Text

Draft - Section B Operating (RO & SRO) (Folder 2)
	ML051400356
Person / Time
Site:	FitzPatrick
Issue date:	01/25/2005
From:	Berry P; FitzPatrick
To:	Conte R; Operations Branch I
	Conte R
References
	50-333/05-301 50-333/05-301
	Download: ML051400356 (102)
	v • d • e

rn Entegy James A. FilzPatrick Nuclear Power Plant Nuclear Northeast OPERATlONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE S/RO NEW TASK TITLE: VERIFY HPCl ISOLATION APPL. TO JPM NUMBER REV:

0 DATE: 3/9/05 NRC K/A SYSTEM NUMBER: 206000 A2.10 4.0/4.1 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

10 Minutes SUBMITTED:

OPERATION REVIEW:

APPROVED:

JAF QUAL STANDARD NUMBER:

---M-N------N---M--V-----------~--~--N-NN--~-~-----N~--~N--V----~-----~---M-~

CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

( ) Simulated (X) Performed Location:

( )Plant (X) Simulator DATE PERFORMED:

TIME TO COMPLETE:

Minutes PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

- - - M - ~ - ~ ~ M N - - ~ N - ~ - - ~ - - N - - - - ~ - M - - - - M - - N - - - - - - - U ~ - - - - - M N - - - ~ - N - M - M U N - - - N - ~ - N ~ - - N EVALUATOR:

SIGNATURUPRINTED Page 1 of 5

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NEW TASK TITLE: VERIFY HPCI ISOLATION APPL. TO JPM NUMBER Current Update:

3/9/05 By:

RWD Date Int.

Outstanding Items:

Technical Review Questions and Answers Procedural Change Required Additional Information Validation X

None Comments:

Page 2 of 5

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIR0 NEW TASK TITLE: VERIFY HPCl ISOLATION APPL. TO JPM NUMBER

1.

II.

111.

IV.

V.

VI.

SAFETY CONSIDERATIONS A.

None REFERENCES A.

8.

OP-15, High Pressure Coolant Injection, Revision 50 AP-12.03, Conduct of Operations, Revision 30, Section 8.3 TOOLS AND EQUIPMENT A.

None SET UP REQUIREMENTS A.

B.

C.

D.

Reset simulator to any 4 5 0 psig IC.

Verify HPCl in normal standby lineup.

Insert Simulator Malfunction HPl 1, HPCl23MOV-15 AUTO ISOLATION FAILURE.

Insert Simulator Malfunction HP06, HPCl STEAM LINE BREAK EVALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

actually performed.

B.

TASK CONDITIONS A.

B.

HPCl has received an auto-isolation signal on a HPCl Steam Line Break The Control Room Supervisor directs that the HPCl Isolation be verified per OP-15.

- CRITICAL STEP Page 3 of 5

S/RO TASK TITLE: START UP MAIN STEAM LEAKAGE COLLECTION VII.

INITIATING CUE The HPCI System has just isolated. Verify that the HPCl Isolation is complete per OP-15.

VIII.

TASK STANDARD The candidate will manually isolate 23MOV-15 (Fails to Close) and verify the HPCl Isolation is complete.

1.

2.

STEP Obtain and review procedure (G.I.1)

Ensure the following valves are closed:

TURB STOP VLV 23HOV-1 0

OUTBD STM SUPP VLV 23MOV-I 6 MIN FLOW VLV 23MOV-25 0

INBD TORUS SUCT VLV 23MOV-58 INBD STM SUPP VLV 23MOV-15 0

OUTBD TORUS SUCT VLV 0

STM LINE WARMING ISOL 23MOV-57 VLV 23MOV-60 INJ VLV 23MOV-19 STANDARD Candidate obtains and reviews OP-15. Candidate determines that the start point is step G. I.

1.

Candidate sequentially locates listed valves and verifies each valve indicates 'CLOSED." At the point where candidate encounters an "OPEN" INBD STM SUPP VLV 23MOV-15 (failure to isolate), candidate will close 23MOV-I 5. Candidate may or may not report the valve out-of-position to CRS.

EVALUATOR:

Respond to candidate report(s) of isolation verification and/or 23MOV-I5 failure to isolate in a manner consistent with the standard rules of three-point communications.

EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT

CRITICAL STEP*

EVALUATOR: Terminate the task at this point.

Page 4 of 5

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~ Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE S/RO FROM LOI-03-01 TASK TITLE: GROUP I ISOLATION RESET APPL. TO JPM NUMBER REV:

1 DATE: 3/3/05 NRC WA SYSTEM NUMBER: 223002 A4.03 3.613.5 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

I O Minutes SUBMITTED:

OPERATION REVIEW:

APPROVED:

JAF QUAL STANDARD NUMBER:

w

w w * ~ w ~

w ~ *

w * * ~ * * * ~ * * * ~ w ~ w w ~ ~

w ~ * ~ m * ~ w

w * ~ w w w * ~ *

w * * * ~ * ~ w w *

w w w

w w

w w ~

w *

CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

( ) Simulated

( X ) Performed Location:

( ) Plant

( X ) Simulator DATE PERFORMED:

PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory TIME TO COMPLETE:

Minutes

~ * ~ ~ * ~ * ~ * ~ * * * * ~ ~ ~ * ~ ~ * ~ * ~ ~ ~ * * * * * ~ * * ~ * * ~ ~

w w * ~ * ~ w w * * ~ * ~ w *

w ~ ~ w

w

w

w * * *

m w * * ~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIG NATURWPR I NTED Page 1 of 7

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SIR0 FROM LOI-03-01 TASK TITLE: GROUP 1 ISOLATION RESET APPL. TO JPM NUMBER Current Update: 3/3/05 By: RWD Date Int.

Outstanding Items:

Technical Review Additional Information Questions and Answers Validation Procedural Change Required X

None Comments:

Simulator validated Page 2 of 7

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIR0 FROM LOI-03-01 TASK TITLE: GROUP 1 ISOLATION RESET APPL. TO JPM NUMBER

1.

II.

111.

IV.

V.

VI.

SAFETY CONSIDERATIONS A.

Ensure proper safety equipment and safety procedures are observed.

REFERENCES A.

AOP-15, ISOLATION VERIFICATON AND RECOVERY Rev 23 TOOLS AND EQUIPMENT A.

None SET UP REQUIREMENTS A.

Current copy of AOP-15.

B.

Setup simulator with post trip conditions following MSlV closure on low steam pressure and ready for re-opening.

EVALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and not actually performed.

The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

B.

TASK CONDITIONS A.

Conditions have occurred which caused the MSlVs to isolate on low steam pressure.

6.

Action to restore the main condenser as a heat sink must be completed

- CRITICAL STEP Page 3 of 7

S/RO/NLO NEW TASK TITLE: GROUP 1 ISOLATION RESET VII.

INITIATING CUE

1.

2.

Conditions have occurred which caused the MSlVs to isolate on low steam pressure. The cause of the isolation has been corrected. All radiological conditions and Reactor Chemistry samples are within normal bands. Reset the MSlV isolation using AOP-15."

Obtain a controlled copy of AOP-15.

CAUTION:

The circumstances leading to an isolation could have caused high radioactivity levels in the drywell or in reactor coolant.

TASK STANDARD The candidate will reset the PClS Group I isolation per AOP-15 Section C.2 I

STEP Verify Group 1 Isolation per posted Item 4.

3.

Determine and correct cause of the isolation.

4.

~

STANDARD Obtains a controlled copy of AOP-15 and selects section C.2.

Informs SM/CRS of CAUTION.

EVALUATOR: Acknowledge candidate and respond that there is no concern for high radioactivity levels in drywell or reactor coolant.

Selects the posted attachment 1 and at panel 09-3 and/or 094 confirms green closed light on and red open light off for:

J 29 AOV-80 A-D J 29 AOV-86 A-D J 29 MOV-74 and 77

~~

Candidate may confim-initiating cue information that cause has been determined and corrected.

EVALUATOR: If asked, confirm that cause is known and corrected and candidate may proceed as directed.

Page 4 of 7

S/RO/NLO NEW ASK TITI

5.

6.

7.

8.

9.

E: GROUP 1 ISOLATION RESET STEP IF cause of isolation was high main steam line radiation, THEN....

Determine whether an undesired release will occur when isolation is reset. Request RES assistance if in doubt.

WHEN it has been determined that an undesired release will not occur when isolation is reset, continue with procedure.

Ensure control switches for the following valves are in CLOSE:

RWR LOOP B SMPL ISOL VLV 02-2AOV-39 RWR LOOP B SMPL ISOL VLV 02-2Aov-40 IF MSlVs are closed, THEN place control switch for each of the following valves in CLOSE:

MSlV 29AOV-80A MSlV 29AOV-800 MSlV 29AOV-80C MSlV 29AOV-80D MSlV 29AOV-86A MSlV 29AOV-86B MSlV 29AOV-86C MSlV 29AOV-86D STANDARD Reviews step and determines that cause was NOT a result of high main steam line radiation and a release will not occur as a result of isolation reset.

EVALUATOR: If candidate requests, respond that an undesirable release will not occur.

Reviews step and determines that release will not occur as a result of isolation reset.

EVALUATOR: If candidate requests, respond that an undesirable release will not occur.

Reviews step and determines that release will not occur as a result of isolation reset.

EVALUATOR: If candidate requests, respond that an undesirable release will not occur.

At 09-3 and 09-4 panels, place the valve switches are in close and confirm green dosed light on and red open light off.

At 09-3 and 09-4 panels, place the valve switches in close and confirm green closed light on and red open light off.

EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT

CRITICAL STEP SAT / UNSAT

CRITICAL STEP*

Page 5 of 7

S/RO/NLO NEW E: GROUP 1 ISOLATION RESET STEP NOTE:

Step C.2.8 is not required to open MSlVs if Group 1 isolation was due to high main steam line radiation (3X normal full power background).

Simultaneously rotate the following PClS VLV RESET switches to both RESET positions, spring return to NORM:

16A-S32 16A-S33 NOTE:

Steps C.2.9 and C.2.10 may be performed in any order at the Shift Manager's discretion.

STANDARD Reviews NOTE and determines that step C.2.8 REQUIRED.

EVALUATOR: If candidate requests feedback regarding note, acknowledge the isolation was not due to high radiation.

~~

~~~

~

At panel 09-5, operates the switches and confirm annunciators 09-5-1 -55 and 56 clear.

Reviews Note and requests feedback from SM regarding priority for action.

EVALUATOR: When candidate requests feedback regarding step priority, acknowledge the MSlVs have priority.

EVALUATION / COMMENT TASK TITI

10.

11.

12.

EVALUATOR: Terminate the task at this point.

SAT / UNSAT SAT I UNSAT

CRITICAL STEP" SAT / UNSAT Page 6 of 7

=== Entegy James A. FitzPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE SIR0 FROM LOI-03-01 TASK TITLE: REOPEN MSIV's WITH RPV PRESSURIZED APPL. TO JPM NUMBER REV:

1 DATE:

3/7/05 NRC K/A SYSTEM NUMBER: 239001 A4.04 3.813.7 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

15 Minutes SUBMITTED:

OPERATION REVIEW:

APPROVED:

JAF QUAL STANDARD NUMBER:

-~---~----5---m----5--m-----5-m---mm-~----~---~--m-~m--m------------m---m~----

CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

( ) Simulated

( X ) Performed Location:

( ) Plant

( X ) Simulator DATE PERFORMED:

TIME TO COMPLETE:

Minutes PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE) -~-----~---~-m-mm----m--m~---~-----------------~-------------~---~-~------m EVALUATOR:

SIGNATURUPRINTED Page 1 of 6

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO FROM LOI-03-01 TASK TITLE: Reopen MSIV's with RPV Pressurized APPL. TO JPM NUMBER Current Update:

3/7/05 Date Outstanding Items:

Technical Review Questions and Answers Procedural Change Required Comments:

Simulator Validated BY: -

RWD Int.

Additional Information Validation X

None Page 2 of 6

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIR0 FROM LOI-03-01 TASK TITLE: Reopen MSIV's with RPV Pressurized APPL. TO JPM NUMBER

1.

II.

111.

IV.

V.

VI.

SAFETY CONSIDERATIONS A.

None REFERENCES A.

EP-9; OPENING MSlV's, Rev 3 TOOLS AND EQUIPMENT A.

None SET UP REQUIREMENTS A.

B.

C.

D.

Rx Scrammed with MSIV's closed.

RPV Level > 126.5 and < 222.5.

RP V Pressure Control on SRVs/HPCI/RCIC at 800-1 000 psig.

PClS Group I isolation signals reset EVALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identied and The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

actually performed.

B.

TASK CONDITIONS A.

Plant is post scram with MSIV's closed

- CRITICAL STEP Page 3 of 6

VII.

INITIATING CUE:

The reactor has scrammed and the MSIVs are closed. MSIV isolation signals have been reset. Another operator has RPV pressure control on the SRVs at 800-1000 psig. The plant is being controlled as directed by the EOPs. To reestablish the main condenser as the heat sink, equalize and reopen the MSIVs per EP-9.

~~

~

The candidate obtains a controlled copy of EP-9.

Candidate uses 06PI-90A, B, and or C at panel 09-5 and MAIN STEAM PRESS A and or B at EHC section of panel 09-5 to determine that differential pressure exceeds 200 psid.

Candidate closes and/or observes green closed light on TASK STANDARD The candidate will equalize to less than a 200 psid D/P and open the MSIVs per EP-9 SAT / UNSAT SAT / UNSAT SAT / UNSAT

1.

2.

3.

STEP Obtain a controlled copy of procedure IF differential pressure across the MSlVs is LESS THAN OR EQUAL TO 200 psid, THEN perform the following:

EP-9, OPENING MSIVS Ensure closed the following valves:

J MSIV 29AOV-80A-D J MSlV 29AOV-86A-D J MAIN STM DRN 29MOV-74,77,78 J

and 79 MAIN STM DRN VLV 29MOV-101A-D J RFPT A and B HP STOP VLV HP SVA-I and SVB-1 J TSV-1-4 J TO PCV 96MOV-SI J PCV BYP 96MOV-S2 J 29MST-105 (SJAE MST supply 29PCV-107 outlet isol valve)

(remote operated from East Electric Bay) 29PCV-107 bypass strainer outlet isol valve) (remote operated from East Electric Bay)

J 29MST-107 (SJAE MST supply STANDARD I EVALUATION I COMMENT Page 4 of 6

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INITIATING CUE:

The reactor has scrammed and the MSIVs are closed. MSlV isolation signals have been reset. Another operator has RPV pressure control on the SRVs at 800-1000 psig. The plant is being controlled as directed by the EOPs.

To reestablish the main condenser as the heat sink, equalize and reopen the MSIVs per EP-9.

Page 6 of 6

m Entegy James A. FittPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE SIR0 NEW TASK TITLE:

CRD PUMP TRIP (ALT PATH1 APPL. TO JPM NUMBER REV:

0 DATE:

1/14/05 NRC WA SYSTEM NUMBER:

201001 A2.01 3.Z3.3 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

10 Minutes SUBMITTED:

APPROVED:

JAF QUAL STANDARD NUMBER:

OPERATI ON REV1 E W:

N-~----~----N-~----N------N----N-----N----------~--------N------~----~-~--

CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

( ) Simulated (X) Performed Location:

( ) Plant (X) Simulator DATE PERFORMED:

TIME TO COMPLETE:

Minutes PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

--~-2---~-----------~-~--N----~-------~N----N-----~--~~----~-----~---~------N-N EVALUATOR:

SIGNATURUPRINTED Page 1 of 6

JOBPERFORMANCEMEASURE RECORD AND CHECKLIST SIR0 NEW TASK TITLE: CRD PUMP TRIP (ALT PATH)

APPL. TO JPM NUMBER Current Update:

1/14/05 By: RWD Date Int.

Outstanding Items:

Technical Review Questions and Answers Procedural Change Required Additional Information Validation X

None Comments:

Page 2 of 6

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NEW TASK TITLE: CRD PUMP TRIP (ALT PATH)

APPL. TO JPM NUMBER

1.

II.

111.

IV.

V.

VI.

SAFETY CONSIDERATIONS A.

None REFERENCES A.

AOP-69, CONTROL ROD DRIVE TROUBLE, Revision 6.

TOOLS AND EQUIPMENT A.

None SET UP REQUIREMENTS A.

B.

C.

Simulator in any power operation IC with the "A" CRD pump in service Insert MFI-RDO6:A (,,K CRD Pump Trip) and allow one accumulator trouble alarm to appear.

Insert MFI-RDO6:B VB CRD Pump Trip)

EVALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and N t actually performed.

The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

B.

TASK CONDITIONS A.

None

- CRITICAL STEP Page 3 of 6

s/Ro TASK TITLE:

CRD PUMP TRIP (ALT PATH)

VII.

INJTIATING CUE The plant was operating normally at power when the A CRD pump tripped unexpectedly. Local inspections indicate catastrophic failure of the gear case requiring extensive maintenance. An NPO is responding to the Accumulator Trouble Alarm. You are instructed to start the B CRD pump per AOP-69.

VIII.

TASK STANDARD The candidate will respond to a CRD Pump Trip per AOP-69

1.

2.

3.

4.

5.

STEP Obtain and review procedure

a. Ensure CRD FLOW CNTRL 03FIC-301 is in MAN.

b. Rotate manual control knob on CRD counterclockwise.

c. Verify inservice CRD flow control valve (03FCV-19A or B) is closed FLOW CNTRL 03FIC-301 fully

~~

~-

~

d. Attempt to start one CRD pump(CRD PMP 03P-16A or CRD PMP 03P-16B).

If the first pump fails to start, attempt to start the other.

STANDARD Candidate obtains and reviews AOP-69. Candidate determines that the start point is step C.1.5 EVALUATOR If requested, A CRD pump did NOT trip on low suction pressure and the CRD pump breakers have been inspected at 71L15 and 71L16.

At 09-5, candidate selects CRD Flow Control GEMAC Controller mode select knob to MAN.

At 09-5, candidate rotates CRD Flow Control GEMAC manual flow control knurled knob counterclockwise.

At 09-5, candidate observes green lamp on and red tamp off for both CRD Flow Control Valves.

At 09-5, Candidate selects B CRD Pump Control Switch to START (Spring Return to NORM)

Candidate recognizes trip of 8 CRD Pump Candidate dispatches NPO to investigate.

EVALUATION / COMMENT

CRITICAL STEP*

SAT / UNSAT SAT / UNSAT

CRITICAL STEP*

Page 4 of 6

SIR0 TASK TITLE:

CRD PUMP TRIP (ALT PATH)

6.

7.

EVALUATOR: Terminate the task at this point.

r STEP

e. IF neither CRD pump can be started, THEN proceed to Subsection C.2.

C.2.1 IF at least one CRD pump will not be made available within a reasonable period of time, as determined by the SM or CRS, AND two or more ACCUM alarm lights are on at panel 09-5 full core display, THEN manually scram reactor and enter AOP-1.

STANDARD EVALUATOR Act as NPO and report the "8" CRD Pump Breaker has exploded.

Candidate determines that neither CRD pump can be EVALUATION / COMMENT started and proceeds to Subsection C.2 EVALUATOR If necessary, provide feedback that several hours will be SAT / UNSAT I

II

CRITICAL STEP' I

required to repair/replace the "B" CRD pump breaker.

Upon receipt of additional Accumulator Trouble Lights, the candidate inserts a manual scram and commences AOP-1 Immediate Actions.

Page 5 of 6

INITIATING CUE The plant was operating normally at power when the A CRD pump tripped unexpectedly. Local inspections indicate catastrophic failure of the gear case requiring extensive maintenance. An NPO is responding to the Accumulator Trouble Alarm. You are instructed to start the 6 CRD pump per AOP-69.

Page 6 of 6

m "Entergy Nuclear Northeast James A. FbPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE S/RO NEW TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)

APPL. TO JPM NUMBER REV:

0 DATE: 3/9/05 NRC WA SYSTEM NUMBER: 259002 A4.06 3.113.2 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

15 Minutes SUBMITTED:

OPERATION REVIEW:

APPROVED:

JAF QUAL STANDARD NUMBER:

N - ~ N N m ~ - - N - N U ~ ~ ~ N ~ - N - N - m N N - ~ N ~ m m ~ N ~ m ~ N ~ - N ~ m ~ U ~ - m N N ~ - U ~ - N N - ~ N N ~ - N ~ - ~ ~ N - N N CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

( ) Simulated (X) Performed Location:

( ) Plant (X) Simulator DATE PERFORMED:

PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

TIME TO COMPLETE:

Minutes

- N N - - N N - - N - - - N N - - ~ - - - N N ~ - U ~ - - N - - - N - - - U N - - N ~ - N N - ~ ~ - - - U - - - N - N N - ~ N - ~ - - ~ - N - - - ~ - - N ~

EVALUATOR:

SIGNATU WPRINTED Page 1 of 9

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SIR0 NEW TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)

APPL. TO JPM NUMBER Current Update:

3/9/05 By: RWD Date Int.

Outstanding Items:

Technical Review Additional Information Questions and Answers Validation Procedural Change Required X

None Comments:

Page 2 of 9

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIR0 NEW TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)

APPL. TO JPM NUMBER

1.

II.

111.

IV.

V.

VI.

SAFETY CONSIDERATIONS A.

None REFERENCES A.

OP-2A, Feedwater System, Rev.54

6.

OP-65, Startup and Shutdown Procedure, Rev. 102 TOOLS AND EQUIPMENT A.

None SET UP REQUIREMENTS A.

Obtain current copies of OP-65, Startup and Shutdown Procedure and OP-2A, Feedwater System.

-30% CTP IC during reactor startup with plant conditions stable.

FWLC in Master Auto Single-Element Control on Either Reactor Feed Pump.

6.

C.

EVALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

actually performed.

B.

TASK CONDITIONS A.

6.

C.

A Reactor Startup is in progress.

Reactor Power is just above 25% CTP.

Currently at Step 0.24.4 of OP-65, Startup and Shutdown Procedure

- CRITICAL STEP Page 3 of 9

SlRO TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)

~~

Candidate verifies that 09-5 Panel Master Control Transfer (Mode Selector) Switch (collar around knurled knob) for RX WTR LVL CNTRL 06LC-83 is in the "BAL" (Balance) position.

VII.

VIII.

SAT / UNSAT INITIATING CUE A reactor startup is in progress. Per OP-65, Step D.24.4, you have been directed to transfer the Feedwater Level Control System from Single-Element to Three-Element control.

TASK STANDARD The candidate will transfer Feedwater Level Control from Single-Element to Three-Element per OP-2A.

1.

2.

3.

4.

STEP

~~

~~~

~

Obtain and review procedure.

(G.34.1)

Stabilize RPV water level at 196.5 to 203 inches on 06LI-94A, B, and C.

(G.34.2)

Verify RX WTR LVL CNTRL 06LC-83 is in BAL.

(G.34.3)

Slowly adjust RX WTR LVL CNTRL 06LC-83 manual control knob to balance controller.

STANDARD I

EVALUATION I COMMENT Candidate obtains and reviews OP-65 and OP-2A.

Candidate determines that the start point is step G.34.1 of OP-2A.

SAT / UNSAT Candidate verifies stable 09-5 Panel RPV Level parameters in the required range (196.5 to 203 inches).

SAT / UNSAT Candidate adjusts 09-5 Panel Manual Output Control (knurled knob potentiometer) until red pointer on Deviation Meter is approximately mid-scale.

SAT / UNSAT

CRITICAL STEP*

Page 4 of 9

S/RO TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)

5.

6.

7.

I STEP

~~

-~

~

(G. 34.4. a)

Ensure RFP A FLOW CNTRL 06-84A in manual as follows:

a. Ensure controller is in BAL (G.34.4.b)

b. Balance controller by adjusting (G.34.4.c)

c. Place controller in MAN manual control knob

~

Candidate verifies that 09-5 Panel M/A Transfer Switch (collar around knurled knob) for RFP A FLOW CNTRL 06-84A is in the 'BAL" (Balance) position.

Candidate adjusts 09-5 Panel Manual Output Control (knurled knob potentiometer) on RFP A FLOW CNTRL 06-84A until pointer is mid-scale on Deviation Meter (top of controller).

Candidate turns 09-5 Panel M/A Transfer Switch (collar around knurled knob) for RFP A FLOW CNTRL 06-84A clockwise one position to "MAN" (Manual).

SAT / UNSAT

CRITICAL STEP*

g. I (G.34.5.b)

8.

b. Balance controller by adjusting manual control knob (G.34.5. a)

Ensure RFP B FLOW CNTRL 06-848 in manual as follows:

a. Ensure controller is in BAL STANDARD I

EVALUATION / COMMENT SAT / UNSAT SAT I UNSAJ

CRITICAL STEP*

SAT / UNSAT Candidate verifies that 09-5 Panel M/A Transfer Switch (collar around knurled knob) for RFP B FLOW CNTRL 06-848 is in the "BAL" (Balance) position.

Candidate adjusts 09-5 Panel Manual Output Control (knurled knob potentiometer) RFP B FLOW CNTRL 06-848 until pointer is mid-scale on Deviation Meter (top of SAT / UNSAT

CRITICAL STEP*

Page 5 of 9

SIR0 TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)

io.

11

12.

13.

14.

STEP (G.34.5.

c)

c. Place controller in MAN (G. 34.6)

Place 1 or 3 ELEMENT LVL CNTRL SEL 06s-2 in 3 ELEMENT.

(G.34.7)

Verify RX WTR LVL CNTRL 06LC-83 remains balanced.

(G.34.8)

Transfer RFP A and B control to automatic per Subsection G.7.

(G.7.1)

Stabilize RPV water level at 197 to 203 inches on 06LI-94A, B, and C.

STANDARD Candidate turns 09-5 Panel MIA Transfer Switch (collar around knurled knob) for RFP B FLOW CNTRL 06-848 clockwise one position to "MAN" (Manual).

EVALUATOR NOTE:

Candidate now has RPV Water Level Control in Manual and will adjust the Manual Control Potentiometer on 06-84A/B, as necessary, to maintain level 196 to 206.5 inches.

Candidate turns Element Control Select Switch on 09-5 Panel clockwise one position to "3 ELEMENT".

~~~

~

Candidate verifies 09-5 Panel RX WTR LVL CNTRL 06LC-83 red pointer on Deviation Meter is approximately mid-scale.

Candidate obtains and reviews OP-2A, Section G.7.

Candidate determines that the start point is step G.7.1 of OP-2A.

~

Candidate verifies stable 09-5 Panel RPV Level parameters in the required range.

EVALUATION I COMMENT SAT / UNSAT

CRITICAL STEP*

SAT / UNSAT

CRITICAL STEP SAT I UNSAT SAT / UNSAT SAT / UNSAT Page 6 of 9

S/RO TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)

15.

16.

17.

I

8.

19.

STEP (G.7.2)

Verify the following controllers are in MAN:

RFP A FLOW CNTRL 06-84A RFP B FLOW CNTRL 06-848 (G.

7.3)

Place RX WTR LVL CNTRL 06LC-83 in MAN.

(G

.7.4)

Slowly adjust RX WTR LVL CNTRL 06LC-83 manual control knob to balance RFP A FLOW CNTRL 06-MA.

(G.7.5)

Place RFP A FLOW CNTRL 06-84A in BAL.

(G.7.6. a)

Line up RX WTR LVL CNTRL 06LC-83 as follows:

a. Balance controller by adjusting setpoint tape.

STANDARD Candidate verifies 09-5 Panel MIA Transfer Switches (collars around knurled knob) for RFP N B FLOW CNTRL 06-84A/B are in the position of "MAN" (Manual).

Candidate turns the 09-5 Panel M/A Transfer Switch (collar around knurled knob) for RX WTR LVL CNTRL 06LC-83 clockwise one position to "MAN" (Manual).

~~

Candidate adjusts 09-5 Panel Manual Output Control (knurled knob potentiometer) on RX WTR LVL CNTRL 06LC-83 until pointer on RFP A FLOW CNTRL 06-84A is mid-scale on Deviation Meter (top of controller).

Candidate turns 09-5 Panel M/A Transfer Switch (collar around knurled knob) for RFP A FLOW CNTRL 06-84A counterclockwise one position to "BAL" (Balance).

Candidate adjusts 09-5 Panel Setpoint Control on RX WTR LVL CNTRL 06LC-83 until red pointer on Deviation Meter is approximately mid-scale.

EVALUATION / COMMENT SAT / UNSAT SAT / UNSAT

CRITICAL STEP*

SAT / UNSAT

CRITICAL STEP*

SAT I UNSAT

CRITICAL STEP*

SAT / UNSAT

CRITICAL STEP*

Page 7 of 9

SIR0 TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)

L STEP

zo.

(G.7.6.b)

b. Place controller in BAL.

21.

(G.7.7.a)

Line up RFP A FLOW CNTRL 06-848 as follows:

a. Balance controller by adjusting manual control knob

22.

(G.7.7.b)

b. Place controller in BAL.

EVALUATOR: Terminate the task at this point.

STANDARD Candidate turns 09-5 Panel Master Control Transfer Switch (collar around knurled knob) for RX WTR LVL CNTRL 06LC-83 counterclockwise one position to "BAL" (Balance).

EVALUATOR NOTE:

This step restores Automatic RPV Water Level Control.

Candidate slowly adjusts 09-5 Panel Manual Output Control (knurled knob potentiometer) RFP B FLOW CNTRL 06-84B until pointer is mid-scale on Deviation Meter (top of controller).

Candidate turns 09-5 Panel M/A Transfer Switch (collar around knurled knob) for RFP B FLOW CNTRL 06-848 counterclockwise one position to "BAL" (Balance).

EVALUATION I COMMENT SAT / UNSAT

CRITICAL STEP*

SAT / UNSAT

CRITICAL STEP*

SAT / UNSAT

CRITICAL STEP*

Page 8 of 9

L c,

aa P

'CI

0) aa L

0 c,

$ E Q b h

'E

$ E Q b h

'E t-9

m

-== Entergv James A. FiePatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE SIR0 26201001A TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVJCE U-4)

APPL. TO JPM NUMBER REV:

0 DATE: 3/10/05 NRC K/A SYSTEM NUMBER: 262001 A4.04 3.613.7 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

15 Minutes SUBMITTED:

OPERATION REVIEW:

APPROVED:

JAF QUAL STANDARD NUMBER:

~

m

~

m

~

m m

m

~

m

~

m m

~

CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

( ) Simulated (X) Performed Location:

( ) Plant (X) Simulator DATE PERFORMED:

TIME TO COMPLETE:

Minutes PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

~ ~ m m m ~ ~ - N ~ ~ - m m ~ ~ N m - * ~ m * *

N m * - * ~ * *

N - * * ~ m 5 ~ m - * ~ ~ - m

m ~ ~ ~

N 5 * ~ * ~ N * - * * * ~ ~ ~ - ~ * ~ * ~

N EVALUATOR:

SIGNATURUPRINTED Page 1 of 10

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST smo NEW TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T-4)

APPL. TO JPM NUMBER Current Update:

311 0105 By: RWD Date Int.

Outstanding Items:

Technical Review Questions and Answers Procedural Change Required Additional Information Validation X

None Comments:

Page 2 of 10

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIR0 NEW TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T4)

APPL. TO JPM NUMBER

1.

II.

111.

IV.

V.

VI.

SAFETY CONSIDERATIONS A.

None REFERENCES A.

B.

TOOLS AND EQUIPMENT A.

Synch Selector Switch Key SET UP REQUIREMENTS A.

B.

C.

OP-46A, 4160V and 600V NORMAL AC POWER DISTRIBUTION, Rev. 48 OP-65, Startup and Shutdown Procedure, Rev. 102 Obtain current copy of OP-46A, 4160V and 600V NORMAL AC POWER DISTRIBUTION.

-20% CTP IC during reactor startup with plant conditions stable.

Main Generator is synchronized to the Grid. The 10700 Bus is deenergized. All 4160 VAC Busses on RSS.

OR1 Running Voltmeter downscale and attach a PID Tag.

D.

EVALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

actually performed.

8.

TASK CONDITIONS A.

A Reactor Startup is in progress. Reactor Power is -20% CTP. Currently at Step 0.23.5 of OP-65, Startup and Shutdown Procedure All prerequisites for transferring from reserve to normal station service have been met. Main Generator is synched to the grid.

The Shift Manager has given direction to transfer loads from Reserve to Normal Station Service.

6.

C.

- CRITICAL STEP Page 3 of 10

SIR0 TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T-4)

I I

VII.

INITIATING CUE I

3*

(D.20/21.2)

Not expected with astaMished conditions. Therefore NIA.

IF a degraded or undervoltage condition occurs while transferring bus, I

THEN immediately establish GREATER 1

THAN 3.9 KV using LTC CONTROL.

A reactor startup is in progress with the plant at approximately 20% CTP and the Main Generator synched to the grid. Per OP-65, Step 0.23.5, you have been directed to transfer loads from Reserve 115kv Transformers T2 and T3 to Normal Station Service Transformer T-4.

I 4'

(D.20/21.3)

At the 09-7 Panel, candidate observes MAIN GEN MW to be greater than or equal to 70MWe.

IF Main Generator is synchronized to 345 KV System, THEN verify Main Generator has a stable load of at least 70 MWe.

VIII.

TASK STANDARD

2.

The candidate will transfer either the 10100 Bus p~ the 10200 Bus per OP46A.

(D.20/21.1)

While performing the remainder of this subsection maintain 4 KV and 600V bus voltage per Section E.

Candidate obtains/reviews OP46A, Section E.

I STEP I

STANDARD I

WALUATION I COMMENT

1. I Obtain and review procedure.

Candidate obtains and reviews OP-65 and OP-46A.

Candidate determines that the start point is either step 0.20 (10700) or 0.21 (10200) of OP46A.

SAT / UNSAT SAT / UNSAT N I A SAT / UNSAT Page 4 of 10

SIR0 TASK TITLE: SWAP ELECTRtCAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T-4)

EVALUATOR:

Inform candidate that a surrogate operator is at the LTC CONTROL to respond to hidher direction.

5.

SAT / UNSAT

6.

Candidate will recognize the need, during performance of next step (D.20/21.8), that this step will be applicable and will obtain and review OP-46A, Section G.14; and determine start point to be G. 14.1.

7.

SAT / UNSAT

0.

(D.20/21.4)

Ensure Clark Energy Control Center and Nine Mile Point 1 Control Room (due to effect on 11 5 KV line loading) have been notified that 10100/10200 Bus will be transferred from reserve to normal service.

(D.20/21.5)

Station operators as follows:

e One to adjust bus voltage at LTC CONTROL 0

One to operate breaker control switches (D.20121.6)

Place BUS 10100/100200 FDR SYNCH SW switch in NORM.

(D.20/21.7)

IF voltages on NON-EMERG BKRS INCOMJNG and RUNNING volt meters can not be matched in following step, THEN perform subsection G.14, Single Meter Voltage Match Method.

STANDARD I EVALUATION I COMMENT EVALUATOR:

Inform candidate that notifications have been made.

SAT / UNSAT At 09-8, candidate inserts Synch Selector Switch Key into BUS 10100 (10200) FDR SYNCH SW and turns clockwise on notch to NORM (Normal) position.

SAT 1 UNSAT

CRITICAL STEP*

Page 5 of 10

S/RO TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE cT-4)

9.

10.

11.

12.

STEP (D.20/21.8)

Match voltages on NON-EMERG BKRS INCOMtNG and RUNNING volt meters using LTC CONTROL switch.

(G.14.1)

IF voltage mismatch is greater than 6 meter increments, THEN obtain guidance for performing bus transfer from Design Engineering.

(G.14.2.a)

IF transferring 4.16 KV bus from reserve to normal, THEN perform the following:

a. Place 4.16 KV bus FDR SYNCH SW switch in RES.

(G.14.2.b)

b. Note voltage on incoming meter.

STANDARD

~

At 09-8, candidate will direct LTC Control adjustment(s) and determine that INCOMING and RUNNING Voltages are unable to be matched within required band, necessitating use of the OP46A, Section G. 14, Single Meter Voltage Match Method.

EVALUATOR:

Surrogate is acting as the extra operator at LTC CONTROL, and will respond to candidate direction only.

EVALUATOR:

Inform candidate that due to the failure of the Running meter, Design Engineering has recommended the use of OP46A, Section G.14.

~

At 09-8, candidate turns Synch Selector Switch Key for BUS 10100 (10200) FDR SYNCH SW counterclockwise two notches to RES (Reserve) position.

Candidate observes 09-8 Panel INCOMING Voltmeter.

Candidate may write the value down or just commit it to memory.

EVALUATOR:

Ensure that you note voltage also.

EVALUATION / COMMENT SAT / UNSAT

CRITICAL STEP*

N I A SAT / UNSAT

CRITICAL STEP SAT / UNSAT Page 6 of 10

SIR0 TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T4)

'1 3.

14.

15.

-~

STEP (G.14.2.c)

c. Place 4.16 KV bus FDR SYNCH SW switch in NORM.

~

(G.14.2.d)

d. Match voltages on NON-EMERG BKRS INCOMING and RUNNING volt meters using LTC CONTROL switch.

(0.20/21.9)

IF phase angle is GREATER THAN 17 degrees NON-EMERG BKRS SYNCHROSCOPE, THEN perform the following:

List not requimd.

At 09-8, candidate turns Synch Selector Switch Key for BUS 10100 (10200) FDR SYNCH SW clockwise two notches to NORM (Normal) position.

SAT / UNSAT

CRITtCAL STEP*

At 09-8, candidate directs LTC CONTROL operator to operate tap changer to obtain voltage mismatch value within 5% (maximum) of value noted / written down in step G.14.2.b (JPM Step 12 above).

EVALUATOR:

The surrogate is acting as the extra operator at LTC CONTROL, and will respond to candidate direction only.

SAT / UNSAT

CRITICAL STEP*

Not expected with established conditions.

At 09-8, candidate locates and correctly reads the phase angle as indicated on Synchroscope, compares the indicated value to value contained in OP46A (17O),

and determines phase angle is less than 17".

SAT / UNSAT Page 7 of 10

SIR0 TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T-4) d

16.

EVALUATION I COMMENT SAT / UNSAT

CRITICAL STEP*

STEP (D.20/21.10)

WHEN incoming and running voltages are matched, AND synchroscope is at approximately 12 o'clock, perform the following bus transfer using the same hand, without unnecessary delay, to perform each breaker operation:

a.

b.

Close NSS TO BUS 101 00

/1 0200 BKR 101 02 / 10202 Open RSS TO BUS 10100

/I0200 BKR 10112 / 10212 STANDARD At 09-8, candidate:

1.

2.

3.

4.

5.

Observes incoming meter Directs voltage adjustment, if necessary, to re-establish matched conditions Observes position of synchroscope When synchroscope is at approximately 12 o'clock

( 4 7 " phase angle)

Without hesitation and with same hand, operates breakers as follows:

0 Close NSS TO BUS 101 00 /lo200 BKR 101 02

/ 10202 by turning control switch clockwise to CLOSE; and releasing on Red light indication of breaker closure.

Open RSS TO BUS 10100 /lo200 BKR 10112

/ 10212 by turning control switch counterclockwise to TRIP; and releasing on Green light indication of breaker open.

EVALUATOR:

Breaker operations should occur in an expeditious and deliberate process. Due to concern for possible high current developing and causing Breaker Trips. Also, the same hand should be used, operating the breakers one at a time, to prevent inadvertently opening both beakers at the same time.

Page 8 of 10

STEP STANDARD I

EVALUATION I COMMENT 11

18.

I (D.20/21.12)

I Candidate proceeds to Panel 09-16, locates white RPS I

17.

I A and RPS B power lights, and observes that they are illuminated.

Verify all white fights for RPS A and RPS B power source selectors are on (0.20/21.11)

'lace Bus 'oloo

'O2O0 FDR SYNCH SW switch in OFF and remove handle.

At 09-8, candidate turns Synch Selector Switch Key for BUS 10100 (10200) FDR SYNCH SW counterclockwise one notch to OFF position and removes key.

SAT / UNSAT 1 at Panel 09-16.

I I

SAT / UNSAT EVALUATOR: Terminate the task at this point.

II Page 9 of 10

INITIATING CUE A reactor startup is in progress with the plant at approximately 20% CTP and the Main Generator synched to the grid. Per OP-65, Step D.23.5, you have been directed to transfer loads from Reserve 11 5kv Transformers T2 and T3 to Normal Station Service Transformer T-4.

Page 10 of 10

m Entergy James A. FiePatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE S/RO FROM LOI-03-01 TASK TITLE: ST-SD, APRM CALIBRATION APPL. TO JPM NUMBER REV:

1 DATE: 3/7/05 NRC WA SYSTEM NUMBER:

215005 Al.07 3.0/3.4 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

20 Minutes SUBMITTED:

OPERATION REVIEW:

APPROVED:

JAF QUAL STANDARD NUMBER:

CANDIDATE NAME:

S.S.

NUMBER:

JPM Completion:

( ) Simulated

( X ) Performed Location:

( ) Plant

( X ) Simulator DATE PERFORMED:

TIME TO COMPLETE:

Minutes PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory EVALUATOR:

SIGNATURHPRINTED Page 1 of 8

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO FROM LOI-03-01 TASK TITLE: ST-SD, APRM CALIBRATION APPL. TO JPM NUMBER Current Update:

3/7/05 By:

RWD Date Int.

Outstanding Items:

Technical Review Questions and Answers Procedural Change Required Comments:

Simulator validated Additional Information Validation X

None Page 2 of 8

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SIR0 FROM LOI-03-01 TASK TITLE: ST-5D, APRM CALIBRATION APPL. TO JPM NUMBER

1.

II.

111.

IV.

V.

VI.

SAFETY CONSIDERATIONS A.

None REFERENCES A.

B.

ST-SD, APRM CALIBRATION, Rev. 2 OP-16, NEUTRON MONITORING, Rev. 25 TOOLS AND EQUIPMENT A.

Small Screwdriver SET UP REQUIREMENTS A.

B.

C.

-98% CTP IC. EPIC/3D available and plant conditions stable.

Adjust all APRMs to an acceptable value per ST-5D.

Adjust D APRM to 34% below desired value of ST-5D (@98% CTP).

EVALUATOR NOTES A.

B.

C.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and The candidate should, at a minimum, identlfy the change in equipment status light indication when equipment operation is simulated.

This JPM performance data based upon D APRM initially 34% low at -98% CTP actually performed.

TASK CONDITIONS A.

Plant returning to 100% CTP following rod pattern exchange. Currently at -98 % CTP B.

ST-5D required prior to continuing to 100% CTP.

- CRITICAL STEP Page 3 of 8

SIR0 FROM LOI-03-01 TASK TITLE: ST-SD, APRM CALIBRATION VII.

INITIATING CUE STEP Obtain and review procedure 8.1 Procedure Performance You are the SNO. The plant is currently operating at -98% CTP following a rod pattern exchange with no equipment out of service. The plant has been stable for several minutes. ST-SD, APRM CALIBRATION is required prior to continuing to 100% CTP.

Perform ST6D.

EVALUATOR Hand partially completed ST-5D to candidate TASK STANDARD The candidate will conduct an APRM calibration as directed by ST-5D. This calibration will require the adjustment to 1 APRM.

STANDARD Candidate obtains and reviews a current copy of ST-5D Candidate selects subsection 8.3

1.

2.

~

~ ~ _ _ _ _ _

EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT Page 4 of 8

SIR0 STANDARD FROM LOI-03-01 i: ST-SD, APRM CALIBRATION STEP EVALUATION I COMMENT 9SK TITI

3.

8.3.1 IF core power has changed GREATER THAN 2%, OR the control rod pattern has changed since the last core performance program was executed, THEN demand an Official 30 Program.

Candidate demands Official 3D at 30 keyboard by selecting:

Option 4, Run Official 30 0

Tab to Execute 0

Select 2 on the number pad SAT / UNSAT

CRITICAL STEP*

8.3.2 Determine APRM DR from the

4.

5.

SAT / UNSAT

CRITICAL STEP*

Candidate selects Percent Core Thermal Power with a value of -98%.

higher of the following values:

0 Largest MFLPD x 100 0

Percent core thermal power 8.3.3 [ITS] Adjust APRMs per Subsection 8.5.

8.5.1 Record initial APRM readings in Table 1.

8.5.2 Record DR in Table 1.

8.5.3 [ITS] Identify any APRM(s) requiring adjustment in Table 1. APRM shall be adjusted to indicate within k2%

of the DR.

SAT / UNSAT Candidate proceeds to subsection 8.5 SAT / UNSAT Candidate records values from Official 30

6.

SAT / UNSAT Candidate records value selected in 8.3.2

7.

Candidate identifies D APRM as requiring adjustment.

8.

SAT / UNSAT

CRITICAL STEP*

SAT / UNSAT EVALUATOR 8.5.4 IF APRM adjustment is required, THEN perform the following for each APRM requiring adjustment:

NOTE: Bypassing APRM may be omitted per SM.

A. Bypass the APRM channel requiring calibration per Section E of OP-16.

Select proper procedure section

9.

The Shift Manager desires that the APRMs be bypassed for adjustments.

Candidate obtains and review OP-16 noting any cautions that may be applicable Candidate selects section E.16 At 09-5 panel, candidate selects B division joystick to SAT / UNSAT

10.

SAT / UNSAT 11 SAT / UNSAT

-E:16.1 Place APRM BYP switch in (*).

12.

Page 5 of 8

S/RO At panel 09-14, candidate selects D APRM and confirms Meter Function switch is in average.

FROM LOI-03-01 SAT / UNSAT ASK TITI At panel 09-14, candidate selects D APRM and confirms Mode switch is in operate.

13.

SAT / UNSAT

14.

15.

16.

1 7.

18.

20.

I: ST-SD, APRM CALIBRATION STEP E. 16.2 Verify APRM (*) is bypassed using one or both of the following:

APRM (*) BYPASS indicating light is on APRM (*) EPIC alarm indicates bypassed E.16.3 Veri@ 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 ST-SD, 8.5.4 continued:

B. Ensure METER FUNCTION switch is set to AVERAGE.

C. Ensure APRM MODE switch is in the OPERATE position.

NOTE: Clockwise turn raises meter reading; counterclockwise turn lowers meter reading.

D. [ITS] Turn gain adjustment control (R16) on LPRM card 2-31 to obtain a meter reading within *2% of DR.

E. Unbypass APRM per Section E of E. 1 7.1 Verify the following lights for APRM (*) are off at panel 09-14:

OP-16.

rN0P UPSCL NEUT TRIP UPSCL THERM TRIP STANDARD At 09-5 panel, candidate observes white bypass lamp for APRM D.

AND / OR Candidate notes EPtC alarm typer indicates selected APRM bypass is ON Candidate notes the absence of the same indications for the remaining APRMs in that RPS division (B and F).

EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT At panel 09-14, candidate inserts small screwdriver into upper left simulated rheostat for the D APRM.

P n n A i A n + n +*

m e n h n h a i e n +n v n i a a inAinnCirrn +n - 0 Q O L

-ai iuiuac= LUI I IJ

~

I W

~

W I

~

O LW I ala= 11 IUIMLIVI I IW.-JW

10.

EVALUATOR In the simulator, 2-31 card can be identified but the nhntnc rln nnt PI 1nnnt-f rnsrlinn R-I fi pm I V ~ V Y uv I I V L uupayvi L I Y L ~ U S S ty I \\

I Y SAT / UNSAT Candidate obtains OP-16 and selects section E.17 AI top OT panel uv-14, canoioare ioenriiies lamps Tor me D APRM.

SAT / UNSAT Page 6 of 8

2 1.

STEP E. 17.2 Place APRM BYP switch for

23.

STANDARD At panel 09-5, candidate selects 6 division APRM joystick to center position.

At 09-5 panel, candidate observes bypass lamp extinguished service using one or both of the APRM (*) BYPASS indicating light is Off No EPIC bypassed alarm for APRM (*)

E. 17.4 Verifl all three 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 three APRMs No EPIC bypassed a l m s for the three following:

EVALUATION / COMMENT SAT I UNSAT SAT / UNSAT I

67. 1 adjusted APRMs in Table 1.

II APRM (*) in center position.

E.17.3 Veri@ APRM (*) is returned to

22.

I Candidate record final reading.

APRMs 8.5.5 Record final APRM readings for 74 I

SAT / UNSAT 1

EVALUATOR: Terminate the task at this point.

I Page 7 of 8

INITIATING CUE You are the SNO. The plant is currently operating at -98% CTP following a rod pattern exchange with no equipment out of service. The plant has been stable for several minutes. ST-SD, APRM CALIBRATION is required prior to continuing to 100% CTP. Perform ST-SD.

Page 8 of 8

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS SURVEILLANCE TEST PROCEDURE APRM CALIBRATION ST-5D REVISION 2 APPROVED BY:

DATE \\ l / Z d l

~ S P O N S ~ B L E PROCEDURI~ OWNER EFFECTIVE DATE:

/2f io. B;I FIRST ISSUE 0 FULL REVISION 0 LIMITED REVISION

~

~~

I I

CONTINUOUS USE TSR t

TECHNICAL

APRM CALIBRATION ST-5D REVISION

SUMMARY

SHEET REV. NO.

CHANGE AND REASON FOR CHANGE 2

Revised Step 8. 5. 5 to require final APRM readings to be recorded only for APRMs that were adjusted. (PCR #1 dated 8/9/00, EC #1 dated 9 / 5 / 0 0 )

Updated subsection 1.1, Frequency and revised section 1.2 in accordance with improved Technical Specifications ( I T S ).

Added subsection 1. 3 Technical Requirements Manual (TRM) and applicable reference.

Revised Steps 8. 2. 1. ~ ~

8. 2. 3. C, 8. 3. 3, 8. 4. 4 t o "Adjust APRM(s) per subsection 8. 5 ". Revised steps 8. 5. 3 and 8. 5. 4. D,

which adjust APRM(s), to obtain a meter reading within k2'a of desired reading (DR).

Marked Step 6.2.7 as CTS. The step implies that APRM can be adjusted to greater than 2 % above desired reading, which is not allowed per ITS SR 3. 3. 1. 1. 2.

Added note to step 8. 5. 5 to state tech spec acceptance criteria and updated section 10.0, Acceptance Criteria.

Rev. No. 2 Page 2 of 2 4

APRM CALIBRATION ST-5D TABLE OF CONTENTS SECTION 1.0 REQUIREMENTS 2.0 PURPOSE........................

3.0 REFERENCES

4.0 PREREQUISITES.....................

5.0 TEST EQUIPMENT. SPECIAL TOOLS. AND MATERIALS 6.0 PRECAUTIONS AND LIMITATIONS..............

7.0 GENERAL TEST METHODS 8.0. PROCEDURE.......................

8.1 Procedure Performance.................

8.2 APRM Calibration Less Than 25% of Rated Power.....

8.3 APRM Calibration Greater Than or Equal to 25%.....

8.4 Manual Calculation by Reactor Analyst Group When Greater Than or Equal to 25%...........

8.5 APRM Gain Adjustments.................

10.0 ACCEPTANCE CRITERIA........

11.0 ACCEPTANCE VERIFICATION................

12.0 ATTACHMENTS.................

1.

TEST SIGNOFF LOG PAGE 4

5 5

6 6

7 9

10 10 11 15 1 6 1 7 1 9 20 23 24 R e v. No. 2 Page 3 of 24

APRM CALIBRATION ST-5D 1.0 REQUIREMENTS 1.1 Frequency

[CTSI Once daily while in the Run Mode

[ITS]

NOTE :

Not required to be performed until 1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after THERMAL POWER 225% RTP.

[ITS]

0 Once every 7 days 1.2 Technical Specifications 1.2.1 Surveillance Requirements

[CTSI 4.1.A 4.1.B

[ITS]

SR 3.3.1.1.2 (Table 3.3.1.1-1, Functions 2. b and 2.c)

SR 3.2.4.2 1.2.2 Limiting Conditions for Operation

[CTSI None

[ITS]

LCO 3.2.4 LCO 3.3.1.1

[ITS]

1.3 Technical Requirements Manual (TRM) 1.3.1 TRO 3.3.B 1.3.2 TRS 3.3.B.2 (Table T3.3.B-1, Function 1.b) 1.4 Other None 1.5 Commitments 1.5.1 LER 90-003, requires implementation of alternate method of calculating core power below 20% of rated.

Rev. No. 2 Page 4 of 24

APRM CALIBRATION ST-5D 1.6 Expectations 1.6.1 OER 940119, Compare heat balance results to calculated power levels to ensure no reactor overpower due to feed flow input errors.

1.6.2 DER-98-02032, ACT-98-35526, Revised procedure for APRM gain adjustment to improve human factors.

1.6.3 JAF-SE-00-028, Added precaution to describe required compensatory actions for a failed or unreliable feedwater temperature input to the 3D Monicore.

2.0 PURPOSE To calibrate Average Power Range Monitor (APRM) System.

3.0 REFERENCES

3.1 Performance References 3.1.1 OP-16, Neutron Monitoring 3.1.2 RAP-7.3.3, Core Thermal Power Evaluation 3.2 Developmental References RAP-7.4.5, APRM Calibration Rev. NO. 2 Page 5 of 24

ST-5D APRM CALIBRATION NOTE:

Sections 4 and 5 may be performed in any order or concurrently.

4.0 PREREQUISITES 4.1 SM has granted permission to perform this test.

Init 4. 2 Revision Number of this Working Copy is the same as the revision number listed in the Master Copy of the Index of Operations Surveillance Test Procedures.

4.3 Test personnel have read this procedure and are thoroughly familiar with its contents.

4.5 Start of test recorded in NCO Log Book.

4.6 No control rod movement or recirculation flow changes are in progress.

5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS 5.1 Test Equipment None 5.2 Special Tools A very small flathead screwdriver 5.3 Materials None Rev. No. 2 Page 6 of 24

APRM CALIBRATION ST-5D 6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions lEXPl. 6.3 If one of the four feedwater temperature inputs to the 3D Monicore (02TE-140Af 02TE-l40B, 02TE-l40C, or 02TE-140D) fails or becomes unreliable, then one of the following compensatory actions is required:

Procedure changes (such as ST-40D) to require that a substitute value is inserted for the associated EPIC point. The substitute value shall be equal to the lowest reading operable feedwater temperature indication from EPIC-A-407, 408, 410, or 411. This value shall be adjusted daily before performing ST-5D and ST-5E, and as soon as practicable after changes in reactor power.

Temporary modification to provide an alternate feedwater temperature input to the plant process computer. This modification shall use the redundant temperature element on the same feedwater line as the sole value for that feedwater line. This method is preferred over operator inserted substitute values.

6.2 Limitations 6.2.1 Test personnel shall immediately notify the NCO or 6.2.2 Test personnel shall print name, sign initials, and CRS of any failure to meet acceptance criteria.

enter date on Attachment 1 before performing Section 8 of this test.

6.2.3 When test personnel complete their assigned portion of this test, they shall enter hours worked on.

6.2.4 Once this test has been started, any additional test personnel shall read this procedure and become thoroughly familiar with its contents before performing any portion of this test.

Rev. NO. 2 Page 7 of 24

ST-5D APRM CALIBRATION 6.2.5 Multiple working copies of this test may be used provided the following requirements are satisfied:

NOTE:

The work site is defined as the location where work is controlled. The location of the work site is at the discretion of the NCO/ SNO.

A. A working copy of this test shall be retained at the work site.

B. The work site working copy shall be the legal record for documenting this test.

C. Data from all steps performed away from the work site, including signatures, initials, and recorded values, is transcribed into the work site working copy following completion of the test.

6.2.6 If the ratio of MFLPD/FRP is greater than 1.0, then compliance with Tech Specs is accomplished by making the APRM read greater than or equal to MFLPD instead of lowering APRM trip setpoints.

[ CTS 1 6.2.7 If an APRM gain adjustment results in nuisance rod block alarms, then the preferred action is to request a rod pattern adjustment from the reactor engineer. As an alternate, the APRM gain may be adjusted with SM permission to bring the alarm in solid. This option should be minimized to prevent masking the alarm.

6.2.8 Conditional (IF, THEN) steps in this test may be marked sNA1 if not applicable.

6. 2. 9 Steps in this test marked rrNR are not required to be initialed.

Rev. No. 2 Page 8 of 24

APRM CALIBRATION ST-5D 7. 0 GENERAL TEST METHODS 7.1 This test consists of five subsections which determines the method used for calibrating the Average Power Range Monitor (APRM) System.

7. 2 This test contains the following subsections:

7. 2. 1 Determine procedure subsection to perform per the criteria provided in Subsection 8.1.

7. 2. 2 Determine APRM desired reading (DR).

7. 2. 3 Calibrate APRMs per Subsection 8.5 Rev. No. 2 Page 9 of 2 4

APRM CALIBRATION ST-5D 8. 0 PROCEDURE 8.1 Procedure Performance Determine the applicable procedure subsection to perform as follows:

(-1 IF reactor power is LESS THAN 25%,

THEN perform Subsection 8. 2.

(-)

IF reactor power is GREATER THAN OR EQUAL TO 25%,

AND the MONICORE programs are operable, THEN perform Subsection 8. 3.

(-1 IF reactor power is GREATER THAN OR EQUAL TO 25%,

AND the MONICORE programs are not operable, THEN have Reactor Engineering perform Subsection 8.4.

Init R e v. No. 2 Page 10 of 24

ST-5D APRM CALIBRATION

]ICOMl.

5.1 8.2 APRM Calibration Less Than 25% of Rated Power NOTE 1: APRM calibration per OP-65 is performed per Steps 8.2.1 and 8.2.2.

NOTE 2:

Core Thermal Power and Flow Log will abort if feedwater flow rate is too low.

8.2.1 IF both of the following conditions exist:

Reactor pressure GREATER THAN 970 psig BPV-1 near full open AND all other bypass valves full closed

(-1 THEN perform the following:

A. Demand Core Power and Flow Log B. Determine APRM DR as follows:

(-1 IF result of Core Power and Flow Log program is BETWEEN 9 and 14% power, THEN DR equals the power level determined per Step 8.2.1.A.

(-1 IF result of Core Power and Flow Log program is not BETWEEN 9 and 14% power, THEN DR equals 10% power.

Init

(-)

IF Core Power and Flow Log aborted, THEN DR equals 10% power.

DR =

C. [CTS]

Adjust APRMs to read GREATER THAN OR EQUAL TO DR per Subsection 8.5.

[ITS]

Adjust APRMs per Subsection 8.5.

NR R e v. No. 2 Page 11 of 24

ST-5D APRM CALIBRATION Init IEXPl. 6.1 8.2.2 IF both of the following conditions exist:

Reactor pressure GREATER THAN 970 psig BPV-1 full open

(-1 BPV-2 near full open

(-1 All other bypass valves full closed

(-1 THEN perform the following:

A. Demand Core Power And Flow Log.

B. IF Core Power and Flow Log program aborts due to low feedwater flow rate, THEN issue a PID for I&C Department to investigate and perform necessary repairs.

NOTE:

While I&C is troubleshooting, APRMs may be calibrated per Steps 8.2.2.C through 8.2.2.E.

C. Determine APRM DR as follows:

(-1 IF result of Core Power and Flow Log program is BETWEEN 17 and 22% power, THEN DR equals the power level determined per Step 8.2.2.A.

(-1 IF result of Core Power and Flow Log program is not BETWEEN 17 and 22% power, THEN DR equals 17% power.

(-1 IF Core Power and Flow Log aborted, THEN DR equals 17% power.

DR =

D. IF Core Power And Flow Log result is not BETWEEN 17 and 22% power, THEN investigate cause of discrepancy before raising power above 20% of rated.

Rev. No. 2 Page 12 of 24

APRM CALIBRATION ST-5D Init E. [CTS]

Adjust APRMs to read GREATER THAN OR EQUAL TO DR per Subsection 8.5.

[ITS 1

Adjust APRMs per Subsection 8.5.

8.2.3 IF both of the following conditions exist:

Reactor pressure GREATER THAN 970 psig Conditions other than specified in Steps 8.2.1 and 8.2.2 exists (such as a different combination of bypass valves open, or main generator in service 1

(-1 THEN perform the following:

A. Demand Core Power and Flow Log.

B. Determine APRM DR as follows:

NR

1. IF both of the following conditions exist:

BPV-1 full open AND BPV-2 is not near full open THEN determine DR as follows:

(-1 IF result of Core Power and Flow Log program is BETWEEN 10 and 17%

power, THEN DR equals the power level determined per Step 8.2.3.A.

(-)

IF result of Core Power and Flow Log program is not BETWEEN 10 and 17% power, THEN DR equals 15% power.

(-1 IF Core Power and Flow Log aborted, THEN DR equals 15% power.

DR =

(Step 8.2.3.B continued on next page)

Rev. No. 2 Page 13 of 24

ST-5D APRM CALIBRATION Init 8.2.3.B (Cont)

2. IF all of the following conditions exist:

BPV-1 full open

(-1 BPV-2 full open

(-1 BPV-3 is not near full open

(-1 THEN determine DR as follows:

(-1 IF result of Core Power and Flow Log program is BETWEEN 17 and 24%

power, THEN DR equals the power level determined per Step 8.2.3.A.

(-1 IF result of Core Power and Flow Log program is not BETWEEN 17 and 24%

power, THEN DR equals 22% power.

(-1 IF Core Power and Flow Log aborted, THEN DR equals 22% power.

DR =

3. IF the main generator is in service, THEN DR is the power level determined per Step 8.2.3.A.

DR =

C. [CTSI Adjust APRMs to read GREATER THAN OR EQUAL TO DR per Subsection 8. 5.

[ITS]

Adjust APRMs per Subsection 8. 5.

NR Rev. No. 2 Page 14 of 24

APRM CALIBRATION ST-5D 8.3 APRM C a l i b r a t i o n Greater Than or Equal to 25%

Init 8.3.1 I F core power has changed GREATER THAN 2%,

OR the control rod pattern has changed since the last core performance program was executed, THEN demand an Official 3D Program.

8.3.2 Determine APRM DR from the higher of the following values:

Largest MFLPD x 100 x 100 =

Largest MFLPD Percent core thermal power Thermal power =

(-1 DR =

8.3.3

[CTSI Adjust APRMs to read GREATER THAN OR EQUAL TO DR per Subsection 8.5.

[ITS]

Adjust APRMs per Subsection 8.5.

Rev. No. 2 Page 15 of 24

ST-5D APRM CALIBRATION 8.4 Manual Calculation by Reactor Analyst Group When Greater Than or Equal to 25%

8.4.1 Calculate core thermal power per RAP-7.3.3.

RE 8.4.2 Use the Manual Monitor Menu to run an Official 3D Program.

8.4.3 Determine the APRM DR from the higher of the following values:

RE Largest MFLPD x 100 x 100 =

(-1 Largest MFLPD FRP x 100 x 100 =

(-1 FRP DR =

RE 8.4.4

[ CTS 1 Adjust APRMs to read GREATER THAN OR EQUAL TO DR per Subsection 8.5.

[ITS]

Adjust APRMs per Subsection 8.5.

NR R e v. No. 2 Page 16 of 24

ST-5 D APRM CALIBRATION JEXPl. 6. 2 8. 5 APRM G a i n Adjustments 8.5.1 Record initial APRM readings in Table 1.

8. 5. 2 Record DR in Table 1.

8. 5. 3

[CTSI Identify any A P R M ( s ) requiring adjustment in Table 1. APRM shall be adjusted to indicate GREATER THAN OR EQUAL TO the DR.

[ITS]

Identify any A P R M ( s ) requiring adjustment in Table 1. APRM shall be adjusted to indicate within *2% of the DR.

8. 5. 4 IF APRM adjustment is required, THEN perform the following for each APRM requiring adjustment:

NOTE:

Bypassing APRM may be omitted per SM.

A. Bypass the APRM channel requiring calibration per Section E of O P - 1 6.

B. Ensure METER FUNCTION switch is set to AVERAGE.

C. Ensure APRM MODE switch is in the OPERATE position.

NOTE:

Clockwise turn raises meter reading; counterclockwise turn lowers meter reading.

D. [CTS]

Turn gain adjustment control (R16) on LPRM card 2-31 to obtain a meter reading GREATER THAN OR EQUAL TO DR.

C ITS I

Turn gain adjustment control (R16) on LPRM card 2 - 3 1 to obtain a meter reading within

? 2 % of D R.

E. Unbypass APRM per Section E of O P - 1 6.

Init NR NR NR NR NR Rev. No. 2 Page 17 of 2 4

APRM CALIBRATION ST-5D APRM A

B C

D E

F INITIAL READING ! % )

DESIRED READING ( % )

REQUIRES ADJUSTMENT ( d )

FINAL READING ( % )

[ITS]

NOTE :

Tech spec acceptance criteria for Final shall be within + 2 % of DR.

Init Re ad i ng I

8. 5. 5 Record final APRM readings for adjusted APRMs in Table 1.

TABLE 1 APRM GAIN ADJUSTMENTS R e v. No. 2 Page 18 of 24

~

APRM CALIBRATION ST-5D 9.0 9.1 9.2 System Restoration 9.1.1 Operable APRMs are unbypassed.

9.1.2 Step 9.1.1 verified by Licensed Operator.

Signature/Date Review and Signoff 9.2.1 Test completed.

Date / Time 9.2.2 Calculations performed in the following steps have been independently verified:

Independent verification

/

Signature/Date 9.2.3 Test personnel have recorded hours worked on.

9.2.4 Man-Hours totalled and recorded on.

9.2.5 Completion of test recorded in NCO Log Book.

10.0 ACCEPTANCE CRITERIA

[CTSI Operable APRMs are reading greater than or equal to DR.

[ITS]

Operable APRMs are reading within +2% of DR.

Rev. NO. 2 Page 19 of 24

ST-5D APRM CALIBRATION 11.0 ACCEPTANCE VERIFICATION 11.1 NCO/SNO Review 11.1.1 11.1.2 11.1.3 11.1.4 11.1.5 11.1.6 11.1.7 Verify required data has been recorded and is within required tolerances.

Verify required initials and signatures have been entered.

Review test to determine if test acceptance criteria has been satisfied.

Check one of the following as appropriate for test results :

(-)

Acceptance criteria satisfied, no corrective

(-)

Acceptance criteria satisfied, corrective action required.

action required.

(-1 Acceptance criteria satisfied.

IF acceptance criteria is satisfied AND corrective action is required, THEN perform the following:

A. Describe in Subsection 11.3, Remarks.

B. Initiate a PID and record PID number.

PID Number IF acceptance criteria is not satisfied, THEN perform the following:

A. Immediately notify SM.

B. Initiate a PID and record PID number.

PID Number Sign and record date and time.

SNO or NCO Date/Time Rev. No. 2 Page 20 of 24

APRM CALIBRATION ST-5D 11.2 Management SRO Review 11.2.1 Verify current revision of surveillance test procedure was used.

11.2.2 Verify surveillance test was completed within required test frequency.

11.2.3 Verify data tables and attachments have been properly completed.

11.2.4 Verify required data has been recorded and is within required tolerances.

11.2.5 Verify required initials and signatures have been entered.

11.2.6 Review test to determine if test results satisfy acceptance criteria.

11.2.7 Check one of the following as appropriate for test results:

(-1 Acceptance criteria satisfied.

11.2.8 IF acceptance criteria is not satisfied, THEN perform the following:

A. Immediately notify Operations Manager or alternate.

B. Record name of person notified.

Person Notified C. Initiate required corrective and compensatory actions.

11.2.9 Sign and record date and time.

Management SRO Rev. No. 2 Date /Time Page 21 of 24

APRM CALIBRATION ST-5D 11.3 Remarks Rev. No. 2 Page 22 of 24

APRM CALIBRATION ST-5D 12.0 ATTACHMENTS

1. TEST SIGNOFF LOG R e v. No. 2 Page 23 of 2 4

APRM CALIBRATION ST-5D ATTACHMENT 1 Page 1 of 1 TEST SIGNOFF LOG Total Rev. No. 2 Page 24 of 24

m "Entegy James A. FitzPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOBPERFORMANCEMEASURE S/RO/N PO 20101012 TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

APPL. TO JPM NUMBER REV:

8 DATE: 3/7/05 NRC WA SYSTEM NUMBER: 201003 K1.01 3.2/3.3 JAF TASK NUMBER:

JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

20 Minutes SUBMITTED:

OPERATION REVIEW: -

APPROVED:

- * * - - * - - * - - - - - - - - r n * * * - - * - ~ - - - - - - - - - - - - - - * *

r n * * * * - ~ - * - * - - * * * * * ~ r n ~ * - ~ - ~ * ~ ~ ~ - ~ r n ~ r n CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

(X) Simulated

( )Performed Location:

(X) Plant

( ) Simulator DATE PERFORMED:

TIME TO COMPLETE:

Minutes PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory EVALUATOR:

SIGNATURUPRINTED Page 1 of 14

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO/NPO 201 01 012 TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

APPL. TO JPM NUMBER Current Update:

3/7/05 By:

RWD Date Int.

Outstanding Items:

Technical Review Additional Information Questions and Answers Validation Procedural Change Required X

None Comments:

Page 2 of 14

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO/NPO 201 01 01 2 TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A APPL. TO JPM NUMBER HYDRAULIC CONTROL UNIT (HCU)

1.

II.

111.

IV.

v.

VI.

SAFETY CONSIDERATIONS A.

Proper safety attire (hardhat, safety shoes, safety glasses, ear protection, etc.) is to be worn while out in the plant.

REFERENCES A.

OP-25, Control Rod Drive Hydraulic System, Rev. 75 B.

N-1 Key TOOLS AND EQUIPMENT A.

Fuse Pullers SET UP REQUIREMENTS A.

Obtain Shift Manager's permission prior to perform this task.

B.

Contact Radiation Protection prior to performance of this task to discuss radiological conditions in the area of the HCU.

EVALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and not actually performed.

B.

The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

TASK CONDITIONS A.

The Plant is Mode 1 at 100% Reactor Power B.

Control Rod 22-19 has been fully inserted and declared inoperable to support maintenance on 03SOV-117 and 03SOV-118.

C.

HCU-22-19 must now be isolated.

EVALUATOR: The HCU chosen for this task may be changed as necessary to accommodate plant conditions.

- CRITICAL STEP Page 3 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT VII. INITIATING CUE The Plant is Mode 1 at 100°rb Reactor Power. Control Rod 22-19 has been fully inserted and declared inoperable 3 support maintenance on the associated Scram Pilot Air Solenoid Valves (03SOV-117 and 03SOV-118). Isolate HCU-22-19 per OP-25, Section G.l. OP-25 actions G.l.l through G.1.6 are complete. Nitrogen depressurization of HCU-22-19 will not be required.

VIII.

TASK STANDARD The candidate will isolate and electrically disarm HCU 22-19 (or alternate HCU chosen to support plant conditions).

1.

2.

3.

STEP Obtain and review procedure (G. 1.7)

IF Control Rods are required to be operable, THEN electrically disarm CRD-(*) per subsection G.24 of OP-25.

(G.24.1)

Notify Control Room that CRD-(') will be electrically disarmed.

STANDARD

~

Candidate obtains and reviews OP-25. Candidate determines that the start point is step G. 1.7.

EVALUATOR:

If candidate requests information to support requirement for Control Rod operability, inform candidate that Control Rods are required to be operable.

Candidate obtains and reviews OP-25, section G.24.

Candidate determines that the start point is step G.24.1.

EVALUATOR:

When the candidate states that he/she would contact the Control Room to notify them that CRD 22-19 will be electrically disarmed, inform the candidate that "CRD 22-19 will be electrically disarmed."

Page 4 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

4.

5.

6.

STEP (G. 24.2)

Unplug amphenol connector from each of the following solenoid operated valves at HCU-(*) and control per AP-12.06.

03SOV-120(*) (WITHDRAW 03SOV-121(') (INSERT 03SOV-122(*) (WITHDRAW 03SOV-123(*) (INSERT DRIVE SETTLE SOV)

EXHAUST WATER SOV)

DRIVE WATER SOV)

WATER SOV)

~

(G.24.3)

Notify Control Room that CRD-(*) has been electrically disarmed.

(G. 1.8)

Close 03HCU-101(*) (CRD INSERT LINE ISOL VALVE).

STANDARD Candidate correctly locates amphenols associated with CRD/HCU 22-19 and indicates that he/she would unplug

/ control them.

EVALUATOR:

When the candidate states that helshe would unplug the respective amphenols, inform the candidate that "The four respective amphenols are unplugged and the PTR is hung."

EVALUATOR NOTE:

HCU-22-19 is isolated RB 272' East.

~

EVALUATOR:

When the candidate states that he/she would contact the Control Room to notify them that CRD 22-19 has been electrically disarmed, inform the candidate that "CRD 22-1 9 has been electrically disarmed."

Candidate correctly locates 03HCU-101 associated with CRD/HCU 22-1 9 and indicates that he/she would close it.

EVALUATOR:

When the candidate goes to the Reactor Building 272' East side HCU area, locates and identifies HCU 22-19 and 03HCU-101; states that he/she would close 03HCU-101, then inform the candidate "03HCU-101 (22-1 9) is CLOSED."

EVALUATION / COMMENT SAT / UNSAT

CRITICAL STEP*

SAT / UNSAT SAT t UNSAT

CRITICAL STEP*

Page 5 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU) d

7.

a.

"9.

STEP (G. 1.9)

Close 03HCU-102(*) (CRD WITHDRAW LINE ISOL VALVE).

(G. 1.lo)

Close 03HCU-l13(*) (CHARGING WATER HEADER ISOL VALVE).

(G.l. l l )

Close 03HCU-104(*) (COOLING WATER SUPPLY ISOL VALVE).

I EVALUATION I COMMENT STANDARD Candidate correctly locates 03HCU-102 associated with CRDIHCU 22-1 9 and indicates that he/she would close it.

SAT / UNSAT

CRITICAL STEP*

EVALUATOR:

When the candidate locates and identifies 03HCU-102 and states that he/she would close 03HCU-102, then inform the candidate "03HCU-102 (22-1 9) is CLOSED."

Candidate correctly locates 03HCU-113 associated with CRD/HCU 22-1 9 and indicates that helshe would close it.

EVALUATOR:

When the candidate locates and identifies 03HCU-113 and states that he/she would close 03HCU-113, then inform the candidate "03HCU-113 (22-19) is CLOSED."

Candidate correctly locates 03HCU-104 associated with CRD/HCU 22-1 9 and indicates that he/she would close it.

SAT I UNSAT

CRITICAL STEP*

SAT / UNSAT

CRITICAL STEP*

EVALUATOR:

When the candidate locates and identifies 03HCU-104 and states that he/she would close 03HCU-104, then inform the candidate "03HCU-104 (22-1 9) is CLOSED."

Page 6 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

lo.

tl.

12.

STEP (G.1.12)

Close 03HCU-103(*) (CRD DRIVE WATER SUPPLY 1SOL VALVE).

(G.1.13)

Close 03HCU-105(*) (EXHAUST WATER SOL VALVE).

(G. 1.14)

Close 03HCU-112(*) (SCRAM DISCHARGE HEADER SOL VALVE).

STANDARD Candidate correctly locates 03HCU-103 associated with CRD/HCU 22-1 9 and indicates that he/she would close it.

EVALUATOR:

When the candidate locates and identifies 03HCU-103 and states that he/she would close 03HCU-103, then inform the candidate "03HCU-103 (22-1 9) is CLOSED."

Candidate correctly locates 03HCU-105 associated with CRDIHCU 22-19 and indicates that he/she would close it.

EVALUATOR:

When the candidate locates and identifies 03HCU-105 and states that heishe would close 03HCU-105, then inform the candidate "03HCU-105 (22-1 9) is CLOSED."

Candidate correctly locates 03HCU-112 associated with CRD/HCU 22-1 9 and indicates that he/she would close it.

EVALUATOR:

When the candidate locates and identifies 03HCU-112 and states that he/she would close 03HCU-112, then inform the candidate "03HCU-112 (22-1 9) is CLOSED."

SAT / UNSAT

CRITICAL STEP SAT / UNSAT

CRITICAL STEP*

SAT / UNSAT

CRITICAL STEP*

Page 7 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT [HCU) with CRD/HCU 22-19 and indicates that he/she would observe mechanical position indication to verify current valve position.

13,

14.

STEP (G. 1. 1 5)

Remove the following fuses to de-energized Scram Pilot Solenoid Operated Valves 03SOV-l17(*)and 09SOV-l18(*):

0 5A-FlQAr) 5A-FI9Br)

(G. 1. I 6)

Verify open the following valves by observing valve position indicators at HCU-(*):

0 03AOV-126(*) (HCU INLET SCRAM AIR OPER VALVE) 03AOV-127(*) (HCU OUTLET SCRAM AIR OPER VALVE)

STANDARD I

EVALUATION / COMMENT Candidate correctly locates Scram Pilot Solenoid Fuses associated with CRD/HCU 22-1 9 SOVs 1 17/118;and indicates that he/she would pull them with the fuse puller.

EVALUATOR:

When the candidate goes to the Scram Solenoid Fuse Panel and states that helshe would open the panel and remove fuses 5A-F19A(22-19) and 5A-F198(22-19),

then inform the candidate "Fuses 5A-FlgA(22-19) and 5A-F196622-19) are removed."

SAT / UNSAT

CRITICAL STEP*

EVALUATOR:

When the candidate locates and identifies 03AOV-126 and 03AOV-127 and states that he/she would use the mechanical position indicators on 03AOV-126 and 03AOV-127 to observe that the valves are open, then inform the candidate "03AOV-126 and 03AOV-127 indicate OPEN."

Page 8 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

15.

16.

STEP (G.1.17)

Verify HCU-(*) blue SCRAM light is on at FULL CLOSE DISPLAY.

(G. 1. 1 8)

Loosen threaded cap on 03HCU-107(*)

(ACCUMULATOR DRAIN VALVE) to thoroughly vent pressure before proceeding to the next step.

STANDARD Candidate recognizes need to obtain information from 09-5 Panel in the Control Room.

EVALUATOR:

When the candidate states that he/she would contact the Control Room and request the status of the blue scram light for control rod 22-19, then inform the candidate "Blue Scram light for Control Rod 22-19 is ON".

Candidate correctly locates O3HCU-107 associated with CRD/HCU 22-1 9 and recognizes WARNING through indicating that he/she would loosen the cap "slowly",

"carefulty", or "in a controlled manner" (or similar wording).

EVALUATOR:

When the candidate states that helshe would loosen threaded cap on 03HCU-107-22-19, then inform the candidate "Threaded cap on 03HCU-107(22-19) is LOOSE and DEPRESSURIZED'.

EVALUATION I COMMENT SAT / UNSAT

~

SAT / UNSAT

CRITICAL STEP*

Page 9 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

17.

18.

19.

STEP (G. 1.19)

Remove threaded cap from 03HCU-107(*) (ACCUMULATOR DRAIN VALVE).

(G. 1.20)

Connect hose to 03HCU-l07(*)

(ACCUMULATOR DRAIN VALVE) and route other end of hose to a floor drain or suitable container.

(G.1.21)

Crack open 03HCU-107(*)

(ACCUMULATOR DRAIN VALVE).

STANDARD Candidate correctly identifies 03HCU-107 associated with CRD/HCU 22-1 9 and indicates that he/she would remove it (may add "by turning counterclockwise")

EVALUATOR:

When the candidate states that he/she would remove threaded cap on 03HCU-107-22-19, then inform the candidate "Threaded cap on 03HCU-107(22-19) is REMOVED."

Candidate correctly identifies 03HCU-107 associated with CRD/HCU 22-1 9 and identifies hose routing location (floor drain / poly bottle in vicinity)

EVALUATOR:

When the candidate locates, identifies and states that he/she would connect a hose to 03HCU-107(22-19) and properly route the other end, then inform the candidate "Hose is INSTALLED'.

Candidate correctly identifies 03HCU-107 associated with CRD/HCU 22-1 9 and indicates that he/she would crack it open.

EVALUATOR:

When the candidate locates and identifies 03HCU-107 and states that he/she would crack open 03HCU-107, then inform the candidate "03HCU-107 (22-1 9) is CRACKED OPEN."

EVALUATION / COMMENT SAT / UNSAT

CRITICAL STEP*

SAT / UNSAT SAT / UNSAT Page 10 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

20.

2 1 STEP (G. 1.22)

WHEN HCU 22-1 9 water accumulator is thoroughly vented, open 03HCU-107r) (ACCUMULATOR DRAIN VALVE).

(G. 1.23)

IF maintenance is to be performed on any of the following:

03AOV-126 (*) (HCU INLET SCRAM AIR OPER VALVE)

SCRAM AIR OPER VALVE)

PILOT AIR SOLENOID OPER VALVE) downstream of 03HCU-116 (*)

(SCRAM PILOT AIR {SOL VALVE) 03AOV-127 (*) (HCU OUTLET 03SOV-117/118 (*) (SCRAM 0

Instrument air piping THEN close 03HCU-116 (*)(SCRAM PILOT AIR SOL VALVE)

STANDARD

-~

Candidate correctly identifies 03HCU-107 associated with CRD/HCU 22-1 9 and indicates that he/she would fully open it upon indications that it was depressurized.

EVALUATOR:

When the candidate locates and identifies 03HCU-107 and states that he/she would fully open 03HCU-107, then inform the candidate "03HCU-107 (22-1 9) is FULL OPEN."

Candidate recognizes need to perform step based on planned maintenance on 03SOV-117/118; and correctly locates 03HCU-116 associated with CRDIHCU 22-1 9 and indicates that he/she would dose it.

EVALUATOR:

When the candidate locates and identifies 03HCU-116 and states that he/she would close 03HCU-116, then inform the candidate "03HCU-116 (22-19) is CLOSED."

EVALUATION I COMMENT SAT / UNSAT

CRITICAL STEP*

SAT I UNSAT

CRITICAL STEP Page 11 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

22.

~

23.

24.

~-

STEP (G. 1.24)

IF maintenance is to be performed that requires depressurizing the HCU nitrogen accumulator, THEN perform the following:

(MA) LIST NOT REQUIRED (G. 1.25)

Verify red light is on at CRD ACCUMULATOR MONITOR & SCRAM VALVE POSITION SELECTOR panel 25-04 (east side) or 25-22 (west side)

Reactor Buitding 272'.

(G. I

.26)

Notify Control Room that HCU-(*) has been removed from service.

STANDARD EVALUATOR:

If requested, inform candidate that no maintenance is planned that required depressurizing the accumulator.

~~

Candidate goes to the CRD ACCUMULATOR MONITOR & SCRAM VALVE POSITION SELECTOR Panel 25-04 (east side) and verifies red light is on for HCU-22-19.

EVALUATOR:

As candidate approaches panel and indicates that he/she would be looking for a red light on Panel 25-04 that corresponds to HCU 22-19, inform candidate that "Red light is on for HCU 22-19 at Panel 25-04."

EVALUATOR:

When the candidate states that he/she would contact the Control Room and inform them that HCU 22-19 has been removed from service, then inform the candidate, "HCU 22-19 has been removed from service".

EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT Page 12 of 14

S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)

STANDARD

25.

EVALUATION / COMMENT STEP (G. 1.27)

Verify HCU-(*) yellow ACCUM light is on at FULL CORE DISPLAY.

Candidate recognizes need to obtain information from 09-5 Panel in the Control Room.

EVALUATOR:

When the candidate states that he/she would contact the Control Room and request the status of the yellow ACCUM light for control rod 22-19, then inform the candidate "Yellow ACCUM light for Control Rod 22-19 is ON".

EVALUATOR: Terminate the task at this point.

SAT / UNSAT Page 13 of 14

i

m "Entegy James A. FitzPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE S/RO NEW TASK TITLE:

START UP MAIN STEAM LEAKAGE COLLECTION APPL. TO JPM NUMBER REV:

0 DATE: 3/7/05 NRC WA SYSTEM NUMBER: 239003 A4.01 3.Z3.2 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

10 Minutes SUBMITTED:

OPERATION REVIEW:

APPROVED:

JAF QUAL STANDARD NUMBER:

N--uN--mm--m---m-------m-----------~---m------~~---N---~--------m----~---

CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

(X) Simulated

( )Performed Location:

(X) Plant

( )Simulator DATE PERFORMED:

TIME TO COMPLETE:

Minutes PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory m

~

m m

m

~

m m

~

m

~

m

~

m

~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURWPRINTED Page 1 of 6

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SIR0 NEW TASK TITLE: START UP MAIN STEAM LEAKAGE COLLECTION APPL. TO JPM NUMBER Current Update:

3/7/05 By:

RWD Date Int.

Outstanding Items:

Technical Review Additional Information Questions and Answers Validation Procedural Change Required X

None Comments:

Page 2 of 6

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NEW TASK TITLE:

START UP MAIN STEAM LEAKAGE COLLECTION APPL. TO JPM NUMBER

1.

II.

111.

IV.

W.

VI.

SAFETY CONSIDERATIONS A.

None REFERENCES A.

AOP40, Main Steam Line Break, Revision 8 TOOLS AND EQUIPMENT A.

None SET UP REQUIREMENTS A.

B.

Obtain permission from the Shift Manager prior to performing this task.

Obtain a current copy of AOP-40, Main Steam Line Break.

EVALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and not actually performed.

The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

B.

TASK CONDITIONS A.

B.

C.

All MSlVs are "CLOSED".

D.

A Main Steam Line Break has occurred in the Turbine Building.

All automatic isolations / initiations were successful.

The "Alpha" Train of the Standby Gas Treatment System is in operation.

- CRITICAL STEP Page 3 of 6

SIR0 TASK TITLE: START UP MAIN STEAM LEAKAGE COLLECTION VII.

INITIATING CUE Locates 29MOV-204A on Panel 29MSLCS in the Relay Room and closes 29MOV-204A.

EVALUATOR:

Inform the candidate 29MOV-204 "Alpha" indicates "CLOSED."

A high energy Main Steam Line Break has occurred in the Turbine Building. All automatic initiations and isolations were successful. The Shift Manager has directed that the Main Steam Leakage Collection System be placed into service per AOP-

40. The SNO has verified that the "Alpha" train of the Standby Gas Treatment System is operating. The SNO directs you to place the "Alpha" train of the Main Steam Leakage Collection System into operation per AOP-40, Section C.3.

SAT I UNSAT "CRITICAL STEP*

VIII.

TASK STANDARD The candidate will start up the "Alpha" train of the Main Steam Leakage Collection System

1.

STEP Obtain and review procedure (C.3.2.a. 1)

Close 29MOV-204A MSLC LINE "Alpha" BYPASS DRAIN VALVE.

(C. 3.2. a. 2)

Open 29MOV-200A MSLC LINE "Alpha" ISOL VALVE.

STANDARD I

EVALUATION / COMMENT Candidate obtains and reviews AOP40. Candidate determines that the start point is step C.3.2 SAT I UNSAT Locates 29MOV-200A on Panel 29MSLCS in the Relay Room and opens 29MOV-200A.

EVALUATOR:

Inform the candidate 29MOV-200 "Alpha" indicates "OPEN."

SAT / UNSAT

CRITICAL STEP*

Page 4 of 6

SIR0 TASK TITLE: START UP MAIN STEAM LEAKAGE COLLECTION

4.

5.

6.

'7.

STEP (C. 3.2. a. 3)

Monitors annunciator 09-5-249 "MSLCS A PRESS HI."

(C. 3.2. a. 3. a)

Open 29MOV-201A MSLC LINE "A* TO SGT UPSTR ISOL VLV.

(C. 3.2. a. 3. b)

Ensure open 29MOV-20% MSLC LINE "A' TO SGT DNSTR ISOL VLV.

(C.3.3)

Open 29MOV-203A MST OUTBD MSlV STEM LEAKOFF LINE "A' SOL VLV.

STANDARD Contacts the Control Room operator and asks to be informed when annunciator 09-5-249 MSLCS "AI PRESS HI Clears.

EVALUATOR:

Act as the Control Room and inform the candidate that the annunciator is clear.

Locates 29MOV-201A on Panel 29MSLCS in the Relay Room and opens 29MOV-201A.

EVALUATOR:

Inform the candidate 29MOV-201A indicates "OPEN" Locates 29MOV-202A on Panel 29MSLCS in the Relay Room and ensures open 29MOV-202A.

EVALUATOR:

Inform the candidate that 29MOV-202A indicates "OPEN".

Locates 29MOV-203A on Panel 29MSLCS in the Relay Room and opens 29MOV-203A.

EVALUATOR: Inform the candidate that 29MOV-203A indicates 'OPEN".

EVALUATOR: Terminate the task at this point.

EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT

CRITICAL STEP*

~

SAT / UNSAT SAT / UNSAT

CRITICAL STEP*

Page 5 of 6

INITIATING CUE A high energy Main Steam Line Break has occurred in the Turbine Building. All automatic initiations and isolations were successful. The Shift Manager has directed that the Main Steam Leakage Collection System be placed into service per AOP-40. The SNO has verified that the Alpha train of the Standby Gas Treatment System is operating. The SNO directs you to ptace the Alpha train of the Main Steam Leakage Collection System into operation per AOPdO, Section C.3.

Page 6 of 6

m

=== E n t q y James A. FkPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE S/RO/NPO 20505005 TASK TITLE: CROSS-TIE FIRE PROTECTION SYSTEM TO INJECT TO RHR SERVICE WATER APPL. TO JPM NUMBER REV:

7 DATE: 3/7/05 NRC K/A SYSTEM NUMBER: 295031 EA1.08 3.813.9 JAF TASK NUMBER:

ESTIMATED COMPLETION TIME:

15 Minutes SUBMITTED:

OPERATION REVIEW:

APPROVED:

JAF QUAL STANDARD NUMBER:

~ ~ ~ m m - - m m ~ m - ~ m m ~ m m ~ ~ ~ ~ ~ ~ ~ - - m - m m ~ m m m ~ - m ~ m ~ - ~ - - m m ~ ~ - m m ~ ~ m - - - ~ - m m m - m m m m - m - ~

CANDIDATE NAME:

S.S. NUMBER:

JPM Completion:

(X) Simulated

( )Performed Location:

(X) Plant

( ) Simulator DATE PERFORMED:

TIME TO COMPLETE:

Minutes PERFORMANCE EVALUATION:

( ) Satisfactory

( ) Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURUPRI NTED Page 1 of 7

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SIROINPO 20505005 TASK TITLE:

CROSS-TIE FIRE PROTECTION SYSTEM TO INJECT TO RHR SERVICE WATER APPL. TO JPM NUMBER Current Update:

3/7/05 BY: -

RWD Date Int.

Outstanding Items:

Technical Review Additional Information Questions and Answers Validation X

None Procedural Change Required Comments:

Page 2 of 7

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO/NPO 20505005 TASK TITLE:

CROSS-TIE FIRE PROTECTION SYSTEM TO INJECT TO RHR SERVICE WATER APPL. TO JPM NUMBER

1.

II.

111.

IV.

V.

VI.

SAFETY CONSIDERATIONS A.

None REFERENCES A.

EP-8, Alternate Injection Systems, Rev. 2 TOOLS AND EQUIPMENT A.

B.

N1 Key Emergency cross connect hose located in the North Safety Pump Room.

SET UP REQUIREMENTS A.

None NALUATOR NOTES A.

If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

actually performed.

B.

TASK CONDITIONS A.

To maintain RPV water level >O" (TAF), water level control must be augmented by using the lake as a source.

The RHRSW pumps are unavailable.

The Shift Manager has directed that the Fire Protection System be utilized to injed water into the RHRSW System.

B.

C.

- CRITICAL STEP Page 3 of 7

S/RO/NPO TASK TITLE: CROSS-TIE FIRE PROTECTION SYSTEM TO INJECT TO RHR SERVICE WATER VIJ.

INtTlATlNG CUE A transient has occurred which has resulted in a break in the RPV causing a loss of inventory. Due to a series of failures, no high pressure and most low pressure injection systems are unavailable. The Shift Manager directs you to align the Fire Protection System header to the "Alpha" RHR Service Water header per EP-8, Section 5.3.

VIII.

TASK STANDARD The candidate will cross-tie the Fire Protection System header to supply RPV injection via RHR Service Water per EP-8.

1.

2.

3.

-~

~

STEP Obtain and review procedure (5.3.1)

Verifies the following RHR pumps are stopped:

RHR PMP IOP-3A RHR PMP IOP-3C (5.3.2)

Removes caps from the following valves:

0 10RHR-432 (RHRSW TO FIRE PROTECTION CROSS-TIE ISOL VALVE)

PROTECTION CROSSTIE ISOL VALVE) 76FPS-720 (RHRSW / FIRE STANDARD I

EVALUATION I COMMENT Candidate obtains and reviews EP-8. Candidate determines that the start point is step 5.3 SAT / UNSAT Contacts the Control Room to verify RHR Pumps "A" and "C" are stopped.

EVALUATOR:

Inform the candidate that "RHR Pumps 3"Alpha" and 3"Charlie" are not running."

SAT / UNSAT EVALUATOR:

When the candidate goes to the North Emergency Service Water Room and states that he/she would remove the hose connection caps at 1ORHR-432 and 76FPS-720, then inform the candidate "Hose connection caps are removed."

SAT / UNSAT "CRITICAL STEP*

~~

Page 4 of 7

S/RO/NPO TASK TITLE: CROSS-TIE FIRE PROTECTION SYSTEM TO INJECT TO RHR SERVICE WATER STANDARD EVALUATOR:

4.

EVALUATION / COMMENT SAT / UNSAT

5.

"Hose is connected."

Contacts Control Room to verify that IOMOV-89A is closed.

STEP SAT / UNSAT (5.3.3)

Connect a hose (stored in cabinet 76CAB-1 on west wall of north emergency setvice water room) between the following valves:

Contacts Control Room to verify that IOMOV-89A is closed.

10RHR-432 (RHRSW TO FtRE PROTECTION CROSS-TIE SOL VALVE)

PROTECTION CROSSTIE ISOL VALVE) 76FPS-720 (RHRSW / FIRE (5.3.4)

Ensure closed IOMOV-89A RHRSW DISCH VLV FROM HX A.

SAT / UNSAT When the candidate opens 76CAB-1 with N-1 key and points out the emergency cross connect hose and tools and states he/she would connect the hose between 1ORHR-432 and 76FPS-720, then inform the candidate "Hose is connected."

CRITiCAL STEP*

EVALUATOR:

Inform the candidate "IUMOV-89A is CLOSED."

EVALUATOR:

Ensure candidate obsetved "CAUTION" pertaining to Screenwell Forebay Water Level. (Le. have candidate point out methods of determining forebay water level.)

6.

(5.3.5)

Start one or more of the following pumps:

ELEC FIRE PMP 76-P2 DIESEL FIRE PMP 76-PI DIESEL FIRE PMP 76-P4 Informs the Control Room that he/she is ready to have one or more of the Fire protection System pumps started.

EVALUATOR:

Inform the candidate "Electric Fire Pump 76P-2 is operating."

SAT / UNSAT

CRITICAL STEP*

Page 5 of 7

S/RO/NPO TASK TITLE: CROSS-TIE FIRE PROTECTION SYSTEM TO INJECT TO RHR SERVICE WATER

7.

STEP (5.3.6)

Unlock and open the following valves:

0 10RHR-432 (RHRSW TO FIRE PROTECTION CROSS-TIE ISOL VALVE)

PROTECTION CROSSTIE ISOL VALVE) 76FPS-720 (RHRSW / FIRE STANDARD EVALUATOR:

When the candidate states that he/she would unlock and open 10RHR-432 by turning the handwheel in the counterclockwise direction until full open, then inform the candidate that 10RHR-432 is OPEN.

When the candidate states that he/she would unlock and open 76FPS-720 by turning the handwheel in the counterclockwise direction until full open, the inform the candidate that 76FPS-720 is OPEN.

EVALUATOR: Terminate the task at this point.

EVALUATION I COMMENT SAT / UNSAT

CRITICAL STEP*

Page 6 of 7

INITIATING CUE A transient has occurred which has resulted in a break in the RPV causing a loss of inventory. Due to a series of failures, no high pressure and most low pressure injection systems are unavailable. The Shift Manager directs you to align the Fire Protection System header to the Alpha RHR Service Water header per EP-8, Section 5.3.

Page 7 of 7

ML051400356

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3.0 REFERENCES

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ML051400356

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SUMMARY

3.0 REFERENCES

3.0 REFERENCES

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