ML20114B583
| ML20114B583 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/19/1992 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114B585 | List: |
| References | |
| NUDOCS 9208280398 | |
| Download: ML20114B583 (7) | |
Text
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'o UNITED STATES I'
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NUCLEAR REGULATORY COMMISSION
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WASHING TON, D. C. 205$5
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l PHILADELPHIA ELECTRIC COMPANJ fMSllC SERVICE ELECTRIC AND GAS COMPANY DELMARVA P0ilER AND LIGHT COMPANY I
ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.169 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated May 18, 1992, as supplemented by letter dated July 9, 1992, complies with the standards and requirements of the i
Atomic Energy Act of 1954, as amended (the Act), and the Commission's l
rules and regulatiore set forth in 10 CFR Chapter I.
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 pubiic, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations ar.d all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating license No. DPR-44 is hereby amended to read as follows:
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9208280398 'i20819 PDR ADOCK 05000277 p
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i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as 3
revised through Amendment No.169, are hcreby incorporated in the i
license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license a.nendment is effective as of its date of issuance.
FOR THE NUCLEAR REGt1LATORY COMMISSION i
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p'pf Charles L. Miller, Director 3
Project Directorate I-2 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation Attcchment:
Changes to the Technical Specifications 1
Date af Issuance: August 19, 1992 f
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ATTACHMENT TO LICENSE AMENDMENT NO. 169 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET N0. 50-277 Replace the following pages of the Appetidix A Technical Specifications with the enclosed pages.
The re'/ised areas are indicated by marginal lines.
Remove ids e_r_t 147 147 J
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PBAPS Ii j
LIMITING CONDITIONS FOR OPERATION SURVEILLAWCE REQUIREMENTS l
3.6,0. Safety and Relief _yalves 4.6.D Safety und Relief Valves 1.
During reactor pcwer operating 1.
At least one safety valve conditions and prior to and 5 relief valves shall be reactor startup from a Cold checked or replaced with bench Condition, or whenever reactor checked valves every 24 l
coolant pressure is greater months.
All valves will be I
l thanatmosphericandtemg-tested every two cycles.
stature greater than 212 F, l
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.
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except as specified in 3.6,0.2.
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2.
At least one of the relief 2.
valves shall be disassembled (a) From and after the date that and inspected every 24 months..
i the safety valve function of l
one relief valve is made or 3.
The integrity of the relief safety l
found to be inoperable, con-valve bellows shall be continuously tinued reactor operation is monitored. The switches shall
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permissible only during tne be calibrated once per operating succeeding thirty days unless cycle.- The accumulators and such valve function is sooner air piping shall be inspected g
made operable, for leakage using leak test fluid once per operating cycle.
4 (b) From and after the date that the safety valve function of 4.
With the reactor pressure l
two relief valves is made or 2 100 psig, each relief valve-found to be inoperable, shall be manually opened once a
i r.ontinued 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 i
made operable, valve closure or load reduction or
_ change in measured steam flow 3.
If Specifiction 3.6.0.1 is not depending on the operating j
met, an orderly shutdown shall configuration existing during j
be initiateo and the reactor the test.
coolant pressure shall be reduced-i to atmospheric within'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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Amendment No. I6. 35. 169
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UM7ED STAVES l'
~k NUCLEAR REGULATORY COMMISSION
.t WASHINGTON D. C. 2055$
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1 PHILADELPHIA ELECTRIC COMPANY 1
PUBLIC SERVICE ELECTRIC AND GAS CQMPANY DELMARVA POWER AND LIGHT COMPANl i
ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278
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EA_CH BOTT0ti ATOMIC POWER STATION. UNIT N0. 3 AMEN 0 MENT TO FACillTY CPERATING LICENSE Amendment No.173 License No. DPR-56 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated May 18, 1992, as supplemented by letter dated July 9, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as cmended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1.
l 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 (1) 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
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t (2) Technical Specifications j
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.173, are hereby incorporated in the 4
I license.
PECO shall operate the facility in accordance with the
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Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance.
i FOR THE NUCLEAR REGULATOR COMMISSION
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5' fygthalesL. Miller, Directer l
Project Directorate 1-2 Division of Reactor Projects - I/II j
Office of Nuclear Reactor Regulation 1
Attachment:
Changes to the Technical j
Specifications l
Date of Issuance:
August 19, 1992 i
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 173 l
l' FAClllTY OPERATING LICENSE NO. OPR-56 I
DOCKET NO. 50-278 1
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Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
ReJsle Insert 147 14/
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Unit 3 PEAPS LIMITING CONDITIONS F00, OPERATION SURVEILLANCE RE_QUIREMENTS 3.6,0. Safety and Relief Valves 4.6.0 Safety and Relief Valves During reactor power operating 1.
At least one safety valve conditions and prior to and 5 relief valves shall be reactor startup from a Cold Condition, or whenever reactor checked or replaced with bench checked valves every 24 l
coolant pressure is greater months. All valves will be than atmospheric and temn-tested every two cycles.
b 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.
l 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 accumulators and such valve function is sooner air piping shall be inspected made operable, for leakage using leak test (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 inoperaole, shall be manually opened once continued reactor operation per operating cycle. Verificaticn is permissible only during the that each relief valve has opened succeeding seven d.ys unless shall either be by observation 7
such valve function is sooner of compensating tutbine bypass made operable, valve closure or load reduction or change in measured steam flow 3.
If Specifiction 3.6,0.1 is not depending on the operating met, an orderly shutdown shall be initiated and tha reactor configuration existing during the test, coolant pressure shall be reduced to atmospheric within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
-147 Amendment No. 25,173 l
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