ML17261A174

Updated LER 79-024/01X-1:on 791217,samples of Boric Acid Storage Tank Concentrations Found Below Min Limits.Caused by Backflow of Refueling Water Through Boric Acid Tank Outlet Motor Operated Valve

ML17261A174
Person / Time
Site:	Ginna
Issue date:	02/13/1980
From:	Schuler T ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML17249A584	List: ML17249A583 ML17261A174
References
LER-79-024-01X, LER-79-24-1X, NUDOCS 8002190506
Download: ML17261A174 (4)

Text

NRC FO+ 366 7 9-024/01X-1 Update Report - previous rep'or'0 8k% D)8975 P 77t ICENSEE EVENT REPORT CONTROL BLOCK: QT (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

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7 8 9 NYREG1Q200 LICENSEE CODE 14 15 0 0 0 LICENSE NUMBER 0 0 - 0 0 25 Qs4 26 1 1 LICENSE TYPE 1 1 30 QE~QE 57 CAT 58 CON'T

~O ~LQB 0 S 0 0 0 2 4 4 7 1 2 1 7 7 9 QB QB 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABI.E CONSEQUENCES Q10 on routine anal sis of sam les of the boric acid stora e tanks concentrations were found to be below the minimum 12'0 boric acid at 10. 2: and 10. 1$ . (T.S. 3. 2. 3.c) .

4 This event is similar to those re orted in LER's79-009 and 79-010. Reactor ower reduction procedures were implemented until required concentrations were achieved.

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~07

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

~OS ~FC Q>> E QT2 ~XPT3 V A L V E X Q4 ~P>> gJ QE' 7 8 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION QET LF RIRO REPRRT ACTION FUTURE EVENT YEAR

~79 21 22 EFFECT

~

23 SHUTDOWN

~02 24 REPORT NO.

4 26

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27

~01 28 ATTACHMENT CODE 29 NPRDA TYPE

~X 30 PRIME COMP.

~31

~1 32 NO.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LXJQTR~Bp>>

33 34 apso 35

~AQEE 36 37 0 O 4 7 40 41 Y Qss ~YQ24 42

~AQ25 43 44 A 2 O O C28!

47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o Backflow of refuelin water throu h BA tank outlet MOV's. Initiall manual valve in BA supply line was closed, sample fre uenc increased to ever 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Further investigation showed problem was eliminated when BA tank outlet MOV's 826 B 6 D were 3

c 1 osed and 8 26 A 5 C were opened . Inspection/maintenance of these va 1 ves (Aloyco 4 Inc. 8" 150 lb ss bolted bonnet gate) planned for annual refueling maintenance 7 8 9 80 FACILITY ~3O METHOD OF STATUS  % POWER OTHER STATUS PQ DISCOVERY DISCOVERY DESCRIPTION Q32 CE31 5 F Q28 ~00 10 3 Q28 NA 44

~BQ3'I S le Anal sis 8 9 12 13 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ3 LOCATION OF RELEASE Q6 8 ~Z Pss ~ZQ34 NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION A3 2 ~00 0 QET Z Q38 7 8 9 11 12 13 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION 43 Z Q42 7 8 9 10 80 o

ISSUED

~NQ44 PUBLICITY DESCRIPTION ~ NRC USE ONI.Y 7 8 9 10 68 69 80 o T. Schuler 716/546-2700 Ext. 291-206 NAME OF PREPARER PHDNE,

0 Attachment to LER 79-024/01X-1 Rochester Gas And Electric Corporation R.E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244 On December 17, 1979, at approximately 1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br /> the Shift Super-visor was notified of the chemical analysis which indicated that both the "A" and the "B" boric acid storage tanks contained 10.2% and 10.1% wt-%

boric acid solution respectively. An orderly power reduction was completed at 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br /> and batching operations were initiated to restore the tanks to the required specifications. On December 19 at approximately 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> the tanks were brought within specifications. To ensure proper sampling and recirculation without solution stratification additional samples were taken at several elevations inside the tanks. Analysis of all samples showed proper correlation with the normal samples. In addition, reagents used in the sample analysis were checked and found to be proper.

To check for the possibility of back flow of reactor makeup water from the reactor makeup water storage tank through the blender and the blender boric acid supply check valve, a manual valve in the boric acid supply line was closed. This was the same action which was taken for the event reported as LER 79-010. The tank sampling frequency was increased to once every twelve hours. Replacement of the suspect check valve with a more suitable style check valve and/or changing the logic of the automatic flow control valve to allow it to remain closed when not blending is currently being reviewed by the Engineering Department (EWR 2460) . It was decided that until such time as a new check valve can be procured and installed and/or the logic change for the flow control valve is provided, the manual valve would remain closed, except during blending.

It was soon determined that dilution was continuing, and further invest-igation indicated leakage from the EST through one of the closed boric acid tank outlet MOVs 826A or 826C. 'Ihe outlet MOVs 826B and D were closed and the MOVs 826A 6 C were opened. This was found to stabilize tank concentrations and indicated that the leakage had stopped. At this point it was no longer necessary to keep the boric acid supply manual valve open, and it has been opened. Sampling frequency has been decreased to once per day. Inspection and any needed maintenance of the boric acid tank outlet MOVs is planned for the 1980 Annual Refueling Maintenance Shutdown.

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