ML20134L225
| ML20134L225 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/21/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134L223 | List: |
| References | |
| NUDOCS 8509030137 | |
| Download: ML20134L225 (2) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION n
j WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 66 AND 52 TO
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FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE NORTH ANNA POWER STATION, UNITS NO. 1 AND NO. 2 DOCKET NOS. 50-338 AND 50-339
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Introduction:==
By lette-dated April 15,1985 (Serial No.85-163) the Virginia Electric and r
Power Company (the licensee) requested a change to the Technical Specifications (TS) for the North Anna Power Station, Units No. I and No. 2 (NA-182). Specifically, the proposed change would revise the NA-182 TS 3/4.9.3 from the presently speci-fied minimum decay time of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> to 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> prior to any fuel movement.
Discussion:
The NA-182 TS currently require that there be a minimum decay time of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to any movement of fuel. However, the design basis of the spent fuel pool coolers and water purification system specified in Section 9.1.3.1 of the NA-182 Updated Final Safety Analysis Report (VFSAR) assumes a minimum decay time of 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />.
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Specifically, items No. I and No. 2 of design basis 9.1.3.1 specify that the L
fuel pit cooling and refueling purification systems are designed to:
1.
Remove the residual heat produced by one-third of an irradiated core 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after reactor shutdown while maintaining the spent-fuel pit water i
temperature at or below 140*F with two fuel pit coolers and one associated pump with 113.2*F component cooling water.
2.
Remove the residual heat produced by one irradiated core 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after shutdown plus one-third irradiated core 45 days after shutdown, while maintaining the spent-fuel pit water at a temperature of 170*F or less with two fuel pit coolers and one pump with 113.2*F component cooling water.
Evaluation:
The minimum decay time of TS 3/4.9.3 must, therefore, be increased from 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> to 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> so that plant operations will remain within the envelope i
of the NA-182 UFSAR. The proposed change constitutes a more stringent surveillance requirement and is, therefore acceptable.
Finally, applicable refueling procedures have been revised to reflect the 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> decay time requirement.
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ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission.has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 551.22(c)(9). Pursuant to 10 CFR 651.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amandments.
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CONCLUSION We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date: August 21, 1985 Principal Contributor:
Leon Engle i
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