ML17328A260
| ML17328A260 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/25/1990 |
| From: | Diianni D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17328A261 | List: |
| References | |
| NUDOCS 9006130341 | |
| Download: ML17328A260 (8) | |
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e UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. 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.
137 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 November 29,
- 1988, 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.
9006i3034i 900525 PDR ADOCK 050003i5 P
PDC 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. 137,.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.
Attachment:
Changes to the Technical Specifications Date of Issuance:
Hay 25, 1990 FOR THE NUCLEAR REGULATORY COMMISSION Dominic C. DiIanni, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
137 FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by amendment number and contains marginal lines indicating the area of change.
Unit 1 REMOVE 3/4 3-26a INSERT 3/4 3-26a
TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT 6.
MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS TRIP SETPOINT ALLOWABLE VALUES a.
Steam Generator Water Level -- Low-Low b..4 kv Bus Loss of Voltage c.
Safety Injection d.
Loss of Main Feedwater Pumps 7.
TURBINE DRIVEN AUXILIARYFEEDWATER PUMPS 17% of narrow range instrument span each steam generator 3280 volts with a 2-second delay Not Applicable Not Applicable
> 16% of narrow range instrument span each steam generator 3280 +120 volts with a 2+ 2 second delay Not Applicable Not Applicable a.
Steam Generator Water Level -- Low-Low b.
Reactor Coolant Pump Bus Undervoltage
> 17% of narrow range instrument span each steam generator
> 2750 Volts--each bus
> 16% of narrow range instrument span each steam generator
> 2725 Volts--each bus 8.
LOSS OF POWER a.
4 kv Bus Loss of Voltage b.
4 kv Bus Degraded Voltage 3280 volts with a 2-second delay 3638 volts with a 2.0 min. time delay 3280 +120 volts with a 2+.2 second delay 3638 +60 volts with a 2.0 minute + 6 second time delay
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I UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
124 License No. DPR-74 The Nuclear Regulatory Commission (the Commission) has found that:
f A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated November 29,
- 1988, 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 wi 11 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-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. >24, '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:
~iay 25, IggO Dominic C. DiIanni, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 124 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by amendment number and contains marginal lines indicating the area of change.
Unit 2 REMOVE 3/4 3-25a INSERT 3/4 3-25a
TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT 6.
MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS a.
Steam Generator Water Level -- Low-Low b.
4 kv Bus Loss of Voltage c.
Safety Injection d.
Loss of Main Feedwater Pumps 7.
TURBINE DRIVEN AUXILIARYFEEDWATER PUMPS TRIP SETPOINT
> 21% of narrow range instrument span each steam generator 3280 volts with a 2 second delay Not Applicable Not Applicable ALLOWABLE VALUES
> 19.2% of narrow range instrument span each steam generator 3280 +120 volts with a 2 + 0.2 second delay Not Applicable Not Applicable a.
Steam Generator Water Level -- Low-Low
> 21% of narrow range instrument span each steam generator
> 19.2% of narro~ range instrument span each steam generator b.
Reactor Coolant Pump Bus Undervoltage
> 2750 Volts--each bus
> 2725 Volts--each bus 8.
LOSS OF POWER a.
4 kv Bus Loss of Voltage b.
4 kv Bus Degraded Voltage 3280 volts with a 2 second delay 3638 volts with a 2.0 minute time delay 3280 +120 volts with a 2 + 0.2 second delay 3638 +60 volts with a 2.0 minute + 6 second time delay