ML20034A702
| ML20034A702 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/09/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034A699 | List: |
| References | |
| NUDOCS 9004240144 | |
| Download: ML20034A702 (3) | |
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 5
>j WASHINGTON, D. C. 20b$6
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l
RELATED TO AMENDMENT NO.127 TO FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT j
FORT CALHOUN STATION, UNIT NO. 1 i
DOCKET NC. 50-285
1.0 INTRODUCTION
i By letter dated February 21, 1990, OmahaPublicPowerDistrict(licensee) requestedchangestotheFortCalhounTechnicalSpecifications-(TSs)toallow
-a performance of a functional test of the steam driven Auxiliary Feedwater (AFW) pump prior to achieving criticality.
In addition, the licensee requested some administrative changes.
t 2.0 EVALUATION l
The licensee's proposed change to TS 2.5, Page 2-28, is to allow a performance i
of a functional test of the steam driven AFW pump prior to achieving criticality.
i The present TSs allow the reactor coolant temperature to attain only 300"F unless both the electrical and steam driven AFW punps are operable. The 300*F coolant temperature will not provide enough steam for a normal operability i
test for the steam driven AFW pump. Also, the present TSs do allow either the I
electrical or steam driven AFW pump to be operable when the reactor coolant temperature is above 300*F for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This was thought to be sufficient i
time for the plant to heat up to the point that a normal operability test for the steans driven AFW pump could be run. However, for the steam driven AFW
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pump, a longer time is required due to the steam generator soak period which affects the steam system's ability to heat up. This issue was resolved and approved by the NRC staff at the_ Palisades Plant by requiring that tFa steam driven pump be operable prior to making the reactor critical. This (.. lows i
sufficient heatup of the plant to be able to perform a normal operability test l
using non-nuclear heat. Therefore, the staff finds this change acceptable.
l In addition, the licensee indicated some administrative changes to TS 2.5, i
Pages 2-28 and 2-29, which are as follows:
(1)correctingatypographical error by changing "(3) changing "FSAR" to "USAR".about" to "above", (2) inserting "
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clarification and The staff finds these acceptable, y
3.0 ENVIRONMENTAL CONSIDERATION
The amendment involves a change in a requirement with respect to the installa-tion or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that l
9004240144 900409 PDR ADOCK 050002S5 F
PDC E
may be released offsite, and that there is no significant increase in individual er cumulative occupational radiation exposures. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no.public comment on for categorical exclusion set forth in 10 CFR Section 51.22(c)y criteria such' finding. Accordingly, the amendment meets the eligibilit (9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assess-ment need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Commission's regulations,.
and the issuance of the amendment will not be inimical to the common defense 4
i and security or to the health and safety of the public, Date: April 9, 1990 Principal Contributcr:
A. Bournia 1
i
Document flane:
FC SHOLLY/75924 Requestet's ID:
00f;ES Author's llame:
P. Milano Document Conrr,ents:
MASTER SHOLLY FOR DUP. DO NOT DELETEl 4
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