ML20206A663

Forwards Safety Evaluation Supporting Util 861024 Request for Relief from Requirements in Section XI of ASME Boiler & Pressure Vessel Code Re Visual Exam of Accessible Areas of Reactor Pressure Vessel at Approx 3-yr Intervals

ML20206A663
Person / Time
Site:	Fort Calhoun
Issue date:	04/01/1987
From:	Thadani A Office of Nuclear Reactor Regulation
To:	Andrews R OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20206A667	List: ML20206A663 ML20206A685
References
TAC-63318, NUDOCS 8704080128
Download: ML20206A663 (2)

Text

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.APR 1 1987

-Docket No. 50-285 .

(IISTRTRllTLON htcket Filed EJordan L ._ NRC PDR BGrimes -

• Mr. R. L. Andrews _

L PDR JPartlow Division Manager - Nuclear Production PBD#8 Rdg NThompson

- Omaha Public Power District. FMiraglia WPaulson 3 1623 Harney Street OGC-Beth PKreutzer Omaha, Nebraska 68102 ACRS-10 Gray File.

SUBJECT:

RELIEF FROM REQUIREMENTS OF SECTION XI-0F THE'AMERICAN SOCIETY -

0F MECHANICAL ENGINEERS (ASME) BOILER AND PRESSURE VESSEL CODE-By_ letter dated October 24, 1986, you requested relief from the requirements set forth in Section XI, Rules.for Inservice Inspection of Nuclear Power Plant Components, of the ASME Boiler and Pressure Vessel Code for the Fort Calhoun '

Station, Unit No. 1. In your letter, you' identified a specific ASME Code requirement that you determined to be impractical to perform and you requested relief from this requirement pursuant to 10 CFR 50.55a(g)(5)(iii). The relief request proposes to eliminate the visual examination of the accessible areas of the reactor pressure vessel at approximately 3 year intervals.

The NRC staff has completed its review of the information you provided to sup-port your determination. A copy of the staff's Safety Evaluation is enclosed.

Pursuant to 10 CFR 50.55a(g)(6)(i), the staff concludes that relief may be granted as requested to eliminate the VT-3 visual examination of the reactor vessel interior, except when the core support barrel is' removed, provided that you implement an alternative program consisting of performing the Examination Category B-N-1, Item ~No. B13.10 requirement each time the core support barrel is removed.

The staff has determined that this action is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest, giving due consideration to the. burden upon the licensee that could result if the code' requirements were imposed on the facilir.y.

Sincerely, Original sigend by:

8704080128 870401 Ackot 'ihrulani PDR ADOCK 05000285 Ashok C. Thadani, Director PDR PWR Project Directorate #8 Division of PWR Licensing-B

Enclosure:

Safety Evaluation .,

cc w/ enclosure:

-See.next page ,

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_} i Mr. R.'L. Andrews -

Fort Calhoun Station 0maha Public Power District ~ Unit No. 1 4 cc:

Harry H. Voigt,. Esq.' .

LeBoeuf,~; Lamb, Leiby'& MacRae

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1333 New Hampshire. Avenue, NW Washington,-D.C. 20036E

. .Mr. Jack Jensen,1 Chairman.

Washington County Board of Supervisors Blair, Nebraska -68008-Mr. Phillip Harrell, Resident _ Inspector-U.S. Nuclear Regulatory Commission

. P. O. Box 309 2 -Fort Calhoun, Nebraska- 68023

-Mr. Charles B. Brinkman, Manager

. Washington Nuclear Operations C-E Power Systems-i 7910 Woodmont Avenue Bethesda, Maryland 20814 ,.

Regional Administrator,_ Region IV U.S. Nuclear' Regulatory- Commission Office of_ Executive Director

-for Operations 611.Ryan_ Plaza Drive,' Suite 1000 Arlington, Texas 76011 Harold Borchert, Director

. Division of Radiological Health

' Department of Health 301 Centennial Mall, South

' P.O. Box 95007 Lincoln, Nebraska 68509 l

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