ML20214J201
| ML20214J201 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/21/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20214J203 | List: |
| References | |
| NLR-N86173, NUDOCS 8612010200 | |
| Download: ML20214J201 (2) | |
Text
.
g Public Service Electric and Gas Company C:;rbin A. McNeill, Jr.
Public Se'vice Electric and Gas Company P.O. Box 236 Hancocks Bridge, NJ 08038 609 339-4800 Vice President -
Nuclear November 21, 1986 NLR-N86173 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfc'.k Avenue Bethesda, Maryland 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate #3 Division of BWR Licensing
Dear Ms. Adensam:
REQUEST FOR ADDITIONAL INFORMATION CONTAINMENT VENT / PURGE VALVE OPERATION HOPE CREEK GENERATING STATION DOCKET NO. 50-354 On October 23, 19E6, a meeting was held in the Bethesda, MD, offices of the NRC to discuss Public Service Electric and Gas Company's ( PS E&G ) June 4, 1986 application for amendment of the Hope Creek containment vent / purge Technical Specification.
Subsequently, the NRC transmitted a summary of this meeting which included requests for additional information (D. Wagner, NRC, to PSE&G, dated November 3, 1986).
This submittal responds to the NRC request for additional information dated November 3, 1986, and revises PSE&G's application for amendment to the Hope Creek Technical Specifications, dated Juna 4, 1986 (C. A. McNeill, PSE&G to E.
1 Ade ns am, NRC).
PSE&G hereby requests approval to operate the Hope Creek drywell and suppression chamber purge system in accordance with the proposed revised technical specification (Enclosure 1) based upon the attached revised demonstration of valve qualification and operability (Enclosure 2).
This revised enclosure provides the following additional information.
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B6120102OO 861121 PDR ADOCK 05000354 P-PDR J
-we
't Director of Nuclear 2
11-21-86 Reactor Regulation Criteria for termination of CPCS operation and commencement of deinerting.
A limit on the amount of time (on a yearly basis) the vent / purge lines may be operated in Operational Conditions 1, 2,
and 3 including justification.
LOCA dose assessment methodology including a summary of the radiological dose calculation.
Valve operability support information including seismic qualification, piping configuration and valve orientation, valve orientation during testing, and post-test examination of valve parts. indicates that the proposed technical specification change does not involve a significant hazard.
The HCGS FSAR revisions in Enclosure 4 supersede those within the June 4, 1986 submittal and will be included in a future amendment to the HCGS FSAR.
PSE&G requests that the proposed revised technical specification be approved prior to December 28, 1986 to support initial containment inerting at Hope Creek Generating Station.
If there are any questions regarding this submittal do not hesitate to contact us.
Sincerely, i
Enclosures (4)
Drawings (2) l C
D.
H. Wagner USNRC Licensing Project Manager R. W.
Borchardt USNRC Senior Resident Inspector R.
Hodor i
l Brookhaven National Laboratory
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