ML20077F563

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Forwards Fifth 60-day Outage Rept Per IE Circular 76-06 Special Requirements Re Exams & Surveillance Used to Maintain Integrity of Piping Sys Containing Stagnant Borated Water
ML20077F563
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/14/1983
From: Liden E
Public Service Enterprise Group
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-SSINS-6830, REF-SSINS-SSINS-6 IEB-79-17, IEC-76-06, IEC-76-6, NUDOCS 8308010436
Download: ML20077F563 (2)


Text

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([]) IP'!sili!(Ji Pubhc Service Electric and Gas Company P.O. Box 236 Hancocks Br;dge, New Jersey 08038 Nuclear Department July 14, 1983 Dr. Thomas E. Murley, Regional Administrator U.S.

Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Gentlemen:

LICENSE NO. DPR-70 DOCKET NO. 50-272 NRC IE CIRCULAR 76-06 SIXTY DAY OUTAGE REPORT V SALEM GENERATING STATION In accordance with the special requirements of IE Circular 76-06, we are forwarding to you our fifth report of examina-tions and surveillances used to provide the necessary measures of assurance that the integrity of piping systems containing stagnant borated water is being maintained.

If you have any questions in this regard, please do not hesitate to call.

Very truly yours, A.

Liden Manager - Nuclear Licensing and Regulation Attachment ec:

Mr. L.

Norrholm Senior NRC Resident Inspector Mr. D.

Fischer Licensing Project Manager U.S. Nuclear Regulatory Commission

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REPORT OF EXAMINATIONS, INSPECTIONS AND TESTS CONDUCTED DURING THE 1982/1983 REFUELING OUTAGE This is the fifth sixty-day report in accordance with the special reporting requirements of NRC, IE Circular 76-06 and IE Bulletin 79-1$

This report is as follows:

1.

LOCATION:

Unit 1, Salem Generating Station, Hancock's Bridge, New Jersey 08038 2.

OUTAGE:

  1. 4 from October 16, 1982 to May 21, 1983 3.

PURPOSE:

Refueling Outage 4.

SUMMARY

There were no adverse findings in any examina-tions, inspections and tests conducted relative to IEC 76-06 and IEB 79-17.

5.

Examinations, inspection and tests conducted during the outage include:

a.

Fifteen (15) nuclear class 2 welds in the Residual Heat Remcval, Safety Injection, Chemical Volume Control and Containment Spray systems were examined by ultrasonic methods during the outage.

b.

Portions of Containment Spray, Safety Injection, and Chemical Volume Control systems were flushed (and continue to be flushed) during the monthly pump capacity surveillance testing as per Surveillance Procedure SP (0) 4.0.5-P.

c.

The Mechanical, Inspection, Examinations and Tests (MIET) Group, under the direction of the Inservice Inspection Engineer, conducted an inspection of all areas in the North Penetration and Auxiliary Building wherein the subject piping systems are installed.

d.

Portions of the CVC-Operation System that do not contain sampling connections in certain stagnant piping are flushed by the Operating Department in accordance with SP (0) 4.0.5-P.

e.

Cloride sampling and testing for cloride content of those samples of fluids in stagnant piping was conducted on a quarterly basis.

During the past 12 months there were no nonconformances identified.

f. Visual Service Pressure Leak Examinations were conducted on the following systems:
1. Safety Injection
2. Chemical and Volume Control
3. Residual Heat Removal Containment Spray s.

7/14/83 4