ML20141A973

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Responds to to Gm Holahan Re in 92-10, Potential for Loss of Remote Shutdown Capability During Control Room Fire. NRC Response to NEI Encl.W/O Encl
ML20141A973
Person / Time
Issue date: 05/12/1997
From: Khadijah West
NRC (Affiliation Not Assigned)
To: Fioravante N
AFFILIATION NOT ASSIGNED
References
IEIN-92-010, IEIN-92-018, IEIN-92-10, IEIN-92-18, NUDOCS 9705150086
Download: ML20141A973 (1)


Text

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May-12,~1997

Mr. Nicholas E. Fioravante

. Technical and Management Consulting Services, Inc.

22312 Rolling Hill Lane Laytonsville, Maryland 20882

Dear Mr. Fioravante:

i I am ' responding to your letter of February 21,1997, to Gary M. Holahan, Director, Division of E

Systems Safety and Analysis, Office of Nuclear Reactor Regulation (NRR). In your letter, you provided your insights regarding information Notice (IN) 92-10 " Potential For Loss of Remote Shutdown Capability During a Control Room Fire," fire-induced hot shorts, and spurious signals; As you are aware, in a letter dated January 14,1997, Nuclear Energy Institute (NEI) expressed concems that the Nuclear Regulatory Commission (NRC) staff was using IN 92-18 to impose new fire protection requirements on licensees. During a public meeting on February 7,-1997, the NRC staff discussed with representatives of the NEl the questions and issues raised in its letter. At that meeting, you also provided your thoughts on the issues. By

' letter dated March 11,1997, the staff provided a written response to NEl. In its response, i

the staff explained how the fire protection regulation and published staff positions and guidance support its positions regarding IN 92-18. As Pat Madden discussed with you, the

. staff considered your insights when it developed its response to NEl. A copy of the staff's response to NEl is enclosed for your information.

4 The staff appreciates your insights and your interest in reactor fire protection. If you have i

any questions about the staff positions or IN 92-18, please contact me. I can be reached at 301-415-1220.

Sincerely, K. Steven West, Chief Fire Protection Engineering Section Plant Systems Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation Ehclosure: As Stated N{b DISTRIBUTION (w/o encQ:

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