ML18094A588

Submits Supplemental Info Re NRC Bulletin 88-008.Visual Insp of Pipe Restraints & Insulation Performed for Indications of Abnormal Pipe Deflection.Pipe Insulation Not Damaged & No Signs of Abnormal Pipe Deflection Found

ML18094A588
Person / Time
Site:	Salem
Issue date:	07/18/1989
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-008, IEB-88-011, IEB-88-8, NLR-N89137, NUDOCS 8908010156
Download: ML18094A588 (5)

Text

Public Service

• Electric and Gas Company .

Stanley LaBruna - Public Service Electric and Gas Company P.O. Box 236. Hancocks Bridge. NJ 08038_ .609-339-~800 July 18, 1989 NLR-N89137 United States Nuclear Regulatory Commission

• Docliment Control Desk Washington, .DC 20555 Gentlemen:

CONFIRMATORY LETTER NRC BULLETIN NO. 88-08 SALEM GENERATING STATION - UNIT NO. 1 DOCKET NO. 50-272 Public Service Electric- and Gas Company (PSE&G) hereby submits supplemental information regarding NRC Bulletin 8~-08. This information, provided in the. enclosure to this letter, was devefoped during the Salem Unit 1 Eighth Refueling Outage in accordance with_ the subject Bulletin.

Should. you have any_ questions with regard to this transmittal'*

please do not hesitate to contact us.

Sincerely, Enclosure

~

'( 1

Document Control Desk 2

-- 7-18-89 NLR-N89137 C Mr. J. c. Stone USNRC Licensing Project Manager Mrs. K. Halvey Gibson USNRC Senior Resident Inspector Mr. w. T. Russeil, Administrator USNRC Region I Mr. K. Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 .

Trenton, NJ 08625

ee ee REF: PSE&G letter NLR-N89137 STATE OF NEW JERSEY. )

) SS.

COUNTY OF SALEM )

S. LaBruna, be.ing duly sworn according to law deposes and says:

I am Vice President - Nuclear Operations of Public Service Electric and Gas company, and as such, I find the matters set forth in our letter dated July .18,. 1989 concerning the Salem Generating Station, Unit No. 1, are true to the best of my knowledge, information and belief.

Subscribed and Sworn re me this / ff...d.. day of 1989

~*.

/blic of New Jersey LAltAlt.IE v~ BEARD Notary Pvblic o~ New Jc r: Y . 91 My Comrn;ss_ion Exp1re$Mcy 1* 1* .

My Commission expires on

ee ee ENCLOSURE CONFIRMATORY LETTER NRC BULLETIN 88-08 SALEM GENERATING STATION, UNIT NO. 1 DOCKET NO.- 50-272

Background

Bulletin 88-08 requested that a review of piping connected

- to the reactor coolant system identify any unisolable piping that could be subjected to thermal cycling due to,valve le~kage. The bulletin addressed both fatigue cracking induced by thermal cycling and piping distortion caused by thermal stratification. -

In a letter dated September 23, 1988, PSE&G identified three paths in each of the Salem plants where _thermal cycling could-possibly occur. These three paths are: 1) downstream of the BIT isolation valve~; 2) downitream of the 1CV76 valve (charging line to the pressurizer); and 3) downstream of the lCVSO valve (charging line to the No. 14 cold leg). PSE&G committed to providing confirmatory letters within thirty days af_ter the completion of the next two refueling outages outlining the NDE results and all actions taken.

The first Bulletin 88-08 confirmatory letter for Salem Unit 2 was transmitted on December 3 O, 19 8 8. - The technical information for the- first confirmatory letter for Salem Unit 1 is provided below.

Actions Takeri ~nd Results Achi~ved During the eighth refueling outage for Salem Unit 1, PSE&G performed NDE examination at the three areas where thermal cycling could potentially induce fatigue cracking. The weld.

inspection consisted of twenty (20) welds using an -

ultrasonic technique developed by Southwest Research for socket welded fitting~. Sixteen (16) welds are on ~he chec~

valves and piping downstream of the BIT_ isolation valves.

Specifically, the welds are located on the downstream side of the ll..;14SJ17 valves. The remaining two locations are at the welds downstream from the 1CV76 and lCVSO check valves.

No recordable indications were found in any of the welds.

Leakage around the Boron Injection Tank (BIT) -could have occurred through the lSJ71 valve. PSE&G eliminated this concern by removing the valve and capping the piping as part of a design cnange package, completed during_ the eighth refueling outage. -

ee PSE&G also performed NDE weld examinations of the f iVe welds whi::h make up the pressurizer surge line. A visual inspection of the pipe restraints and insulation was performed for -indications of abnormal pipe def lectiori. - The weld NDE on the pressurizer surge line consisted of both a liquid dye penetrant and an ultrasonic examination. The NDE results did not reveal any recordable indications in the pressurizer surge line welds. The visual inspection to*

verify support and HEBA restraint clearances was acceptable.

The pipe insulation was not damaged and no signs of abnormal pipe deflection were found.

• The. thermal cycling caused by stratification in the-pressurizer *surge line has been included in the requirements of NRC Bulletin 88-11. The PSE&G response to-Bulletin 88-11 will include.a fatigue analysis on the effects of thermal cycling. _ *