IR 05000369/1984028

Informs of Withdrawal of Notices of Violation & Deviation for Violation IV of Insp Repts 50-369/84-28 & 50-370/84-25 Re Electray Supporting Structural Steel Fire Effects Analysis

ML20215A690
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/22/1986
From:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Tucker H DUKE POWER CO.
References
TAC-60320, TAC-60321, NUDOCS 8610060188
Download: ML20215A690 (3)

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SEP 2 21986 Duke Power Company

@N: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:

1 SUBJECT: REPORT NOS. 50-369/84-28 AND 50-370/84-25 This letter refers to your original April 30, 1985, response and subsequent August 20, September 24, October 28, and November 4, 1985, responses to our Notice of Violation and Notice of Deviation issued March 1985, concerning activities authorized under NRC Operating License Nos. NPF-9 and NPF-17 for McGuire Nuclear Station, Units 1 and As stated in our December 19, 1985 letter, the two technical analyses which were submitted to NRC, Region II, as a part of your November 4,1985, response to further support your denial of Violation IV were referred to the Office of Nuclear Reactor Regulation (NRR) for revie Based on NRR's evaluation of your electray supporting structural steel fire effects analyses and their conclusions, i we accept your denial of Violation IV. Therefore, this violation has been rescinded. NRC Region II records have been revised to reflect the withdrawa Should you have any questions concerning this letter, please contact u

Sincerely, E!^ " J BY1 1. G -.ACS '

J. Nelson Grace

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Regional Administrator Enclosure:

Staff Evaluation of Licensee Response to Inspection Report Nos. 50-369/84-28 and 50-370/84-25 cc w/ enc 1:

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ENCLOSURE Staft Evaluation of Licensee Response To Inspection Reports 50-369/84-28 and 50-370/84-25 Dated November 4, 1985 Acceptance of Licensee's Denial of Violation IV Sections 2.C.(4) and 2.C.(7) of Operating License Nos. NPF-9 and NPF-17 for McGuire Nuclear Station, Units 1 and 2, respectively, require that Duke Power Company (the licensee) meet Section III.G of Appendix R to 10 CFR 50. Sections III.G.2.a and III.G.2.c of Appendix R require that structural steel members supporting fire barriers be provided with fire resistance equivalent to that of the fire barrie Region II conducted a special safety inspection at McGuire Nuclear Station, Units 1 and 2 on September 24 through 28, 198 During the inspection, it was noted that structural steel members supporting (1) a three-hour fire rated barrier enclosing valves 1CA-161C and ICA-162C and associated cabling in the Unit 1 mechanical pipe chase and (2) a one-hour fire barrier enclosing valves 2CA-161C and 2CA-162C and associated cabling in the Unit 2 auxiliary feedMater pump room, were not protected to provide fire resistance equivalent to that of the fire barriers. Therefore, following the Appendix R inspection on March 15, 1985, Region II issued a Notice of Violation to the licensee. This inspection finding is documented in Inspection Reports 50-369/84-28 and 50-370/84-25 and in Violation I By letter, dated November 4, 1985, the licensee submitted two technical analyses to support its denial of this violation. By memorandum dated December 12, 1985, Region II requested that the Office of Nuclear Reactor Regulation (NRR) review the licensee's analyses associated with the subject unprotected electray/ valve structural steel support On August 8,1986, NRR completed its review of the licensee's analyses. There-fore, based on NRR's evaluation, it is concluded that on the bases of the fire hazards present, the installed fire protection, the revised shutdown procedures, and the 4}-hour time line available to perform the required manual actions to open the subject safe shutdown system controlled auxiliary feedwater suction valves, that protection of the subject structural steel members with a fire rated material would not significantly increase the level of fire safet Thus, as supported by the licensee's analyses, the fireproofing for the structural steel members supporting the one-hour fire rate barrier enclosure for valves 2CA-161C and 2CA-162C and associated cabling in the Unit 2 auxiliary feedwater pump room, and the three-hour fire barrier enclosure for valves 1CA-161C and ICA-162C and associated cabling in the Unit 1 pipe chase and mechanical penetration room is not required. Therefore, we have withdrawn the violation.