ML20215A628
| ML20215A628 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 06/10/1987 |
| From: | Bournia A Office of Nuclear Reactor Regulation |
| To: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| Shared Package | |
| ML20215A631 | List: |
| References | |
| TAC-65057, NUDOCS 8706170008 | |
| Download: ML20215A628 (3) | |
Text
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- UNITED STATES O
8' NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20556 f
June 10,1987 Docket.No. 50-285 Mr. R. L. Andrews Division Manager - Nuclear Production Omaha Public Power District.
1623 Harney Street Omaha, Nebraska 68102
Dear Mr. Andrews:
SUBJECT:
CHANGES TO BASES OF FORT CALHOUN STATION, UNIT 1 TECHNICAL SPECIFICATION SECTION 2.4, " CONTAINMENT COOLING" By letter dated March 26, 1987, Omaha Public Power District (OPPD) submitted
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proposed changes to the Bases to the Technical Specifications appended to Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No.1.
The proposed changes would corre'ct the Bases of the amount of heat that can be removed by the three component cooling water heat exchangers.
The Updated Safety Analyses Report (USAR), Section 9.7.5 (consistent with the Final Safety Analysis Report (FSAR)), specifigs the accident capacity of a component cogling water heat exchanger as 134 x 10 Btu /hr, resulting in a total of 402 x 10 6
Btu /hr for three component water heat exchangers instead 420 x 10 Btu /hr presently in the Bases of the Technical Specifications.
In addition, to make the Technical Specifications more explicit and make phrases and statements more accurate, the phrase "with ample reserve" and the statement, "the component cooling water system equipment is accessible for the repair 'after a. loss-of-coolant accident" are being proposed to be deleted.
Also, the reference to FSAR is proposed to be changed to USAR to reflect the current terminology.
We have reviewed your request and agree that the accident capacity of the component cooling water heat exchangers for Fort Calhoun is 402 x 10 Btu /hr.
We also concur that deletion of:
(1) the phrase "with ample reserve" is a subjective term and not definitive; and (2) the statement, "the component water system equipment is accessible for the repair after a loss-of-coolant accident,"
is somewhat misleading and not too specific to be part of a Bases to the Technical Specifications.
The last correction we agree, is an editorial correction to reflect the current terminology of USAR instead of FSAR.
A copy of our evaluation is enclosed.
Because the proposed changes are to the Bases and not to the Technical l
Specifications, an amendment to the license is not required and is not being k[300 K
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'i n,, ~ June.10, 1987 issued.. We have, however, revised the Fort Calhoun-Technical Specifications pages, 2-26:and 2-27'to denote these changes.- A copy of these revised pages.
is enclosed.
Sincerely,_
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Anthony Bournia, Project Manager Project Directorate -.IV Division of Reactor Projects - III, IV,-V and Special Projects
Enclosure:
As stated:
cc w/ enclosure:
See next page
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-Mr. R, L.:Andrews-Fort Calhoun. Station Omaha Public Power District ^
Unit No. 1 CC Harry H. Voigt, Esq.
LeBoeuf, Lamb,-Leiby & MacRae i
1333 New Hampshire Avenue, NW Washington,-D.C.
20036' 1
Mr. Jack.Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008
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Mr.' Phillip Harrell, Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 309 J
-l Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations C-E Power Systems-7910 Woodmont Avenue Bethesda, ' Maryland. 20814 Regional Administrator, Region IV j
U.S. Nuclear Regulatory Commission
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Office of Executive Director j
for Operations bl ri on a
Harold Borchert, Director l
Division of Radiological Health l
Department of Health 1
301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska 68509 W. G. Gates, Manager Fort Calhoun Station P. O. Box 399 Fort Calhoun, Nebraska 68023 1
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