ML20024J043

Accepts Changes to Operational Quality Assurance Program for Facility

ML20024J043
Person / Time
Site:	Crystal River
Issue date:	07/23/1993
From:	Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Beard P FLORIDA POWER CORP.
References
NUDOCS 9308310206
Download: ML20024J043 (4)

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o Docket No. 50-302 License No. DPR-72 j

I Florida Power Corporation j

Mr. P. M. Beard, Jr.

'I Sr. VP, Nuclear Operations ATTN:

Mgr., Nuclear Licensing P. O. Box 219-NA-21 Crystal River, FL 34423-0219 l

i Gentlemen:

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SUBJECT:

ACCEPTANCE OF CHANGES TO THE OPERATIONAL QUALITY ASSURANCE PROGRAM FOR CRYSTAL RIVER UNIT 3 On June 26, 1992, Florida Power Corporation (FPC) submitted a proposed change to the Crystal River Unit 3 (CR-3) Quality Program Description to reduce your commitment to comply with Regulatory Guide 1.54 (Revision 0), " Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants," for painting the inside of the CR-3 Reactor Building.

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As currently established, the CR-3 quality assurance program requires that paint on the inside surfaces of the Reactor Building conform with the provisions of Regulatory Guide 1.54.

In the June 26, 1992, submittal, you stated that the current program is not supporting your objective of improving the conditions of coatings within the Reactor Building for material i

preservation and appearance because of the broad application of stringent j

requirements needed to ensure that coatings would not fail if exposed to loss-of-coolant-accident (LOCA) conditions.

While all areas of the Reactor i

Building would be exposed to LOCA conditions, you asserted that only areas where flaking paint could reach the emergency sump (referred to in your submittal as "near field" and "far field" areas) should be required to be painted in accordance with the provisions of Regulatory Guide 1.54.

Therefore, you proposed to change the Quality Program commitment in Section 1.7 of the CR-3 Final Safety Analysis Report (FSAR) and to modify the plant's Requirement Outline R0-3147, " Painting and Protective Coatings," to specify i

two levels of protective coatings control for the Reactor Building. With this change, only the painted portions of the Reactor Building comprising the "near field" and "far field" areas would be considered as a Class 1 Service Level system and would be required to meet the provisions of Regulatory Guide 1.54.

The remaining areas in the Reactor Building would be exempt from those provisions, but would continue to meet high quality standards.

We have reviewed the material submitted by FPC to justify your proposed change to the CR-3 Quality Program Description, including verification of the analyses and assumptions made for determining the "near field" and "far field" areas in the Reactor Building. Although the staff considers that FPC has l

provided sufficient justification for the requested modifications to your j

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Florida Power Corporation 2

quality assurance program, the assumptions in your submittal must be considered in responding 10 NRC Bulletin 93-02 (May 11,1993), " Debris Plugging of Emergency Core Cooling Suction Strainers," or in any subsequent evaluation of sump screen blockage. With this provision, the staff has determined that the proposed changes to Section 1.7 of the CR-3 FSAR and the resultant revision of the methodology described in Requirement Outline R0-3147 are acceptable because the modified quality program for Reactor Building paint will meet the intent of Regulatory Guide 1.54.

We find that the CR-3 quality assurance program, with the proposed change, continues to meet the requirements of 10 CFR 50, Appendix B; therefore, the change is acceptable.

If there are changes to other operative quality assurance commitments existing in docketed correspondence outside of the Quality Assurance Program Description, you are obligated to notify this office.

Implementing such changes should be based on 10 CFR 50.54(a)(3).

Any questions you may have concerning this review should be directed to Caudie A. Julian, Chief, Engineering Branch, Division of Reactor Safety, at 404-331-5585.

Sincerely, original signed by J.

P.

Jaudon/for Albert F. Gibson, Director Division of Reactor Safety cc:

Gary L. Soldt Vice President, Nuclear Production Florida Power Corporation P. D. Box 219-SA-2C Crystal River, FL 34423-0219 B. J. Hickle, Director Nuclear Plant Operations Florida Power Corporation P. O. Box 219-NA-2C Crystal River, FL 34423-0219 R. C. Widell, Director Nuclear Operations Site Sepport Florida Power Corporation P. O. Box 219-NA-21 Crystal River, FL 34423-0219 (cc cont'd - See page 3)

Florida Power Corporation 3

JUL 2 3 1933 (cc cont'd)

Gerald A. Williams Corporate Counsel Florida Power Corporation MAC - ASA P. O. Box 14042 St. Petersburg, FL 33733 Attorney General Department of Legal Affairs The Capitol l

Tallahassee, FL 32304 4

Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Boulevard Tallahassee, FL 32399-0700 Administrator l

Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, FL 32301 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL 32399-2100 Chairman Board of County Commissioners Citrus County 110 N. Apopka Avenue Inverness, FL 36250 Robert B. Borsum B&W Nuclear Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852-1631 (bcc - See Page 4)

i Florida Power Corporation 4

Jty 2 3 93 bcc:

K. Landis, RII P. Holmes-Ray, RII H. Silver, NRR i

Document Control Desk NRC Resident Inspector U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, FL 34428

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