ML17329A374
| ML17329A374 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/03/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17329A375 | List: |
| References | |
| NUDOCS 9202100174 | |
| Download: ML17329A374 (4) | |
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~O 0y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON.O. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 161 License No. DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated January 22, 1992, 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 wil'1 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.
9202i00i74 920203 PDR ADOCK 050003i5i PDR
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-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
ig, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 3, ig92 L. B. Marsh, Director Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
161 FACILITY OPERATING LICENSE NO.
DPR>>58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment nUmber and contain marginal lines indicating the area of change.
RENOVE 3/4 3-55 INSERT 3/4 3-55
POST-ACCIDENT MONITORING INSTRUMENTATION A
Oo INSTRUMENT
- 1. Containment Pressure
- 2. Reactor Coolant Outlet Temperature-THOT (Wide Range)
- 3. Reactor Coolant Inlet Temperature-TC ~ (Wide Range)
- 4. Reactor Coolant Pressure-Wide Range
- 5. Pressurizer Water Level 6.
Steam Line Pressure 7.
Steam Generator Water Level-Narrow Range
- 8. Refueling Water Storage Tank Water Level
- 9. Boric Acid Tank Solution Level 10.Auxiliary Feedwater Flow Rate 11.Reactor Coolant System Subcooling Margin Monitor 12.PORV Position Indicator -- Limit Switches*~
13.PORV Block Valve Position Indicator -- Limit Switches 14.Safety Valve Position Indicator -- Acoustic Monitor 15.Incore Thermocouples (Core Exit Thermocouples) 16.Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication) 17.Containment Sump Level 18.Containment Water Level MINIMUM CHANNELS
~OPERABL 2
2 2
2 2
2/Steam Generator 1/Steam Generator 2
1 1/Steam Generator 1/Valve 1/Valve 1/Valve~
2/Core Quadrant One Train (3 Channels/Train) 2 Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.
PRODAC 250 subcooling margin readout can be used as a substitute for the subcooling monitor instrument.
Acoustic monitoring of PORV position (1 channel per three valves
- headered discharge) can be used as a substitute for the PORV Indicator - Limit Switches instruments.
- The requirements for these instruments will become effective after the level transmitters are modified or replaced and become operational.
The schedule for modification or replacement of the transmitters is described in the Bases.
- Pressurizer safety valve (SV-45A) position indicator acoustic monitor QR-107A is exempted from the above requirements until the end of Cycle 12.
Amendment No. 406, 414 (Effective before start up following the refueling outage currently scheduled in 2/89),