ML20056G363
| ML20056G363 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/18/1993 |
| From: | Boyle M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056G364 | List: |
| References | |
| NUDOCS 9309030044 | |
| Download: ML20056G363 (4) | |
Text
o UNITED STATES
~g NUCLEAR REGULATORY COMMISSION n
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W ASHINGTON, D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY l
PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.183 i
License No. DPR-56 l '. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated January 28, 1993, complies with the standards i
and requirements of the Atomic Energy Act of 1954, as amended (the j
Act), and the Commission's rules and regulations 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 (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 and safety of the public; and t
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.
~
i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, I
and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
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9309030044 930018-PDR ADOCK-05000278 P.
PDR 1
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! i (2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.183, are hereby incorporated in the i
license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR-THE NUCLEAR REGULATORY COMMISSION i
g' O I
Michael L. Myle, Acting Director Project Directorate I-2 l
Division of Reactor Projects - I/II l
l Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical l
Specifications-i Date of' Issuance:
August 18, 1993 I
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i ATTACHMENT TO LICENSE AMENDMENT N0.183 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
Remove Insert 9
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a l3 Unit 3 PBAPS l
SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING l
1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Aeolicability:
Aeolicability:
The Safety Limits established The Limiting Safety System to preserve the fuel cladding Settings apply to trip integrity apply to those settings of the instruments variables which monitor the and devices which are provided
' fuel thermal behavior, to prevent the fuel cladding integrity Safety Limits from Obiectives:
being exceeded.
The objective of the Safety Obiectives:
Limits is to establish limits l
l which assure the integrity of The objective of the Limiting the fuel cladding.
Safety System Settings is to define the level of the process variables at which l
Soecification:
automatic protective action is l
initiated to prevent the fuel l
A. Reactor Pressure a 800 usia-cladding integrity Safety and Core Flow = 10% of Limits from being exceeded.
Rated Soecification:
The existence of a minimum critical power ratio (MCPR)
The limiting safety system i less than 1.07 for two settings shall be as specified i
recirculation loop below:
l operation,_or 1.08 for i
single loop operation, A. Neutron Flux Scram shall constitute violation of the fuel cladding
Settino (Run Mode)
To ensure that this safety When the Mode Switch is in 3
limit is not exceeded, the RUN position, the APRM neutron flux shall not be flux scram trip setting above the scram setting shall be:
established in i
specification 2.1.A for S s 0.58W + 62% - 0.5841W longer than 1.15 seconds as indicated by the process where:
l computer.
When the process computer is out of service S=
Setting in percent of l
this safety limit shall be rated thermal power assumed to be exceeded if (3293 MWt) the neutron flux exceed:
its scram' setting and a W=
Loop recirculating control rod scram does not flow rate in percent l
occur.
of design.
W is 100 for core flow of 102.5 l
million lb/hr or greater.
Amendment No. 15 -47,
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183
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