05000311/LER-1981-040-03, /03L-0:on 810609,investigation Revealed Leak in RCS Chemical & Vol Control Sys at Weld for Vent Valve 2CV396.Caused by Excess Vibration & Pressure Transient.Valve Removed & Vent Line Capped

/03L-0:on 810609,investigation Revealed Leak in RCS Chemical & Vol Control Sys at Weld for Vent Valve 2CV396.Caused by Excess Vibration & Pressure Transient.Valve Removed & Vent Line Capped

ML20009G004
Person / Time
Site:	Salem
Issue date:	07/09/1981
From:	Espey J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20009G002	List: 05000311/LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl 05000311/LER-1981-040-03, /03L-0:on 810609,investigation Revealed Leak in RCS Chemical & Vol Control Sys at Weld for Vent Valve 2CV396.Caused by Excess Vibration & Pressure Transient.Valve Removed & Vent Line Capped
References
LER-81-040-03L-01, LER-81-40-3L-1, NUDOCS 8108030229
Download: ML20009G004 (1)

LER-1981-040, /03L-0:on 810609,investigation Revealed Leak in RCS Chemical & Vol Control Sys at Weld for Vent Valve 2CV396.Caused by Excess Vibration & Pressure Transient.Valve Removed & Vent Line Capped

Event date:
Report date:
3111981040R03 - NRC Website

text

__

O O

Report Number:

81-40/03L Report Date:

July 9, 1981 Occurrence Date:

6-9-81 Facility:

Salem Generating Station, Unit 2 Public Service Electric & Gas Company l

Hancocks Br' age, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Chemical and Volume Control System Letdown Line Weld Failure.

This report was initiated by Incident Report 81-186.

CONDITIONS PRIOR TO OCCURRENCE:

Made 3 - Rx Power 0% - Unit Load 0 MWe DESCRIPTION OF OCCURRENCE:

At 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br />, June 9, 1981, the Chemical and Volume Control System letdown line was isolated due to closure of letdown isolation valve 2CV7 for unknown reasons.

The closure of 2CV7 caused the pressure in the letdown line to increase to the lift setting of safety valve 2CV6 (600 psig).

In the Control Room alarms were received for Containment Sump Pump start, Containment Sump overflow and Pressurizer Relief Tank high pressure.

It was apparent there was a leak on the letdown line in containment.

A containment entry was initiated to investigate 'he c

l source of leakage on the letdown line.

The investigation revealed the l

weld at vent valve 2CV396 had failed.

Approximately 3000 gallons of coolant was released to the containment due to the weld failure.

There was no release of radioactivity exterior to the containment.

Action Statement 3.4.7.2.b was entered at 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br />.

This constituted operation in a degraded mode in accordance with Technical Specification 6.9.1.9.d.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Equipment failure.

The combination of excessive vibration and the pressure transient caused the weld at 2CV396 to fail.

ANALYSIS OF OCCURRENCE:

Technical Specification 3.4.7.2.b requires that with any Reactor Coolant System leakage greater than the limits specified, excluding pressure i

i boundary leakage and leakage from Reactor Coolant System pressure i

isolation valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shut-down within the followint 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

8108030229 810709 DR ADOCK 05000311 PDR a

pV,

)

v LER 81-40/03L July 9, 1981

CORRECTIVE ACTION

After the leak was isolated by isolating the letdown system; 2CV396 was removed and the vent line was capoed off with a welded pipe cap.

The weld was inspected with satisfactory results and the letdown system was returned to service.

Action Statement 3.4.7.2.b was terminat:d at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />, June 9, 1981.

FAILURE DATA:

P!ne 3/4" Schedule 40 Prepared By J.J.

Espey

/

)Sd[!w Manager '-- S6lem tenerating. Station SORC Meeting No.

81-59 i

s l

l l

[

64C FOIM 366 U. 5. NUCLE AR CEGULATCQY COMMIS5 TON 87 77)

O

'"$ " '" ' "' " " " " ' O CONTROL BLOCK: l l

l l

l l

l@

(PLE ASE PRINT CA TYPE ALL CEOUIRED INFORMATION)

ITTT1 In IJ IS la IS 12 l@l el el -1 ol ol ol of ol -l ol ol@l 41111l11ligi I

ig e7 8 9 LICENSEE CODE le it UCENSE NLMSER 25 26 taCENSE Tvrt JO 67 CAT be CON'T lOI1l ERCE l 0l 5l 0l 0l Ol 3l 1l 1hl 0 l 6 l 0 l 9 l 8 l ljl 01710 l 9 l 8l tj@

7 8

60 61 DOCKET NUM8EP G8 89 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPflCN AND PROBABL'E CONSEQUENCES h IOl2l l At 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br />, on June 9, 1981, it was determined that a possible Reactor Coolant j

g 3 l System leak existed. Action Statement 3.4.7.2.b was entered.

Investigation reveale<j

o i,, l the leak to be in the Chemical and Volume Control System at the weld for vent valvej io Is1 l 2CV396. This constituted operation in a degraded mode in accordance with Technical l 1o is l l Specification 6.9.1.9.b.

l ULUJl J

lot 8Il

}

C DE CODE

$ 8C &

COMPONENT CODE SUS DE 5

DE ioisi lP lC lh lE lh [h lP l Il Pl El XlX lh l A lh [h 7

8 9

to 11 12 13 18 19 20 SE QUENTI AL OCCURRENCE REPORT REVISION LE R EVENTvEAR REPORT NO CODE TYPE No.

O s =RO L8 I il 1-1 I o f 41 ol l'l lo 13 I UJ I-1 Lo_]

_ 21 22 23 24 26 27 28 29 30 31 32 4;5 T HOURS 22 58 i POR 8.

SUPP IER MANUFACTURER N A T ON ON PL NT l F jgl34 lg l35 lg l36Zl@ l0 l0 l0 l0 l {Q l Nlg {@

lXl9l9l9jg Z

Z 33 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l i l o l l The combination of excessive vibration and a pressure transient caused the weld to l

g j fail. The leak was isolated by isolating the letdown line.

2CV396 was removed and_i l the vent line was capped off with a welded pipe cap.

The weld was inspected and I

~

g l letdown was returned to service. Action Statement 3.4.7.2.b was terminated at 2045 l g j hours, June 9, 1981.

l 80 7

8 9 STA U

% POWER OTHER$TATUS DISCO RV OISCOVERY DESCRIPTION Cverator Observation N/A I b h!

W d h l0l0lOlhl ACTIVITY CO TENT RELE Asto OF RELE ASE AMOUNT OF ACTIVITY LOCAf:ON OF RELEASE Lttej tzj @ l 21@l nA I

wA I

7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 1 of of ol@l zl@ DESCRIPTION I

NUUSE R TYPE l

nt.

i 7 PERsONNE t iN;uZEs DESCRik JION@

1 d ou@l i a nA 7

8 9 11 12 80 Loss OF OR DAuACE TO FACILITY Q TYPE

DESCRIPTION

%,,/

hl i 9 NA 7

8 9 to 80 ISSU

DESCRIPTION

2 LoJ Lv]E81 nA I

Illilillilill:

8 9 to or 69 80 g NAME OF PREPARER PHONE:

{

.________________________________________J