ML20247H620

Forwards Safety Evaluation Granting Request for Relief from Requirements of ASME Section XI for Plant

ML20247H620
Person / Time
Site:	Fort Calhoun
Issue date:	07/24/1989
From:	Bournia A Office of Nuclear Reactor Regulation
To:	Morris K OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20247H625	List: ML20247H620 ML20247H642
References
TAC-71988, NUDOCS 8907310082
Download: ML20247H620 (3)

Text

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" July 24. 1989 Docket No. 50-285, Mr. Kenneth J. Morris Division Manager - Nuclear Operations Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102

SUBJECT:

RELIEF FROM REQUIREMENTS OF ASME SECTION XI, FORTCALHOUNSTATION(TACNO.71988)

In your letter dated January 18, 1989, you identified two welds in'the Raw Water System that could not be hydrostatically tested following' a modification to the system in accordance with the.1SME Code requirements. 10CFR50.55a(g)(4)-

requires that applicable ASME Code components of a pressurized water-cooled-nuclear power facility meet the requirements set forth in Section XI, " Rules for Inservice. Inspection of Nuclear Power Plant Components," of ASME Boiler and Pressure Vessel Code except where specific written relief has been granted'by the Commission. Your January 18, 1989 letter addresses this relief request.

The staff has reviewed your submittal and determined that the relief. requested may be granted. The staff's findings are indicated in the enclosed Safety Evaluation based on your information.

Sincerely,

/s/

Anthony Bournia, Project Manager Project Directorate - IV Division of Reactor. Projects - III, IV, Y and Special Projects Office of Nuclear Reactor-Regulation

Enclosure:

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July 24, 1989 Docket No. 50-285-1 Mr. Kenneth J. Morris Division Manager - Nuclear Operations Omaha Public Power District l

1623 Harney Street Omaha, Nebraska 68102

SUBJECT:

RELIEF FROM REQUIREMENTS OF ASME SECTION XI, FORT CALHOUN STATION (TAC NO 71988)

In your letter dated January 18, 1989, you identified two welds in the Raw Water System that could not be hydrostatically tested following a modification to the systen in accordance with the ASME Code requirements.

10CFR50.55a(g)(4) requires that applicable ASME Code components d 1 pressurized water-cooled nuclear power facility meet the requirements sei arth in Section XI, " Rules for Inservice Inspection of Nuclear Power Plant a sponents," of ASME Boiler and i

Pressure Vessel Code except where specific written relief has been granted by the Commission. Your January 18, 1969 letter addresses this relief r0 guest.

The staff has reviewed your submittal and determined that the relief requested may be granted. The staff's findings are indicated in the enclosed Safety Evaluation based on your information.

Sincerely.

(luthe

/$%ano Anthony Bournia, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV,.V and_Special Projects Office of Nuclear Reactor Regulation i

Enclosure:

i As stated

]

l cc w/ enclosure:

See next page 3

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Mr. Kenneth J. Morris Fort Calhoun Station Omaha Public Power District Unit No. I cc:

1 Harry H. Voigt Esq.

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C.

20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Phillip Herrell, Resident Inspector U.S. Nuclear Regulatory Commission i

P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager q

Washington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 PJan Plaza Drive, Suite 1000 Arlington, Texas 76011 i

Harold Borchert, Director Division of Radiological Health i

Department of Health 301 Centennial Mall, South i

P.O. Box 95007 i

Lincoln, Nebraska 68509 Mr. G. R. Peterson, Manager Fort Calhoun Station P. O. Box 399 Fort Calhoun, Nebraska 68023 Y

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