B11491, Amend to Final Significant Design & Const Deficiency Rept SD-70 Re Nonmotor Operated curtain-type Fire Dampers. Initially Reported on 850116.Testing & Evaluation Will Be Extended to QA Category II & III Fire Dampers

Amend to Final Significant Design & Const Deficiency Rept SD-70 Re Nonmotor Operated curtain-type Fire Dampers. Initially Reported on 850116.Testing & Evaluation Will Be Extended to QA Category II & III Fire Dampers

ML20113C524
Person / Time
Site:	Millstone
Issue date:	03/20/1985
From:	Counsil W, Werner R NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
B11491, SD-70, NUDOCS 8504110675
Download: ML20113C524 (2)

Text

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• *<*"Ea m acm*a" soomvegatt utdf 5 EEav Cs C(heessv (203) 666-6911 as0ATHE Alf sa4Lgan genmov couraser March 20,1985 Docket No. 50-423 Bil491 Dr. Thomas E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

References:

1. W. G. Counsil letter to T. E. Murley, F0674A, dated February 22,1985.

2. U.S. Nuclear Regulatory Commission, Branch Technical Position CMEB 9.5-1, dated July 1981.

Dear Dr. Murley:

Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Design and Construction:

Non-Motor Operated Curtain-Type Fire Dampers (SD-70)

Amendment to Final Report in a January 16, 1985 telephone conversation between your Mr. T. Rebelowski and our Mr. J. Putnam, Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency in the construction of Millstone Unit No. 3 as required by 10CFR50.55(e). We determined that this is a significant deficiency for Millstone Unit No. 3 and provided you with a final report in Reference 1.

The significant deficiency involved non-motor operated curtain-type fire dampers which may not close under flow conditions. These fire dampers are used in the HVAC systems at Millstone Unit No. 3 and are manufactured by Air ,

Balance Company or Ruskin Manufacturing. '

We informed you in Reference 1 that all of the subject QA Category 1 fire dampers requiring closure under design flow would be tested in place for closure under design flow conditions. Any dampers which fail this test will be evaluated on a case-by-case basis to determine the best course of corrective action and modified accordingly.

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- Subsequent discussions with the NRC identified the need to extend this testing and evaluation to QA Category 11 and til fire dampers. Therefore, we would like to amend our final report on SD-70 to include testing in place for closure under design flow conditions for all QA Category 11 and 111 fire dampers installed in fire boundaries separating redundant safety-related areas at Millstone Unit No. 3, as defined in Reference 2.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

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_W. G. Counsi,t)

Senior Vice Pr'sident e

h By: R. P. Werner Vice President cc: Mr. 3. M. Taylor, Director

. Division of Inspection and Enforcement U.S. Nuclear Regulatory Commission Phillips Building -

7920 Norfolk Avenue Bethesda, MD 20814 4

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