05000338/LER-1980-108-03, /03L-0:on 801227,tests Showed Primary Identified Leakage Was 12.73 Gpm & Primary Unidentified Leakage Was 2.37 Gpm.Caused by Excessive Leakage of RCP a Seal 2.Seal Will Be Replaced

/03L-0:on 801227,tests Showed Primary Identified Leakage Was 12.73 Gpm & Primary Unidentified Leakage Was 2.37 Gpm.Caused by Excessive Leakage of RCP a Seal 2.Seal Will Be Replaced

ML19341A640
Person / Time
Site:	North Anna
Issue date:	01/21/1981
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19341A636	List: 05000338/LER-1980-108, Forwards LER 80-108/03L-0 05000338/LER-1980-108-03, /03L-0:on 801227,tests Showed Primary Identified Leakage Was 12.73 Gpm & Primary Unidentified Leakage Was 2.37 Gpm.Caused by Excessive Leakage of RCP a Seal 2.Seal Will Be Replaced
References
LER-80-108-03L, LER-80-108-3L, NUDOCS 8101270588
Download: ML19341A640 (3)

LER-1980-108, /03L-0:on 801227,tests Showed Primary Identified Leakage Was 12.73 Gpm & Primary Unidentified Leakage Was 2.37 Gpm.Caused by Excessive Leakage of RCP a Seal 2.Seal Will Be Replaced

Event date:
Report date:
3381980108R03 - NRC Website

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U.S. NUCLEAR REGULATORY COMMISSION (3

LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1)

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT

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

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On December 27, 1980, while operating Unit 1 at 58 percent power, results of a /

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primary leakage test showed that primary identified leakage was 12.73 gpm and /

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primary unidentified leakage was 2.37 gpm.

This event is reportable pursuant /

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to T.S. 6.9.1.9.b.

Unit I was shutdown in accordance with the action state-

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ment of the LCO (T.S. 3.4.6.2). The public health and safety were not

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affected.

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SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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/C/B/ (11) g/ (12) [B/ (13) /P/U/M/P/X/X/ (14) /B/ (15)

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

CODE TYPE NO.

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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTIOF ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER [Z/ (18) g/ (19) /A/ (20) /A/ (21) /0/0/7/2/ (22) H/ (23) [N/ (24) $/ (25) /W/1/2/0/ (26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

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Excessive leakage by RCP "A" no. 2 seal caused the RCS leakage to exceed limits /

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specified by the LCO. During the current refueling outage the no. 2 RCP "A"

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seal will be replaced. The current refueling outage started two days early due/

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to the event.

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FACILITY METHOD OF STATUS

% POWER OTHER STATUS

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NA [B/ (31)

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ROUTINE TEST

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ACTIVITY CONTENT RELEASEli 0F RELEASE AMOUNT OF ACTIVITY (35)

LOCATION OF RELEASE (36)

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PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)

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PERSONNEL INJURIES NUMBER DESCRIPTION (41)

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LOSS OF OR DAMAGE TO FACILITY G3)

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PUBLICITY ISSUED DESCRIPTION (45)

NRC USE ONLY

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NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 D0127r; NTf

Virginia Electric and Power Company North Anna Power Station, Unit #1 Attachment: Page 1 of 2 Docket No. 50-338 Report No. LER 80-108/03L-0

Description of Event

On December 27, 1980, while operating Unit I at 58 percent power, the Control Room Operator noted an increasing primary drain tank level coincident with increased charging flow and erratic RCP "A" no. I seal leak oif flow. A primary leakage test was performed. Results of the test showed that primary identified leakage was 12.73 gpm and primary unidentified leakage was 2.37 gpm. This event is reportable pursuant to T.S. 6.9.1.9.b.

Probable Consequences of Occurrence Unit I was shutdown in accordance with the action statement of the LC0 (T.S. 3.4.6.2).

The current refueling outage started two days early due to the event. The public health and safety were not affected.

Cause of Event

Excessive leakage by RCP "A" no. 2 seal caused the RCS leakage to erceed limits specified by the LCO.

The RCP no. 2 and 3 seals are rubbing-face type seals consisting of a Graphitar 114S insert which is shrunk into a stainless steel seal ring. The seal ring insert rubs on aluminum-oxide coating plates on a Type 304 SST runner which rot-tes with the shaft.

Initial inspection indicates that the aluminum oxide coating runner plates might have degraded slightly due to the relatively high pH of the RCS. A rela-tively high pH (approximately 9.6) existed in the RCS because boron concentration was minimized to allow coast down operation.

savestigation of the cause of the seal failure is continuing.

Immedlite Corrective Action Unit I was placed in Hot Standby 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 5 minutes after the event.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 47 minutes after the event Unit I was in Cold Shutdown.

Scheduled Corrective Action Vepco and Westinghouse personnel are scheduled to inspect the no. 2 RCP "A" seal to determine the cause of the tailure during the current refueling outage. All three RCP no. 2 and 3 seal runners on Unit I will be replaced with runners that have chrome carbide coating runner plates which are not susceptible to high Ph degradation.

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Attachment:

Page 2 of 2 Actions Taken to Prevent 3ecurrence t

The scheduled corrective action should prevent recurrence.

Generic Implications The current investigation of the cause of the seal failure will determine generic implications, if any.

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