05000293/LER-1981-005-03, /03L-0:on 810202,unidentified Reactor Drywell Coolant Leakage Rates Measured Above Tech Spec Level.Cause Not Stated.Recirculation Pump Suction Valves a & B & Discharge Valves Backseated

/03L-0:on 810202,unidentified Reactor Drywell Coolant Leakage Rates Measured Above Tech Spec Level.Cause Not Stated.Recirculation Pump Suction Valves a & B & Discharge Valves Backseated

ML20003C674
Person / Time
Site:	Pilgrim
Issue date:	03/02/1981
From:	Mcloughlin M BOSTON EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20003C672	List: 05000293/LER-1981-005, Forwards LER 81-005/03L-0 05000293/LER-1981-005-03, /03L-0:on 810202,unidentified Reactor Drywell Coolant Leakage Rates Measured Above Tech Spec Level.Cause Not Stated.Recirculation Pump Suction Valves a & B & Discharge Valves Backseated
References
LER-81-005-03L, LER-81-5-3L, NUDOCS 8103090523
Download: ML20003C674 (1)

LER-1981-005, /03L-0:on 810202,unidentified Reactor Drywell Coolant Leakage Rates Measured Above Tech Spec Level.Cause Not Stated.Recirculation Pump Suction Valves a & B & Discharge Valves Backseated

Event date:
Report date:
2931981005R03 - NRC Website

text

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSl!N

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(7 77) V LICENSEE EVENT REPORT I

CONTR6L BLOCK: l l

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lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATiONI 1

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60 61 DOCKET NUMBE R 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l o 121 l On February 2, 1981 at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, and again on Februarv 23, 1981 at 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> un-1 Io lai l identified drywell leakage rates were measured as 8.7 gpm and 9.7 gpm, respectively. l l o 14 l l Tech. Specs. requires that the reactor be in cold shutdown condition within 24 hrs.

l 1o isi l after unidentified reactor coolant leakage rate into primary containment exceeds 5 l

lo is l l gp m.

Operating personnel icmediately initiated reactor shutdowns and notified the I

l o l 7 l l NRC Operations Center. The leakage was reduced to within permitted limits within l

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for both incidences and the reactor returned to steady state power levels.

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'B' Recirculation Pump Suction Valves l

1il,l l and Discharge Valves eliminated the excessive leakaee on both occasions. On Februarv I l 23 a drywell entry was conducted at thirty (30) percent power to identify the leak.

l g One of recirculation system's Talves has bdn repacked with preformed packing.

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g l remaining three will be. similarly repacked prior to startup following the current outajge.

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% POWER OTHER STATUS DIS RY DISCOV ERY DESCRIPTION N.A.

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I115 l d@ l0 l 7 l 5 l@l A TIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE N.A.

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l l t i 6 l l Z l @ l Z l@l PERSONNEL EXPOS ES NUMBER TYPE

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PERSONNE L INJURIES NUMBER

DESCRIPTION

N.A.

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3 9 11 12 80 LOSS OF OR DAM AGE'TO FACILITY TYPE

DESCRIPTION

li 191 l Zl@l N.A.

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8 9 10 80 PUBLICITY NRC USE ONLY l 2 l o l jSKg 8108 09 o 5 a3 N.A.

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8 9 10 M. Thomas McLoushlin 617-746-7900