ML022550501

Technical Specification Pages for Amendment 270

ML022550501
Person / Time
Site:	Cook
Issue date:	09/09/2002
From:	Boyd R Office of Nuclear Reactor Regulation
To:	Indiana Michigan Power Co
References
TAC MB5729, TAC MB5730
Download: ML022550501 (2)

Text

2.C.(9) The steam generator tube inspection surveillance requirements of Technical Specification 4.4.5.3 have been extended until the start of cycle 17, not to exceed January 31, 2001. In the event the steam generators are replaced prior to the start of cycle 17, the retired steam generators are exempted from further surveillance under T/S 4.4.5.3.

2.C(10) Technical Specification surveillance requirements 4.6.5.3.1.b.3, 4.6.5.3.1.b.4, and 4.6.5.3.1.b.5 need not be performed until prior to ascension into Mode 4 at the completion of fuel cycle 18 refueling outage. If Unit 1 enters Mode 5 for sufficient duration prior to the fuel cycle 18 refueling outage, I&M will perform the surveillance testing required by TS 4.6.5.3.1 .b.3, 4.6.5.3.1 .b.4, and 4.6.5.3.1 .b.5.

2.C(11) During the essential service water pump replacement, a one-time extension of the Technical Specification 3.4.7.1 Action a and b requirement that an inoperable essential service water loop be restored to an operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be extended to 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />. This extension is applicable only during the preplanned replacement of an essential service water pump with a modified pump and may not be used when an essential service water pump is found to be inoperable. The extension is subject to the following conditions:

"* This allowance may be invoked once for each essential service water pump to allow replacement of the pump with a modified pump.

"* This allowance may be invoked once for each Unit 1 essential service water loop when the associated Unit 2 essential service water pump is being replaced. This will be done in accordance with Unit 2 Technical Specification 3.7.4.1 Action b.1.

"* This allowance is applicable until January 31, 2003.

"* When the essential service water loops are declared inoperable during the pump replacement, the systems supported by the essential service water system need not enter their limiting conditions for operation action statements.

2.D Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Donald C. Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988; "Donald C. Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 19, 1986; and Donald C. Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

2.E. Deleted.

2.F. Deleted.

Amendment No. 45, 49, 74, 80, 4-144, 227, 2-65, 270

-5a-2.G In all places of this license, the reference to the Indiana and Michigan Electric Company is amended to read Indiana Michigan Power Company.

2.H System Integrity The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low a practical levels. The program shall include the following:

1. Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

2.1 Iodine Monitorinq The licensee shall implement a program which will ensure the capability to accurately Renumbered determine the airborne concentration in vital areas under accident conditions. Added per per Amd. 70 Amd. 49 2-22-83 & per 1. training of personnel, 8-25-81 Amd. 175 2

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

2.J The licensee is authorized to use digital signal processing instrumentation in the reactor protection system.

3. This amended license is effective as of the date of issuance and shall expire at Added per midnight October 25, 2014. Amd. 157 10-1-91 FOR THE NUCLEAR REGULATORY COMMISSION See D. L.

Order, 11-18-77 Original Signed by Roger S. Boyd Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation

Enclosure:

Appendix A - Technical Specifications Date of Issuance: March 30, 1976 D. C. COOK UNIT 1 Amendment No. 475, 270