ML20091A626
| ML20091A626 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 11/22/1976 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9105160417 | |
| Download: ML20091A626 (3) | |
Text
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NSWB NOMTHEMN 8TATES POWEM COMPANY
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Mr Victor Ste.o, Directot Division of...srating Reactors U S Nucicar Regulatory Commission g
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Dear 11r Stello:
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W MONTICELLO UUCLEAR CENERATING PIMT
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gg 3'.N Docket No. 50-263 License No. DPR 22
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\\tb 9[p' g Re ferences t (a) Letter dated May 11, 1976 from Victor Stel b, (USNRC) to L 0 Mayer (NSP)
L,M (b) Letter dated June 3,1976 from L 0 Mayer (USP) to Victor Stello (USNRC)
(c) Letter dated September 30, 1976 f rom Ka rl R Go? er (USNRC) to L 0 Mayer (USP)
Referenca (a) requested that we conduct an examination to compare the existing fire protection provisions at this facility with the guidelines of Standard Review Plan 9.5.1.
Re f e renc e (b) stated that a date of December 3,1976 had been scheiuled for submittal of the requested infomation. This review has been underwa/ since May and we t-xpect to have the information ready for submittal within a veck of the originally scheduled date.-
Reference (c), which was not received until October 13, 1976, requested that we conduct a fire hazards analysis based upon additional guidance provided in to t. hat letter. This specific type of analysis was not contemplated in the scope or schedule for the review that has been underway in response to Reference (a). We have retained the original plant Architect / Engineer organi-zation to perform a fire hazards analysis for this facility. The proposal received from the consul' ant has resulted in the establislunent of a scheduled date of March 12, 1977 for submittal of the fire hazards analysis.
Reference (c) further requested that we propose fire protection technical specifi-cations and incbde them with the response to our presently scheduled cubmittal.
We believe that the request to sulait fire protection technical specifications In our opinion, a more appropriate program would be for the licensee is premature.
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NORTF. AN OTATCG POWER COM6.NY Mr Victor Stello Page 2 November 22, 1976 to make the various required subnittals, have the NRC complete the necessary reviews, reach agreement on those physical and procedural changes that are neces-sary for the protection of the health and safety of the public, and then develop l
the required technical specifications based upon the modified fire protection provisions.
During the above review period, it would be appropriate for the NRC to prepare draf t guidance for the content of fire protection technical specifi-cations and allow a period of time for industry cornent prior to licensee submittal of proposed technical specifications.
A comprehensive program of periodic inspections and surveillance testing is being conducted for existing fire protection equipment at this facility. These include fire protection systm tests, diesel fire ptunp tests, transfomer deluge tests, i
hose station and portable fire extinguisher inspections, unoke detector tests, Descriptions of the scope and f requency of these surveillance programs are etc.
described in a letter dated Decmber 5,1975 to Mr J G Keppler, IE-III in response to IE Bulletin 75 04B. Many of these surveillance tests are not of a nature that could be categorized as suitabic for technical specifications.
We believe, however, that the existence and use of these surveillance tests, which can be audited by NRC/IE-III inspectors, provides assurance that the existing fire pro-tection systems will perfom their intended function.
Reference (c) further requested that we infom you of the date we intend to meet Section B of Appendix A " Administrative Procedures, Controls and Fire Brigade".
We intend to evaluate our programs in this area in conjunction with the fire hazards analysis studies and will provide a response with the latter submittal.
Yours very truly, W6.
v L 0 Maye r, PE Manager of Nuclear Support Services LOM/ deb cc:
J G Keppler G Charnoff MPCA Attn:
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A, CKNOWLEDGED.
FI. ANT !UME: IDNTICELLO DO NOT REMUv4 DISTRIBtTIION OF TIRE PROTECTION INTO TER S.SilEPTARD 9-22 76 FOR OPERATit'G REACTORS F OR ACT ION /IN F O ht.i A16_Of 4
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