05000311/LER-1981-005-03, /03L-0:on 810413,all Reactor Coolant & Residual Heat Removal Pumps Were de-energized Longer than Time Allowed by Tech Specs.Caused by Replacement of Relief Valve 2RH3 in Residual Heat Removal Sys

/03L-0:on 810413,all Reactor Coolant & Residual Heat Removal Pumps Were de-energized Longer than Time Allowed by Tech Specs.Caused by Replacement of Relief Valve 2RH3 in Residual Heat Removal Sys

ML18086A523
Person / Time
Site:	Salem
Issue date:	05/11/1981
From:	Steele W Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18086A520	List: 05000311/LER-1981-005, Forwards LER 81-005/03L-0.Detailed Event Analysis Encl 05000311/LER-1981-005-03, /03L-0:on 810413,all Reactor Coolant & Residual Heat Removal Pumps Were de-energized Longer than Time Allowed by Tech Specs.Caused by Replacement of Relief Valve 2RH3 in Residual Heat Removal Sys
References
LER-81-005-03L, LER-81-5-3L, NUDOCS 8105190437
Download: ML18086A523 (1)

LER-1981-005, /03L-0:on 810413,all Reactor Coolant & Residual Heat Removal Pumps Were de-energized Longer than Time Allowed by Tech Specs.Caused by Replacement of Relief Valve 2RH3 in Residual Heat Removal Sys

Event date:
Report date:
3111981005R03 - NRC Website

text

NRC FORM 366 11-111~

U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK:._I _..___._

_ _._____.l'---_.l.__-!!10 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

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LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T [iliJ 7

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=~~~~~ UJ© I o I s 1 o I o I o I 3 I 1 I 1 101 o I 4 I 1 I 3 I 0 I 1 KV I o I s 11 I 1 I a I 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABL~ CONSEQUENCES@

((J]J I At 1823 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.936515e-4 months <br /> on April 13, 1981, Action Statement 3.4.1.1.b.2.b was entered

~

I because all Reactor Coolant and Residual Heat Removal Pumps were de-energized

((II]

to facilitate the replacement of relief valve 2RH3 in the Residual Heat Removal System.

Technical Specifications allow for all these pumps to be de-energized for up to one hour.

The task of replacing 2RH3 and returning the Residual Heat

~

I Removal System to operation required 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 22 minutes.

The Action Statement

((II] I was terminated at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />.

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SYSTEM CODE le IF I@

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20 l=1 31 REVISION NO.

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ATTACHMENT ON PLANT METHOD HOURS ~ SUBMITTED NPRD-4 FORM ~us.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

43 44 47 DJ)) I The time allowed by Technical Specifications for all the pumps to be de-energized was not sufficient for the completion of the task of replacing 2RH3 and returning the system to operation.

PSE&G feels that this particular event warrants no

£III] f specific corrective action.

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80 FACILITY STATUS

% POWER

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ACTIVITY CONTENT t::;;\\

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10 11 OTHER STATUS METHOD OF A

DISCOVERY DISCOVERY DESCRIPTION

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NUMBER

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DESCRIPTION

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11 12 1-3--""~----------------------------------------------------80 PERSONNEL INJURIES Q

NUMBER DESCRIPTION6 ETIJ I cl ol ol@

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B 9 111 -~~-------------------------------------------------------------80 LOSS OF OR DAMAGE TO FACILITY 143' TYPE

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NRC USE ONLY

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NAMEOFPREPARER _____..;.___________________

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