05000280/LER-1979-042-01, /01T-0:on 791220,as Result of Pipe Stress Reanalysis on Show Cause Lines Outside Containment,Support on Line 10 CC-143-121 Found to Be Overstressed Beyond 50% Ultimate Capacity.Cause Not Stated.Mod Completed

From kanterella
(Redirected from ML18136A353)
Jump to navigation Jump to search
/01T-0:on 791220,as Result of Pipe Stress Reanalysis on Show Cause Lines Outside Containment,Support on Line 10 CC-143-121 Found to Be Overstressed Beyond 50% Ultimate Capacity.Cause Not Stated.Mod Completed
ML18136A353
Person / Time
Site: Surry Dominion icon.png
Issue date: 01/02/1980
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18136A352 List:
References
LER-79-042-01T, LER-79-42-1T, NUDOCS 8001040554
Download: ML18136A353 (2)


LER-1979-042, /01T-0:on 791220,as Result of Pipe Stress Reanalysis on Show Cause Lines Outside Containment,Support on Line 10 CC-143-121 Found to Be Overstressed Beyond 50% Ultimate Capacity.Cause Not Stated.Mod Completed
Event date:
Report date:
2801979042R01 - NRC Website

text

111RCr011 IVl Sob

~---"-------

u. 3. nu'-".... cAH iiCQOCA I UH I ""'o.:;a.ytrssaol\\i (7-77)

  • ~ **

LICENSEE EVENT REPORT


C-O~TROL BLOCK: 1

.8 (PLEASE PRINT OR TYPE ALL.UIRED INFORMATION)

~1 _..____,__......___,__.......___.6

!IE]

7 8 I VI A I s I p I s I 1 101 ° I O, - I O I O I O I O I O I-IO I O 1014 11 11 11 11 101 I I 0 9

LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE

JO 57 CAT 58 CON'T

~

7 8

~~~~~~ LJ© I o I 5 I o I o I o 12 I s I o 101 11 21 2 I o I 71 9 I© I o I 1 I o I 21 s I o I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

1As a result of pipe stress reanalysis on show cause lines outside contairrnent, a

~

1 support on line lO"CX:::-143-121, Unit No. 2 supply to the Spent Fuel Pit Coolirg Heat

~

I Exchangers, was foun:l to be overstressed beyon:l 50 percent ultimate capacity. 'Ibis

~

I event is reportable in accordance with Tech. Spec. 6.6.2.a.9 an:l the NRC order liftirg I

[§))] I suspension of unit operation dated August 22, 1979.

'Ihe health am safety of the

[§JI] I pub! ic were not affected.

[£1))

7 8 9 [ill]

7 8

SYSTEM CODE 1w1B I@

9 10 LE R/RO CV ENT YEAR REPORT I 7 j 9 j NUMBER 21 22

CAUSE

CAUSE CODE SUBCODE COMPONENT CODE

~@ ~@ jS jUjP!OjRjT I@

11 L==l 23 12 13 SEQUENTIAL REPORT NO; I O 14 I 2 I 24 26 1/1 27 18 OCCURRENCE CODE IO 11 I 28 29 COMP.

SUBCODE LU 19 REPORT TYPE u 30 VALVE SUBCODE l!.J@

20 l=J 31 REVISION NO.

LQ_J 32 80 TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED ACTION FUTURE EFFECT SHUTDOWN ij ATTACHMENT L:_J@~ ~@ ~ I O I O I O I I ~@

NPRD-4 FORM SUB.

PRIME C.OMP.

SUPPLIER COMPONENT MANUFACTURER 33 34 35 36 3 7 40 41

~(§) ~@ 1x 19 !9 19 I@

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

42 43 44 1Stress analysis calculations revealed that initiai configuration of the hanger did ITJJ] 1not meet acceptance criteria. lVJodification to the support was canpleted based upon [II2],preliminary design drawings prior to final stress calculation.

OJI!

7 8

9 FACILITY STATUS

% POWER OTHER STATUS @

DISCOVERY DISCOVERY DESCRIPTION 32 47 80 [DI] ~@ I O I O I O 1@1...-I NA _____

METHOD OF

~

lEJ.... I _ARm

__ I_TECT' EN_G_I_NEER AN_AL_;YS_I ___

8 9

10 12 13 ACTIVITY CONTENT

~

RELiASED OF RELEASE AMOUNT OF ACTIVITY ~

~

~@) U@1-I _NA ______

7 8

9 10 11 7

45 46 44 NA LOCATION OF RELEASE @

80 44 45 80 PERSONNEL EXPOSURES r::;;,.

NUl)(lBER A

TYPE DESCRIPTION~

ITDJ j O I u IO Jl:J@L....-__

NA _____________________

7 8

9 11 12 13 80 PERSONNEL INJURIES

~

0 NUt,(1BE"1.,

DESCRIPTION 41 CQTI I I u 1° l@L....-________________________ __,

7 8

9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '43\\

TYPE

DESCRIPTION

i.::.::J QJIJ l:_j(§).._____NA ____________________ ~--~--~---'

7 8

9 10 PUBLICITY C\\

lr~r,'44\\ DES~TI01'J ~

~ 0 7

8 9

10 80 NRC USE ONLY 1111111111111~

68 69 (804) 357 :31S4 80* 0:

0 Cl.

Cl

~..,_.,...

--~-*

e SURRY I0\\1ER STATION, UNIT NO. 1 REPORI' NO:.

50-280 EVENT MJ:

79-042/0lT-O E\\ENT DATE: 12/20/79 TITLE OF REPORT:

Excess Stress on Pipe Harger, Line 10"-0:::-143-121

1.

IBSCRIPI'ION OF EVENT:

llirir:g the pipe stress analysis it was discovered that a rupport on line 10"-

CC-143-121 was overstressed am exceeded 50 percent ultimate capacity.

'lhe event is reportable in accordance with the NRC order liftir:g ruspension of operation dated August 22, 1979, an:l Technical Specification 6.6.2.a.9.

This CX: water rupply for the Spent Fuel Pit Coolers canes fran the discharge side of "C" an:l "D" Canponent Coolir:g Heat Exchangers.

A breach of the affected line could negate the use of these Heat Exchar:gers.

'Jhe health an:l safety of the public were not affected.

3.

CAUSE OF EVENT

The architect er:gineer encountered the problem while comuctir:g the pipe stress analysis precipitated by the NRC Show Cause Order.

4.

IM\\1EDIATE ffiRRECI'IVE ACTION:

Corrective act ion taken was to rmdi fy the rupport iri accordance with preliminary design drawir:gs.

'Ihe modi fica:tion was canpleted prior to identification of overstressed comitions.

5.

SUBSH2()Em' a:ERECTI\\E ACTION:

Since rrxxlifications have been In1de to eliminate the overstressed con:litions, no subsequent action is required.

6.

roruRE CDRRECT'I VE ACTION:

7.

Modifications wi 11 be ma.de to relieve any additional overstress con:li-tions identified.

GENERIC Il\\Il?LICATIONS:

Analysis contirues on both units to discern am rectify all overstressed corrli tions.