ML20246P415
| ML20246P415 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/30/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246P412 | List: |
| References | |
| NUDOCS 8909110110 | |
| Download: ML20246P415 (2) | |
Text
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UNITED STATES
['p NUCLEAR REGULATORY COMMISSION 1
- p WASHINGTON D. C. 20555
%;.....}
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 33 TO FACILITY OPERATING LICENSE NO. NPF-37 AND AMENDMENT NO. 33 TO FACILITY OPERATING LICENSE NO. NPF-66 COMMONWEALTH EDISON COMPANY BYRON STATION, UNITS I AND 2 DOCKET N05. 50-454 AND 50-455
1.0 INTRODUCTION
l By letter dated April 7,1989, Commonwealth Edison Company (CECO), the licensee, submitted a proposed amendment to Facility Operating Licenses NPF-37 and NPF-66 for Bryon Station, Units I and 2.
The proposed amendment removes two motor-operated valves from Technical Specification Tables 3.8-2a and 3.8-2b.
2.0 DISCUSSION AND EVALUATION Motor-operated valves OSX063A and OSX063B are the essential service water inlet valves to the control room chillers. They were originally designed to isolate essential service water from the chillers if the essential service water temperature was close to the freezing point.
It has since been determined that this was unnecessary because the essential service water temperature during the winter does not decrease to a point recuiring chiller isolation.
Therefore, the licensee, prior to the issuance of the operating license for Unit 1, converted these motor-operated valves to manual locked open valves.
This minimizes the pctential of an inadvertent closure of these valves interrup-ting the water supply to the control room chillers.
Since these valves are now manual, they do not meet the criteria for inclusion in Technical Specification 3.6.4.2, Motor-Operated Valves Thermal Overload Protection Devices.
Thus we conclude that removing these two valves, OSX003A and OSXO63B, from Tables 3.8-2a and 3.8-2b is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
The amendment involves 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 amendment involves 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 exposures. The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public coment on such finding. Accordingly, the amendment meets the eligibility criteria for 8909110110 890830 DR ADOCK 0500 4
s.
4 categorical exclusion set forth in 10 CFR Section 51.22(c)(9).
Pursuant to 30 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
The staff has further 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 this amendment will not be inimical to the common defense and security or the health and safety of the public.
Principal Contributor: Leonard N. Olshan Dated:
August 30, 1989
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