ML20049H813
| ML20049H813 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/09/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20049H811 | List: |
| References | |
| NUDOCS 8203040110 | |
| Download: ML20049H813 (2) | |
Text
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UNITED STATES
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENTS NOS. 83 AND 82 TO FACILITY
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OPERATING LICENSES NOS. DPR-44 AND DPR-56 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS C0'MPANY i
DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY k
PEACH BOTTOM ATOMIC POWER STATION. UNITS NOS. 2 AND 3 DOCKETS NOS. 50-277 AND 50-278 Introduction By letter dated October 1,1981, Philadelphia Electric Company (PECo or the licensee) requested changes to the Technical Specifications (TSs) appended to f
Facility Operating Licenses Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic I
Power Station, Units Nos. 2 and 3.
The proposed changes would allow adminis-l trative revisions to three areas. These changes involve the following items:
1.
correction to the Low-Low Reactor water level designation; 2.
correction to the responsibilities of tho Plant Operation Review Com-mittee; and 3.
modification to the startup report description.
Evaluation Our evaluation of the three proposed changes is as follows:
1.
The proposed change would correct a typographical error on Table 3.2.B l
regarding Low-Low Reactor water level to read as Low-Low-Low Reactor water level. We find that the change is administrative with no safety con:,equences and is therefore acceptable.
2.
The proposed change in TS 6.5.1.7.b is administrative in nature; it increases the authority of the Plant Operation Review Committee to the level delineated in the Standard TSs.
Therefore, we conclude the change is acceptable.
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3.
Since the testing program following the return to service requires col-lection of data at full power, the proposed change would replace the word
" power" with " full power". The change would also delete obsolete references to initial criticality and startup testing. These proposed changes are t
adninistrative without any adverse safety consequences, and we therefore find them acceptable.
i 8203040110 820209 PDR ADOCK 05000277 l
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. i-Environrental Consideration We have determined that the amendments do 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 made this determination, we have further concluded that the amendments involve an action which is insign'*icant from the standpoint of environrental impact and,. pursuant to 10 CFR 551.:'d)(4),
that an environmental impact staterent, or negative declaration and environ-mental impact appraisal need not be prepared in connection with the' issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a signi-ficant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these anendments will not be inimical to the conron defense and security or to the health and safety of the public.
Dated: February 9,1982 The principal NRC staff contributor to this Safety Evaluation was Helen Nicolaras.
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