ML051400356
| 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) | |
Text
rnEntegy Nuclear Northeast James A. FilzPatrick Nuclear Power Plant 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: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATION REVIEW:
APPROVED:
---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
---M-~-~~MN--~N-~--~--N----~-M----M--N-------U~-----MN---~-N-M-MUN---N-~-N~--N COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
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 Additional Information Questions and Answers Validation Procedural Change Required 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. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-15, High Pressure Coolant Injection, Revision 50
- 8. AP-12.03, Conduct of Operations, Revision 30, Section 8.3 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset simulator to any 4 5 0 psig IC.
B. Verify HPCl in normal standby lineup.
C. Insert Simulator Malfunction HPl 1, HPCl23MOV-15 AUTO ISOLATION FAILURE.
D. Insert Simulator Malfunction HP06, HPCl STEAM LINE BREAK V. EVALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and actually performed.
B. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI. TASK CONDITIONS A. HPCl has received an auto-isolation signal on a HPCl Steam Line Break B. 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.
STEP STANDARD EVALUATION I COMMENT
- 1. Obtain and review procedure Candidate obtains and reviews OP-15. Candidate SAT / UNSAT determines that the start point is step G. I.
1.
- 2. (G.I.1) Candidate sequentially locates listed valves and verifies SAT / UNSAT Ensure the following valves are closed: each valve indicates 'CLOSED." At the point where TURB STOP VLV 23HOV-1 candidate encounters an "OPEN" INBD STM SUPP VLV *CRITICAL STEP*
0 OUTBD STM SUPP VLV 23MOV-15 (failure to isolate), candidate will close 23MOV-I6 23MOV-I 5. Candidate may or may not report the valve MIN FLOW VLV 23MOV-25 out-of-position to CRS.
0 INBD TORUS SUCT VLV 23MOV-58 EVALUATOR:
INBD STM SUPP VLV 23MOV- Respond to candidate report(s) of isolation verification 15 and/or 23MOV-I5 failure to isolate in a manner 0 OUTBD TORUS SUCT VLV consistent with the standard rules of three-point 23MOV-57 communications.
0 STM LINE WARMING ISOL VLV 23MOV-60 INJ VLV 23MOV-19 EVALUATOR: Terminate the task at this point.
Page 4 of 5
ui P;
e 0
i3 e
v)
Y-O I v)
m Entergy
~
Nuclear Northeast James A. FitzPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE S/RO FROM LOI-03-01 TASK TITLE: GROUP IISOLATION RESET APPL. TO JPM NUMBER REV: 1 DATE: 3/3/05 NRC WA SYSTEM NUMBER: 223002 A4.03 3.613.5 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: IO Minutes SUBMITTED: OPERATION REVIEW:
APPROVED:
- 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: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: ( ) Satisfactory ( ) Unsatisfactory
- ~ * ~ ~ * ~ * ~ * ~ * * * * ~ ~ ~ * ~ ~ * ~ * ~ ~ ~ * * * * * ~ * * ~ * * ~ ~
- w w * ~ * ~ w w * * ~ * ~ w *
- w ~ ~ w
- w
- w
- w * * *
- m w * * ~
COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
EVALUATOR:
SIGNATURWPRINTED 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. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.
II. REFERENCES A. AOP-15, ISOLATION VERIFICATON AND RECOVERY Rev 23 111. TOOLS AND EQUIPMENT A. None IV. 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.
V. 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.
VI. 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 Conditions have occurred which caused the MSlVs to isolate on low steam pressure. The cause of the isolation has been corrected. All radiologicalconditions and Reactor Chemistry samples are within normal bands. Reset the MSlV isolation using AOP-15."
TASK STANDARD The candidate will reset the PClS Group I isolation per AOP-15 Section C.2
~
I STEP STANDARD
- 2. CAUTION: Informs SM/CRS of CAUTION.
The circumstances leading to an isolation could have caused high radioactivity levels in the drywell or in EVALUATOR: Acknowledge candidate and respond that there is no concern for high radioactivity levels in drywell reactor coolant.
or reactor coolant.
- 3. Verify Group 1 Isolation per posted Selects the posted attachment 1 and at panel 09-3 Attachment 1 Item 4. and/or 0 9 4 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
~~
- 4. Determine and correct cause of the Candidate may confim-initiating cue information that isolation. 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 E: GROUP 1 ISOLATIONRESET STEP STANDARD EVALUATION ICOMMENT
- 5. IF cause of isolation was high main Reviews step and determines that cause was NOT a SAT / UNSAT steam line radiation, THEN .. . . 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.
- 6. Determine whether an undesired Reviews step and determines that release will not occur SAT / UNSAT release will occur when isolation is as a result of isolation reset.
reset. Request RES assistance if in doubt. EVALUATOR: If candidate requests, respond that an undesirable release will not occur.
- 7. WHEN it has been determined that an Reviews step and determines that release will not occur SAT / UNSAT undesired release will not occur when as a result of isolation reset.
isolation is reset, continue with procedure. EVALUATOR: If candidate requests, respond that an undesirable release will not occur.
- 8. Ensure control switches for the At 09-3 and 09-4 panels, place the valve switches are in SAT / UNSAT following valves are in CLOSE: close and confirm green dosed light on and red open RWR LOOP B SMPL ISOL VLV 02- light off.
- CRITICAL STEP RWR LOOP B SMPL ISOL VLV 02-2Aov-40
- 9. IF MSlVs are closed, THEN place At 09-3 and 09-4 panels, place the valve switches in SAT / UNSAT control switch for each of the following close and confirm green closed light on and red open valves in CLOSE: light off.
MSlV 29AOV-80A
- CRITICAL STEP*
MSlV 29AOV-800 MSlV 29AOV-80C MSlV 29AOV-80D MSlV 29AOV-86A MSlV 29AOV-86B MSlV 29AOV-86C MSlV 29AOV-86D Page 5 of 7
S/RO/NLO NEW TASK TITI E: GROUP 1 ISOLATION RESET STEP STANDARD EVALUATION/ COMMENT
- 10. NOTE: Reviews NOTE and determines that step C.2.8 SAT / UNSAT Step C.2.8 is not required to open REQUIRED.
MSlVs if Group 1 isolation was due to EVALUATOR: If candidate requests feedback regarding high main steam line radiation (3X note, acknowledge the isolation was not due to high normal full power background). radiation.
- ~~~ ~ ~~ ~
- 11. Simultaneously rotate the following At panel 09-5, operates the switches and confirm SAT I UNSAT PClS VLV RESET switches to both annunciators 09-5-1-55 and 56 clear.
RESET positions, spring return to NORM: *CRITICAL STEP" 16A-S32 16A-S33
- 12. NOTE: Reviews Note and requests feedback from SM SAT / UNSAT Steps C.2.9 and C.2.10 may be regarding priority for action.
performed in any order at the Shift Manager's discretion. EVALUATOR: When candidate requests feedback regarding step priority, acknowledge the MSlVs have priority.
EVALUATOR: Terminate the task at this point.
Page 6 of 7
===Entegy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant 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: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATION REVIEW:
APPROVED:
-~---~----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 -~-----~---~-m-mm----m--m~---~-----------------~-------------~---~-~------m COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
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 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 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. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-9; OPENING MSlV's, Rev 3 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Rx Scrammed with MSIV's closed.
B. RPV Level > 126.5 and < 222.5.
C. RPV Pressure Control on SRVs/HPCI/RCIC at 800-1000 psig.
D. PClS Group I isolation signals reset V. EVALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identied and actually performed.
B. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI. 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.
TASK STANDARD The candidate will equalize to less than a 200 psid D/P and open the MSIVs per EP-9 STEP
~~ ~
STANDARD I EVALUATION I COMMENT
- 1. Obtain a controlled copy of procedure The candidate obtains a controlled copy of EP-9. SAT / UNSAT EP-9, OPENING MSIVS
- 2. IF differential pressure across the Candidate uses 06PI-90A, B, and or C at panel 09-5 SAT / UNSAT MSlVs is LESS THAN OR EQUAL TO and MAIN STEAM PRESS A and or B at EHC section of 200 psid, THEN perform the following: panel 09-5 to determine that differential pressure exceeds 200 psid.
- 3. Ensure closed the following valves: Candidate closes and/or observes green closed light on SAT / UNSAT J MSIV 29AOV-80A-D J MSlV 29AOV-86A-D J MAIN STM DRN 29MOV-74,77,78 and 79 J 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)
J 29MST-107 (SJAE MST supply 29PCV-107 bypass strainer outlet isol valve) (remote operated from East Electric Bay)
Page 4 of 6
h W
c k I I-h W
c u) v) z 3 z u) a s
3 3 a E
\ \
k U k v) k cn a P P I
I Y-0 (0
Y-O m
lze . .
P ri I
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 Nuclear Northeast James A. FittPatrick Nuclear Power Plant 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: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATION REV1EW:
APPROVED:
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
--~-2---~-----------~-~--N----~-------~N----N-----~--~~----~-----~---~------N-N COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
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 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: CRD PUMP TRIP (ALT PATH)
APPL. TO JPM NUMBER
- 1. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-69, CONTROL ROD DRIVE TROUBLE, Revision 6.
111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Simulator in any power operation IC with the "A" CRD pump in service B. Insert MFI-RDO6:A (,,KCRD Pump Trip) and allow one accumulator trouble alarm to appear.
C. Insert MFI-RDO6:B VB CRD Pump Trip)
V. 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.
B. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI. 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 STEP STANDARD EVALUATION / COMMENT
- 1. Obtain and review procedure Candidate obtains and reviews AOP-69. Candidate determines that the start point is step C.1.5 EVALUATOR If requested, ACRD pump did NOT trip on low suction pressure and the CRD pump breakers have been inspected at 71L15 and 71L16.
- 2. a. Ensure CRD FLOW CNTRL 03FIC- At 09-5, candidate selects CRD Flow Control GEMAC 301 is in MAN. Controller mode select knob to MAN.
- CRITICAL STEP*
- 3. b. Rotate manual control knob on CRD At 09-5, candidate rotates CRD Flow Control GEMAC SAT / UNSAT FLOW CNTRL 03FIC-301 fully manual flow control knurled knob counterclockwise.
counterclockwise.
- 4. c. Verify inservice CRD flow control At 09-5, candidate observes green lamp on and red SAT / UNSAT valve (03FCV-19A or B) is closed tamp off for both CRD Flow Control Valves.
~- ~~ ~
- 5. d. Attempt to start one CRD pump(CRD At 09-5, Candidate selects B CRD Pump Control PMP 03P-16A or CRD PMP 03P-16B). Switch to START (Spring Return to NORM)
If the first pump fails to start, attempt to *CRITICAL STEP*
Candidate recognizes trip of 8 CRD Pump start the other.
Candidate dispatches NPO to investigate.
Page 4 of 6
SIR0 TASK TITLE: CRD PUMP TRIP (ALT PATH)
STEP STANDARD EVALUATION / COMMENT
- 6. e. IF neither CRD pump can be started, EVALUATOR THEN proceed to Subsection C.2. Act as NPO and report the "8"CRD Pump Breaker has exploded.
Candidate determines that neither CRD pump can be started and proceeds to Subsection C.2
- 7. C.2.1 IF at least one CRD pump will not be made available within a reasonable EVALUATOR If necessary, provide feedback that several hours will be I SAT / UNSAT period of time, as determined by the SM or CRS, AND two or more ACCUM alarm lights are on at panel 09-5 full required to repair/replace the "B" CRD pump breaker.
Upon receipt of additional Accumulator Trouble Lights, I *CRITICAL STEP' I
core display, THEN manually scram the candidate inserts a manual scram and commences reactor and enter AOP-1. AOP-1 Immediate Actions.
EVALUATOR: Terminate the task at this point.
- r 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 6CRD 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: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATION REVIEW:
APPROVED:
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: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: ( ) Satisfactory ( ) Unsatisfactory
-NN--NN--N---NN--~---NN~-U~--N---N---UN--N~-NN-~~---U---N-NN-~N-~--~-N---~--N~
COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
EVALUATOR:
SIGNATUWPRINTED 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
- 6. OP-65, Startup and Shutdown Procedure, Rev. 102 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Obtain current copies of OP-65, Startup and Shutdown Procedure and OP-2A, Feedwater System.
C. FWLC in Master Auto Single-Element Control on Either Reactor Feed Pump.
V. EVALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and actually performed.
B. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI. TASK CONDITIONS A. A Reactor Startup is in progress.
- 6. Reactor Power is just above 25% CTP.
C. 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)
VII. 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.
VIII. TASK STANDARD The candidate will transfer Feedwater Level Control from Single-Element to Three-Element per OP-2A.
~~ ~~~
STEP
~ ~
STANDARD I EVALUATIONI COMMENT
- 1. Obtain and review procedure. Candidate obtains and reviews OP-65 and OP-2A. SAT / UNSAT Candidate determines that the start point is step G.34.1 of OP-2A.
- 2. (G.34.1) Candidate verifies stable 09-5 Panel RPV Level SAT / UNSAT parameters in the required range (196.5 to 203 inches).
Stabilize RPV water level at 196.5 to 203 inches on 06LI-94A, B, and C.
~~
- 3. Candidate verifies that 09-5 Panel Master Control SAT / UNSAT (G.34.2)
Transfer (Mode Selector) Switch (collar around knurled Verify RX WTR LVL CNTRL 06LC-83 is knob) for RX WTR LVL CNTRL 06LC-83 is in the "BAL" in BAL.
(Balance) position.
- 4. (G.34.3) Candidate adjusts 09-5 Panel Manual Output Control SAT / UNSAT (knurled knob potentiometer) until red pointer on Slowly adjust RX WTR LVL CNTRL Deviation Meter is approximately mid-scale. *CRITICAL STEP*
06LC-83 manual control knob to balance controller.
Page 4 of 9
S/RO TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)
I STEP
~~ -~ ~ - ~
STANDARD I EVALUATION / COMMENT
- 5. (G.34.4.a) Candidate verifies that 09-5 Panel M/A Transfer Switch SAT / UNSAT (collar around knurled knob) for RFP A FLOW CNTRL Ensure RFP A FLOW CNTRL 06-84A 06-84A is in the 'BAL" (Balance) position.
in manual as follows:
- a. Ensure controller is in BAL
- 6. (G.34.4.b) Candidate adjusts 09-5 Panel Manual Output Control SAT / UNSAT
- b. Balance controller by adjusting (knurled knob potentiometer) on RFP A FLOW CNTRL 06-84A until pointer is mid-scale on Deviation Meter (top *CRITICAL STEP*
manual control knob of controller).
- 7. (G.34.4.c) Candidate turns 09-5 Panel M/A Transfer Switch (collar SAT I UNSAJ around knurled knob) for RFP A FLOW CNTRL 06-84A
- c. Place controller in MAN clockwise one positionto "MAN" (Manual). *CRITICAL STEP*
- 8. (G.34.5.a) Candidate verifies that 09-5 Panel M/A Transfer Switch SAT / UNSAT (collar around knurled knob) for RFP B FLOW CNTRL Ensure RFP B FLOW CNTRL 06-848 in manual as follows: 06-848 is in the "BAL" (Balance) position.
- a. Ensure controller is in BAL
- g. I (G.34.5.b) Candidate adjusts 09-5 Panel Manual Output Control (knurled knob potentiometer) RFP B FLOW CNTRL 06-SAT / UNSAT
- b. Balance controller by adjusting *CRITICAL STEP*
848 until pointer is mid-scale on Deviation Meter (top of manual control knob Page 5 of 9
SIR0 TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)
STEP STANDARD EVALUATION I COMMENT
- io. (G.34.5. c) Candidate turns 09-5 Panel MIA Transfer Switch (collar SAT / UNSAT
- c. Place controller in MAN around knurled knob) for RFP B FLOW CNTRL 06-848 clockwise one position to "MAN" (Manual). *CRITICAL STEP*
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.
- 11 (G.34.6) Candidate turns Element Control Select Switch on 09-5 SAT / UNSAT Place 1 or 3 ELEMENT LVL CNTRL Panel clockwise one position to "3 ELEMENT".
SEL 06s-2 in 3 ELEMENT. *CRITICAL STEP
~~~ ~
- 12. (G.34.7) Candidate verifies 09-5 Panel RX WTR LVL CNTRL SAT I UNSAT Verify RX WTR LVL CNTRL 06LC-83 06LC-83 red pointer on Deviation Meter is remains balanced. approximately mid-scale.
- 13. (G.34.8) Candidate obtains and reviews OP-2A, Section G.7. SAT / UNSAT Transfer RFP A and B control to Candidate determines that the start point is step G.7.1 automatic per Subsection G.7. of OP-2A.
~
- 14. (G.7.1) Candidate verifies stable 09-5 Panel RPV Level SAT / UNSAT Stabilize RPV water level at 197 to 203 parameters in the required range.
inches on 06LI-94A, B, and C.
Page 6 of 9
S/RO TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)
STEP STANDARD EVALUATION / COMMENT
- 15. (G.7.2) Candidate verifies 09-5 Panel MIA Transfer Switches SAT / UNSAT Verify the following controllers are in (collars around knurled knob) for RFP N B FLOW MAN: CNTRL 06-84A/B are in the position of "MAN" (Manual).
RFP A FLOW CNTRL 06-84A RFP B FLOW CNTRL 06-848
- 16. (G.7.3) Candidate turns the 09-5 Panel M/A Transfer Switch SAT / UNSAT Place RX WTR LVL CNTRL 06LC-83 in (collar around knurled knob) for RX WTR LVL CNTRL MAN. 06LC-83 clockwise one position to "MAN" (Manual). *CRITICAL STEP*
~~ - ~~
- 17. (G.7.4) Candidate adjusts 09-5 Panel Manual Output Control SAT / UNSAT (knurled knob potentiometer) on RX WTR LVL CNTRL Slowly adjust RX WTR LVL CNTRL 06LC-83 until pointer on RFP A FLOW CNTRL 06-84A *CRITICAL STEP*
06LC-83 manual control knob to is mid-scale on Deviation Meter (top of controller).
balance RFP A FLOW CNTRL 06-MA.
- I8. (G.7.5) Candidate turns 09-5 Panel M/A Transfer Switch (collar SAT I UNSAT around knurled knob) for RFP A FLOW CNTRL 06-84A Place RFP A FLOW CNTRL 06-84A in counterclockwise one position to "BAL" (Balance). *CRITICAL STEP*
BAL.
- 19. (G.7.6.a) Candidate adjusts 09-5Panel Setpoint Control on RX SAT / UNSAT WTR LVL CNTRL 06LC-83 until red pointer on Line up RX WTR LVL CNTRL 06LC-83 Deviation Meter is approximately mid-scale. *CRITICAL STEP*
as follows:
- a. Balance controller by adjusting setpoint tape.
Page 7 of 9
SIR0 TASK TITLE: SWAP FEEDWATER LEVEL CONTROL (SINGLE TO THREE-ELEMENT)
L - -
STEP STANDARD EVALUATION I COMMENT
- zo. (G.7.6.b) Candidate turns 09-5 Panel Master Control Transfer SAT / UNSAT
- b. Place controller in BAL. Switch (collar around knurled knob) for RX WTR LVL CNTRL 06LC-83 counterclockwise one position to "BAL" *CRITICAL STEP*
(Balance).
EVALUATOR NOTE:
This step restores Automatic RPV Water Level Control.
- 21. (G.7.7.a) Candidate slowly adjusts 09-5 Panel Manual Output SAT / UNSAT Line up RFP A FLOW CNTRL 06-848 Control (knurled knob potentiometer) RFP B FLOW as follows: CNTRL 06-84B until pointer is mid-scale on Deviation *CRITICAL STEP*
Meter (top of controller).
- a. Balance controller by adjusting manual control knob
- 22. (G.7.7.b) Candidate turns 09-5 Panel M/A Transfer Switch (collar SAT / UNSAT
- b. Place controller in BAL. around knurled knob) for RFP B FLOW CNTRL 06-848 counterclockwiseone position to "BAL" (Balance). *CRITICAL STEP*
EVALUATOR: Terminate the task at this point.
Page 8 of 9
L aa c,
P
'CI 0) aa L
0 c,
$ E
'E Q b h t-9
m
-== Entergv Nuclear Northeast James A. FiePatrick Nuclear Power Plant 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: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATION REVIEW:
APPROVED:
~ ~ - 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
~ ~ m m m ~ ~ - N ~ ~ - m m ~ ~ N m - * ~ m * *
- N m * - * ~ * *
- N - * * ~ m 5 ~ m - * ~ ~ - m
- m ~ ~ ~
- N 5 * ~ * ~ N * - * * * ~ ~ ~ - ~ * ~ * ~
- N COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
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: 3110105 By: RWD Date Int.
Outstanding Items:
Technical Review Additional Information
-Questions and Answers Validation Procedural Change Required 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. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-46A, 4160V and 600V NORMAL AC POWER DISTRIBUTION, Rev. 48 B. OP-65, Startup and Shutdown Procedure, Rev. 102 111. TOOLS AND EQUIPMENT A. Synch Selector Switch Key IV. SET UP REQUIREMENTS A. Obtain current copy of OP-46A, 4160V and 600V NORMAL AC POWER DISTRIBUTION.
B. -20% CTP IC during reactor startup with plant conditions stable.
C. Main Generator is synchronized to the Grid. The 10700 Bus is deenergized. All 4160 VAC Busses on RSS.
D. OR1 Running Voltmeter downscale and attach a PID Tag.
V. EVALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and actually performed.
- 8. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI. 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
- 6. All prerequisites for transferring from reserve to normal station service have been met. Main Generator is synched to the grid.
C. The Shift Manager has given direction to transfer loads from Reserve to Normal Station Service.
- CRITICAL STEP Page 3 of 10
SIR0 TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T-4)
VII. 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 0.23.5, you have been directed to transfer loads from Reserve 115kv Transformers T2 and T3 to Normal Station Service Transformer T-4.
VIII. TASK STANDARD The candidate will transfer either the 10100 Bus p~ the 10200 Bus per OP46A.
I STEP I STANDARD I WALUATION I COMMENT
Candidate determines that the start point is either step SAT / UNSAT I
I 0.20 (10700)or 0.21 (10200) of OP46A.
- 2. (D.20/21.1) Candidate obtains/reviews OP46A, Section E. SAT / UNSAT While performing the remainder of this subsection maintain 4 KV and 600V bus voltage per Section E.
I 3* (D.20/21.2) Not expected with astaMished conditions. Therefore NIA NIA.
IF a degraded or undervoltage condition occurs while transferring bus, I THEN immediately establish GREATER 1 THAN 3.9 KV using LTC CONTROL.
I 4' (D.20/21.3) At the 09-7 Panel, candidate observes MAIN GEN MW SAT / UNSAT 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.
Page 4 of 10
SIR0 TASK TITLE: SWAP ELECTRtCAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T-4)
STANDARD I EVALUATION I COMMENT
- 5. (D.20/21.4) EVALUATOR: SAT / UNSAT Ensure Clark Energy Control Center Inform candidate that notifications have been made.
and Nine Mile Point 1 Control Room (due to effect on 115 KV line loading) have been notified that 10100/10200 Bus will be transferred from reserve to normal service.
- 6. (D.20/21.5) EVALUATOR: SAT / UNSAT Station operators as follows: Inform candidate that a surrogate operator is at the LTC e One to adjust bus voltage at LTC CONTROL to respond to hidher direction.
CONTROL 0 One to operate breaker control switches
- 7. (D.20121.6) At 09-8, candidate inserts Synch Selector Switch Key SAT 1 UNSAT into BUS 10100 (10200) FDR SYNCH SW and turns Place BUS 10100/100200 FDR SYNCH clockwise on notch to NORM (Normal) position. *CRITICAL STEP*
SW switch in NORM.
- 0. (D.20/21.7) Candidate will recognize the need, during performance SAT / UNSAT of next step (D.20/21.8), that this step will be applicable IF voltages on NON-EMERG BKRS and will obtain and review OP-46A, Section G.14; and INCOMJNG and RUNNING volt meters determine start point to be G. 14.1.
can not be matched in following step, THEN perform subsection G.14, Single Meter Voltage Match Method.
Page 5 of 10
S/RO TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE cT-4)
STEP STANDARD EVALUATION / COMMENT
~
- 9. (D.20/21.8) At 09-8, candidate will direct LTC Control adjustment(s) SAT / UNSAT and determine that INCOMING and RUNNING Voltages Match voltages on NON-EMERG BKRS *CRITICAL STEP*
are unable to be matched within required band, INCOMtNG and RUNNING volt meters necessitating use of the OP46A, Section G.14, Single using LTC CONTROL switch.
Meter Voltage Match Method.
EVALUATOR:
Surrogate is acting as the extra operator at LTC CONTROL, and will respond to candidate direction only.
- 10. (G.14.1) EVALUATOR: NIA IF voltage mismatch is greater than 6 Inform candidate that due to the failure of the Running meter increments, THEN obtain meter, Design Engineering has recommended the use guidance for performing bus transfer of OP46A, Section G.14.
from Design Engineering.
~
- 11. (G.14.2.a) At 09-8,candidate turns Synch Selector Switch Key for SAT / UNSAT BUS 10100 (10200) FDR SYNCH SW counterclockwise IF transferring 4.16 KV bus from two notches to RES (Reserve) position. *CRITICAL STEP reserve to normal, THEN perform the following:
- 12. (G.14.2.b) Candidate observes 09-8 Panel INCOMING Voltmeter. SAT / UNSAT Candidate may write the value down or just commit it to
- b. Note voltage on incoming meter.
memory.
EVALUATOR:
Ensure that you note voltage also.
Page 6 of 10
SIR0 TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T4)
-~
STEP
'1 3. (G.14.2.c) At 09-8, candidate turns Synch Selector Switch Key for SAT / UNSAT BUS 10100 (10200) FDR SYNCH SW clockwise two
- c. Place 4.16 KV bus FDR SYNCH notches to NORM (Normal) position. *CRITtCAL STEP*
SW switch in NORM.
~
- d. Match voltages on NON-EMERG operate tap changer to obtain voltage mismatch value BKRS INCOMING and RUNNING within 5% (maximum) of value noted / written down in *CRITICAL STEP*
step G.14.2.b(JPM Step 12 above).
volt meters using LTC CONTROL switch.
EVALUATOR:
The surrogate is acting as the extra operator at LTC CONTROL, and will respond to candidate direction only.
- 15. (0.20/21.9) Not expected with established conditions. SAT / UNSAT IF phase angle is GREATER THAN 17 At 09-8, candidate locates and correctly reads the degrees NON-EMERG BKRS phase angle as indicated on Synchroscope, compares SYNCHROSCOPE, THEN perform the the indicated value to value contained in OP46A (17O),
following: and determines phase angle is less than 17".
List not requimd.
Page 7 of 10
SIR0 TASK TITLE: SWAP ELECTRICAL BUSES FROM RESERVE STATION SERVICE TO NORMAL STATION SERVICE (T-4) d STEP STANDARD EVALUATION I COMMENT
- 16. (D.20/21.10) At 09-8,candidate: SAT / UNSAT WHEN incoming and running voltages 1. Observes incoming meter
- CRITICAL STEP*
are matched, AND synchroscope is at
- 2. Directs voltage adjustment, if necessary, to re-approximately 12 o'clock, perform the establish matched conditions following bus transfer using the same hand, without unnecessary delay, to 3. Observes position of synchroscope perform each breaker operation:
- 4. When synchroscope is at approximately 12 o'clock
- a. Close NSS TO BUS 10100 ( 4 7 " phase angle)
/10200 BKR 10102 / 10202 5. Without hesitation and with same hand, operates breakers as follows:
- b. Open RSS TO BUS 10100
/I0200 BKR 10112 / 10212 0 Close NSS TO BUS 10100 /lo200 BKR 10102
/ 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
- 17. (0.20/21.11) At 09-8, candidate turns Synch Selector Switch Key for SAT / UNSAT BUS 10100 (10200) FDR SYNCH SW counterclockwise
'laceBus 'oloo 'O2O0 FDR SYNCH one notch to OFF position and removes key.
SW switch in OFF and remove handle.
11 18. I (D.20/21.12) I Candidate proceeds to Panel 09-16, locates white RPS I SAT / UNSAT Verify all white fights for RPS A and RPS B power source selectors are on 1 at Panel 09-16. I A and RPS B power lights, and observes that they are illuminated.
II I EVALUATOR: Terminate the task at this point.
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 115kv Transformers T2 and T3 to Normal Station Service Transformer T-4.
Page 10 of 10
m Entergy Nuclear Northeast James A. FiePatrick Nuclear Power Plant 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: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 20 Minutes SUBMITTED: OPERATION REVIEW:
APPROVED:
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 -Additional Information Questions and Answers Validation Procedural Change Required X None Comments:
Simulator validated 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. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-SD, APRM CALIBRATION, Rev. 2 B. OP-16, NEUTRON MONITORING, Rev. 25 111. TOOLS AND EQUIPMENT A. Small Screwdriver IV. SET UP REQUIREMENTS A. -98% CTP IC. EPIC/3D available and plant conditions stable.
B. Adjust all APRMs to an acceptable value per ST-5D.
C. Adjust D APRM to 34% below desired value of ST-5D (@98% CTP).
V. EVALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and actually performed.
B. The candidate should, at a minimum, identlfy the change in equipment status light indication when equipment operation is simulated.
C. This JPM performance data based upon D APRM initially 3 4 % low at -98% CTP VI. 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 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.
~ ~ ~ _ _ _ _ _
STEP STANDARD EVALUATION I COMMENT
- 2. 8.1 Procedure Performance Candidate selects subsection 8.3 SAT / UNSAT Page 4 of 8
SIR0 FROM LOI-03-01 9SK TITI i: ST-SD, APRM CALIBRATION STEP STANDARD EVALUATION I COMMENT
- 3. 8.3.1 IF core power has changed Candidate demands Official 3D at 3 0 keyboard by SAT / UNSAT GREATER THAN 2%, OR the control selecting:
rod pattern has changed since the last core performance program was Option 4, Run Official 3 0
- CRITICAL STEP*
executed, THEN demand an Official 3 0 0 Tab to Execute Program.
0 Select 2 on the number pad
- 4. 8.3.2 Determine APRM DR from the Candidate selects Percent Core Thermal Power with a SAT / UNSAT higher of the following values: value of -98%.
0 Largest MFLPD x 100 *CRITICAL STEP*
0 Percent core thermal power
- 6. 8.5.1 Record initial APRM readings in Candidate records values from Official 3 0 SAT / UNSAT Table 1.
- 7. 8.5.2 Record DR in Table 1. Candidate records value selected in 8.3.2 SAT / UNSAT
- 8. 8.5.3 [ITS] Identify any APRM(s) Candidate identifies D APRM as requiring adjustment. SAT / UNSAT requiring adjustment in Table 1. APRM shall be adjusted to indicate within k2% *CRITICAL STEP*
of the DR.
- 9. 8.5.4 IF APRM adjustment is required, EVALUATOR SAT / UNSAT THEN perform the following for each APRM requiring adjustment: The Shift Manager desires that the APRMs be NOTE: Bypassing APRM may be bypassed for adjustments.
omitted p e r SM.
- 10. A. Bypass the APRM channel requiring Candidate obtains and review OP-16 noting any SAT / UNSAT calibration per Section E of OP-16. cautions that may be applicable 11 Select proper procedure section Candidate selects section E.16 SAT / UNSAT
- 12. -E:16.1 Place APRM BYP switch in (*). At 09-5panel, candidate selects B division joystick to SAT / UNSAT Page 5 of 8
S/RO FROM LOI-03-01 ASK TITI I: ST-SD, APRM CALIBRATION STEP STANDARD EVALUATION I COMMENT
- 13. E.16.2 Verify APRM (*) is bypassed At 09-5 panel, candidate observes white bypass lamp SAT / UNSAT using one or both of the following: for APRM D.
APRM (*) BYPASS indicating light is on APRM (*) EPIC alarm indicates AND / OR bypassed Candidate notes EPtC alarm typer indicates selected APRM bypass is ON
- 14. E.16.3Veri@the other two APRM Candidate notes the absence of the same indicationsfor SAT / UNSAT channels associated with the same the remaining APRMs in that RPS division (B and F).
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
- 15. ST-SD, 8.5.4 continued: At panel 09-14, candidate selects D APRM and SAT / UNSAT B. Ensure METER FUNCTION switch is confirms Meter Function switch is in average.
set to AVERAGE.
- 16. C. Ensure APRM MODE switch is in the At panel 09-14, candidate selects D APRM and SAT / UNSAT OPERATE position. confirms Mode switch is in operate.
- 17. NOTE: Clockwise turn raises meter At panel 09-14, candidate inserts small screwdriver into SAT / UNSAT reading; counterclockwiseturn lowers upper left simulated rheostat for the D APRM.
P n n A i A n + n +*
- m e +nv n i a a inAinnCirrn +n- 0 Q O L meter reading. n h n h a i e n
-ai iuiuac= LUI I IJ ~ I W ~ W ILW ala= 11 IUIMLIVI
~ IO I IW .-JW 10.
D. [ITS] Turn gain adjustment control EVALUATOR (R16) on LPRM card 2-31 to obtain a In the simulator, 2-31 card can be identified but the meter reading within *2% of DR. pm I V ~ V Yrln nhntnc nnt uv I IVL PI 1nnnt-f rnsrlinn uupayvi L I YL~USS ty R
I \
- II fi Y
- 18. E. Unbypass APRM per Section E of Candidate obtains OP-16 and selects section E.17 SAT / UNSAT OP-16.
- 20. E. 17.1 Verify the following lights for AI top OT panel uv- 14,canoioare ioenriiies lamps Tor me SAT / UNSAT APRM (*) are off at panel 09-14: D APRM.
rN0P UPSCL NEUT TRIP UPSCL THERM TRIP Page 6 of 8
STEP STANDARD EVALUATION / COMMENT 21.
E. 17.2 Place APRM BYP switch for At panel 09-5, candidate selects 6division APRM SAT I UNSAT I 22.
APRM (*) in center position.
E.17.3 Veri@ APRM (*) is returned to service using one or both of the joystick to center position.
At 09-5 panel, candidate observes bypass lamp extinguished SAT / UNSAT following:
APRM (*) BYPASS indicating light is Off No EPIC bypassed alarm for APRM (*)
- 23. 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 III 74 67.
APRMs 8.5.5 Record final APRM readings for 1 adjusted APRMs in Table 1.
Candidate record final reading. 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 LPROCEDURI~
E OWNER EFFECTIVE DATE: /2fio. B;I FIRST ISSUE 0 FULL REVISION 0 LIMITED REVISION
~ ~~
I I
- CONTINUOUS USE
- TSR t
- TECHNICAL
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.
. 2 . 3 . C , 8 . 3 . 3 , 8 . 4 . 4 t o "Adjust Revised Steps 8 . 2 . 1 . ~8 ~
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 24
APRM CALIBRATION ST-5D TABLE OF CONTENTS SECTION PAGE 1.0 REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . 4 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . 5
3.0 REFERENCES
. . . . . . . . . . . . . . . . . . 5 4.0 PREREQUISITES . . . . . . . . . . . . . . . . . . . . . 6 5.0 TEST EQUIPMENT. SPECIAL TOOLS. AND MATERIALS . . . . . 6 6.0 PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . 7 7.0 GENERAL TEST METHODS . . . . . . . . . . . . . . . . . 9 8.0 . PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . 10 8.1 Procedure Performance . . . . . . . . . . . . . . . . . 10 8.2 APRM Calibration Less Than 25% of Rated Power . . . . . 11 8.3 APRM Calibration Greater Than or Equal to 25% . . . . . 15 8.4 Manual Calculation by Reactor Analyst Group When Greater Than or Equal to 25% . . . . . . . . . . . 16 8.5 APRM Gain Adjustments . . . . . . . . . . . . . . . . . 17 10.0 ACCEPTANCE CRITERIA . . . . . . . . 19 11.0 ACCEPTANCE VERIFICATION . . . . . . . . . . . . . . . . 20 12.0 ATTACHMENTS . . . . . . . . . . . . . . . . . 23
- 1. TEST SIGNOFF LOG . . . . . . . . . . . . . . . . . 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 4of 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
APRM CALIBRATION ST-5D NOTE: Sections 4 and 5 may be performed in any Init order or concurrently.
4.0 PREREQUISITES 4.1 SM has granted permission to perform this test.
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-140Af02TE-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 CRS of any failure to meet acceptance criteria.
6.2.2 Test personnel shall print name, sign initials, and 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 Attachment 1.
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 7of 24
APRM CALIBRATION ST-5D 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 sNA1if not applicable.
6.2.9 Steps in this test marked rrNRare 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 24
APRM CALIBRATION ST-5D 8.0 PROCEDURE Init 8.1 Procedure Performance Determine the applicable procedure subsection to perform as follows:
(-1 IF reactor power is LESS THAN 2 5 % ,
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.
R e v . No. 2 Page 10 of 24
]ICOMl.5.1 Init 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.
(-) 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
APRM CALIBRATION ST-5D 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.
[ITS1 Adjust APRMs per Subsection 8.5.
NR 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 service1 (-1 THEN perform the following:
A. Demand Core Power and Flow Log.
B. Determine APRM DR as follows:
- 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 n o t 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
APRM CALIBRATION ST-5D 8.2.3.B (Cont) Init
- 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 2 4 %
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 T h a n or E q u a l t o 2 5 % 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
APRM CALIBRATION ST-5D 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.
RE 8.4.3 Determine the APRM DR from the higher of the following values:
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 Rev. No. 2 Page 16 of 24
APRM CALIBRATION ST-5 D JEXPl.6 . 2 Init 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 D R .
[ITS]
Identify any A P R M ( s ) requiring adjustment in Table 1. APRM shall be adjusted to indicate within
- 2 % of the D R .
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 . NR B. Ensure METER FUNCTION switch is set to AVERAGE. NR C. Ensure APRM MODE switch is in the OPERATE position. NR 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 D R .
C ITSI Turn gain adjustment control (R16) on LPRM card 2 - 3 1 to obtain a meter reading within
? 2 % of D R .
NR E. Unbypass APRM per Section E of O P - 1 6 . NR Rev. No. 2 Page 17 of 24
[ITS]
NOTE : Tech spec acceptance criteria for Final Re ad i ng I shall be within + 2 % of DR.
8.5.5 Record final APRM readings for adjusted APRMs in Table 1.
TABLE 1 APRM GAIN ADJUSTMENTS APRM A B C D E F
- INITIAL READING ! % )
DESIRED READING ( % )
REQUIRES ADJUSTMENT ( d )
FINAL READING (%)
Rev. No. 2 Page 18 of 24
~
APRM CALIBRATION ST-5D 9.0 9.1 System Restoration 9.1.1 Operable APRMs are unbypassed.
9.1.2 Step 9.1.1 verified by Licensed Operator.
Signature/Date 9.2 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 Attachment 1.
9.2.4 Man-Hours totalled and recorded on Attachment 1.
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
APRM CALIBRATION ST-5D 11.0 ACCEPTANCE VERIFICATION 11.1 NCO/SNO Review 11.1.1 Verify required data has been recorded and is within required tolerances.
11.1.2 Verify required initials and signatures have been entered.
11.1.3 Review test to determine if test acceptance criteria has been satisfied.
11.1.4 Check one of the following as appropriate for test results :
(-) Acceptance criteria satisfied, no corrective action required.
(-) Acceptance criteria satisfied, corrective action required.
(-1 Acceptance criteria satisfied.
11.1.5 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 11.1.6 IF acceptance criteria is not satisfied, THEN perform the following:
A. Immediately notify SM.
B. Initiate a PID and record PID number.
PID Number 11.1.7 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.
(-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 S R O Date/Time Rev. No. 2 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 24
APRM CALIBRATION ST-5D ATTACHMENT 1 Page 1 of 1 TEST SIGNOFF LOG Total Rev. No. 2 Page 24 of 24
m"Entegy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS JOBPERFORMANCEMEASURE S/RO/NPO 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:
-**--*--*--------rn***--*-~--------------***rn****-~-*-*--*****~rn~*-~-~*~~~-~rn~rn 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 20101012 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 20101012 TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)
APPL. TO JPM NUMBER
- 1. SAFETY CONSIDERATIONS A. Proper safety attire (hardhat, safety shoes, safety glasses, ear protection, etc.) is to be worn while out in the plant.
II. REFERENCES A. OP-25, Control Rod Drive Hydraulic System, Rev. 75 B. N-1 Key 111. TOOLS AND EQUIPMENT A. Fuse Pullers IV. 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.
- v. 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.
VI. 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)
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).
STEP STANDARD EVALUATION ICOMMENT
~
- 1. Obtain and review procedure Candidate obtains and reviews OP-25. Candidate SAT / UNSAT 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.
- 2. (G. 1.7) Candidate obtains and reviews OP-25, section G.24. SAT / UNSAT Candidate determines that the start point is step G.24.1.
IF Control Rods are required to be operable, THEN electrically disarm CRD-(*) per subsection G.24 of OP-25.
- 3. (G.24.1) EVALUATOR: SAT / UNSAT Notify Control Room that CRD-(') will When the candidate states that he/she would contact be electrically disarmed. 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)
STEP STANDARD EVALUATION/ COMMENT
- 4. (G.24.2) Candidate correctly locates amphenols associated with SAT / UNSAT CRD/HCU 22-19 and indicates that he/she would unplug Unplug amphenol connector from each / control them. *CRITICAL STEP*
of the following solenoid operated valves at HCU-(*) and control per AP-12.06.
EVALUATOR:
03SOV-120(*) (WITHDRAW SETTLE SOV) When the candidate states that helshe would unplug the 03SOV-121(') (INSERT respective amphenols, inform the candidate that "The EXHAUST WATER SOV) four respective amphenols are unplugged and the PTR 03SOV-122(*) (WITHDRAW is hung."
DRIVE WATER SOV) 03SOV-123(*) (INSERT DRIVE EVALUATOR NOTE:
WATER SOV) HCU-22-19 is isolated RB 272' East.
~ ~
- 5. (G.24.3) EVALUATOR: SAT / UNSAT Notify Control Room that CRD-(*) has When the candidate states that he/she would contact been electrically disarmed. the Control Room to notify them that CRD 22-19 has been electrically disarmed, inform the candidate that "CRD 22-19 has been electrically disarmed."
- 6. (G.1.8) Candidate correctly locates 03HCU-101 associated with SAT t UNSAT CRD/HCU 22-19 and indicates that he/she would close Close 03HCU-101(*) (CRD INSERT it. *CRITICAL STEP*
LINE ISOL VALVE).
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 (22-19) is CLOSED."
Page 5 of 14
S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU) d STEP STANDARD I EVALUATION I COMMENT
- 7. (G.1.9) Candidate correctly locates 03HCU-102 associated with SAT / UNSAT Close 03HCU-102(*) (CRD CRDIHCU 22-19 and indicates that he/she would close WITHDRAW LINE ISOL VALVE). it. *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 (22-19) is CLOSED."
- a. (G. 1.lo) Candidate correctly locates 03HCU-113 associated with SAT IUNSAT Close 03HCU-l13(*) (CHARGING CRD/HCU 22-19 and indicates that helshe would close WATER HEADER ISOL VALVE). it. *CRITICAL STEP*
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."
"9. (G.l . l l ) Candidate correctly locates 03HCU-104 associated with SAT / UNSAT Close 03HCU-104(*) (COOLING CRD/HCU 22-19 and indicates that he/she would close it. *CRITICAL STEP*
WATER SUPPLY ISOL VALVE).
EVALUATOR:
When the candidate locates and identifies 03HCU-104 and states that he/she would close 03HCU-104, then inform the candidate "03HCU-104 (22-19) is CLOSED."
Page 6 of 14
S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)
STEP STANDARD
- lo. (G.1.12) Candidate correctly locates 03HCU-103 associated with SAT / UNSAT Close 03HCU-103(*) (CRD DRIVE CRD/HCU 22-19 and indicates that he/she would close WATER SUPPLY 1SOL VALVE). it. *CRITICAL STEP EVALUATOR:
When the candidate locates and identifies 03HCU-103 and states that he/she would close 03HCU-103, then inform the candidate "03HCU-103 (22-19) is CLOSED."
- tl. (G.1.13) Candidate correctly locates 03HCU-105 associated with SAT / UNSAT Close 03HCU-105(*) (EXHAUST CRDIHCU 22-19 and indicates that he/she would close WATER SOL VALVE). it. *CRITICAL STEP*
EVALUATOR:
When the candidate locates and identifies 03HCU-105 and states that heishe would close 03HCU-105, then inform the candidate "03HCU-105 (22-19) is CLOSED."
- 12. (G.1.14) Candidate correctly locates 03HCU-112 associated with SAT / UNSAT Close 03HCU-112(*) (SCRAM CRD/HCU 22-19 and indicates that he/she would close DISCHARGE HEADER SOL VALVE). it. *CRITICAL STEP*
EVALUATOR:
When the candidate locates and identifies 03HCU-112 and states that he/she would close 03HCU-112, then inform the candidate "03HCU-112 (22-19) is CLOSED."
Page 7 of 14
S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT [HCU)
STEP STANDARD I EVALUATION / COMMENT
- 13, (G. 1.15) Candidate correctly locates Scram Pilot Solenoid Fuses SAT / UNSAT Remove the following fuses to de- associated with CRD/HCU 22-19 SOVs 117/118;and energized Scram Pilot Solenoid indicates that he/she would pull them with the fuse *CRITICAL STEP*
Operated Valves 03SOV-l17(*)and puller.
09SOV-l18(*):
0 5A-FlQAr) 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."
- 14. (G. 1. I6)
Verify open the following valves by with CRD/HCU 22-19 and indicates that he/she would observing valve position indicators at observe mechanical position indication to verify current HCU-(*): valve position.
0 03AOV-126(*) (HCU INLET SCRAM AIR OPER VALVE) EVALUATOR:
03AOV-127(*) (HCU OUTLET When the candidate locates and identifies 03AOV-126 SCRAM AIR OPER VALVE) 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: ISOLATEAND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)
STEP STANDARD EVALUATION I COMMENT
- 15. (G.1.17) Candidate recognizes need to obtain information from SAT / UNSAT Verify HCU-(*) blue SCRAM light is on 09-5 Panel in the Control Room.
at FULL CLOSE DISPLAY.
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".
~
- 16. (G.1.18) Candidate correctly locates O3HCU-107 associated with SAT / UNSAT Loosen threaded cap on 03HCU-107(*) CRD/HCU 22-19 and recognizes WARNING through (ACCUMULATOR DRAIN VALVE) to indicating that he/she would loosen the cap "slowly", *CRITICAL STEP*
thoroughly vent pressure before "carefulty", or "in a controlled manner" (or similar proceeding to the next step. 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'.
Page 9 of 14
S/RO/NPO TASK TITLE: ISOLATEAND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)
STEP STANDARD EVALUATION / COMMENT
- 17. (G. 1.19) Candidate correctly identifies 03HCU-107 associated SAT / UNSAT with CRD/HCU 22-19 and indicates that he/she would Remove threaded cap from 03HCU- remove it (may add "by turning counterclockwise") *CRITICAL STEP*
107(*) (ACCUMULATOR DRAIN VALVE).
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."
- 18. (G. 1.20) Candidate correctly identifies 03HCU-107 associated SAT / UNSAT with CRD/HCU 22-19 and identifies hose routing Connect hose to 03HCU-l07(*) location (floor drain / poly bottle in vicinity)
(ACCUMULATOR DRAIN VALVE) and route other end of hose to a floor drain or suitable container.
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'.
- 19. (G.1.21) Candidate correctly identifies 03HCU-107 associated SAT / UNSAT with CRD/HCU 22-19 and indicates that he/she would Crack open 03HCU-107(*) crack it open.
(ACCUMULATOR DRAIN VALVE).
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 (22-19) is CRACKED OPEN."
Page 10 of 14
S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)
STEP STANDARD EVALUATION I COMMENT
-~
- 20. (G. 1.22) Candidate correctly identifies 03HCU-107 associated SAT / UNSAT with CRD/HCU 22-19 and indicates that he/she would WHEN HCU 22-19 water accumulator fully open it upon indications that it was depressurized. *CRITICAL STEP*
is thoroughly vented, open 03HCU-107r) (ACCUMULATOR DRAIN VALVE).
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 (22-19) is FULL OPEN."
- 2 1 (G. 1.23) Candidate recognizes need to perform step based on SAT I UNSAT planned maintenance on 03SOV-117/118; and correctly IF maintenance is to be performed on locates 03HCU-116 associated with CRDIHCU 22-19 *CRITICAL STEP any of the following: and indicates that he/she would dose it.
03AOV-126 (*) (HCU INLET SCRAM AIR OPER VALVE) 03AOV-127 (*) (HCU OUTLET EVALUATOR:
SCRAM AIR OPER VALVE) When the candidate locates and identifies 03HCU-116 03SOV-117/118 (*) (SCRAM and states that he/she would close 03HCU-116, then PILOT AIR SOLENOID OPER inform the candidate "03HCU-116 (22-19) is CLOSED."
VALVE) 0 Instrument air piping downstream of 03HCU-116 (*)
(SCRAM PILOT AIR {SOL VALVE)
THEN close 03HCU-116 (*)(SCRAM PILOT AIR SOL VALVE)
Page 11 of 14
S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)
- ~-
STEP STANDARD EVALUATIONI COMMENT
- 22. (G.1.24) EVALUATOR: SAT / UNSAT IF maintenance is to be performed that If requested, inform candidate that no maintenance is requires depressurizing the HCU planned that required depressurizing the accumulator.
nitrogen accumulator, THEN perform the following:
(MA) LIST NOT REQUIRED
~ - ~~ ~~
- 23. (G. 1.25) Candidate goes to the CRD ACCUMULATOR SAT / UNSAT MONITOR & SCRAM VALVE POSITION SELECTOR Verify red light is on at CRD Panel 25-04 (east side) and verifies red light is on for ACCUMULATOR MONITOR & SCRAM HCU-22-19.
VALVE POSITION SELECTOR panel 25-04 (east side) or 25-22 (west side)
Reactor Buitding 272'.
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."
- 24. (G. I.26) EVALUATOR: SAT / UNSAT Notify Control Room that HCU-(*) has When the candidate states that he/she would contact been removed from service. 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".
Page 12 of 14
S/RO/NPO TASK TITLE: ISOLATE AND ELECTRICALLY DISARM A HYDRAULIC CONTROL UNIT (HCU)
STEP STANDARD EVALUATION / COMMENT
- 25. (G. 1.27) Candidate recognizes need to obtain information from SAT / UNSAT 09-5 Panel in the Control Room.
Verify HCU-(*) yellow ACCUM light is on at FULL CORE DISPLAY.
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.
Page 13 of 14
i m
"Entegy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant 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: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATION REVIEW:
APPROVED:
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. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP40, Main Steam Line Break, Revision 8 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Obtain permission from the Shift Manager prior to performing this task.
B. Obtain a current copy of AOP-40, Main Steam Line Break.
W. 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.
VI. TASK CONDITIONS A. A Main Steam Line Break has occurred in the Turbine Building.
B. All automatic isolations / initiations were successful.
C. All MSlVs are "CLOSED".
D. 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 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.
VIII. TASK STANDARD The candidate will start up the "Alpha" train of the Main Steam Leakage Collection System STEP STANDARD I EVALUATION / COMMENT
- 1. Obtain and review procedure Candidate obtains and reviews AOP40. Candidate SAT I UNSAT determines that the start point is step C.3.2 (C.3.2.a.1) Locates 29MOV-204A on Panel 29MSLCS in the Relay SAT I UNSAT Close 29MOV-204A MSLC LINE Room and closes 29MOV-204A.
"Alpha" BYPASS DRAIN VALVE. "CRITICAL STEP*
EVALUATOR:
Inform the candidate 29MOV-204 "Alpha" indicates "CLOSED."
(C.3.2.a.2) Locates 29MOV-200A on Panel 29MSLCS in the Relay SAT / UNSAT Open 29MOV-200A MSLC LINE Room and opens 29MOV-200A.
"Alpha" ISOL VALVE. *CRITICAL STEP*
EVALUATOR:
Inform the candidate 29MOV-200 "Alpha" indicates "OPEN."
Page 4 of 6
SIR0 TASK TITLE: START UP MAIN STEAM LEAKAGE COLLECTION STEP STANDARD EVALUATION I COMMENT
- 4. (C.3.2.a.3) Contacts the Control Room operator and asks to be SAT / UNSAT informed when annunciator 09-5-249 MSLCS "AI Monitors annunciator 09-5-249 PRESS HI Clears.
"MSLCS A PRESS HI."
EVALUATOR:
Act as the Control Room and inform the candidate that the annunciator is clear.
- 5. (C.3.2. a.3.a) Locates 29MOV-201A on Panel 29MSLCS in the Relay SAT / UNSAT Room and opens 29MOV-201A.
Open 29MOV-201A MSLC LINE "A* TO
- CRITICAL STEP*
SGT UPSTR ISOL VLV. EVALUATOR:
Inform the candidate 29MOV-201A indicates "OPEN"
~
- 6. (C.3.2. a.3.b) Locates 29MOV-202A on Panel 29MSLCS in the Relay SAT / UNSAT Room and ensures open 29MOV-202A.
Ensure open 29MOV-20% MSLC LINE "A' TO SGT DNSTR ISOL VLV. EVALUATOR:
Inform the candidate that 29MOV-202A indicates "OPEN".
'7. (C.3.3) Locates 29MOV-203A on Panel 29MSLCS in the Relay SAT / UNSAT Room and opens 29MOV-203A.
Open 29MOV-203A MST OUTBD MSlV
- CRITICAL STEP*
STEM LEAKOFF LINE "A' SOL VLV. EVALUATOR: Inform the candidate that 29MOV-203A indicates 'OPEN".
EVALUATOR: Terminate the task at this point.
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 Nuclear Northeast James A. FkPatrick Nuclear Power Plant 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: JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATION REVIEW:
APPROVED:
~ ~ ~ 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:
SIGNATURUPRINTED 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 Procedural Change Required - X None 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. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-8, Alternate Injection Systems, Rev. 2 111. TOOLS AND EQUIPMENT A. Emergency cross connect hose located in the North Safety Pump Room.
B. N1 Key IV. SET UP REQUIREMENTS A. None V. NALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and actually performed.
B. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI. TASK CONDITIONS A. To maintain RPV water level >O" (TAF), water level control must be augmented by using the lake as a source.
B. The RHRSW pumps are unavailable.
C. The Shift Manager has directed that the Fire Protection System be utilized to injed water into the RHRSW System.
- 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.
-~
I
~
STEP STANDARD EVALUATION ICOMMENT
- 1. Obtain and review procedure Candidate obtains and reviews EP-8. Candidate SAT / UNSAT determines that the start point is step 5.3
Verifies the following RHR pumps are stopped:
EVALUATOR:
Inform the candidate that "RHR Pumps 3"Alpha" and RHR PMP IOP-3A RHR PMP IOP-3C 3"Charlie" are not running."
- 3. (5.3.2) EVALUATOR: SAT / UNSAT Removes caps from the following When the candidate goes to the North Emergency valves: "CRITICAL STEP*
Service Water Room and states that he/she would remove the hose connection caps at 1ORHR-432 and 0 10RHR-432 (RHRSW TO FIRE 76FPS-720, then inform the candidate "Hose connection PROTECTION CROSS-TIE caps are removed."
ISOL VALVE) 76FPS-720 (RHRSW / FIRE PROTECTION CROSSTIE ISOL VALVE) ~~
Page 4 of 7
S/RO/NPO TASK TITLE: CROSS-TIE FIRE PROTECTION SYSTEM TO INJECT TO RHR SERVICE WATER STEP STANDARD EVALUATION / COMMENT
- 4. (5.3.3) EVALUATOR: SAT / UNSAT Connect a hose (stored in cabinet When the candidate opens 76CAB-1 with N-1 key and 76CAB-1 on west wall of north *CRITiCAL STEP*
points out the emergency cross connect hose and tools emergency setvice water room) and states he/she would connect the hose between between the following valves: 1ORHR-432 and 76FPS-720, then inform the candidate "Hose is connected."
10RHR-432 (RHRSW TO FtRE PROTECTION CROSS-TIE SOL VALVE) 76FPS-720 (RHRSW / FIRE PROTECTION CROSSTIE ISOL VALVE)
- 5. (5.3.4) Contacts Control Room to verify that IOMOV-89A is SAT / UNSAT closed.
Ensure closed IOMOV-89A RHRSW DISCH VLV FROM HX A. 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) Informs the Control Room that he/she is ready to have SAT / UNSAT one or more of the Fire protection System pumps Start one or more of the following started. *CRITICAL STEP*
pumps:
EVALUATOR:
ELEC FIRE PMP 76-P2 DIESEL FIRE PMP 76-PI Inform the candidate "Electric Fire Pump 76P-2 is DIESEL FIRE PMP 76-P4 operating."
Page 5 of 7
S/RO/NPO TASK TITLE: CROSS-TIE FIRE PROTECTION SYSTEM TO INJECT TO RHR SERVICE WATER STEP STANDARD EVALUATION I COMMENT
- 7. (5.3.6) EVALUATOR:
SAT / UNSAT Unlock and open the following valves: When the candidate states that he/she would unlock and open 10RHR-432 by turning the handwheel in the *CRITICAL STEP*
0 10RHR-432 (RHRSW TO FIRE counterclockwise direction until full open, then inform PROTECTION CROSS-TIE the candidate that 10RHR-432 is OPEN.
ISOL VALVE) 76FPS-720 (RHRSW / FIRE When the candidate states that he/she would unlock PROTECTION CROSSTIE and open 76FPS-720 by turning the handwheel in the ISOL VALVE) counterclockwise direction until full open, the inform the candidate that 76FPS-720 is OPEN.
EVALUATOR: Terminate the task at this point.
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