ML18081A672

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Updated LER 79-054/01X-1:on 790824,three Snubbers on Main Feedwater 14 During Refueling Outage Per Followup to NRC Insp Rept 50-311/79-19.Caused by Extreme Shock Load.Snubbers Replaced
ML18081A672
Person / Time
Site: Salem PSEG icon.png
Issue date: 11/10/1979
From: Kapple A
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18081A671 List:
References
LER-79-054-01X, LER-79-54-1X, NUDOCS 7912040395
Download: ML18081A672 (1)


Text


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  • NRC FORM '365 - UP~ATE REPORT - p'Ot:A.us REPORT DATE 9 /7 /7 9 .NUCLEAR REGULATURY COMMISSION 17-771 ~~

LICENSEE EVENT REPORT CONTROL BLOCK: I I 11(!) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 (ITl] I N !J I s I G I s I 1 IG)l o I. oI -1 o I o I oI o I o I - I o I o 101 4 I 1 I l I 1 I l 101 I I G) 7 8 9 L.ICENSEE COOE 1-4 15 L.ICENSE NUMBER 25 26 L.ICENSE TYPE ;JO 57 CAT SS CON'T lIIT1 7 8

~~~~~ LlJG) 1*o I *s I *o I o I *o I 2 I 60 61 DOCKET NUMBER 7 I 2 GI o 1*s I 2 I 4 1 7 l 9 68 69 EVENT CATE I© I 1 11 74 75 tL *I o I 1 I 9 10 REPORT CATE 80 EVENT. OESCRIPT10N ANO PROBABLE CONSEOUENCes@)

!During the refueling outage, as follow-up to NRC Inspection 50-311/79-19, three

(]l!J tsnubbers on No. 14 Main Feedwater were found to have failed. These_ snubbers were

[Q:rrl f included in the stress calculations for the seismic safety analysis of the nuclear

[))!] !Portion of the main feed water piping. Stress calculations indicated the increase I.

[]Jr) lin stress in the piping is small and remains well below the allowable stress rIIZJ llimit. Seismic stresses would not be affected as the snubbers would be locked

())]J !under that condition. .,

7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE cooE CODE suBCODE COMPONENT CODE suscooE SUBCOOE

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  • 7 8 9 10 '1 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

/;':;\ L.ER!RO LVENTYEAR REPORT NO. . CODE TYPE NC.

\:.:.J NUMBER REPORT I I I 7 9 I I Io ls 14 I 1......-1 Io I 1 I W bl UJ 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN t.;::;\ ATTACHMENT NPRD--4 PRIME COMP. COMPONENT TAKEN . ACTION. ON PL.ANT METHOD HOURS ~ SUBMITTED FORM :;us. SUPPLIER MANUFACTURER 1£.J@l.K.J@

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CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @

jThe failure of the snubbers appears to be an extreme shock load or occurred when o::DJ tthe snubber was in the fully retracted condition. The snubbers were replaced in kindj o::IiJ I and corresponding snubbers on No~ 11, 12 and 13. lines were checked satisfactory *

.OJI) I I.nstrumentation will be installed to measure and record acceleration and linear

[!I!J !displacement of the piping at the snubber location.

7 8 9 BO FACILITY IJQ\ METHOD OF (.;;\

STATUS. 1' POWER O'ER STATU.S \;;:::/ DISCOVERY DISCOVERY DE$Cl'lll"fl0N ~

ITlIJ L£J@) I 0 I O! 0 l@I N/A I 1..£.J@I Follow-Up to NRC Inspection 7 8 9 ' 10 12 1'3 "" 45 46 BO ACTIVITY CONT£NT ~

  • . RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ . LOCATION OF REL.EASE @

OJI] l.!J@ l!J@I N/A I

  • N/A 1 a s 10 11 80 PERSONNEL EXPOSURES t::::-.. .~

NUMBER ~TYPE~ DESCRIPTION~

ITIIJ J oI o I o l~W~l~_ _N_._/_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____,

7 B 9 11 12 13 BO PERSONNEL. INJURIES I'.:':\

DESCRIPTION~

ITTIJ lololol@)...____~N-....-A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~

NUMBER 7 8 SI tt 12 BO L.OSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION 1.i3'

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7 9

. N A 1~0-----------------------------------------------------------------------------------'

90 PUBLICITY C\ E ISSUEOC,;'\ DESCRIPTION~ NRC US ONL y filEJ Lz.J~A _________ N.....

/A...___ _ _ _ _ _ _ _ _ _ _ _ ___, I I I 11 I I I I I I I I 7 8 SI 10 68 69 80 NAMEOFPREPARER _________ A__*__w__._;,_K_a~p~p~l_e____~~~ PHONE:-........--.-..--............-...._..-=--..-.-..,.,.

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