ML20154M813

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Requests Addl Info to Complete Review of Identifying & Providing Justification for Deviations from Fire Protection Program.Fire Loading in Terms of Btus Per Square Ft Needed for Listed Areas/Locations
ML20154M813
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 03/10/1986
From: Youngblood B
Office of Nuclear Reactor Regulation
To: Tucker H
DUKE POWER CO.
References
NUDOCS 8603140497
Download: ML20154M813 (3)


Text

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i Docket Nos.: 50-369 and 50-370 Mr. H. B. Tucker, Vice President Nuclear Production Department MAR 101986 Duke Power Company 422 South Church Street Charlotte, North Carolina 28242

Dear Mr. Tucker:

Subject:

Request for Additional Information Regarding Deviation from 10 CFR 50 Appendix R - McGuire Nuclear Station, Units 1 and 2 The NRC staff is reviewing your letter of August 3,1984 which identifies and provides justification for several apparent deviations of the Fire Protection Program at McGuire from 10 CFR 50 Appendix R. Our review is being performed with the technical assistance of the Franklin Research Center. We find that additional information, identified in the enclosure, is needed to complete this review.

Your reply to the enclosure is requested within 60 days of this letter.

If you have questions re Manager, Darl Hood, 301) at (garding 492-8060.the enclosure, contact your Project Sincerely, .

\S\

B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A

Enclosure:

As stated cc: See next page DISTR::BUTION:

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Mr. H. B. Tucker Duke Power Company McGuire Nuclear Station cc:

Mr. A. Carr Dr. John M. Barry Duke Power Company Department of Environmental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 Mr. F. J. Twogood County Manager of Mecklenburg County Power Systems Division 720 East Fourth Street Westinghouse Electric Corp. Charlotte, North Carolina 28202 P. O. Box 355 Pittsburgh, Pennsylvania 15230 Chairman, North Carolina Utilities Commission Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street Nuclear Production Department Raleigh, North Carolina 27602 P. O. Box 33189 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief Radiation Protection Branch J. Michael McGarry, III, Esq. Division of Facility Services Bishop, Liberman, Cook, Purcell Department of Human Resources and Reynolds P.O. Box 12200 1200 Seventeenth Street, N.W. Raleigh, North Carolina 27605 Washington, D. C. 20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission Route 4, Box 529 Hunterville, North Carolina 28078 Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 L. L. Williams Operating Plants Projects Regional Manager Westinghouse Electric Corporation - R&D 701 P. O. Box 2728 Pittsburgh, Pennsylvania 15230

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wr g ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REGARDING APPENDIX R DEVIATIONS MCGUIRE NUCLEAR STATIONS, UNITS 1 AND 2 The following information is needed to evaluate the Appendix R deviations discussed in the Licensee's August 3, 1984 submittal.

[ Note: Page numbers in this request refer to those of the Licensee submittal, " Deviations from Appendix R Justifications".]

1. Provide fire loading in terms of BTUs per square foot for the following areas / locations:
a. Nuclear Service Water Pumps at Elevation 716
b. Component. Cooling Water Pumps at Elevation 733
c. Turbine Driven AFW
d. Motor Driven AFW
e. Areas containing piping penetrations in reactor building shield walls
f. Auxiliary building electrical penetration rooms at Elevations 733 and 750
g. Locations having unrated HVAC duct penetrations in reactor building walls
h. Access portals to the reactor building from the auxiliary building
1. Wall locations having modified fire doors equipped with security hardware J. Area on Elevation 733 (directly above Elevation 716) having 3 inch seismic gap filled with cork Also, for items "a" through "j" above, verify that no fire hazardous equipment and/or concentrated fire load (s) exist in the vicinity of an area for which a deviation has been identified.
2. Verify that for all locations, for which a deviation has been identified, manual hose station and fire extinguisher coverage is provided.
3. Describe the spacing and/or protection afforded redundant hot shutdown cables located in the auxiliary building electrical penetration rcoms on Elevations 733 and 750 (Page 1).
4. State (and describe if applicable) whether or not safe shutdown cables / equip-ment exist in the areas having access portals to the reactor building from the auxiliary building (Page 2).
5. Identify nearby safe shutdown cables / equipment on either side of fire doors equipped with unrated security hardware (Page 3).

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