ML19317F699
| ML19317F699 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/20/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317F691 | List: |
| References | |
| NUDOCS 8001230594 | |
| Download: ML19317F699 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 1 TO LICENSE NO. NPF-3 THE TOLED0 EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 DOCKET N0. 50-346 INTRODUCTION By telecopy dated May 20, 1977, the Toledo Edison Company requested a change in the Technical Specifications appended to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit 1.
The proposed change allows as a limiting condition for operation in Modes 3, 4 and 5 that all reactor coolant pumps and decay heat removal train pumps can be de-energized for up to one (1) hour to accomodate decay heat removal pump switching operations, provided no operations are permitted which could cause dilution of the reactor coolant system boron concentration.
DISCUSSION The Davis-Besse Nuclear Power Station, Unit 1 f>,'lity Operating License No. NPF-3 conditions Part (3), item (1), togeWr with Appendix "A" Technical Specification 3.4.1, item (a) fo '. odes 3, 4 and 5 imposed an operating restriction preventing the er '.etion of the Toledo Edison Company's preoperational test program require 6 p.1or to entering Mode 4(hot shutdown).
The identified conditions preclW. the applicant's ability to transfer operation from one decay hea', iemoval train to the other which is necessary to complete several testing program requirements.
The proposed changes to the technical specifications will allow the Toledo Edison Company to accommodate decay heat removal pump switching operations for preocerational testing in Modes 3, 4 and 5.
8001230 6
,-s 2-EVALUATION We recognize tnat 'tnere will be brief periods of time required for transferring from one decay heat removal train to the other train for the purposes of preoperational testing. The change in Technical Speci-fication 3.4.1, item (a) of action Modes 3, 4 and 5 does not involve any increase in the probability or consequences of accidents previously considered in our Safety Evaluation Report, Supplement I to the Safety
. Evaluation Report and the Final Safety Analysis Report where analysis shows that the reactor coolant system without reactor coolant pumps operating will provide natural circulation flow capable of assuring conservative heat transfer capability for core cooling and decay heat removal. Also, we have required that no operations be allowed during decay heat removal pump switching operations which could cause an inadvertent dilution of the reactor coolant system boron concentration.
We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having nade this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) the amendment does not involve a significant increase in the proba-bility or consequences of accidents previously considered and does not involve a significant hazards consideration, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: May 20, 1977
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