ML18086A523

LER 81-005/03L-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

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: ML18086A519 ML18086A523
References
LER-81-005-03L, LER-81-5-3L, NUDOCS 8105190437
Download: ML18086A523 (1)

Text

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 11-111~ ' ...

• LICENSEE EVENT REPORT

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

[}TI IN I J Is I G Is 12 10l 0 I 0 I -I 0I 0I 0I 0I 0I - I 0I 0101 4 I l I 1 I l I 1101 I I© 7 B 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

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=~~~~~ UJ© I oI 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 oI 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 />.

7 B 9 BO SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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7 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

/;:;'\ LE RiRO CVENT YEAR REPORT NO. CODE TYPE NO.

\.!.!) REPORT NUMBER I 11 I 8 I I I o IoI sI I /I I al 3 I L!J l=1 L£.J 21 22 23 24 . 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN r.;;;.. ATTACHMENT NPRD-4 .PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD . HOURS ~ SUBMITTED FORM ~us. SUPPLIER MANUFACTURER UJ@l.Ll@) , Ll..J@

33 34 35 W

36 37 I o Io I oI o40I 41W@ L!Ll@) ~@ I z I 9 I 9 I 9 I@

42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

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.

7 rrm 8 9 80 FACILITY METHOD OF A STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

~ l.§J@ 10I ol al ol@I NA ~@)_I _________N~/_A___________________

7 B 9 12 1-1'.3-----'-'-----44~

45 46 80 ACTIVITY CONTENT t::;;\

AMOUNT OF ACTIVITY ~ @

ITTIJ 7 B w @) LIJ@I RELEASED OF RELEASE 9 10 11 NA . I 45 NA LOCATION OF RELEASE BO PERSONNEL EXPOSURES f;;;;\

NUMBER (.;:;\TYPE DESCRIPTION EI?]

7 B 9 I oJ ol gj0LJJ@I 11 12 NA 1-3--""~----------------------------------------------------80 PERSONNEL INJURIES Q NUMBER DESCRIPTION6 ETIJ 7 B I9 cl ol 1 ol@11 NA

-~~-------------------------------------------------------------80 LOSS OF OR DAMAGE TO FACILITY 143' TYPE DESCRIPTION '\:::J Em W@

7 B 9 NA 1~0~--=-=---------------------------------------------------------------------8~0 PUBLICITY Q\

ISSUED/,;';\ DESCRIPTION~ NRC USE ONLY .,

~ UU~--~N=A.:..____________________________________________~ I JI I I I I I I I I I I~

7 s e 10 8105190 1./37 NAMEOFPREPARER _____..;.___________________

w. J. Steele PHONE: __

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