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

{{#Wiki_filter:NRC FORM 366 ' ... U.S. NUCLEAR REGULATORY COMMISSION '

• 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 0 I 0 I 0 I 0 I 0 I -I 0 I 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 [iliJ 7 B 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 CONSEQUENCES@

[[J]J I At 1823 hours 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 hours and 22 minutes. The Action Statement [[II] I was terminated at 2345 hours. 7 B 9 BO 7 B SYSTEM CODE le IF I@ 9 10 /;:;'\ LE RiRO CVENT YEAR \.!.!) REPORT I 8 11 I NUMBER 21 22 CAUSE CAUSE CODE SUBCODE COMPONENT CODE lli.J@ w@ lzlzlzlzlzlzl@ 11 12 13 18 SEQUENTIAL OCCURRENCE REPORT NO. CODE I I I o I o I s I I/ I I al 3 I 23 24 . 26 27 28 29 COMP. SUBCODE w@ 19 REPORT TYPE L!J 30 VALVE SUBCODE 1.!J@ 20 l=1 31 REVISION NO. L£.J 32 ACTION FUTURE TAKEN ACTION EFFECT SHUTDOWN r.;;;.. ATTACHMENT ON PLANT METHOD . HOURS SUBMITTED NPRD-4 FORM .PRIME COMP. SUPPLIER COMPONENT MANUFACTURER UJ@l.Ll@) , Ll..J@ W I o Io I o I o I W@ 33 34 35 36 37 40 41 L!Ll@) 42 I z I 9 I 9 I 9 I@ 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. rrm 7 8 9 80 FACILITY STATUS % POWER l.§J@ I ol al ol@I NA 7 B 9 10 12 ACTIVITY CONTENT t::;;\ RELEASED OF RELEASE AMOUNT OF ACTIVITY ITTIJ w @) LIJ@I NA . I 7 B 9 10 11 OTHER STATUS METHOD OF A DISCOVERY DISCOVERY DESCRIPTION

_________ _________________ __ 45 46 80 LOCATION OF RELEASE @ NA 45 BO PERSONNEL EXPOSURES f;;;;\ NUMBER (.;:;\TYPE DESCRIPTION EI?] I oJ ol gj0LJJ@I NA 7 B 9 11 12 PERSONNEL INJURIES Q NUMBER DESCRIPTION6 ETIJ I cl ol ol@ NA 7 B 9 111 LOSS OF OR DAMAGE TO FACILITY 143' TYPE DESCRIPTION '\:::J Em W@ NA 7 B 9 PUBLICITY Q\ ISSUED/,;';\ NRC USE ONLY ., ___________________________________________ I JI I I I I I I I I I 7 s e 10 8105190 1./37 w. J. Steele 6B 69 so NAMEOFPREPARER _____ ..;.___________________ PHONE: __ 6_0_9_-_9_3_5_-_0_9_9_8 _________}}