05000338/LER-1981-009-03, Combined Leakage in Excess of Allowable Limits Noted from 14 Electrical Penetrations & 23 Valves.Valve Leakage Caused by Valve Seat Deterioration or Limit Switch Drift

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Combined Leakage in Excess of Allowable Limits Noted from 14 Electrical Penetrations & 23 Valves.Valve Leakage Caused by Valve Seat Deterioration or Limit Switch Drift
ML19345H567
Person / Time
Site: North Anna 
Issue date: 05/15/1981
From: Cartwright W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19345H565 List:
References
LER-81-009-03X, LER-81-9-3X, NUDOCS 8105210275
Download: ML19345H567 (4)


LER-1981-009, Combined Leakage in Excess of Allowable Limits Noted from 14 Electrical Penetrations & 23 Valves.Valve Leakage Caused by Valve Seat Deterioration or Limit Switch Drift
Event date:
Report date:
3381981009R03 - NRC Website

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s UPDATE REPORT - PREVIOUS REPORT DATE JANUARY 28, 1981 hq U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1)

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT 0/1/

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E DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)

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While performing Type B and C containment penetration leak testing, 14 electr- /

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cal penetrations and 23 valves had combined leakage in excess of allowable li- /

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mits. The electrical penetration leakage resulted from leaking mechanical fit-/

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tings outside containment in the nitrogen system. The leaking valves had addi- /

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itional boundary isolation valves or were in closed systems that prevented di- /

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rect contact with the environment. Therefore the health and safety of the pub- /

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lic were not affected. This event is reportable pursuant to T.S. 6.9.1.9.b.

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SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO.

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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LD/ (18) LZ/ (19) g/ (20) LZ/ (21) /0/0/0/0/ (22) g/ (23) /N/ (24) LA/ (25) /X/9/9/9/ (26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

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Valve leakage was due to deterioration of the valve seats or to limit switch

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drift. Leakage from electrical penetrations was due to leaking piping

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connections.

In all cases, leaking components were reworked or readjusted

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until the leakage was acceptable.

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FACILITY METHOD OF STATUS

% POWER OTHER STATUS DISCOERY DESCRMM (32)

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TYPE B & C TESTING

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ACTIVITY CONTENT I

RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)

LOCATION OF RELEASE (36) l

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PERSONNEL EXPOSURES NDiBER TYPE DESCRIPTION (39) j

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PERSONNEL INJURIES j

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LOSS OF OR DAMAGE TO FACILITY G3) l TYPE

DESCRIPTION

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ISSUED DESCRIPTION (45)

NRC USE ONLY l

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NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 l

8.1052,10 25 j

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UPDATED REPORT - PREVIOUS REPC'1T DATE JANUARY 28, 1981 Virginia Electric and Power Company North Anna Power Station, Unit #1

Attachment:

Page 1 of 3 Docket No. 50-338 Report No. LER 81-009/03X-1

Description of Event

While performing Type B and C penetratiou testing, 14 electrical penetrations and 23 valves had combined leakage that exceeded the maximum (0.6La) limit. These valves and electrical penetrations are noted on the attached list.

Probable Consequences of Occurrence The penetrations containing the leaking valves either had additional isolation valves or were in completely closed systems which prevented any direct contact with the environment. There was no throuFh-leakage detected for the electrical penetrations; the problen instead was caused by leaking mechanical fitting located external to the containment.

Therefore, the health and safety of the public were not affected.

Cause of Event

Valve leakage was due to normal deterioration of the valve seats or because of limit switch drift. Electrical penetration leakage was due to leaking connections on the nitrogen system. There was no leakage experienced from the penetration caps.

Immediate Corrective Action

All Type B and C penetrations that exhibited leakage in excess of allowable were repaired or readjusted.

In addition the leakage from all of the Type B or C penetrations (after repair) that were not e sposed to the overall Type A Containment Leakage test were summarized and used as a penalty for the total containment leak rate test. As such, the overall leak rate was less than the 10 CFR 50 Appendix J limit.

Scheduled Corrective Action No further action is required.

Actions Taken to Prevent Recurrence The surveillance program for containment penetrations has been instituted at North Anna in accordance with NRC guidelines. This program is designed to identify potential leakage paths and repair these valves and penetrations on a regularly scheduled basis. Therefore, no further actions are required.

Generic Implications There are no generic implications associated with this event.

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UPDATED REPORT - PREVIOUS REPORT DATE JANUARY 28, 1981 Attachment: Page 2 of 3 Valves Comp. Subcode Valve Code Component Manufacturer 1-CC-559 C

D M-360 1-CC-572 C

D M-360 1-CH-322 C

D E-090 TV-BD-100A F

D F-130 TV-BD-100B F

D F-130 TV-BD-100C F

D F-130 T5-BD-100D F

D F-130 TV-BD-100E F

D F-130 TV-BD-100F F

D F-130 TV-BD-100D F

D F-130 TV-SI-101 F

D F-130 TV-SV-102-1 F

D F-130 MOV-HV-100D B

D F-130 MOV-RS-101A B

D F-130 MOV-SW-103B B

D A-180 MOV-SW-103C B

D A-180 MOV-SW-103D B

D A-180 MOV-SW-104B B

D A-180 MOV-RS-104C B

D A-180 TV-DA-100A F

D F-130 TV-DA-100B F

D F-130 1-SI-79 C

A V-085 1-FP-272 A

D C-620

.. -- o UPDATED REPORT-PREVIOUS REPORT DATE JANUARY 28, 1981 Attachment: Page 3 of 3 Penetration

  • Penetration Number Type 1A I-VA-4160V 6B I-III-2(5TW) s000V 10A I-III-3(5TW)-3000V ISA I-III-6(5TW)-3000V 16D I-IA-20(ATW)-480V 18A I-III-8(5TW)-3000V 18B I-III-9(STW)-3000V 19A I-IC-8-480V 20A I-IIB-5-480V 21A I-IIA-3-480V 21C I-IIC-4-480V 21D I-IIC-5-480V 22A I-IIE-6-480V 22B I-IIE-7-480V
  • Component Manufacturer - C515

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