ML17332A633
| ML17332A633 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/06/1995 |
| From: | Hannon J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17332A635 | List: |
| References | |
| NUDOCS 9503150318 | |
| Download: ML17332A633 (8) | |
Text
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i POR J
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-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
- 191, 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 issuance, with full implementation within 180 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 6, 1995 C)~9(~w Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
TTACHMENT TO LICENSE AMENDMENT NO.
191 TO 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 vertical lines indicating the area of change.
REMOVE 3/4 3-55 INSERT 3/4 3-55
TABI.F. 3 3-11 POST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPFRABLE 1.
2.
3.
4..
5.
6.
7.
8.
9.
10.
11.
12.
13.
14.
15.
16.
17.
18.
Containment Pressure Reactor Coolant Outlet Temperature-T>oT (Wide Range)
Reactor Coolant Inlet Temperature-Tc<<> (Wide Range)
Reactor Coolant Pressure-Wide Range Pressurizer Water Level Steam Line Pressure Steam Generator Water Level-Narrow Range Refueling Water Storage Tank Water Level Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position Indicator -- Limit Switches***
PORV Block Valve Position Indicator -- Limit Switches Safety Valve Position Indicator -- Acoustic Monitor Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)
Containment Sump Level Containment Water Level 2.
2 2
2 2
2/Steam Generator 1/Steam Generator 2
1 1/Steam Generator+
1/Valve 1/Valve 2 Out of 3 Total 2/Core Quadrant One Train (3 Channels/Train)
Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.
PPC 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.
COOK NUCLEAR PLANT - UNIT 1 3/4 3-55 Amendment No.ff8, Nf, NH, 1N 191
1.0,R RE00C c>,
Wp~o Cy
++*+~
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 177 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
C.
The application for amendment by Indiana Michigan Power Company (the licensee) dated August 12, 1992 as supplemented April 12,
- 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 set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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-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.
177
, 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 issuance, with full implementation within 180 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes:to the Technical Specifications Date of Issuance:
March 6, 1995 ac~
Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 177 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 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 vertical lines indicating the area of change.
REMOVE 3/4 3-46 INSERT 3/4 3-46
TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTAT ON NSTRUMEN MINIMUM CHANNELS OPERABLE l.
2.
3.
4 ~
5.
6.
7 ~
8.
9 10
'1.
12 13 14.
15.
16.
17 18.
Containment Pressure Reactor Coolant Outlet Temperature Tgpz (Wide Range)
Reactor Coolant Inlet Temperature -
Tgpgp (Wide Range)
Reactor Coolant Pressure Wide Range Pressurizer Water Level Steam Line Pressure Steam Generator Water Level Narrow Range Refueling Hater Storage Tank Water Level Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System subcooling Margin Monitor PORV Position Indicator Limit Switches***
PORV Block Valve Position Indicator Limit Switches
.Safety Valve Position Indicator Acoustic Monitor Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)
Containment Sump Level Containment Water Level 2
2 2
2 2
2/Steam Generator 1/Steam Generator 2
1 1/Steam Generator*
1**
1/Valve 1/Valve 2 Out of 3 Total 2/Core Quadrant One Train (3 Channels/Train) 1 2
- Steam Generator Hater Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.
PPC 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.
COOK NUCLEAR PLANT - UNIT 2 3/4 3-46 Amendment No. 9&, 95, 44&, ~ ~
177