ML18139A307

LER 80-003/03L-0:on 800514,w/unit in Cold Shutdown, MOV-CW-2008 Failed to Close on Safeguard Signal.Caused by Electrical Malfunction Due to Repairs in Progress.Redundant Inlet Valve Shut.Valve Will Be Repaired & Tested

ML18139A307
Person / Time
Site:	Surry
Issue date:	06/06/1980
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A306	List: ML18139A305 ML18139A307 ML18139A308
References
LER-80-003-03L-02, LER-80-3-3L-2, NUDOCS 8006120339
Download: ML18139A307 (2)

Text

NRC FORM 366 - U.S. NUCLEAR REGULATORY COMMISSION (7-77)

.LICENSEE EVENT REPORT e CONTROL BLOCK: I ~ I\V L---'--....._-'-'----'---'----'6 r.j'\ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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7 8 CTA I s Ip Is I 2 101 °I OI -1 °I O I O I O [ 0 I - [ 0 I O 10[ 4 [1 [ 1 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE

[1 [1 181 30 I I© 57 CAT 58 CON'T

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I With the unit at cold shutdown, MOV-CW-200B was found inoperable. The failure of the

[£JI] I MOV to close on a safeguards signal is non-conservative with respect to Technical

~ I Specification 3.14.A.l. This event is reportable per Technical Specification 6.6.2.b.2.

1

[§I§] I The health and safety of the general public was not affected because the safety related

[QJI] I function of the redundant valve was operable.

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7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q LER!RO LVENTYEAR REPORT NO. CODE TYPE NO.

\!..Y REPORT NUMBER I 8 10 I I23 . I I o I o I 326I I/[ I28 oI 329I l.1J l.=J l_QJ 21 22 24 27 30 31 32 ACTION FUTURE EFFECT SHUTDOWN Q., ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

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43 I PI 3 14 I O I 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

I The valve was under mechanical repair and will be repaired and tested for operability.

((OJ I The corrective action taken was to shut the redundant inlet valve.

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7 8 9 80 FACILITY METHOD OF A STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION '23; o=ITJ W@ 0 ! 0 I O!@)IL-_..:;!:NA:.=___ _ _ .,-l W@L.l-~o~p~e=.=r...:.a""'t=..)o.._r"---'o,...b""""'s_,.e.,.r-"v_..a....t....i.,,o,...n,__________ ---,1 8 9 10 12 1'3 44 45 46 80 ACTIVITY CONTENT ~

RELEASED OF RELEASE AMOUNT OF ACTIVITY~ ..LOCATION OF RELEASE @

[£JI] W@ LIJ@I NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES r::;:;,_

NUMBER Q. TYPE DESCRIPTION~

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7 8 9 11 12 13 80 PERSONNEL INJURIES Q NUMBER DESCRIPTION6

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8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '4J' TYPE DESCRIPTIO*, ~

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, ~ATTACHMENT (PAGE 1 OF 1)

SURRY POWER STATION, UNIT DOCKET NO:

REPORT NO:

50-281 80-005/0lT-Q EVENT DATE: 3-6-80.

TITLE OF EVENT: RECIRCULATION SPRAY HEAT EXCHANGER

1. DESCRIPTION OF EVENT:

During preparation for Type "A 11 testing, leakage was identified through Recirculation Spray Heat Exchanger diaphragm plate seal weld cracks. The components affected were 2-RS-E-lB, C, and D. The event is reportable per Tech. Specs. 6.6.2.a.9.

2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:

The affected reactor unit was at cold shutdown and the leakage was discovered during testing, therefore, there were no consequences as a result of the event, and the health and safety of the public were not affected-.

3. CAUSE:

The leaking seal weld cracks are attributed to lack of fusion and slag inclusion in the weld areas from previous maintenance work.

4. IMMEDIATE CORRECTIVE ACTION:

The immediate corrective action was to have the Architect~Engineer perform a detailed stress analysis on the heat exchangers to determine if a design error had been committed. Simultaneously, discussions were held with maintenance personnel and all maintenance histories were searched to determine the exact repairs that had been made to the affected components.

5. SUBSEQUENT CORRECTIVE ACTIONS:

All defects found to date have been in the diaphragm plate seal weld area.

All welds will be liquid penetrant inspected and all defects will be repaired.

Stress analysis proved the design of the heat exchangers to be conservative; however, a modification is being made to incorporate a gasket between the diaphragm plate and heat exchanger cover to reduce stress on the diaphragm plate seal weld from external pressure forces.

6. FUTURE CORRECTIVE ACTION:

No further corrective action is anticipated.

7. GENERIC IMPLICATIONS:

Two of four RSHX's in Unit 1 have been subjected to maintenance by the manufac-turer's (YUBA) personnel. The welds on all four heat exchangers will be examined by Non-destructive methods during the next scheduled unit shutdown of sufficient duration. A gasket will be installed in Unit l's RSHX's between diaphragm plate and heat exchanger cover at that time.