ML19253A987

LER 79-033/03X-1:on 790524,during Plant Sys Review,Noted That Seismic Stress Analysis Not Performed for Reactor Bldg Cooling Sys Supply & Return Lines to Drywell Sump.Caused by Failure to Implement Procedural Instructions

ML19253A987
Person / Time
Site:	FitzPatrick
Issue date:	09/11/1979
From:	W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19253A986	List: ML19253A985 ML19253A987
References
LER-79-033-03X, LER-79-33-3X, NUDOCS 7909140304
Download: ML19253A987 (2)

Text

. . . . .

LICENSEE EVENT REPORT

, CONTROL BLoCie l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 o i 8 9 lN lY lJ lA lF 'l l@l0 l0l- 0l0l0l0l-l0l0l0l@l4 1l1l1l1 @l57 CATl 58lg LICENSEE CODE 14 15 LICENSE NLYtlEH 25 26 LICENSE TYPE JO CON'T I

0 1 8

$RCE "

60 II hl 0l 5 j 0 [ 0 l 0 l 3 l 3 l 3 @l 0 l 5 2l4l7l9l@l0l9l1l1l7l9l@

61 DOCKET NUY8ER t>d 63 EVENT DATE 74 75 REPORT D ATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l Please See Attachment l 0 3 I l 0 4 l l O 5 l l 0 16 l l 7  ! I O a L '

l 7 8 9 80 SYSTEV CAUSE CAUSE COYP.

CCDE VALVE CODE SUSCODE COYPONE NT CODE SUBCOOE SUER 0DE 7

O 9 8

lN blh 9 10 11

@ l5 l@ lZlZlZlZlZlZlQ 12 13 18 13 20 l 9l@

_ SEOU E NTI A L OCCURRENCE REFORT REVISION LE R RO EVENTTEAR REPORTNO COOE TYPE NO.

@ REP m

_ 21 l7l9l 22 l _._ l 23 l0l3l3l 24 26 lg l0 l3 l Xl l_l l1 l 27 23 23 30 31 32 A E ACTO O PLANT iT HOURS S B IT D FO N5 8. SUPPLIE MAN FACTURER d@d@ d@

33 J4 35 l36Z l@ l0l0l0l0l 3/ 40 l Y l@

41 lN @

42 l43Z l@ l Z l 9 l 9 l 947l@

44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h

, g Please See Attachment

[ j li lil l 1 1

l It l 3J l i

4] I I 7 3 9 80 F ACit TTY YE THOD OF STATUS *.POWER CTHER STATUS CISCOVERY DISCOVERY DESCRIPTION li B G l@ l0 l 0 0lg NA l Clgl Bulletin 79-02 Investi ion l

' ' 12 n 44 45 46 80 ACTiviry cod rE NT RRE ASED OF RRUSE i

AYOUNT NA OF ACTIVITY @ NA lLOCATION OF RELEASE @

1 o8 ! l Z l @ LZJ@

'd 10 ti 44 l

45 l

i 80 NHSONNEL EXPOSURES O ' f'O ; C NUYBER TYPE DESCRIPTION I !I q

- i i 7 l0l0l0l@jZl@[ '

A J - ' Wl d u l PERSONN[LINJ ES f ,j'j!/,\

NUvefa cESCRIPTION Q' llC , r; i! *'( l jm ,I i a l0l0 0[@l NA dl ) L.'L. J & J ULj ud b 7 8 9 11 12 go

'T$5,

' " ' ' '^c"

"cs^c%^PTON @ NA 7 9 0914 030$

l'l9 7 8 9 l lShl 10 l

' 80 NRC USE ONLY g n Jg.(,y;b l ,9 ,

i 2 o a 3 issuf lNl 10 o@l DES mPTION @ NA llllll[;;;;;lj 68 69 80 &

NAVE OF PREPARER PHONE: 315-342-3840

POWER AITril0RITY OF Ti!E STATE OF NEW 10RK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACIBENT TO LER 79-033/03X-1 Page 1 of 1 While in a cold shutdown condition, during the conduct of a review of plant sys. ems to satisfy the requirement of NRC Bulletin 79-02, it was determined that the Reactor Building Cooling System Supply and Return Lines to the Drywell Equip-ment Drain Sump did not have a seismic stress analysis performed. Investigation indicated that a seismic analysis should have been performed, thus the event is an exr gle of failure to implement administrative or procedural instructions that are required by Technical Specification Appendix A, Paragraph 6.9. A.4.2.c.

Re-analysis of the supply and return lines, including those branches which were added as part of a modification to replace the original cooler in 1978, has been completed. The analysis included cooler nozzle loading, thermal and dead load stresses in addition to seismic stresses and revealed that the existing design configuration is acceptable without modification to either the lines or supports. In view of these findings the event did not represent any hazard to the public health and safety.

NOTE: Revision 1 of this LER is submitted to reflect the completion of the re-analysis. Items 9,17,19 and this attachment have been revised.

343094

-- - .. -