05000333/LER-1979-033-03, /03L-0 on 790524:during Review of Plant Sys, Determined That Reactor Bldg Cooling Sys Supply & Return Lines to Drywell Equipment Drain Sump Did Not Have Seismic Stress Analysis Performed.Uncertain If It Is Required

From kanterella
(Redirected from 05000333/LER-1979-033-03)
Jump to navigation Jump to search
/03L-0 on 790524:during Review of Plant Sys, Determined That Reactor Bldg Cooling Sys Supply & Return Lines to Drywell Equipment Drain Sump Did Not Have Seismic Stress Analysis Performed.Uncertain If It Is Required
ML19270H244
Person / Time
Site: FitzPatrick 
Issue date: 06/20/1979
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
ML19270H240 List:
References
LER-79-033-03L, LER-79-33-3L, NUDOCS 7906250277
Download: ML19270H244 (2)


LER-1979-033, /03L-0 on 790524:during Review of Plant Sys, Determined That Reactor Bldg Cooling Sys Supply & Return Lines to Drywell Equipment Drain Sump Did Not Have Seismic Stress Analysis Performed.Uncertain If It Is Required
Event date:
Report date:
3331979033R03 - NRC Website

text

..,

LICENSEE EVENT REPORT y

' CONTROL 8 LOCK: l l

l l

l l

l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i 6

10 t i l i N l Y l J ! A l F l 1 !@! n l n

!nlnlnlnl_ln!n!nlhl4 l1 l1 Il l1 lh!

l 7

8 9 LICENSEE CODE 14 15 LICENSE NUMBEH 25 26 LICENSE TYPE JO 57 CAT $8 C O*4* T

^

" ' Q' "' P. l@ 0 1 s ololo1313 3 !@l o i s 12 14 17 19 l@lo 612 lo 17 lo l@

O i

C I

8 60 61 DOCKET NUMBER 68 69 EVENT OATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 121 l Please See Attachment i

O 3 1

]

O 4

1 1

0 5

l 10161l O

7 l

0 s l I

80 7

8 9 DE CCDE SU8C E COMPONE NT CODE SUSC DE SU DE I W l B l@ g@ ]@ l Z l Zl Z l Z l Z l Z l@ l Z @ lZ @

O 9

7 8

9 10 11 12 13 18 19 20 SE QUE N TI AL OCCURRENCE REPORT REVISION LE R RO EVENT YE AR REPORT NO.

CODE TYPE NO.

@ gag; 17 19 I l-l Io 3 31 1/l IoIsI Ltj L-_]

Lo.J

_ 21 22 23 24 26 27 29 29 30 31 32 TAKE?

AC ON ON PLA T ET HOURS SB IT FOR b 8 SUPPLIER MANUFACTURER lx l@l xi@

l ZI@

LzJ8 lo l o o 01 Ly_]@

Nl@

Zl@

l2l9 9I9l@

33 34 3d 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1

O I

Please See Attachment I

lilil I

I l

i 1 131 l l

i 4

l l

7 8 9 80 STA S

% POWER OTHER STATUS ISCO RY DISCOVERY DESCRIPTION lGl@ lol0lolh!

NA l

Cl@l Bulletin 79-02 Investigation i

5 ACTIVITY CONTENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA l

l 9

l 1

6 1

8 9 10 11 44 45 80 PERSONNEL E XPOSURES l o l o l o l@l 2 l@ DESCRIPTION -

NUMBE R TYPE NA l

i 7

PERSONNe'< i~;u' RIES DESCn, prion @

NUvuR lo lo lo l@l NA i

a 7

8 9 11 12 80 LOSStF OR DAVAGs TO FACILITY 2238 258 i

TYPE D E SCRIP TION LZj@l NA i o 7

8 9 10 80 PUBLIC ;,YCRIPTION @

79062509-77 NRC Use oNov d

@l NA l

llllll llIll I

7 8 9 10 68 69 80 &

315-342-3840 E

NAME OC PREPARER

POWER ALTTHORITY OF Tile STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLAKr DOCKET NO. 50-333 ATTACHMENT TO LER 79-033/03L-0 Page 1

of 1

While in a cold shutdown condition, during the conduct of a review of plant systems 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. At this time it has not been determined, with certainty, if a seismic stress analysis is re-quired for the 1 1/2" Cooling Water Supply and Return Lines associated with the sump cooler.

If the investigation indicates that a seismic analysis should have been performed this event will be an example of failure to implement administrative or procedural instructions that are required by Technical Specification Appendix A, Paragraph 6.9.A.4.2.c.

When the investigation has been completed a follow-up to this interim report will be submitted.

2238 259 d