05000311/LER-1982-079, Forwards LER 82-079/03L-0.Detailed Event Analysis Encl

Forwards LER 82-079/03L-0.Detailed Event Analysis Encl

ML20027B165
Person / Time
Site:	Salem
Issue date:	09/03/1982
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20027B166	List: 05000311/LER-1982-079, Forwards LER 82-079/03L-0.Detailed Event Analysis Encl 05000311/LER-1982-079-03, /03L-0:on 820811,control Room Operator Determined by Containment Sump Pump Run Times,Unidentified Leakage of Greater than 1 Gpm.Caused by Valve 24GBS & Steam Generator Steam Flow Trap Leaking
References
NUDOCS 8209160498
Download: ML20027B165 (3)

LER-1982-079, Forwards LER 82-079/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3111982079R00 - NRC Website

text

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O PSEG Public Service Ele'tric and Gas Company P.O Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station September 3, 1982 Mr.

R.

C.

Haynes Regional Administrator USNRC Region 1 631. Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-079/03L Pursuant to the requirements of Salem Generating Station Unit No.

2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-079/03L.

This report is required within thirty (30) days of the occurrence.

Sincerely yours,

),/l b f'< ls w H.

J. Midura General Manager -

Salem Operations f,4[

RH:ks CC:

Distribution 8209160498 820903 PDR ADOCK 05000311 S

PDR The Energy People

$b m unm n e

Report Number:

82-079/03L Report Date:

09-03-82 Occurrence Date:

08-11-82 Facility:

Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Unidentified Leakage in Containment - Greater than 1 GPM.

This report was initiated by Incident Report 82-226.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 79% - Unit Load 900 MWe.

DESCRIPTION OF OCCURRENCE:

At 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, August 11, 1982, during normal operation, the Control Room Operator determined by the Containment Sump Pump run times, that he had indication of greater than 1 GPM of unidentified leakage.

Action Statement 3.4.7.2b was entered at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, and a containment entry was made to identify the source of leakage.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Investigation revealed that Valve 24GB3 was leaking at the i

flange.35 GPM, and No. 22 Steam Generator Steam Flow Trap was leaking.25 GPM.

Because this leakage was not previously identified on Surveillance Procedure 4.4.7.2, it had raised i

the unidentified leakage volume to greater than 1 GPM.

ANALYSIS OF OCCURRENCE:

The reactor coolant leakage detection systems are provided to l

monitor and detect leakage from the Reactor Coolant Pressure Boundary.

Industry experience has shown that while a limited i

araount of leakage is expected from the Reactor Coolant System, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.

This threshold value is l

sufficiently low to ensure early detection of additional leakage.

The 10 GPM identified leakage limitation provides allowance for a limited amount of leakage from known sources whose presence l

will not interfere with the detection of unidentified leakage by the leakage detection systems.

Therefore, leakage from identified and unidentified sources must be maintained within the limits l.

specified by the Technical Specifications, to maintain the capa-bility of detecting possible pressure boundary leakage.

l

\\

LER 82-079/03L.

ANALYSIS OF OCCURRENCE:Pressure boundary leakage of-any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Action Statement 3.4.7.2b requires:

With any Reactor Coolant System leakage greater than 1 GPM unidentified leakage, or 10 GPM identi-fied leakage, excluding pressure boundary leakage and leakage from Reactor Coolant System Pressure 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 shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Operation with unidentified leakage of greater than 1 GPM, there-fore constituted operation in a degraded mode permitted by a limiting condition for operation, and is reportable in accordance with Technical Specification 6.9.1.9.b.

As noted, investigation revealed that Valve 24GB3 was leaking at the flange, and No. 22 Steam Generator Steam Flow Trap was leaking.

The volume of this leakage was identified on Surveillance Procedure 4.4.7.2 and subtracted from the Containment Sump Pump run time leakage indication.

The resulting unidentified and identified leakage rates were determined to be within the limits permitted by the Technical Specifications.

Therefore, Action Statement 3.4.7.2b was terminated at 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, August 11, 1982.

All leakage was contained and within the limits allowed by the Technical Specifi-cation.

Therefore, this occurrence involved no risk to the health l

and safety of the general public.

CORRECTIVE ACTION

i I

As noted, a containment entry was made to determine the source of leakage.

Two sources of leakage were identified and work orders were issued to correct the problems.

FAILURE DATA:

Velan Valve Corp.

3" Gate Valve Type B10-254B-2TS Velan Valve Corp.

1" Steam Trap Type N-4

'[$ b*

Prepared By R.

Heller Gene'ral Manager -

SORC Meeting No.

82-80