ML17332A598
| ML17332A598 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/23/1995 |
| From: | Hannon J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17332A599 | List: |
| References | |
| NUDOCS 9503060264 | |
| Download: ML17332A598 (8) | |
Text
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uN)TED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20M!i4001 DIANA MICHIGAN POWER COHPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.
19O License No.
DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company, (the licensee) dated November 18,
- 1994, 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.
i 9503060264 9'50223 PDR ADOCK 05000315 P......
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. 190
, 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:
February 23, 1995 I
John N. Hannon, Directo}
Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
190 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 0-2 INSERT 3/4 0-2
3 4 0 APPLICABILITV SURVEILLANCE RE UIREHENTS 4.0.1 Surveillance requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveil1ance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
4.0.3 Performance of a
Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.
Surveillance requirements do not have to be performed on inoperable equipment.
4.04 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1,
2, and 3
components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1,
2, and 3
components and inservice testing of ASME Code Class 1,
2 and 3
pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.
COOK NUCLEAR PLANT-UNIT 1 3/4 0-2 AMENDMENT NO.
<A,~,190
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UNITED STATES XueLEAR REGULATORY GOIVIMISSION WASH1NGTON, 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.
>76 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 November 18,
- 1994, 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-74 is hereby amended to read as follows:
Technical S ec icat ons The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
- 176, 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:
February 23, 1995 John N. Hannon, Director Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
176 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 0-2 INSERT 3/4 0-2
~ ~
3 4 0 APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.1 Surveillance requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.
Surveillance requirements do not have to be performed on inoperable equipment.
4'4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
a ~
Inservice inspection of ASME Code Class 1,
2, and 3
components and inservice testing of ASME Code Class 1,
2 and 3
pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.
COOK NUCLEAR PLANT-UNIT 2 3/4 0-2 AMENDMENT NO. $ 3,j30, 176