ML20013K287
| ML20013K287 | |
| Person / Time | |
|---|---|
| Issue date: | 06/08/1998 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | Larkins J Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-GENERAL, FACA, NUDOCS 9806120003 | |
| Download: ML20013K287 (4) | |
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81 UNITED STATES o
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NUCLE AR REGULATORY COMMISSION "E
WASHWGTON, D.C. 205$54001
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June 8, 1996 John T. Larkins, Executive Director Advisory Committee on Reactor Safeguards l
11545 Rockville Pike l
Mail Stop T-2E26 l
Washington, DC 20555 j
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SUBJECT:
ACRS REVIEW Or REACTOR FIRE PROTECTION ISSUES l
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Dear Mr. Larkins:
i The Office of Nuclear Reactor Regulation staff would like to meet wi'h the Advisory Committee on Reactor Safeguards (ACRS) during the July 1998 meeting to discuss two high priority reactor fire protection issues. The two issues, which the staff has discussed with the ACRS during previous meetings, are fire barrier penetration seals and post-fire safe snutdown analyses.
The staff has recently completed a reassessment of fire barrier penetration sealissues. The staff has documented the iesults of its reassessment in a NUREG report thet it plans to issue form public comment by the end of June 1998. The staff is seeking ACRS review and comment on the results of its reassessment.
The staff has found problems with licensee implementation of regulatory guidance and staff positions that specify that facilities be designed such that fire-induced circuit failures will not adversely impact the ability to achieve and mairitain a safe shutdown condition. Specifically, NRC inspections, licensee event reports, and information submitted by the Nuclear Energy Institute (NEI) have revealed that some licensees have failed to properly identify, analyze, and protect electrical circuits required to achieve and maintain post-fire safe shutdown. Meetings with and correspondence from NEl indicate that industry is largely in disagreement with the staff positions on this issue. However, during two of the three fire protection function inspections the staff has performed to date, the staff did not find problems with the licensee's circuit analyses.
To resolve this issue, the staff plans to alert licensees to potential problems associated with fire-l induced circuit failures through an information notice ~ and to clarify the regulatory requirements l
through_ a generic letter. To help ensure that the staff and the industry reach a common j
understanding of the regulatory requirements and the staff's concems, the staff is also l
l considering an industry workshop. The staff is seeking ACRS review and comment on the circuit analysis issue and its plans for resolving the issue.
The staff will provide the draft NUREG report on fire barrier penetration seals and the draft information notice on circuit analysis to your staff. Although the staff plans to issue the draft NUREG report on seals and the information notice on circuit analysis before the ACRS meeting 4
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of July 1998, they are currently predecisional. As such, the staff is requesting that these documents not be made publicly available at this time and should be for ACRS information only.
If you have any questions or comments, please contact Steven West at 301-415-1220.
Sincerely, cLu l
Ledyard B. Marsh, Chief Plant Systems Branch j
Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation l
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John T. L: rains 2
i of July 1998, they are currently predecisional. As such, the staff is requesting that these documents not be made publicly available at this time and should be for ACRS information only.
If you have any questions or comments, please contact Steven West at 301-415-1220.
i Sincerely, Ledyard B. Marsh, Chief Plant Systems Branch D;visien of Systems Safety and Analysis Office of Nuclear Reactor Regulation DISTRIBUTION:
Central File PUBLIC SPLB R/F GHolahan LBMarsh KWest BSheron BBoger DOCUMENT NAME: G:\\SECTIONC\\ WEST \\ACRS.WPD *see previous concurrence
- SPLB:DSSA SPLB:DSSi KSWest:Ik LBMarsh p' 6 v 6/04/98 6/f/98 OFFICIAL RECORD COPY I
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- John T. Lerkins, Ex:cutiva Director Advisory Committee on Ructor S:fegu rds J
11545 Rockville Pike Mail Stop T-2E26 l
Washington, DC 20555 i
SUBJECT:
ACRS REVIEW OF REACTOR FIRE PROTECTION sSSUES i
i
Dear Mr. Larkins:
The Office of Nuclear Reactor Regulation staff would like to meet with the Advisory Committee on Reactor Safeguards (ACRS) during the July 1998 meeting to discuss two high priority i
reactor fire prclection issues. The two issues, whicn the staff has discussed with the ACRS 1
during previous meetings, are fire barrier penetration seals and cost-fire safe shutdown analyses.
The staff has rece'n completed a reassessment of fire barrier penetr ion sealissues. The staff has documente the results of its reassessment in a NUREG r ort that it plans to issue form public comment the end of June 1998. The staffis seekin ACRS review and comment on the results ofits rea essment.
l The staff has found proble s with licensee implementation o egulatory guidance and staff positions that specify that fa 'lities be designed such that fir -iaduced circuit failures will not adversely impact the ability to chieve and maintain a saf shutdown condition. Specifically, I
NRC inspections, licensee eve reports, and informati submitted by the Nuclear Energy Institute have revealed that som icensees have faile to properly identify, ana!yze, and protect electrical circuits required to achie and maintain st-fire safe shutdown. To resolve tnis issue, the staff plans alert licensees potential pr lems associated with fire-induced circuit failures through an information notice nd to clar the regJlatory requirements through a generic letter. The staffis seeking ACh revi and comment on the circuit analysis issue and its plans for resolving the issue.
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The staff will provide the draft NUREG r o on fire barrier penetration seals and the draft ir. formation notice on circuit analysis t your aff. Although the staff plans to issue the draft NUREG report on seals and the info.ation n ice on circuit analyds before the ACRS meeting of July 1998, they are currently pr ecisional.
such, the staff is requesting that these documents not be made publict available at this 'me and should be for ACRS information only.
if you have any questions o mments, please cont et Steven West at 301-415-1220.
Sincerely, Ledyard B. Marsh, hief Plant Systems Bran '
Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation DISTRIBUTION: Central File SPLB R/F GHolahan LBMarsh KWest l.
l DOCUMENT NAME: G:\\SECTIONC\\WESTV. ORS.WPD SPLB:DSSA SPLB:DSSA KSWest:lk LBMarsh 6/k/98 6/ /98 g@
OFFICIAL RECORD COPY i
l