ML18101A426

Describes How Compliance W/Nrc Bulletin 88-008 for Safety Injection Lines Will Be Accomplished & Advises That Per Discussions During 941027 Meeting,Mod for Double Valve Isolation Cancelled

ML18101A426
Person / Time
Site:	Salem
Issue date:	12/22/1994
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-008, IEB-88-8, NLR-N94195, NUDOCS 9412300026
Download: ML18101A426 (6)

Text

Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President ~ Nuclear Engineering DEC 2; 2, 199Lt NLR-N94195 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

NRC BULLETIN 88-08 THERMAL CYCLING IN PIPING CONNECTED TO THE RCS SALEM GENERATING STATION UNIT NOS. l AI;i"D 2 DOCKET NOS. 50-272 AND 50-311 By letter dated, March 1, 1993 (re: NLR-N93028), Public Service Electric & Gas Company (PSE&G) committed to address the Bulletin 88-08 concerns for Salem Unit Nos. 1 and 2 by providing double valve isolation on the safety injection lines.

In order to close the second set of valves, a thermal relief valve was required to be installed on the boron injection tank.

PSE&G committed to and was prepared to.install the relief valve by the end of the twelfth refueling on Unit No. 1 (Spring 1995) and the eighth refueling on Unit No. 2 (Fall 1994).

PSE&G has identified an alternate method of satisfying the criteria specified.

PSE&G will perform a leakage monitoring surveillance on a quarterly frequency during Operational Modes 1 through 3 to detect if leakage past 1(2)SJ12 or 1(2)SJ13 motor operated safety injection valves is below procedure acceptance criteria.

The leakage acceptance criteria of less than or equal to 0.05 gallons per minute (gpm) has been established to preclude the potential for thermal fatigue in the downstream piping.

Leakage monitoring has been approved by the NRC as being equivalent to pressure monitoring for Byron and Braidwood Nuclear Power Stations by letter to Commonwealth Edison Corporation from the NRC dated September 24, 1992.

9412300026 941222 PJ)R ADOCK 05000272 pi PDR

Document Control Desk NLR-N94195 2

DEC2 2~,4 PSE&G has performed this leakage monitoring periodically since the issuance of Bulletin 88-08.

To date, no leakage has been noted.

Should unacceptable leakage occur, PSE&G will perform troubleshooting to determine if the leakage is Reactor Coolant system (RCS) pressure isolation valve leakage, or leakage past 1(2)SJ12 and 1(2)SJ13.

Based on the results of the troubleshooting, PSE&G will evaluate and take the necessary actions.

During a telephone conversation between PSE&G and NRC personnel on October 9, 1994 and a subsequent meeting on October 27, 1994, concern was expressed by the NRC that the leakage past the subject valves might not be detected by the proposed test method.

To address this concern, PSE&G agreed to the following: During the current Salem Unit No. 2 outage 2R8 and the upcoming Unit No.

1 outage.1R12 (Spring 1995), PSE&G will perform a test to demonstrate that the flow line.in each unit is unobstructed and that the installed flow meter is capable of measuring low flow conditions equal to 0.05 gpm.

Since the October 27, 1994 meeting, PSE&G has successfully completed this test on Salem Unit No. 2.

The results indicate that the flow line and flow meter are capable of performing these leakage monitoring functions at flow rates as low as 0.05 gpm.

The results of the Salem Unit No. 1 test will be reported upon completion.

The instrumentation being used to measure the leak rate consists of two in-line flow meters arranged in series.

One flow meter has a range of 0-1 gpm, the second has a range of 0-10 gpm.

These flow meters are simple rotameters and are not normally in service.

They are periodically placed into service to perform technical specification reactor coolant system pressure isolation valve leakage surveillances.

The meters were procured with an accuracy of 2% full scale.

The vendor instructions state that these rotameters require very little maintenance other than cleaning and visual inspection for wear on the metering float

• head.

No wear or corrosion has been noted to date.

Recurring tasks are in place to periodically clean and inspect these flow meters in accordance with vendor recommendations.

A copy of the vendor specification sheet and the PSE&G blueprint drawing have been included as Enclosure 1.

Per our discussions during the October 27, 1994 meeting, the modification for double valve isolation has been cancelled.

Compliance with Bulletin 88-08 for the safety injection lines will be accomplished as stated above.

95-4933

Document Control Desk NLR-N94195 3

DEC 2 21994 Should there be any questions with regard to this submittal, please do not hesitate to contact us.

Sincerely, c

Mr. T. T. Martin, Administrator - Region I

u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager -

Salem

u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. Marschall -

Salem (S09)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 95-4933

Document Control Desk NLR-N94195 ENCLOSURE 1

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FIG. 1 T}pe 20.Q6SO.e610 (tft!'Na9d acm.11Jc;tlons).

FEATURES FfG. 2 fype 20-9650.S510 manged oonnectior.a)

• Accuracy-Computerized callbretions provide a high degree of accuracy.

Co:"l'Osion~Rtsistance-Meu'

~ rotameters can be made from a variety of corrosion-resistant materials. Meter bodies anc connections are avail*

able in steel, stainless s1et:l, Hastelloy 1 and other special materials. Extension housings feature weather-tight stainless steel construction.

• Flexihility-Met.1.l tube rotameter!i can be equippe<l with flow alarm systems and other devices to 11:.1it a ranse of application&.

• Convenient Installation-Extension hou&inss can be rotated a full 360° without disconnecting piping.

No specific piping configurations tc worry about-simply mount meter in ve11ical positfon.

DESCRIPTION Schutte cl KDerting metal tube row.meters are rugged, yet highly sensitive imtNments specifically designed fur measur*

ing the flow of high pressure or hazardous fluids. The!e in-struments operate on the variable~area flow measuremenr principle and provide a direct reading indication of flow rate.

Su.Ddud meW tube roiameten: are equlpped wilh 11tainless I JM ot SIOJ/flO ON.. C:.001 COfP s~l hcusing5 and stainless steel now indicators mounted on threndee or flanged me!Jil metering tubes. Other extension housings such as transmitters and alflrms are also available (s.oe page 5).

Accuracy of these meters is :::2 ~ f..ll.l scale with standard cfilibration, hov.'e\\er, spedally calibrated me~rs arc available with +/-1 % ES. accU!'8.L.)'. Maximum temperature and pressure ratings for standurd metal tubes are 400 *p B."ld 2500 psig.

~signs for hlgher pressures and temperatures are available.

All metal tube rotameters are manufactured in accordance whh Standard S-16 published by the l.S.A.

OPERATION Fluid enters the wpered metal tube through the small inlet at the bottom, flows up the tube and exili through the horizontal outlet. Fluid in t11e tut>e ~rts a force on the float directly proportions! to the rate of flow.

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• • *oocument ID

• 134335 Revision: 004

• • Sheet No Print Date: 11/18/94 **