ML18082B347: Difference between revisions

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{{Adams
#REDIRECT [[05000272/LER-1980-052-03, /03L-0:on 800910,record Review Prior to Reactor Startup Revealed Required Inservice Insp Surveillance of Valves Had Not Been Completed During Previous Reactor Shutdown.Caused by Improper Surveillance Scheduling]]
| number = ML18082B347
| issue date = 10/10/1980
| title = LER 80-052/03L-0:on 800910,record Review Prior to Reactor Startup Revealed Required Inservice Insp Surveillance of Valves Had Not Been Completed During Previous Reactor Shutdown.Caused by Improper Surveillance Scheduling
| author name = Randolph J
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| docket = 05000272
| license number =
| contact person =
| document report number = LER-80-052-03L, LER-80-52-3L, NUDOCS 8010200592
| package number = ML18082B345
| document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT
| page count = 1
}}
 
=Text=
{{#Wiki_filter:.. 17-771
* LICENSEE EVENT REPORT e CONTROL BLOCK: I I. 10 1 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!
[il:I] IN I J Is I G*I sl l 101 o I o I. o I o I o IO I o I -I o I o IG)l4 I i I l I i I l l©I I I@ 7 8 9 LICENSEE cone 14 15 . LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T [ITJJ 7 8 UJ©I ol s I o Io I o I 2 I 1 I 2 GI o I 9 I i I o I 0 I o 1@11 I o 11 I o I a I o 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT CATE BO EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES
@ * . /During a record.review in preparation for a reactor startup, it was determined that ' [[]]] !the required inservice inspection surveillance of valves per Technical Specification . I . !4.0.S had not been completed, as required at the previous reactor shutdown.
Similar []]!] 1occurrences include 76-03, 78-21, 78-81, 80-10 and 80-33. . J um 7 8 9 SYSTEM CAUSE CAUSE COMP. V.C.LVE CODE CODE SUSCODE COMPONENT CODE SUBCOOE SUBCOOE rim 1z 1z 1@ 1£.J@ w@ 1v IA IL 1v IE 1x 1e Ll.J@ w 7 B 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT t::;\ LE R RO *cVENT YEAR REP.ORT NO. CODE TYPE *"-.:.JRePoRr I0lol I*! lolsl2! I/I lo 13 I W 1-1 NUMBEFI 21 22 23 24 26 27 28 29 30 31 . ACTION FUTURE EFFECT SHUTDOWlll
/::;':;\ ATTACHMENT NPRD-4 PRIME COMP. REVISION NC. LQJ 32 COMPONENT MANUFACTURER 80 TAKE'.; ACTION ON PLANT METHOO HOURS SUBMITTED FORM ::.uB. SUPPLIER E...J@W@ W@ W I o Io I 0.1 o I L!J@ L!J@ 33 34 35 36 37 40 41 42 43 I z 19 19 19 I@ CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ .. 47 *o::Ir]* !The surveillance is scheduled on a calendar basis and does not accommodate the II:DJ jcontingency of a reactor shutdown.
The surveillance was completed and an on-the-spot rrm !Change issued to Operating Ins'!:rUction*
I-3.3, Hot Standby to Minimum Load, to add this OJiJ jsurveillance to the mode change checklist.
lilil 7 8 9 FACILITY l3Q\ STATUS '!GPOWER OTHERSTATUS ITJII I 0 I 0 I 0 l@l....._
__ N.._/A ___ , 7. B 9 10 12 l'l 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY QJI] L!.I  L!J@I N/A 7 8 9 10 It PERSONNEL EXPOSURES t::;::<., 80 DISCOVERY DISCOVERY DESCRIPTION 32 METHOD OF
___________
_________
_. 45 46 LOCATION OF RELEASE @) N/A 80 BO NUMBER DESCRIPTION rrrn 1 a 1 o 1 a
_____ , B 9 11 12 13 . BO PERSONNEL INJURIES t:&deg;:\ NUMBER IT:GJ I 0 I 0 I 0 I@ . N A 7 8 9 11 __ .._ ________ ....,:::..,:;:_
__________
_... ______________________________
Loss OF OR OAMAGE TO FACILITY '43' TVPE DESCRIPTION ITI2J
___ 7 B 9 10 .SO PUBLICITY
(.:\ NRC USE ONLY "' ISSUEOc:;\
OESCRIPTION . NA I I I I I I I I I I I I I 7 8 9 10. J. M. Randolph (j 010200 !s'I PHONE: 68 &9 80 "* 609-935-0998 .;. -----___________________________________________
_J}}

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