ML20057B604

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Discusses Response to GL 92-08, Thermo-Lag 330-1 Fire Barriers
ML20057B604
Person / Time
Site: Maine Yankee
Issue date: 09/17/1993
From: Trottier E
Office of Nuclear Reactor Regulation
To: Frizzle C
Maine Yankee
References
GL-92-08, GL-92-8, TAC-M83892, NUDOCS 9309220320
Download: ML20057B604 (4)


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I UNITED STATES t

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20566-0001 September 17, 1993 Docket No. 50-309 Mr. Charles D. Frizzle, President Maine Yankee Atomic Power Company l

83 Edison Drive Augusta, Maine 04336

Dear Mr. Frizzle:

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SUBJECT:

MAINE YANKEE - RESPONSE TO GENERIC LETTER 92-08, " THERM 0-LAG 330-1 i

FIRE BARRIERS" (TAC NO. M83892) 1 By letter dated April 9,1993, you provided a response to Generic Letter (GL) 92-08 for Maine Yankee Atomic Power Station.

Your response states that the Thermo-Lag fire barriers installed at Maine Yankee (MY) were qualified by the l

vendor (TSI, Inc.), based on the vendor's understanding of the NRC guidance in existence at the time of installation, and that the fire barrier configurations installed at the plant are covered by the generic testing j

performed for TSI, Inc.

Your response also states that MY has not evaluated any deviations from tested configurations.

i Although Thermo-Lag barriers were evaluated and may have been considered qualified, the results of recent tests and inspections indicate that further l

actions are now necessary to address fire endurance and n.?acity derating.

Your response states that appropriate actions to resolve these concerns are being developed. These actions include cable rerouting to eliminate the need for all 1-and 3 hour-rated Thermo-Lag fire barriers, use of standard masonry fire barriers, and use of materials with the appropriate Underwriters Laboratory fire endurance rating.

In considering these alternative fire barrier systems, your selection should be properly qualified by appropriate fire endurance testing, and the appropriate ampacity derating evaluation of l

the replacement fire barrier systems used should be performed to ensure correct derating of the safety related components. This qualification testing, specimen construction techniques, and the size of the specimens tested should bound and be consistent with in-plant applications.

In addition, the qualification testing acceptance criteria should be consistent with fire endurance test standards and NRC guidance (e.g., ASTM E-119 for i

walls and building structural components; Generic Letter 86-10, Implementation of Fire Protection Requirements, Enclosure 2, Question 3.2.1, Acceptance Criteria, for raceway fire barrier systems). Compensatory measures for inoperable fire protection barriers are in place at MY and will remain in place until the necessary plant modifications are completed, and the fire barriers can be declared operable.

Your fire barrier modifications will be evaluated during 'a future NRC inspection.

Finally, the staff finds that the schedule you provided for completing these plant modifications appears reasonable.

l 9309220320 930917

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Charles D. Frizzle September 17, 1993 The information requested by this letter is within the scope of the overall burden estimate in GL 92-08, which was an average of 300 person-hours for each addressee's response. This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires on June 30, 1994.

Sincerely, Original signed by:

E. H. Trottier, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:

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OFFICIAL RECORD COPY

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FILENAME: A:\\MYM83892.LTR

Charles D. Frizzle September 17, 1993 The information requested by this letter is within the scope of the overall burden estimate in GL 92-08, which was an average of 300 person-hours for each-addressee's response. This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires on June 30, 1994.

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l Since E. H. Trottier, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page i

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Mr. Charles D. Frizzle Maine Yankee Atomic Power Station i

cc:

Mr. Charles B. Brinkman Mr. James R. Hebert, Manager Manager - Washington Nuclear Nuclear Engineering and Licensing Operations Maine Yankee Atomic Power Company Combustion Engineering, Inc.

83 Edison Drive 12300 Twinbrook Parkway, Suite 330 Augusta, Maine 04336 Rockville, Maryland 20852 Mr. Robert W. Blackmore Thomas G. Dignan, Jr., Esquire Plant Manager Ropes & Gray Maine Yankee Atomic Power Company One International Place P.O. Box 408 Boston, Massachusetts 02110-2624 Wiscasset, Maine 04578 Mr. Uldis Vanags Mr. G. D. Whittier, Vice President State Nuclear Safety Advisor Licensing and Engineering State Planning Office Maine Yankee Atomic Power Company State House Station #38 83 Edison Drive Augusta, Maine 04333 Augusta, Maine 04336 Mr. P. L. Anderson, Project Manager Mr. Patrick J. Dostie Yankee Atomic Electric Company State of Maine Nuclear Safety 580 Main Street Inspector Bolton, Massachusetts 01740-1398 Maine Yankee Atomic Power Company P. O. Box 408 Regional Administrator, Region I Wiscasset, Maine 04578 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Graham M. Leitch King of Prussia, Pennsylvania 19406 Vice President, Operations Maine Yankee Atomic Power Company First Selectman of Wiscasset P. O. Box 408 Municipal Building Wiscasset, Maine 04578 U.S. Route 1 Wiscasset, Maine 04578 Mr. J. T. Yerokun Senior Resident Inspector Maine Yankee Atomic Power Station U.S. Nuclear Regulatory Commission P. O. Box E Wiscasset, Maine 04578

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