ML022630202

NRC Job Performance Measure; JPP-112; Loss of Containment Integrity (XVG-503A)

ML022630202
Person / Time
Site:	Summer
Issue date:	09/16/2002
From:	NRC/RGN-II
To:
References
FOIA/PA-2002-0371
Download: ML022630202 (7)

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V.C. SUMMER NUCLEAR STATION NRC JOB PERFORMANCE MEASURE JPP-112 LOSS OF CONTAINMENT INTEGRITY (XVG-503A)

Revision No. 3

LOSS OF CONTAINMENT INTEGRITY (XVG-503A)

It TRAINEE EVALUATOR EVALUATOR SIGNATURE Ii II II II II ii II II II II II II II I!

I!

DATE SIMULATE PLANT 15.0 MINUTES TIME STARTED:

OBSERVE AND SAFELY CONTROL THE OPERATING BEHAVIOR CHARACTERISTICS OF THE FACILITY FAULTED JPM:

No SATISFACTORY UNSATISFACTORY

'I READ TO OPERATOR:

WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE JJ INITIATING CUES.

I WILL DESCRIBE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS I

TASK.

BEFORE STARTING, I

WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS I

TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES.

WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS I,

JOB PERFORMANCE MEASURE WILL BE SATISFIED.

I' INITIAL CONDITIONS:

1.

The Plant has experienced an SI from 100% power with the CRS implementing EOP-l.0.

Blowdown isolation valve XVG00503A has failed to close on a valid phase 'A' containment isolation signal.

TOOLS AND EQUIPMENT NEEDED:

1. EOP-1.0 ATT.

3 PG 5 OF 8 REFERENCED DOCUMENTS:

1.

EOP*I.0 REACTOR TRIP/SAFETY INJECTION ACTUATION REV DATE 05/09/96 0

PAGE 0 Ii II EVALUATION METHOD:

EVALUATION LOCATIC ESTIMATED TIME:

10CFR55.45 (a) 5 TIME CRITICAL:

No TRAINEE PERFORMANC II I -

DN:

_E :

l l I

l l

I J

I

PAGE 1 LOSS OF CONTAINMENT INTEGRITY (XVG-503A) ii TASK STANDARDS:

1.

S/G Blowdown from loop 'A' is isolated per EOP-1.0, Att.

4.

INITIATING CUES:

1.

Control Room Supervisor directs you to close IFV-4701A (Backup Isolation Valve for XVG-503A-BD) per EOP-l.0, Attachment 4.

TERMINATING CUES:

1. IFV-4701A is closed locally.

SAFETY CONSIDERATIONS:

1.

VALVES ARE IN A CONTAMINATED AREA

JOB PERFORMANCE MEASURE CHECKLIST (S)

DENOTES SEQUENCED ELEMENT

(*)

DENOTES CRITICAL ELEMENT PERFORMANCE CHECKLIST:

SAT.

UNSAT.

iNOTE 1:

When operator simulates operation of controller or control switch inform him that indications remain "as seen" (i.e.,

red "open" light on)

STEP STANDARD

1.

Attempts to close IFV-4701A Places and holds the BD LOOP A FLOW CTRL using the switch on the IFV-4701A switch in the CLOSE position Nuclear Blowdown Processing or rotates the BD LOOP A FLOW CTRL Panel (AB-436)

IFV-4701A potentiometer counterclockwise to zero until the red light goes out INOE 2:

If the operator reports to the Control Room that the valve did not close from the Blowdown Panel, the Examiner as the CRS should direct the operator to locally isolate Instrument Air to IFV04701B-BD and vent off its supply regulator.

1 STEP STANDAR S*2.

Close Instrument air isolation Closes IFVO47OlAW 7B-AW.solation valve.

(AB-412, West Valve for IFV

-D ( urns Penetration))

clockwise d 0

CODRME=TS:

STEP STANDARD S*3.

Vents air from regulator to Vents air from IFV04701A-PRI-BD, IA close IFV-4701A.

SUPPLY REG FOR IFV47OIA-BD by turning the regulator T-Bar in the counterclockwise direction.

COM=ENTS:

[NOTE 4:

Have operator point out valve stem position indication.

Cue examinee that IFV-4701A indicates fully closed.

PAGE 2

"JOB PERFORMANCE MEASURE CHECKLIST (S)

DENOTES SEQUENCED ELEMENT

(-) DENOTES CRITICAL ELEMENT PERFORMANCE CHECKLIST:

PAGE 3 SAT. UNSAT.

JOB PERFORMANCE MEASURE CHECKLIST PERFORMANCE CHE(

STEP (S) DENOTES SEQUENCED ELEUMET

(*)

DENOTES CRITICAL ELEMENT 2KLIST:

STANDARD PAGE 4 SAT. UNSAT.

S 4.

Verify valve IFV-4701A closed Examiner Stops JPM At This Point TIME STOPPED:

GENERAL COMMENT

S:

Checks valve stem position to verify that valve is closed NRC KA

REFERENCES:

KA NUMBER 000069.EAI. 01 Ability to operate and monitor isolation valves; dampers and electro-pneumatic devices following a loss of containment integrity.

IMPORTANCE RO 3.5 FACTOR SRO 3.7

0 LOCALLY START AN EMERGENCY D/G DURING A LOSS OF OFFSITE POWER NRC KA

REFERENCES:

KA NUMBER 064000.K3.02 Knowledge of the effect that a loss of the ED/G system will have on ESF controlled or actuated systems.

IMPORTANCE FACTOR RO SRO 4.2 4.4 I.

PAGE 6 II