ML20214G109: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 4
| page count = 4
| project =  
| project = TAC:54373
| stage = Draft Approval
| stage = Draft Approval
}}
}}
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FSV into compliance with 10 CFR Part 50, Appendix R. Specific guidance for FSV had been provided by the NRC in our letter of June 4,1984.
FSV into compliance with 10 CFR Part 50, Appendix R. Specific guidance for FSV had been provided by the NRC in our letter of June 4,1984.
Your submittals also evaluated the fire protection features for Building 10 against the guidelines of Appendix A to Branch Technical Position APCSB 9.5-1. We have reviewed these evaluations. Previous evaluations concerning fire protection at FSV are given by License Amendments Nos.14 and 21 (dated June 18, 1976 and June 6, 1979 respectively).
Your submittals also evaluated the fire protection features for Building 10 against the guidelines of Appendix A to Branch Technical Position APCSB 9.5-1. We have reviewed these evaluations. Previous evaluations concerning fire protection at FSV are given by License Amendments Nos.14 and 21 (dated June 18, 1976 and June 6, 1979 respectively).
The enclosure to this letter contains a final draft of our SE on your submittals. (A portion of this draft SE concerning emergency lighting has been previously sent to you by letter dated August 20,1986.) We are providing this draft SE for your comments to assure that the basis for our approval of your design and requested exemptions is correct. Please provide your comments to us ir writing within 60 days of the date of this letter.
The enclosure to this letter contains a final draft of our SE on your submittals. (A portion of this draft SE concerning emergency lighting has been previously sent to you by {{letter dated|date=August 20, 1986|text=letter dated August 20,1986}}.) We are providing this draft SE for your comments to assure that the basis for our approval of your design and requested exemptions is correct. Please provide your comments to us ir writing within 60 days of the date of this letter.
Please note that there are several items in this evaluation which will be closed out during on-site inspections. The NRC's inspection program is described in Section B of Generic Letter 86-10, dated April 24, 1986.
Please note that there are several items in this evaluation which will be closed out during on-site inspections. The NRC's inspection program is described in Section B of Generic Letter 86-10, dated April 24, 1986.
This draft SE contains four open items, as summarized in Section 4.3.
This draft SE contains four open items, as summarized in Section 4.3.

Latest revision as of 17:41, 4 May 2021

Forwards Draft Fire Protection Safety Evaluation Supporting Util 850401 Request for Exemption from 10CFR50,App R Requirements & Proposed Safe Shutdown Sys.Status Rept on Listed Items & Comments Re Draft Evaluation Requested
ML20214G109
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 11/18/1986
From: Heitner K
Office of Nuclear Reactor Regulation
To: Robert Williams
PUBLIC SERVICE CO. OF COLORADO
Shared Package
ML20214G112 List:
References
GL-86-10, TAC-54373, NUDOCS 8611250577
Download: ML20214G109 (4)


Text

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'go UNITED STATES NUCLEAR REGULATORY COMMISSION e

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  • November 18, 1986 o

Docket No. 50-267 Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840

Dear Mr. Williams:

SUBJECT:

DRAFT FIRE PROTECTION SAFETY EVALUATION (SE) FOR FORT ST. VRAIN (FSV)

We have completed our review of your submittals concerning fire protection at FSV. A detailed listing of these submittals is provided in our enclosed draft SE. These submittals discussed in detail your proposals for bringing \

FSV into compliance with 10 CFR Part 50, Appendix R. Specific guidance for FSV had been provided by the NRC in our letter of June 4,1984.

Your submittals also evaluated the fire protection features for Building 10 against the guidelines of Appendix A to Branch Technical Position APCSB 9.5-1. We have reviewed these evaluations. Previous evaluations concerning fire protection at FSV are given by License Amendments Nos.14 and 21 (dated June 18, 1976 and June 6, 1979 respectively).

The enclosure to this letter contains a final draft of our SE on your submittals. (A portion of this draft SE concerning emergency lighting has been previously sent to you by letter dated August 20,1986.) We are providing this draft SE for your comments to assure that the basis for our approval of your design and requested exemptions is correct. Please provide your comments to us ir writing within 60 days of the date of this letter.

Please note that there are several items in this evaluation which will be closed out during on-site inspections. The NRC's inspection program is described in Section B of Generic Letter 86-10, dated April 24, 1986.

This draft SE contains four open items, as summarized in Section 4.3.

Please provide the additional information required to close these items when ~

you provide your comments as requested above.

Furthermore, in order for the staff to determine the status of the plant relative to compliance with 10 CFR Part 50, Appendix H, you are r.equested to provide a status report containing the following information:

- Status of the relate.1 modifications and schedule for their completion,

- Status of the revision of the fire protection procedures and operator training that support compliance with Appendix R, and 8611250577 861118

{DR ADOCK 05000267 PDR

,' November 18, 1986 Mr. R. O. Williams, Jr. - Status of your compliance with Sections C, D, and F of Generic Letter 86-10.

This information should be provided with the comments requested above.

Note that at this time you must continue all interim compensatory measures as described in your letters of April 1 and July 11,1985(P-85113and P-85245),respectively. Relief from these measures will be granted when full compliance with 10 CFR Part 50, Appendix R, is achieved. We may request certification conc.erning your compliance with 10 CFR Part 50, Appendix R, at a later time. If you have any questions concerning this matter, please call Charles S. Hinson at (301) 492-7930 or me at (301) 492-8288.

The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Original signed by Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page DISTRIBUTION:

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Mr. R. O. Williams, Jr. - Status of your compliance with Sections C, D, and F of Generic Letter 86-10.

This information should be provided with the comments requested above.

Note that at this time you must continue all interim corpensatory measures as described in your letters of April 1 and July 11, 1985 (P-85113 and P-85245),respectively. Relief from these measures will be granted when full compliance with 10 CFR Part 50, Appendix R. is achieved. We may request certification concerning your compliance with 10 CFR Part 50, Appendix R, at a later time. If you have any questions concerning this matter, please call Charles S. Hinson at (301) 492-7930 ormeat(301)492-8288.

The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely.

-. m Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B

. Office of Nuclear Reactor Regulation

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Enclosure:

As stated cc w/ enclosure:

See next page l

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. Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain cc:

Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc. Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2

- Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Diviston Mr. L. W. Singleton, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840, Public Service Company of Colorado Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker P. 0. Box 840 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 92138 Kelley, Stansfield & 0'Donnell Public Service Company Building Connitment Control Program Room 900 Coordinator

. 550 15th Street Public Service Company of Colorado u- Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-D Regional Administrator, Region IV U.S. Nuclear Regulatory Conaission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413 1

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