05000293/LER-1981-001-03, /03L-0:on 801226,unidentified Drywell Leakage Measured at Rate Contrary to Tech Specs.Cause Not Known Excessive Leakage Eliminated by Backstating B Recirculation Pump Suction Valve Mo 202-4B & Discharge Valve Mo 202-5B

/03L-0:on 801226,unidentified Drywell Leakage Measured at Rate Contrary to Tech Specs.Cause Not Known Excessive Leakage Eliminated by Backstating B Recirculation Pump Suction Valve Mo 202-4B & Discharge Valve Mo 202-5B

ML20003B123
Person / Time
Site:	Pilgrim
Issue date:	02/03/1981
From:	Mcloughlin M BOSTON EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20003B119	List: 05000293/LER-1981-001, Forwards LER 81-001/03L-0 05000293/LER-1981-001-03, /03L-0:on 801226,unidentified Drywell Leakage Measured at Rate Contrary to Tech Specs.Cause Not Known Excessive Leakage Eliminated by Backstating B Recirculation Pump Suction Valve Mo 202-4B & Discharge Valve Mo 202-5B
References
LER-81-001-03L, LER-81-1-3L, NUDOCS 8102100379
Download: ML20003B123 (1)

LER-1981-001, /03L-0:on 801226,unidentified Drywell Leakage Measured at Rate Contrary to Tech Specs.Cause Not Known Excessive Leakage Eliminated by Backstating B Recirculation Pump Suction Valve Mo 202-4B & Discharge Valve Mo 202-5B

Event date:
Report date:
2931981001R03 - NRC Website

text

(7 77)

LICENSEE EVENT REPORT CONTOOL BLOCK: I I

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l l lh CrLEASE PRINT C2 TYPE ALL CE!UIRED INFCCMATl!N) i e

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8 60 61 OOCKET NUMBER 68 69 EVENT OATE 74 7S REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O 2 !

On December 26. 1980 at approximate 1v 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />. unidentified drvwell lenkage 1

[ O"TT] l rate was measured as 8.7 gpm.

Tech Spec requires that the reactor be in cold i

10 l 4 ! I shutdown condition within 24 hrs. af ter unidentified reactor coolant lenknge rneo I

lo Isl l into primary containment exceeds 5 gpm.

Operating personnel immediatelv initiated l

l 1016 l l a reactor shutdown and notified the NRC Onerneinnn concor_

Tha lonknco t.in a l o 17 l l reduced and the reactor returned to 100 nercent never ne nnnrnvf-nen1v 1600 knura I

[ 0181 l the same day.

I 80 7

8 9 OE CODE SUSC E COMPONENT CODE SUSCOO'E S

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10 11 12 13 18 19 20 SEQUEN TI AL OCCURRENCE REPORT REVISION LE R EVENT YE AR REPORT NO.

CODE TYPE N O,

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CAUSE DESCRIPTION AND CORRECTIVE ACTION 3 11 10 l l Operations personnel by backseatine the "B" Recirculation Pu-n Suction Valve I

i i l FO 202-4B and Discharge Valve MD 202-5B eliminated rhn ovcnaafva lanknea-A I

11 #2i l check of the "B" Recirculation Pumps valve's packine hns been scheduled for rho I

yl next planned outage, which requires drvwell entry.

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L.$ L4_J l 80 7

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% POWER OTHER STATUS DIS O RY OtSC'OVERY DESCRIPTION NA l

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' JT,ViTY COaTENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE i

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8 9 10 13 44 45 80 PERSONNEL EXPOSURES FiTil in In In l@lzJ@ DESCRIPTION NUM8ER TYPE l

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,ERSO~NEtiN;ubS DESCRi,TiO~@

NUMBER NA l

l01010 l@l i s 7

8 9 11 12

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80 LOSS OF OR OAMAGE TO FACILITY TYPE

DESCRIPTION

Li LJ LzJ@l NA' l

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8 9 10 80 L2.J.oj LdUE @OE CRIPTION ISS l

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