLC pump C per OP-40 section G.1.

2. Lower Reactor power using Recirculation flow per the provided Reactivity Maneuver Instructions.

LOI 14-2 NRC Examination Scenario 3 Page 5 of 25

Critical Tasks/Standards Critical Task #1: Given a stuck open SRV, the crew will scram the Reactor before Torus water temperature exceeds the Boron Injection Initiation Temperature, in accordance with AOP-36 and EOP-4.

Critical Task #2: Given the inability to maintain Primary Containment conditions inside the Pressure Suppression Pressure, the crew will perform an Emergency RPV Depressurization, in accordance with EOP-4.

LOI 14-2 NRC Examination Scenario 3 Page 6 of 25

EVENT NO. EVENT SEQUENCE

1. Swap RBCLC Pumps (Normal: BOP, SRO)

Lower Reactor Power to 95% (Reactivity: ATC, SRO)

2. Using Recirculation Flow Recirc Flow Unit Failure (Instrument: All) 3.

(Tech Spec: SRO)

Electrical Fault on Bus L-15 (Component: BOP, SRO) 4.

(Tech Spec: SRO)

5. SRV C Inadvertently Opens (Component: BOP, SRO)

SRV C Re-Opens, SRV Tailpipe (Major: All) 6.

Break Into Torus Airspace

7. Main Turbine Fails to Trip (Instrument: ATC, SRO)

,) 8.

RHR Pump Trip, RHR Pump Suction Valve (Component: BOP, SRO)

Fails Closed, RHRSW Crossties Fail Closed D. TERMINATION CUES:

All control rods are inserted

Emergency RPV Depressurization is in progress

Reactor water level is controlled above 0" LOI 14-2 NRC Examination Scenario 3 Page 7 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow All no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch Event1 SRO SAT/UNSATINA Swap RBCLC Pumps

Perform Crew Brief

Direct BOP to start RBCLC pump A and secure RBCLC pump C per OP-40 section G.1 BOP SAT I UNSAT INA Role Play:

Start RBCLC pump A If dispatched to perform any pump checks, immediately

Verify RBCLC pump motor current is LESS THAN maximum normal amps report that the requested pump checks are SAT.

Place and hold control switch for RBCLC pump C in STOP until RBCLC System discharge header pressure is stable at GREATER THAN 75 psig, then release control switch

Verify RBCLC pump motor current for the running RBCLC pumps is LESS THAN maximum normal amps LOI 14-2 NRC Examination Scenario 3 Page 8 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event2 SRO SAT I UNSAT INA Lower Reactor Power to 95%

Using Recirculation Flow

Direct ATC to lower power to 95% with Recirc flow

Provide oversight for reactivity manipulation ATC SAT I UNSAT INA

Lower Recirc flow alternately with RWR MG A(B) SPEED CNTRL '

Monitor APRMs, CTP, Recirc flow, Reactor water level BOP SAT I UNSAT INA

Assist ATC with peer checks and plant monitoring LOI 14-2 NRC Examination Scenario 3 Page 9 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event3 ATC SAT I UNSAT INA On Lead Examiner Cue:

Recognize I report multiple annunciators, including 09-5-2-25, ACTIVATE TRIGGER 1 FLOW REF OFF NORM Recirc Flow Unit Failure

Recognize I report APRMs 8, D, and F indicate normally but have an upscale trip

Recognize I report half scram SRO SAT I UNSAT INA

Acknowledge report

Direct ARP response

Direct bypassing Recirc flow unit 8 per OP-16

Direct reset of half scram

Determine one of two required channels of Technical Specification Table 3.3.1 .1-1 Function 2b is not operable with an inoperable Recirc flow unit

Determine Technical Specification 3.3.1 .1 Condition A must be entered (place channel in trip or place associated trip system in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

Determine one of four required channels of TRM Table T3.3.8-1 Function 1b is not operable with an inoperable Recirc flow unit

Determine TRM 3.3.8 Condition A must be entered (restore inoperable channel within 7 days)

LOI 14-2 NRC Examination Scenario 3 Page 10 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC SAT/UNSAT/NA

Coordinate with BOP to bypass Recirc flow unit 8 per OP-16 Section E.21:

0 Place RWR FLOW UNIT BYP switch in 8 0 Verify the following FLOW UNIT indications:

Associated BYPASS indicating light is on

Associated UPSC OR INOP light is off

Associated COMPAR light is off SAT I UNSAT INA 0 Verify BYPASS light is off for other flow unit channel on same side 0 Verify white BYP light in on at top of panel 09-14 for FLOW UNITS 0 IF a flow unit is declared inoperable, THEN one of the two required APRM Neutron Flux-High (flow biased) Channels in the associated trip system must be considered inoperable 0 Coordinate with BOP to place switch S-1 on FLOW UNIT 8 to INT TEST at panel 09-14

Reset half scram per ARP:

' 0 Place RX SCRAM RESET switch to GROUP 2 & 3, then to GROUP 1 & 4, spring return to NORM 0 Verify RPS 8 SCRAM GROUPS 1, 2, 3, and 4 lights are on BOP SAT I UNSAT INA

Assist ATC with actions and/or plant monitoring, as required

Place switch S-1 on FLOW UNIT 8 to INT TEST at panel 09-14 LOI 14-2 NRC Examination Scenario 3 Page 11 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event4 BOPIATC SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 2

Recognize I report multiple annunciators Electrical Fault on Bus L-15

Recognize I report loss of L-15 SRO SAT I UNSAT INA

Acknowledge reports

Enter AOP-18A, Loss of Switchgear L 15

Enters I exits EOP-5, Secondary Containment Control, due to Reactor Building DIP

Determine operability is affected for Core Spray, RHR, SLC, PCIS, MSLCS, LPCI MOV IPS, and SGT

Determine most limiting Technical Specification entry is LCO 3.8.7 Condition A, which requires restoring L-15 to operable status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months BOP SAT I UNSAT INA Role Play: I

Execute AOP-18A, Loss of Switchgear L 15 If dispatched to investigate, wait 2 minutes, then report 0 Attempt to maintain drywell pressure by controlling drywell that the L-15 supply breaker temperature as follows:

(11502) is tripped and appears

Ensure running Drywell Cooling Fans 68FN-2B, 2D, to be damaged. 4B, 4D

Consider initiating Torus Vent per OP-37

Consider lowering RBC temperature below normal LOI 14-2 NRC Examination Scenario 3 Page 12 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP cont. SAT/UNSAT/NA 0 Isolate Reactor Building Ventilation as follows:

0 Ensure running, Standby Treatment System "B" per OP-20

Open BELOW EL 369' SUCT 01-125MOV-12

Open TRAIN B INLET 01-125MOV-14B 0 Depress RB VENT ISOL B pushbutton at 09-75 0 Verify Reactor Building Isolation per Section G of OP-51A, refer to Attachment 1 for de-energized valves 0 Refer to Attachment 1 for affected loads 0 Refer to Attachment 2 for multiple alarms associated with L151oads 0 Consider shutting down the following systems:

RWCU System

Fuel Pool Cooling System 0 Direct Electricians to measure "A" LPCI Inverter Battery 71 BAT-3a parameters every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LOI 14-2 NRC Examination Scenario 3 Page 13 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 5 BOPIATC SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 3

Recognize I report annunciators:

SRV C Inadvertently Opens 0 09-4-1-16, SRV Leaking 0 09-4-2-6, SRV Sonic Man Alarm Hi

Recognize I report SRV C open Note: SRO SAT I UNSAT INA RHR loop A is unavailable for

Acknowledge report Torus Cooling due to loss of Bus L-15.

Enter AOP-36, Stuck Open Relief Valve

If Torus water temperature exceeds 95°F or Torus water level exceeds 14.0 feet, enter EOP-4, Primary Containment Control

Direct initiation of Torus Cooling

Determine SRV C is inoperable, but is not a required ADS valve per Technical Specification 3.5.1 BOP SAT I UNSAT INA

Execute AOP-36 0 Identify open SRV 0 Determine annunciator 09-4-2-37 is NOT in alarm 0 Determine annunciator 09-4-3-3 is NOT in alarm 0 Cycle SRV C control switch at panel 09-4 0 Direct Operator to place SRV C isolation switch in LOCAL at panel 25ASP-5 0 Determine SRV C closed LOI 14-2 NRC Examination Scenario 3 Page 14 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP SAT I UNSAT INA Role Play:

0 Direct Operator to remove the four control power fuses for When directed to place SRV C SRV C at panel 09-45 isolation switch in LOCAL, wait 2 minutes, insert Trigger 0 Direct Operator to place SRV C isolation switch in 25, wait approximately 15 REMOTE at panel 25ASP-5 seconds, then report task 0 Monitor Torus water temperature completion.

Initiate Torus Cooling per OP-138 posted attachment:

Role Play: 0 Ensure at least one of the RHR pumps is running When directed to remove SRV 0 Open RHR TEST TORUS CLG & SPRAY 1OMOV-398 C fuses, wait 1 minute, insert 0 Throttle RHR TEST & TORUS CLG 1OMOV-348 to Trigger 26, then report task completion. establish desired/flow 0 WHEN RHR Loop A(B) flow is GREATER THAN 1500 Role Play: gpm, ensure closed MIN FLOW VLV 10MOV-168 When directed to place SRV C 0 Establish RHRSW flow and temperature control isolation switch in REMOTE,

Initiate RHRSW per OP-13C posted attachment:

wait 1 minute, re-insert remote AD07:C in remote, wait 0 Start one of the RHRSW pumps approximately 15 seconds, 0 Throttle RHRSW DISCH VLV FROM HX 8 10MOV-89B to then report task completion. establish 2500 to 4000 gpm 0 Start the second RHRSW pump if desired 0 Throttle RHRSW DISCH VLV FROM HX 8 10MOV-898 to establish 2500 to 4000 gpm per RHRSW pump 0 Close HX 8 BYP VLV 1OMOV-668 LOI 14-2 NRC Examination Scenario 3 Page 15 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Events 6 1 7 1 & 8 BOP I ATC SAT I UNSAT INA On Lead Examiner Cue:

Recognize I report annunciator 09-4-2-6, SRV Sonic Mon ACTIVATE TRIGGER 4 Alarm Hi SRV C Re-Opens, SRV Tailpipe Break Into Torus

Recognize I report SRV C open Airspace, Main Turbine Fails to Trip, RHR Pump Trip, RHR Pump Suction Valve Fails Closed, RHRSW Crossties Fail Closed Note:

Ensure Trigger 6 automatically goes active when the Reactor scrams to cause the SRV tailpipe break.

Critical Task #1 Given a stuck open SRV, the crew will scram the Reactor Pass I Fail before Torus water temperature exceeds the Boron Injection Initiation Temperature, In accordance with AOP-36 and EOP*

4.

Critical Tak ..W Standard: The Reactor Ia scrammed.

Critical Taka Given the Inability to maintain Primary Containment Pass/Fall c:ondllona Inside tile Pressure Suppreaalon Pressure, the crew Wfll Pllfon'b .,. Emergency RPV Depressurization, in accordanc.wlth EOP-4.

7SRVsareopen.

Critical Tak t2 Standard:

LOI 14-2 NRC Examination Scenario 3 Page 16 of 25

IINSTRUCTORACTIVITY --T POSITION I OPERATORACTIONS/STANDARD I COMMENTS/EVALUATION I SRO SAT I UNSAT INA

Acknowledge report

Enter AOP-36, Stuck Open Relief Valve

Acknowledges SRV C will NOT close

Enters I re-enters EOP-4, Primary Containment Control on high Torus water temperature, if required

May direct rapid Reactor power reduction with Recirculation flow and/or CRAM rods

Before Torus water temperature exceeds 110°F, direct Reactor scram Critical Task #1

Enter AOP-1 , Reactor Scram

Enter EOP-2, RPV Control, on low Reactor water level

Direct Reactor water level controlled 180-220" using Feedwater

Direct Reactor pressure controlled 800-1 000# using Turbine Bypass Valves

Direct preventing injection from Core Spray and RHR as Reactor pressure lowers

May direct closing MSIVs

Acknowledge degrading Primary Containment conditions

Re-enter EOP-2 on high Drywell pressure

Re-enter EOP-4 on high Drywell pressure and temperature LOI 14-2 NRC Examination Scenario 3 Page 17 of 25

I INSTRUCTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD I COMMENTS/EVALUATION SRO cont. SAT I UNSAT INA

When Primary Containment pressure exceeds 2. 7 psig and before Torus pressure exceeds 15 psig, direct initiation of Torus Spray

Acknowledge trip of RHR pump and inability to spray using RHR

Direct Torus Spray using RHRSW per EP-14

Acknowledge inability to spray using RHRSW

When Torus pressure exceeds 15 psig, determine unable to spray Drywell Note:

Monitor Primary Containment conditions on Pressure The Pressure Suppression Suppression Pressure curve Pressure is approximately 26-

When Torus pressure cannot be maintained below the 28 psig at the Torus water Pressure Suppression Pressure, direct opening 7 ADS Critical Task #2 level expected during this valves scenario.

Acknowledge that less than 7 ADS valves are open

Direct opening additional SRVs until a total of 7 SRVs are open

Acknowledge that 7 SRVs are open LOI 14-2 NRC Examination Scenario 3 Page 18 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP SAT I UNSAT INA Role Play:

Execute AOP-36 When directed to place SRV C isolation switch in LOCAL, 0 Identify open SRV wait 2 minutes, then report 0 Determine annunciator 09-4-2-37 is NOT in alarm task completion . Use Trigger 27 and the associated 0 Determine annunciator 09-4-3-3 is NOT in alarm annunciator override as 0 Cycle SRV C control switch at panel 09-4 necessary to simulate opening/closing the door to 0 Direct Operator to place SRV C isolation switch in LOCAL 25ASP-5 (but do NOT use at panel 25ASP-5 remotes to actually cycle 0 Determine SRV C is open isolation switch or pull SRV fuses). 0 Direct Operator to place SRV C isolation switch in REMOTE at panel 25ASP-5 0 Monitor Torus water temperature

Enter AOP-1

Control Reactor water level 180-220" using Feedwater LOI14-2 NRC Examination Scenario 3 Page 19 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC SAT I UNSAT INA

Enter AOP-1

Depress MANUAL SCRAM A and MANUAL SCRAM 8 push buttons Critical Task #1

Place RX MODE switch in SHUTDOWN

Fully insert IRMs and SRMs

Observe Reactor power lowering

Ensure closed SDIV vent and drain valves

Recognize I report failure of Main Turbine to automatically trip, if not manually tripped before automatic trip required

Manually trip Main Turbine

Verify 4KV loads transfer to reserve power ATC I BOP SAT I UNSAT INA

May attempt to initiate Torus spray:

Note: 0 Place SPRAY CNTRL 10A-S17B switch to MANUAL, i spring return to normal RHR loop A is unavailable to spray due to loss of Bus L-15. 0 Verify white SPRAY PERM 1OA-DS678 light is on RHR pumps B and D trip on a 0 May attempt to start RHR pump time delay after the scram.

Therefore, RHR is unavailable 0 Recognize I report trip of RHR pumps 8 and D to spray either the Torus or 0 Recognize I report inability to spray using RHR the Drywell.

LOI 14-2 NRC Examination Scenario 3 Page 20 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC/80P SAT I UNSAT INA

cont.

Attempt to initiate Torus spray using RHRSW per EP-14:

0 Verify RHR pumps 8 and D are stopped 0 Ensure closed 1OMOV-268 and/or 1OMOV-31 8 0 Ensure closed 1OMOV-398 and/or 1OMOV-388 0 Ensure closed 1OMOV-398 and/or 1OMOV-348 0 Ensure closed 1OMOV-258 and/or 1OMOV-278 0 Ensure RHRSW pumps 8 and D are running 0 Ensure RHRSW DISCH VLV FROM HX 8 10MOV-898 is throttled to establish 2500 to 4000 gpm per RHRSW pump.

0 Attempt to open both of the following valves:

RHRSW TO RHR 10MOV-1488

RHRSW TO RHR 10MOV-1498 0 Recognize I report 10MOV-1498 fails to open 0 Recognize I report inability to spray using RHRSW LOI 14-2 NRC Examination Scenario 3 Page 21 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION .

ATC/BOP SAT/UNSAT/NA cont.

May close MSIVs, as directed Note:

Verify isolations per AOP-15, as time permits Critical Task #2 SRV C is inoperable and unable to be opened. SRV G

Attempt to open 7 ADS valves is failed open, and therefore

Recognize I report less than 7 ADS valves open may not be counted by the crew as open for the purposes

Open additional SRVs until 7 SRVs are open of Emergency RPV Depressurization. Therefore,

Restore and maintain Reactor water level 180-220" using the crew may open either one available injection systems or two additional non-ADS

Control Core Spray injection:

SRVs.

0 Throttle 14MOV-12B

Control LPCI injection:

0 Throttle 10MOV-27A 0 Secure RHR pumps if needed

'~** -----------

Termination Criteria:

All control rods are inserted

Emergency RPV Depressurization is in progress

Reactor water level is controlled above 0" LOI 14-2 NRC Examination Scenario 3 Page 22 of 25

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 100% power.

Air Compressor 8 is out of service for maintenance.

When you take the shift:

1. Start RBCLC pump A and secure RBCLC pump C per OP-40 section G.1.

2. Lower Reactor power using Recirculation flow per the provided Reactivity Maneuver Instructions.

LOI 14-2 NRC Examination Scenario 3 Page 23 of 25

ATTACHMENT 9.4 REACTIVITY MANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps- (site specific control rod movement control sheet format is to be used)

Power Reduction EN-RE-215 Attach 9.4 Today Page 1 of 1 From To Cplg RSCS I nit Step Action Rod Method Notes Notch Notch Chk Grp Lower power Target rate= 1% RTP per 1

to 95% RTP

- - - RWR NA - minute

('

Prepared By: SM Approval: VOIN~'&~

(RxEng) (Shift Manager)

Reviewed By: 'Bob- Tone.t (RxEng or SRO)

Stamps CONTROL ROOM OPERATOR LOI14-2 NRC Examination Scenario 3 Page 24 of 25

ATTACHMENT 9.4 REACTIVITY MANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps- (site specific control rod movement control sheet format is to be used)

Power Reduction EN-RE-215 Attach 9.4 Today Page 1 of 1 From To Cplg RSCS Init Step Action Rod Method Notes Notch Notch Chk Grp Lower power Target rate= 1% RTP per 1

to 95% RTP

- - - RWR NA - minute 0

Prepared By: SM Approval: Va.v~'RO"et (RxEng) (Shift Manager)

Reviewed By: Bob- TO'rt.e4' (RxEng or SRO)

Stamps INDEPENDENT VERIFIER LOI14-2 NRC Examination Scenario 3 Page 25 of25

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 14-2 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 65% power. Circulating Water pump C is ready to be returned to service following maintenance.

Turnover: Start Circulating Water pump C per OP-4 section 0 .17. Then , raise Reactor power using Recirculation flow per the provided reactivity instruction .

Event Malf. Event Event No. No. Type* Description N- Start Circulating Water Pump C 1 N/A BOP, SRO OP-4 R- Raise Reactor Power with Recirculation Flow 2 N/A ATC, SRO OP-27 1-ATC, Recirculation Pump B Runs High 3 Override SRO OP-27, Technical Specifications C- Loss of Steam Packing Exhauster A 4 Override BOP, SRO ARP 09-7-3-43, OP-240 C- Loss of RBCLC Flow to Recirculation Pump B 5 SW01:B BOP, SRO OP-27, AOP-8, Technical Specifications Main Steam Leak into Turbine Building 6 MS05 M-All AOP-40, AOP-1 , EOP-2 1-ATC, All MSIVs Fail to Automatically Close 7 RP12 SRO AOP-40 FW03/04 Loss of High Pressure Injection 8 RD06 M-All EOP-2 Override Override I-BOP, HPCI Flow Controller Failure in Automatic, HPCI Trips 9

HP02 SRO OP-15, EOP-2 RC02 RCIC Fails to Automatically Initiate, RCIC Trips, ADS Fails to 10 RC03 I-AII Automatically Initiate AD01 OP-19, EOP-2

(N)ormal , (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 14-2

1. Total malfunctions (5-8) 8 Even~3,4,5,6, 7,8,9,10

2. Malfunctions after EOP entry (1-2) 3 Even~ 7, 9, 10

3. Abnormal events (2-4) 3 Even~ 3, 4, 5

4. Major transients (1-2) 2 Even~ 6 & 8

5. EOPs entered/requiring substantive actions (1-2) 1 EOP-2

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS:

CT -1: Given a loss of all RBCLC flow to an operating Recirculation pump, prevent a prolonged Recirculation seal loss of coolant accident by one or more of the following, in accordance with OP-27:

Securing the Recirculation pump

Isolating the Recirculation pump CT-2: Given a Main Steam leak into the Turbine Building and a failure of the MSIVs to automatically close, isolate the Main Steam lines, in accordance with AOP-40.

CT-3: Given the Reactor above the injection pressure of adequate injection sources, lower Reactor pressure to allow adequate Reactor injection, in accordance with EOP-2.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI14-2 NRC EXAMINATION SCENARIO 4 TITLE: LOI14-2 NRC EXAMINATION SCENARIO 4 SCENARIO NUMBER: NRC4 PATH: STAND ALONE Validation: _;z;:-/"- --;z _.. . _. -- Training: J~ Operations~~z~

u CANDIDATES CRS ATC BOP LOI 14-2 NRC Examination Scenario 4 Page 1 of 23

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INinATOR REVIEWED 5/22/14 New New Scenario T. Hooper LOI 14-2 NRC Examination Scenario 4 Page 2 of 23

A. TITLE: LOI14-2 NRC EXAMINATION SCENARIO 4 B. SCENARIO SETUP:

1. IC-64

2. Speciallnstructions:

a. The Plant is operating at approximately 65% power.

b. Circulating Water pump C is ready to be returned to service.

3. Preset Conditions:

a. TRIGGER 1, O:RR ZAID218416B, MG Set B Digital Speed Control, lnitial=14.3, Final=25, Ramp=4 minutes

b. TRIGGER 2, O:MS ZDI11VACN05, SPE A, STOP

c. TRIGGER 3, M:SW01 :B, Loss of RBCLC Flow to Recirculation Pump B

d. TRIGGER 4, M:MS05, Steam Leakage Outside Primary Containment, Final=15, Ramp=3 minutes

e. Preset, M:RP12:A, PCIS Group 1 Inboard MSIV Isolation Failiure

f. Preset, M:RP12:B, PCIS Group 1 Outboard MSIV Isolation Failiure

g. Preset, M:HP04, HPCI Flow Auto Flow Controller Failure, 0%

h. TRIGGER 5, M:HP02, HPCI Turbine Trip, Delay=1 0 seconds

i. Preset, M:RC02, RCIC System Failure to Auto Start

j. TRIGGER 6, M:RC03, RCIC System Turbine Trip, Delay=1 minute

k. Preset, M:AD01, ADS Timer Fails to Start I. TRIGGER 7, M:FW03:A, Rx Feedwater Pmp A Auto Controller Failure, Finai=O, Delay= 10 seconds

m. TRIGGER 7, M:FW03:B, Rx Feedwater Pmp B Auto Controller Failure, Finai=O, Delay= 10 seconds

n. TRIGGER 7, M:FW04:A, Rx Feedwater Pmp A Manual Controller Failure, Finai=O, Delay= 10 seconds

o. TRIGGER 7, M:FW04:B, Rx Feedwater Pmp B Manual Controller Failure, Finai=O ,

Delay= 10 seconds

p. TRIGGER 7, M:RD06:A, CRD Hydraulic Pump Trip A , Delay=1 0 seconds

q. TRIGGER 7, M:RD06:B, CRD Hydraulic Pump Trip B, Delay=1 0 seconds

r. Preset, OS:SL ZDI11S1, SBLC Selector Switch, STOP

s. Preset, M:HP04, HPCI Flow Auto Controller Failure, 0%

t. Event Trigger 1, Event: rrfpa(2)>3150, Command: None

u. Event Trigger 5, Event: hpfd>1 00, Command : None

v. Event Trigger 6, Event: rcfd>15, Command: None

w. Event Trigger 7, Event: (zlo5ads8a == 0) && (zlo5ads8b == 0), Command: None

4. Consumable Forms and Procedures:

+ AOP-1, AOP-8, AOP-40 LOI 14-2 NRC Examination Scenario 4 Page 3 of 23

C. SCENARIO

SUMMARY

"'The scenario will begin with the plant operating at approximately 65% power. The crew will begin by starting Circulating Water pump C. The crew will then raise power with Recirculation flow.

Recirculation pump B will run high. The crew will lock the Recirculation pump B scoop tube to stop the uncontrolled positive reactivity addition. This malfunction will result in a Recirculation flow mismatch. The SRO will determine the Technical Specification impact.

The running Steam Packing Exhauster will trip. The crew will respond to the ARP to start the standby Steam Packing Exhauster, and re-establish adequate system parameters.

All RBCLC flow to Recirculation pump B will isolate. This will cause multiple high temperature alarms. If left unmitigated, this will cause degradation of both Recirculation pump B seals and loss of coolant into the Drywell. The crew will secure Recirculation pump B. If damage has occurred to both pump seals, the crew will also isolate Recirculation pump B to stop the loss of coolant. The crew will execute AOP-8 due to the reduction in core flow. The SRO will determine the Technical Specification impact.

A Main Steam leak will develop in the Turbine Building. All automatic closures of the MSIVs will fail. The crew may lower Reactor power in anticipation of a Reactor scram. The crew will scram the Reactor and manually close the MSIVs to stop the leak.

, Following the scram , the Feedwater pump controllers will fail low, resulting in a loss of the normal high pressure injection source. HPCI will be available for start, however the automatic flow controller will fail such that HPCI does not automatically inject. The crew will inject with HPCI by taking manual control of the flow controller. HPCI will trip soon after injection is started. RCIC will be available for start, but will fail to automatically start if an automatic initiation signal is received. The crew will manually start RCIC . The running CRD pump will trip and the standby pump will trip upon start. Both SLC pumps will fail to start. With MSIVs closed, the crew will control Reactor pressure with SRVs. With Reactor coolant inventory being lost through the SRVs and only RCIC available as a high pressure injection source, Reactor water level control will be challenged.

RCIC will then trip. The crew will lower Reactor pressure using SRVs and inject with Condensate Booster pumps to restore Reactor water level.

The scenario will be terminated when all control rods are inserted and Reactor water level is controlled above 0".

LOI14-2 NRC Examination Scenario 4 Page 4 of 23

Shift Turnover

' T he Plant is operating at approximately 65% power.

Circulation Water pump C is ready to be returned to service following maintenance.

When you take the shift:

1. Start Circulating Water pump C per OP-4 section 0.17. The procedure is in progress up to step D.17.3.e.

2. Then , raise Reactor power using Recirculation flow per the provided reactivity instruction.

Stop at approximately 75% power for further Reactor Engineering instructions.

LOI14-2 NRC Examination Scenario 4 Page 5 of 23

Critical Tasks/Standards

' Critical Task #1: Given a loss of all RBCLC flow to an operating Recirculation pump, prevent a prolonged Recirculation seal loss of coolant accident by one or more of the following, in accordance with OP-27:

Securing the Recirculation pump

Isolating the Recirculation pump Critical Task #2: Given a Main Steam leak into the Turbine Building and a failure of the MSIVs to automatically close, isolate the Main Steam lines, in accordance with AOP-40 .

Critical Task #3: Given the Reactor above the injection pressure of adequate injection sources, lower Reactor pressure to allow adequate Reactor injection, in accordance with EOP-2.

LOI 14-2 NRC Examination Scenario 4 Page 6 of 23

EVENT NO. EVENT SEQUENCE

1. Start Circulating Water Pump C (Normal: BOP, SRO)

2. Raise Reactor Power with Recirculation Flow (Reactivity: ATC, SRO)

3. Recirculation Pump B Runs High (Instrument: ATC, SRO)

4. Loss of Steam Packing Exhauster A (Component: BOP, SRO)

5. Loss of RBCLC Flow to Recirculation Pump B (Component: BOP, SRO)

6. Main Steam Leak into Turbine Building (Major: All)

7. All MSIVs Fail to Automatically Close (Instrument: ATC, SRO)

8. Loss of High Pressure Injection (Major: All)

HPCI Flow Controller Failure in Automatic, (Instrument: BOP, SRO)

9. HPCI Trips RCIC Fails to Automatically Initiate, RCIC Trips, (Instrument: All) 10.

ADS Fails to Automatically Initiate D. TERMINATION CUES:

All control rods are inserted .

Reactor water level is being controlled above 0".

L0114-2 NRC Examination Scenario 4 Page 7 of 23

INSTkuCTOR ACTIVITY POSITION OPERAI OR ACTIONS/STANDARD COMMENTS I EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow All no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch I

Event1 SRO SAT/UNSAT/NA I Start Circulating Water Pump c

Perform Crew Brief

Direct BOP to start Circulation Water pump C per OP-4 section D.17 BOP SAT I UNSAT INA

Place and hold CIRC WTR PMP C 36P-1 C control switch in START Role Play:

WHEN Circulating Water Pump C 36P-1C starts, release CIRC If asked for pre- and post-start WTR PMP C 36P-1 C control switch checks, immediate report checks are SAT.

Verify CIRC WTR PMP DISCH VLV 36MOV-100C is full open When asked about seal water

Verify discharge valve for each running circulating water pump pressure, wait 1 minute, then is full open report Circulating Water pump C seal water pressure is 25

Verify seal water pressure is GREATER THAN OR EQUAL TO psig and stable. 20 psig on 36PI-111 C (eire water pump C seal water press indic) at northwest corner of eire pump pit

Verify all white lights for RPS A and RPS B power source selectors are on at panel 09-16 LOI14-2 NRC Examination Scenario 4 Page 8 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Event 2 SRO SAT I UNSAT INA Raise Reactor Power with Recirculation Flow

Direct ATC to raise power to 75% with Recirc flow

Provide oversight for reactivity manipulation ATC SAT I UNSAT INA Booth Operator:

Raise Recirc flow alternately with RWR MG A(B) SPEED Ensure Trigger 1 automatically CNTRL activates when Recirculation pump B flow exceeds

Monitor APRMs, CTP, Recirc flow, Reactor water level approximately 11.5 Mlbmlhr to initiate the next event.

LOI 14-2 NRC Examination Scenario 4 Page 9 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Event3 ATC SAT I UNSAT INA Recirculation Pump B Runs High

Recognize I report Recirculation pump B speed controller is malfunctioning SRO SAT I UNSAT INA

Acknowledge report

Direct lock-up of Recirculation pump B scoop tube per OP-27 Section G.6 Note:

Enter AOP-8 (Unexpected Change in Core Flow)

Depending on the speed of

Enter AOP-32 (Unexplained/Unanticipated Reactivity Change) the crew's actions to lock-up Recirculation pump B scoop

Determine compliance with Technical Specification 3.4.1:

tube, the resulting 0 If core flow <70% (53.9 Mlb/hr), flow mismatch must be Recirculation loop flow ~10% (7.7 Mlb/hr) mismatch may vary.

0 If core flow ~70% (53.9 Mlb/hr), flow mismatch must be

~5% (3.85 Mlb/hr) 0 If these limits not met, enter Condition Band restore within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ATC SAT I UNSAT INA Role Play:

Place RWR B SCOOP TUBE control switch to TRIP If asked as management or Reactor Engineering about

Place SCOOP TUBE B AUTO UNLOCK control switch in ON how to restore Recirculation

Monitor for Thermal Hydraulic Instabilities I flow mismatch to within limits, direct the crew to maintain

Monitor Feedwater response Recirculation flow at the current value until further investigation and analysis is completed.

LOI 14-2 NRC Examination Scenario 4 Page 10 of 23

INSTRuCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Event 4 ATC/BOP SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 2

Recognize I report annunciator 09-7-3-43, SPE VAC LO Loss of Steam Packing

Recognize I report neither Steam Packing Exhauster is running Exhauster A SRO SATIUNSATINA

Acknowledge report

Direct ARP response

Direct starting standby Steam Packing Exhauster BOP SATIUNSATINA Role Play:

Execute ARP 09-7-3-43 If dispatched to investigate Steam Packing Exhauster A,

Start Steam Packing Exhauster B per OP-24D section G.1:

wait 2 minutes, then report 0 Start SPE B 38C-5B that the breaker for Steam Packing Exhauster A is tripped 0 Throttle open SPE B DISCH 38MOV-D2 until red open but there are no other indicating light comes on (dual position indication) abnormal conditions. 0 Close SPE A DISCH 38MOV-D1, while throttling SPE B DISCH 38MOV-D2 to establish 10 to 20 inches of water vacuum on VAC 94PI-09 LOI 14-2 NRC Examination Scenario 4 Page 11 of 23

INSTkLJCTOR ACTIVITY POSITION OPERAl OR ACTIONS/STANDARD COMMENTS I EVALUATION Event 5 BOPIATC SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 3

Recognize I report EPIC low flow alarm Loss of RBCLC Flow to

Recognize I report multiple annunciators, including:

Recirculation Pump B 09-4-3-16, RWR PMP B SEAL CLR FLOW LO 0

0 09-4-3-26, RWR PUMP B MTR WINDING CLR FLOW LO 0 09-4-3-33, RWR PMP A OR B TEMP HI Critical Task *1 Given a loss of all RBCLC flow to an operating Recirculation Pass/ Fall pump, prevent a prolonged Recirculation seal loss of coolant accident by one or more of the following, In accordance with OP-27:

Securing the Recirculation pump

Isolating the Recirculation pump Critical Task *1 Standard: Stop Recirculation pump B.

And/or Isolate Recirculation pump B.

SRO SATIUNSATINA

Acknowledge reports

Direct ARP execution Critical Task #1

Direction shutdown of Recirculation pump B per OP-27

Enter AOP-8 (Unexpected Change in Core Flow)

Determine Technical Specification 3.3.1.1 Condition C and TRO 3.3.8 Condition C entry is required (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to establish single loop limits for APRM flow biased scram and rod block)

Determine Technical Specification 3.4.1 Condition B entry is required (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

LOI 14-2 NRC Examination Scenario 4 Page 12 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION BOP SAT I UNSAT INA

Execute ARP 09-4-3-16, as time permits:

0 Monitor seal cavity temps on 02TR-031 (points 20 & 21) 0 If seal cavity temp increases to 250°F, then shutdown B Note: RWR pump per Section G of OP-27 Some indication for 15FIS- 0 Ensure open 15AOV-132B and 15AOV-133B 102B is available on EPIC Verify RBC flow rate >300 gpm on 15FIS-102B 0

screen RWRB 1.

0 Monitor OW leakage for signs of seal leakage Role Play:

Execute ARP 09-4-3-26, as time permits:

If dispatched to check RBC 0 Monitor temps on 02-2TR-31 flow rate to RWR pump B, wait 2 minutes, then report that 0 Verify RBC flow rate >300 gpm on 15FIS-102B there is no RBC flow to RWR 0 If RBC flow cannot be restored and RWR pump and motor pump B. temps are rising, then shut down RWR loop B per OP-27 Section G 0 Monitor OW sump levels

Execute ARP 09-4-3-33, as time permits:

0 Check 02-2TR-31 0 Check RBC temp 0 Check RBC lineup and verify at least 300 gpm on 15-FIS-102B 0 Monitor computer and annunciators for problem 0 Monitor OW leakage for possible leak in RBC system 0 If any RWR motor bearing exceeds 220°F, then shut down RWR pump per Section G of OP-27 LOI 14-2 NRC Examination Scenario 4 Page 13 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION BOP cont. SAT I UNSAT INA

Secure Recirculation pump B per OP-27:

0 Close RWR PMP 8 DISCH 02MOV-538 Critical Task #1 Note: 0 Verify RWR PMP 02-2P-1 B is tripped If Recirculation pump B is 0 Place RWR PMP 02-2P-1 B control switch in PULL TO secured before damage to the LOCK seals results in coolant 0 Verify open RWR MG B GEN FIELD BKR leakage into the Drywell, isolation of the pump is not 0 IF loop 8 isolation is required, THEN ensure closed the required to meet the critical following valves: Critical Task #1 task.

RWR PMP 8 DISCH 02MOV-538 Role Play:

RWR PMP 8 SUCT 02MOV-438 If dispatched to close 02-

02-2RWR-39B (RWR pump B seal purge upstr isol 2RWR-39B, wait 2 minutes, valve) then report task completion.

Coordinate with ATC to execute AOP-8, as time permits

Monitor for thermal-hydraulic instability Note:

It is expected to move to the

Ensure RPV water level returns to normal and stabilizes next event before the crew

Determine operating point on Power-Flow Map addresses Recirculation loop temperature and SLO

Demand a 3D Monicore Official Program and review margin to scram/rod block setpoint thermal limits issues.

ATC SAT I UNSAT INA

Monitor Reactor power

Monitor for thermal-hydraulic instability

Monitor Feedwater response

~~ -

LOI14-2 NRC Examination Scenario 4 Page 14 of 23

INSTklJCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION Events 61 71 81 & 9 ATCIBOP SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 4

Recognize I report annunciator 09-3-1-39, TURB BLDG ARM RADHI Main Steam Leak into Turbine Building , All MSIVs Fail to

Recognize I report rising radiation levels in Turbine Building Automatically Close Loss of High Pressure Injection HPCI Flow Controller Failure in Automatic, HPCI Trips RCIC Fails to Automatically Initiate, RCIC Trips, ADS Fails to Automatically Initiate r Critical Task #2 Given a Main Steam leak into the Turbine Building and a Pass I Fail failure of the MSIVs to automatically close, isolate the Main Steam lines, in accordance with AOP-40.

I Critical Task #2 Standard: Close at least one MSIV in each Main Steam line.

Critical Task #3 Given the Reactor above the injection pressure of adequate Pass I Fail injection sources, lower Reactor pressure to allow adequate Reactor injection, in accordance with EOP-2.

Critical Task #3 Standard: Lower Reactor pressure using SRVs to below the discharge pressure of the Condensate Booster pumps.

LOI14-2 NRC Examination Scenario 4 Page 15 of 23

INSTkLJCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION SRO SAT I UNSAT INA

Acknowledge reports

Direct ARP execution

May direct Reactor power reduction with CRAM rods, as time Note: permits The crew will monitor Main

Enter AOP-40 (Main Steam Line Break)

Steam Tunnel temperatures and likely set a benchmark of

Direct a manual Reactor scram 185°F for inserting a scram.

Enter AOP-1 (Reactor Scram)

Direct closure of MSIVs Critical Task #2

Enter EOP-2 (RPV Control) on low Reactor water level

Direct Reactor water level controlled 180 to 220" (expands band as necessary due to injection failures)

Direct Reactor pressure controlled 800-1000 psig using SRVs Note:

Acknowledge failure of Feedwater controllers Depending on the pre-scram power level, Reactor water

Direct manual start of HPCI level may not reach the HPCI

Acknowledge failure of HPCI to inject in automatic and RCIC automatic initiation setpoint of 126.5" on the

Direct manual control of HPCI flow scram.

Acknowledge trip of HPCI

Acknowledge failure of RCIC to automatically start

Direct manual start of RCIC

Acknowledge trip of RCIC (after one minute of injection)

May direct maximizing CRD injection

May direct injection with SLC Critical Task #3

Direct reducing Reactor pressure using SRVs LOI 14-2 NRC Examination Scenario 4 Page 16 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION SRO cont. SATIUNSATINA

Direct Reactor water level controlled 180 to 220" using Condensate Booster pumps

As time permits, direct Turbine Building evacuation, verification of isolations, and alignment of Control Room, Relay Room, and TSC ventilation

As time permits, direct initiation of Torus Cooling ATC SAT I UNSAT INA

May insert CRAM rods, as time permits

Enter AOP-1

Depress MANUAL SCRAM A and MANUAL SCRAM B push buttons

Place RX MODE switch in SHUTDOWN

Fully insert IRMs and SRMs

Observe Reactor power lowering

Ensure closed SDIV vent and drain valves

Ensure Main Turbine is tripped

Verify 4KV loads transfer to reserve power

Close MSIVs Critical Task #2

Control Reactor pressure 800-1 000 psig using SRVs Critical Task #3

Reduce Reactor pressure using SRVs LOI 14-2 NRC Examination Scenario 4 Page 17 of 23

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION BOP SAT I UNSAT INA Role Play:

Execute ARP 09-3-1-39, as time permits:

If dispatched to investigate in Turbine Building, wait 2 0 Determine which ARM is in alarm minutes, then report there is a 0 Evacuate personnel at location of ARM in alarm lot of steam coming from the Turbine Deck and very high 0 Attempt to reset ARM temperatures. 0 Direct RP to survey area

Enter AOP-1 Role Play:

If dispatched as RP to survey

Attempt to control Reactor water level 180-220" using Turbine Building, wait 2 Feedwater minutes, then report radiation

Recognize I report inability to inject with high pressure levels matching current status Feedwater pumps of ARMs.

Recognize I report failure of HPCI to inject Role Play:

Take manual control of HPCI flow controller and raise flow If dispatched to investigate

Recognize I report HPCI trip Feedwater pump control , wait 2 minutes, then report that you

Recognize I report failure of RCIC to automatically start have found no indications why

Start RCIC per OP-19 posted attachment:

Feedwater pump control has failed . 0 Verify Annunciator 09-4-0-32 RCIC LOGIC RX LVL HI is clear Role Play: 0 Verify RCIC is lined up to one of the following suction If dispatched to investigate paths:

HPCI trip, wait 2 minutes, then

CST SUCT VLV 13MOV-18 open for suction from CSTs report that there appears to be damage to the HPCI Turbine

The following valves open for suction from torus :

Stop Valve, 23HOV-1 .

INBD TORUS SUCT 13MOV-41

OUTBD TORUS SUCT 13MOV-39 0 Start VAC PMP 13P-3 LOI 14-2 NRC Examination Scenario 4 Page 18 of 23

INSTFn.JCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION BOP cont. SAT I UNSAT INA

Start RCIC per OP-19 posted attachment (cont.):

0 Open OIL CLR WTR SUPP 13MOV-132 Note: 0 Perform the following without unnecessary delay:

RCIC will trip approximately

Open TURB STM SUPP VLV 13MOV-131 one minute after start.

Open INJ VLV 13MOV-21

Recognize I report trip of RCIC Role Play:

If dispatched to investigate

Recognize I report trip of CRD pump RCIC trip, wait 2 minutes, then

May attempt to start standby CRD pump report that there appears to be I damage to the RCIC 0 Recognize I report trip of 2"d CRD pump trip/throttle valve, 13HOV-1.

May attempt to initiate SLC 0 Recognize I report failure of SLC pumps to start Note:

Condensate Booster pumps

Control Reactor water level 180 to 200" using Condensate will be capable of injection to Booster pumps the Reactor once Reactor pressure is reduced to approximately 700 psig.

LOI 14-2 NRC Examination Scenario 4 Page 19 of 23

INSTkUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS I EVALUATION ATC I BOP SAT I UNSAT INA

As time permits, verify isolations per AOP-15

May initiate Torus Cooling per OP-138 posted attachment:

0 Ensure at least one of the RHR pumps is running 0 Open RHR TEST TORUS CLG & SPRAY 1OMOV-39A(B) 0 Throttle RHR TEST & TORUS CLG 1OMOV-34A(B) to establish desired/flow 0 WHEN RHR Loop A(B) flow is GREATER THAN 1500 gpm, ensure closed MIN FLOWVLV 10MOV-16B 0 Establish RHRSW flow and temperature control

May initiate RHRSW per OP-13C posted attachment:

0 Start one of the RHRSW pumps 0 Throttle RHRSW DISCH VLV FROM HX A(B) 1OMOV-89 A(B) to establish 2500 to 4000 gpm 0 Start the second RHRSW pump if desired 0 Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-89 A(B) to establish 2500 to 4000 gpm per RHRSWpump 0 Close HX A( B) BYP VLV 1OMOV-66 A( B)

Termination Criteria:

All control rods are inserted.

Reactor water level is being controlled above 0".

LOI 14-2 NRC Examination Scenario 4 Page 20 of 23

Shift Turnover The Plant is operating at approximately 65% power.

Circulation Water pump C is ready to be returned to service following maintenance.

When you take the shift:

1. Start Circulating Water pump C per OP-4 section 0.17. The procedure is in progress up to step 0.17.3.e.

2. Then, raise Reactor power using Recirculation flow per the provided reactivity instruction . Stop at approximately 75%

power for further Reactor Engineering instructions.

LOI 14-2 NRC Examination Scenario 4 Page 21 of 23

ATTACHMENT 9.4 REACTIVITY MANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps- (site specific control rod movement control sheet format is to be used)

Power Ascension EN-RE-215 Attach 9.4 Today Page 1 of 1 From To Cplg RSCS Init Step Action Rod Method Notes Notch Notch Chk Grp Raise power 1

to 75% RTP - - - RWR NA - Target rate= 1% per minute WaitS minutes, then 2 demand 3D - - - - - -

Monicore case c

Prepared By: SM Approval: VCVtler'R~

(RxEng) (Shift Manager)

Reviewed By: Bob- TO!'\AW (RxEng or SRO)

Stamps CONTROL ROOM OPERATOR LOI14-2 NRC Examination Scenario 4 Page 22 of 23

ATTACHMENT 9.4 REACTIVITY MANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps- (site specific control rod movement control sheet format is to be used)

Power Ascension EN-RE-215 Attach 9.4 Today Page 1 of 1 From To Cplg RSCS Init Step Action Rod Method Notes Notch Notch Chk Grp Raise power 1

to 75% RTP

- - - RWR NA - Target rate= 1% per minute WaitS minutes, then 2 demand 3D - - - - - -

Monicore case 0

Prepared By: SM Approval: Vcwet'RO"et (RxEng) (Shift Manager)

Reviewed By: Bob- Tc?t'\.e4:,

(RxEng or SRO)

Stamps INDEPENDENT VERIFIER LOI 14-2 NRC Examination Scenario 4 Page 23 of 23

v t e Letter Sequence Other
TAC:U01887, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML14119A389, ML14119A390, ML14119A391, ML14119A392, ML14141A187, ML14318A458, ML14318A466, ML14318A474, ML14318A510
MONTHYEAR2014-04-04 [Table View]

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