ML18093A707
| ML18093A707 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/26/1988 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N88029, NUDOCS 8803080367 | |
| Download: ML18093A707 (4) | |
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Public Service Electric and Gas Company Steven E. Miltenberger Vice President -
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4199 Nuclear Operations February 26, 1988 NLR-N88029 United States Nuclear Regulatory Commission Document Control Desk Washinqton, DC 20555 Gentlemen:
RESPONSE TO NOTICE OF DEVIATION NRC INSPECTION REPORT NO. 50-311/87-29 UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric and Gas Company (PSE&G) has received the Notice of Deviation dated January 26, 1988, regarding a deviation from the Fire Hazards Analysis commitment to provide fire detection throughout the Reactor Plant Auxiliary Equipment Area and the Radwaste Storage Area.
Pursuant to the requirements of 10CFR2.201, our response to this Notice of Deviation is provided in the attachment to this letter.
Should you have any questions regarding this submittal, please feel free to contact us.
Attachment 8803080367 880226.
PDR ADOCK 05000311 Q
PDR Sincerely,
Document Control Desk 2
C Mr. D. c. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 02-26-88
ATTACHMENT PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM GENERATING STATION UNIT NO. 2 RESPONSE TO NOTICE OF DEVIATION Salem Unit 2 Fire Hazard Analysis (FHA) dated September 11, 1987 states that automatic fire detectors have been installed throughout the Reactor Plant Auxiliary Equipment Area and the Radwaste Storage areas.
Contrary to the above on September 18, 1987, it was identified that automatic fire detectors were not installed in the following locations of the Reactor Plant Auxiliary Equipment Area:
(1) East end of the corridor outside the counting room:
(2) the corridor to the mechanical penetration area; (3) the storage area behind the counting room; (4) the ventilation room over the counting room: (5) the boric acid evaporator room: and (6) the ISI calibration storage room.
Also, area fire detectors were not installed in the control console room of the radwaste storage area.
RESPONSE
PSE&G DOES NOT DISPUTE THE DEVIATION.
The root cause of this deviation is considered to be a misinterpretation of the use of the word "throughout" in the FHA.
Fire detection for the 100' elevation of the Auxiliary Building was committed to in the SER and the original commitment was to provide coverage of the corridor areas and the exemption request dated January 17, 1986 clearly indicates this configuration.
~eneric Letter 8E~l0 indicates that detection is not required throughout an ar~a to satisfy Appendix R.
The 1987 Fire Hazards Analysis states that "Ionization type fire detectors and manual fire alarm detectors and manual fire alarm stations are provided throughout the area."
This statement was intended to reflect the Generic Letter 86-10 guidance.* The word "throughout" was used inappropriately.
The NRC Inspectors indicated that detection in six areas on elevation 100' would be needed, in addition to the existing detectors to be considered as being "throughout" the area.
PSE&G has responded to the Inspectors' advice to add detectors.
CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED During the inspection, PSE&G committed to install detection in the six areas noted in the deviation.
Additionally, fire watch coverage was established for the subject areas.
The Fire Hazards Analysis was reviewed against this issue with a subsequent walkdown in October 1987.
The Fire Hazards Analysis is currently in the update cycle.
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CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER DEVIATIONS The Fire Hazards Analysis has been issued as a controlled document." The revision noted in the response to Item 1 and future revisions will be controlled via the design change process.
THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED The design change package which installs detection in the six subject areas is currently in the review and approval cycle.
Installation will begin subs.equent to the design change package being issued and can be expected to be completed by October 1, 1988.
The Fire Hazards Analysis revision/update related to Item 1 is currently scheduled for April 18, 1988.