ML17331A100
| ML17331A100 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/16/1993 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17331A101 | List: |
| References | |
| NUDOCS 9303230280 | |
| Download: ML17331A100 (12) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.
17O License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 27,
- 1991, 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.
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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. 170
, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 16, 1993 Ledyard B. Harsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
TTACHMENT TO LICENSE AMENDMENT NO. 17 TO 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 vertical lines indicating the area of change.
REMOVE 3/4 6-14 INSERT 3/4 6-14
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CONTAINMENT SYSTEMS 3 4.6.3 CONTAINMENT ISOLATION VALVES
.LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.
The ACTION statement of T/S 3/4.6.3 is not applicable to the containment purge supply and exhaust isolation valves, VCR-101 through 106 and VCR-201 through 206, listed in Table 3.6-1.
The Limiting Condition for Operation and its associated ACTION statement for these valves is given in Technical Specification 3/4.6.1.7.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve(s) specified in Table 3.6-1 inoperable, either:
a.
Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.6.3.1.1 The isolation valves specified in Table 3.6>>1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated
- actuator, control or power circuit by performance of a cycling test and verification of isolation time.
COOK NUCLEAR PLANT - UNIT 1 3/4 6-14 AMENDMENT NO. P$ 170
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT O.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. >53 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 21,
- 1991, complies with the standards and requirements of the Atomic Energy Act of l954, 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 5l 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 8, as revised through Amendment No.
- 153, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 16, 1993 Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 153 CILITY OPERATING ICE S
NO.
D R-74 OCKET NO. 50-3 6
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 vertical lines indicating the area of change.
REMOVE 3/4 6-13 INSERT 3/4 6-13
CONTAINMENT SYSTEMS 3 4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION POR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.
The ACTION statement of Technical Specification 3/4.6.3 is not applicable to the containment purge and exhaust isolation valves, VCR-101 through 106 and VCR-201 through 206, listed in Table 3.6-1.
The Limiting,Condition for Operation and its associated ACTION statement for these valves is given in Technical Specification 3/4.6.1.7.
APPLICABILITY'ODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve(s) specified in Table 3.6-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and eitherc a.
Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated
- actuator, control or power circuit by performance of a cycling test and verification of isolation time.
COOK NUCLEAR PLANT - UNIT 2 3/4 6-13 AMENDMENT NO.
$ 7,153
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