ML20058G221
| ML20058G221 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  (DPR-56-A-187) |
| Issue date: | 11/29/1993 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058G225 | List: |
| References | |
| NUDOCS 9312090136 | |
| Download: ML20058G221 (4) | |
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E UNITED STATES i
NUCLEAR REGULATORY COMMISSION -
WASHINGTON, D.C. 20555-0001
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PHILADELPHIA ELECTRIC COMPANY 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'.187 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission).has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated November 22, 1993,' complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules.and regulations setL forth in 10 CFR Chapter I; B.
The facility will operate in conforn ty 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 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:
9312090136 931129
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yDR ADOCK 05000278' PDR
. t (2) Technical Specifications t
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.187, are hereby incorporated in the i
license.
PEC0 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 pLr+ '
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Jose A. Calvo, Assistant Director for Region I Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 29. 1993 l
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9 ATTACHMENT TO LICENSE AMENDMENT NO.187 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 area is indicated by a marginal.line.
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Unit 3 PBAPS j
i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.A Reactivity limitations 4.3.A Reactivity limitations (Cont'd)
(Cont'd) f.
Inoperable control rods shall be positioned such that specification i
3.3.A.1 is met.
In addition, during
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reactor power operation, no more than one control rod in any 5 x 5 array may be operable (at least 4 operable control rods must separate any 2 inoperable ones).
If this l
Specification cannot be met the I
reactor shall not be started, or if at power, the reactor shall be brought to a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Control Rods 1.
Each control rod shall be B. Control Rods coupled to its drive or completely inserted and the
- 1. The coupling integrity shall control rod directional be verified for each withdrawn control valves disarmed control rod as follows:
electrically except as in 3.3.B.I.a.
This requirement
- a. When a rod is withdrawn-does not apply in the refuel the first time after each condition when the reactor refueling outage or after is vented. Two control maintenance, observe discernible i
rod drives ma be removed response of the nuclear l
as long as Specification 3.3.A.1 instrumentation and rod l
is met.
position indication for the " fall-in" and " full-out"
- a. For control rod 54-35, for position. However, for initial the remainder of cycle 10 (to rods when response is not be completed before 10/30/95).
discernible, subsequent l
exercising of these rods after j
If coupling cannot be the reactor is above the Rod Worth t
accomplished, the uncoupled control Minimizer low power setpoint rod may be withdrawn when 210%
shall be performed to verify l
of rated thermal power instrumentation response.
l only if all the following conditions are satisfied:
- b. When the rod is fully withdrawn the first time
- 1) no other uncoupled control after each refueling outage rod is withdrawn; or after maintenance observe that the drive does not go
- 2) the uncoupled control rod to the overtravel position.
L may not be withdrawn past notch position 46.
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-101-Amendment No. I6. G.153. I66 187 f
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