05000293/LER-1985-001, :on 850101,reactor Shut Down Due to Inoperable Standby Liquid Control Sys (Slcs).Caused by Debris in SLCS Storage Tank & Test Tank.Slcs Components & Sys Cleaned.W/

:on 850101,reactor Shut Down Due to Inoperable Standby Liquid Control Sys (Slcs).Caused by Debris in SLCS Storage Tank & Test Tank.Slcs Components & Sys Cleaned.W/

ML20106A140
Person / Time
Site:	Pilgrim
Issue date:	01/30/1985
From:	Hamilton P, Harrington W BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
85-021, 85-21, LER-85-001, LER-85-1, NUDOCS 8502110052
Download: ML20106A140 (3)

LER-1985-001, on 850101,reactor Shut Down Due to Inoperable Standby Liquid Control Sys (Slcs).Caused by Debris in SLCS Storage Tank & Test Tank.Slcs Components & Sys Cleaned.W/

Event date:
Report date:
2931985001R00 - NRC Website

text

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APPsIOVE3 OMS No. 3190-T104

• • • 'REs; st3ms LICENSEE EVENT REPORT (LER)

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NAME TELEPHONE NUMSER

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Paul J. Hamilton - Senior Plant Engineer 6:1 7 74,6 i 7,90,0 i

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I On 1/1/85, a reactor shutdown was completed due to an inoperable Standby Liquid Control System (SLCS).

Cause of the inoperable system was debris in the SLCS storage tank and test tank. Corrective action was to clean and/or flush the SLCS components and systems.

In addition, the cover for the test tank was reinstalled with locking mechanisms and the cover for the main tank bolted in place.

This event did not impact the health and safety of the public.

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.m a nco m ew nn On 1/1/85, during post-refuel startup testing, the Standby Liquid Control System (SLCS) was declared inoperable. The reactor, which was at approximately 22% power, was brought to the cold shutdown condition in accordance with the requirements of Technical Specificatien (T.S.) Section 3.4.0.

The problem was discovered when the "A" SLCS relief valve lifted low (approximately 600 psi vs. a 1425 psi setpoint) during normal surveillance testing of the SLCS. The redundant "B" SLCS was then tested and, although the "B" train met T.S. flow requirements, it was declared inoperable when debris was observed to be floating in both the main and test SLCS tanks.

Corrective action was to drain, clean, and inspect both tanks. The "A" relief valve which had lifted low during the surveillance was bench tested several times and lifted at the required setpoint.

Cause of "A" relief valve lifting low is unknown.

The "B" relief valve which had lifted within specification but lower than its setpoint was found with pieces of rubber glove between the blowdown adjusting orifice and plunger. The pieces of glove were removed and the valve reassembled. Various check valves were inspected for blockage and none was found.

In addition to these visual inspections of some components' internals, the SLCS was air-blown and/or flushed in sub-sections in order to verify that the debris had been cleared from the process system. The SLCS surveillance was successfully completed on 1/5/85.

An investigation was initiated to determine why the debris, which included rubber gloves and masking tape, was in the tanks.

T' investigation found that both the test tank cover and the main tark manwt were open at certain times during the recently completed recirculation pipe replacement and refuel outage.

It is postulated that some time during the outage, the debris either fell or was thrown into the tanks.

Long-term corrective action was to reinstall the test tank cover with locking mechanisms and bolt the manway cover to the top of the main tank.

This event did not impact the health and safety of the public. A search of records indicates that this was an isolated event.

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EOSTON EOisON COMPANY 800 SOYLETON STREET BDaTON. MAmeAcHUSETTa 02199 WILLIAM D. HARRINGTON

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January 3Q 1985 BECo Ltr. #85- 021 Document Control Desk U.S. Nuclear Regulatory Commission-Washington, D.C. 20555 Docket Number 50-293 License DPR-35

Dear Sir:

The attached Licensee Event Report 85-001-00, " Standby Liquid Control System Inoperable," is hereby submitted in accordance with the requirements of 10CFR50.73.

If there are any questions on this subject, please do not hesitate to contact me.

Respectfully submitted, W. D. riarrington PH: caw Enclosure: LER 85-001-00 cc: Dr. Thomas-E. Murley Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Standard BECo LER Distribution f

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