ML20128P529
| ML20128P529 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/12/1993 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128P532 | List: |
| References | |
| NUDOCS 9302240400 | |
| Download: ML20128P529 (4) | |
Text
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' UNITED STATES i
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- NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20006.
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY l
ATLANTIC CITY ELECTRIC COMPANY
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DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2-AMENDMENT TO FACILITY OPERATING LICENS1'
-Ame6dmentNo.172 License No. OPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The ap)1ication for amendment by-Philadelphia Electric Company, et.
al. (tie licensee) dated February 2,1993,,as supplemented by letter dated February 8, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended.(the Act), and the-Comission's rules and regulations set forth in 10.CFR Chapter 1.
B.
The facility will operate in conformity with:the-application, the provisions of the Act,-and the rules and regulations of the.
Commission; C.
There is reasonable-assurance-(i) that~the activities authorized by this amendment can be conducted without endangering the health and.
safety of the public,.and (ii) that such activities will be conducted-in compliance with the Comission's regulations;-
1 D.
The-issuance of this amendment will not be inimical to the common -
defense and security o'r to the health or safety of the public; and!
E.
The issuance of this amendment is-in accordance with P R Part 51 of the Comission's regulations and all applicable.requiricents have been satisfied.
2.
Accordingly.- the-license.is amended by changes to the : Tech'nical Specifications as indicated in the attachment to this license l amendment, and paragraph 2.C(2)- of Facility Operating License No. DPR-44 is hereby-amended to read as follows:
-9302240400-930212
- PDR-ADOCK 05000277
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l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.172, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and is to remain in effect until the next outage of sufficient duration requiring a drywell entry.
The amendment shall expire no later than February 28, 1994.
FOR THE NUCLEAR REGULATORY COMMISSION N M 124, I M b Charles L. Miller Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: February 12, 1993 i
ATTACHMENT TO LICENSE AMENDMENT NO.172 FACILITY OPERATING LICENSE NO. DPR-44 QQU ET NO. 50-277 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised areas are indicated by marginal lines.
Remove Insert 147 147 9
Unit 2 PBAPS LlHITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.6.D Safety and Relief Valves 4.6.D Safety and Relief Valves 1.
During reactor power operating 1.
At least one safety valve conditions and prior to and 5 relief volves shall be reactor startup from a Cold checked or repleace with bench Condition, or whenever reactor checked valves every 24 coolant pressure is greater months. All valves will be than atmospheric and temp-tested every two cycles.
erature greater than 212*F, both safety valves and the The set point of the safety safety modes of all relief valves shall be as specified valves shall be operable, in Specifications 2.2.
except as specified in 3.6,0.2.
2.
At least one of the relief 2.
valves shall be disassembled (a)
From and after the date that and inspected every 24 months.
the safety valve function of one relief valve is made or 3.
The integrity of the relief safety found to be inoperable, con-valve bellows shall be continuously tinued reactor operation is monitored. The switches shall-permissible only during the be calibrated once per operating succeeding thirty days unless cycle. The. iccumulators and such valve function is sooner air piping shall be inspected g
made operable.*
for leakage using leak test fluid once per operating cycle.
(b)
From and after the date that the safety valve function of 4.
With the reactor pressure two relief valves is made or 2:100 psig, each relief valve found to be inoperable, shall be manually opened once continued reactor operation per operating cycle. Verification is permissible only during the that each relief valve has opened succeeding seven days unless.
shall either be by observation such valve function is sooner of compensating turbine bypass made operable, valve closure or load reduction or change in measured steam flow 3.
If Specification 3.6.D.1 is not depending on the operating met, an orderly shutdown shall configuration existing during be initiated and the reactor the test.
coolant pressure shall be reduced to atmospheric.vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- This 30 day LC0 has a one time extension until the next outage of sufficient duration that requires a drywell entry. This extension shall expire no'later than Feb. 28, 1994
-147-Amendment No. 16, 35, 169, 172
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