ML20151Z245

Forwards Revised Emergency Procedures,Including Rev 1 to EP IV-107, Manual Effluent Dose Calculations & Rev 1 to EP IV-106, Computerized Effluent Dose Calculations in Response to NRC Concerns from Rms 860117 Meeting W/Util

ML20151Z245
Person / Time
Site:	Hope Creek
Issue date:	02/12/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Adensam E Office of Nuclear Reactor Regulation
Shared Package
ML20151Z248	List: ML20151Z245 ML20151Z258
References
NUDOCS 8602140110
Download: ML20151Z245 (3)

Text

Pubhc Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box 236, Hancocks Bndge, NJ 08038 609 339-48CO

- vice President -

Nuclear February 12, 1986 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention: Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing-

Dear Ms. Adensam:

RESPONSE TO JANUARY 17, 1986 RMS MEETING CONCERNS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Servi'ce Electric and Gas Company (PSE&G) submits the following in response to the NRC concerns discussed during the PSE&G/NRC Radiation Monitoring System (RMS) meeting held in Bethesda, Maryland on January 17, 1986.

1. The seismic testing has been completed and qualification reports for the sample flow splitter skid and suppression pool temperature monitoring circuit boards have been received and are being reviewed. Seismic qualification for the aforementioned items will be complete prior to fuel load.

2. PSE&G has posted output units on the RMS instrument cabinet (10C604) to aid the operators in interpreting the RM-23 output.

3. PSE&G has developed a procedure for surveillance of the continuous air monitor (CAM). This procedure is identified as RP-TE.SP-002Q " Interim Radiation Monitoring System Activities". This procedure contains requirements for performing CAM surveillance twice a shift.

4. Attachments I & II provide a detailed description of the procedures to be utilized when performing emergency dose assessment calculations manually or by employing computerized methods, respectively. These procedures will be used until the Micro Vax II computer is operational.

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l Director of Nuclear 2 2-12-86 Reactor Regulation 5.- The NRC requested additional information pertaining to the failure time for the drywell leak detection -

RMS when temperatures exceed 120 F. With respect to the above, PSE&G notes that the temperature sensitive components which comprise the' detector assembly are the plastic scintillator, which is rated for 160 F and the photomultiplier tube, which is rated for 140*F.

Per the General Atomics Operations and Maintenance Manual, Ell 5-1317, this detector is rated for 120 F nominal operating temperature. If'the detector is

. operated at temperatures approaching 140 F, the expected life of the photomultiplier tube will decrease from 4-5 years to approximately 1 year. Also at elevated temperatures the minimum detectable concentration sensitivity value will increase and the drift in the photomultiplier output will increase.

In the event there are any questions with respect to the above, do not hesitate to contact us.

Sincerely,

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Attachments C D.H. Wagner USNRC Licensing Project Manager R.W. Borchardt USNRC Senior Resident Inspector

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