ML20205P468
| ML20205P468 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/31/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20205P470 | List: |
| References | |
| DPR-57-A-135, TAC 63572 NUDOCS 8704030283 | |
| Download: ML20205P468 (4) | |
Text
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- h NUCLEAR REGULATORY COMMISSION 3
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET N0. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No. OPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated September 9, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 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 (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 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-57 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.135, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f$f V
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Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1987
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ATTACHMENT TO LICENSE AMENDMENT NO.135 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix A Technical Specifications with enclosed page. The revised areas are indicated by marginal lines.
Pages 3.10-1
1LIMITINGCONDITONSFOROPERATION SURVEILLANCE REQUIREMENTS 3.10.
REFUELING 4.10.
REFUELING Acolicability Applicability The Limiting Conditions for The Surveillance Requirements apply Operation apply to the fuel to the periodic testing of those handling and associated core interlocks and instrumentation used reactivity limitations.
during refueling and core alterations.
Objective Ob.lective The objective of the Limiting Conditions for Operation is to
. The objective of the Surveillance Requirements is to verify the assure that core reactivity is operability of instrumentation and within the capability of the
. interlocks used in refueling and control rods and to prevent core alterations.
criticality during refueling.
Specifications Specifications 1
A.
Refuelino Interlocks A.
Refuelino Interlocks 1.
Reactor Mode Switch 1.
Reactor Mode Switch s
The Mode Switch shall Prior to any core alterations, be locked in the REFUEL posi-the reactor mode switch refuel-l tion during core alterations ing interlocks shall be function-and the refueling interlocks ally tested. They shall be tested shall be operable except as at weekly intervals there,af ter 4
stated in Specification untti no longer required. They 3.10.E.
shall also be tested following any repair work associated with the interlocks.
2.
Fuel Grapple Hoist load 2.
Fuel Grapple Hoist load Settina Interlock Settino Interlock The fuel grapple hoist load Prior to any movement of fuel setting interlock switch assemblies or control rods 4
shall be set at 485 1 30 lbs.
within the reactor pressure vessel, this refueling interlock shall be functionally tested. It shall be tested at weekly intervals thereafter until no longer required and following any repair work associated with this interlock.
3.
Auxiliary Hoists load Settina 3.
Auxiliary Hoists Load Settino Interlock Interlock If the frame-mounted auxiliary Prior to any movement of fuel i
hoist, the monorail-mounted assemblies or control rods within auxiliary hoist, or the service the reactor pressure vessel, this platform hoist is to be used refueling interlock shall be for handling fuel with the functionally tested. It shall be head off the reactor vessel, tested at weekly intervals there-the load setting interlock after until no longer required and l
on the hoist to be used shall following any repair work associated be set at 485 1 30 lbs.
with this interlock.
8.
Fuel loadino Fuel shall not be loaded into the reactor core unless all control rods are fully inserted.
HAlCH - UNIT 1 3.10-1 I
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