ML17332A908

Amend 185 to License DPR-74,deleting TS 3/4.3.4,associated Bases & Associated Index Listings for Unit 2 Turbine Overspeed Protection Sys

ML17332A908
Person / Time
Site:	Cook
Issue date:	09/01/1995
From:	John Hickman NRC (Affiliation Not Assigned)
To:
Shared Package
ML17332A909	List: ML17332A908 ML17332A910
References
NUDOCS 9509080291
Download: ML17332A908 (9)

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UNITED STATES NUCLEAR REGULATORY COMMlSSION 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.

185 License No.

DPR-74 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 15,

1994, as supplemented June 29,

1995, 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.

950908029i 95090i PDR-,,ADQCK 050003ib P

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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-74 is hereby amended to read as follows:

Technical S ec'fications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.

185

, 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:

September 1, ]995 ohn B. Hickman, Project Manager Project Directorate 111-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

185 FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NO.

50-316'evise 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 V

XI 3/4 3-56 3/4 3-57 B 3/4 3-3 INSERT V

XI B 3/4 3-3

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CABI B 3/4 0-1 3/4.1.1 3/4.1.2 V

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BORATION CONTROL B 3/4 1-1 BORATION SYSTEMS................................

B.3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES..................

B 3/4 1-4 3/4.2.1 OWER AXIAL FLUX DIFFERENCE B 3/4 2-1 3/4. 2. 5 3/4.2.6 DNB PA1MTERS e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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ALLOWABLE POWER LEVEL 3/4.2.2 and 3/4.2 '

HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4.2.4 QUADRANT POWER TILT RATIO B 3/4 2-4 B 3/4 2-5 B 3/4 2-5 B 3/4 2-5 4

NS UMENT 0

3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAF~~

FEATURE INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-1 B 3/4 3-la l

4 4 REACTOR COO 3/4.4.1 REACTOR COOLANT LOOPS 3/4.4.2 and 3/4.4.3 SAFETY VALVES 3.4.4.4 RESSURIZER

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3/4.4.5 STEAM GENERATOR TUBE INTEGRITY...............

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3.4.4.7 CHEMISTRY B 3/4 4-1 B 3/4 4-2 B 3/4 4-2 B 3/4 4-2a B 3/4 4-3 B 3/4 4-4 B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 2 XI AMENDMENT NO.

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185

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STRUM ENTA ON BASES 3 4 3

3 6

POST-ACCIDENT NSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.

3 4.3.3.7 Deleted.

3 4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.

This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

Use of containment temperature monitoring is allowed once per hour if containment fire detection is inoperable.

3 4 3.3.9 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the Paste Gas Holdup System.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C.

Cook Nuclear Plant.

COOK NUCLEAR PIANT - UNIT 2 B 3/4 3-3 AMENDMENT NO. 44, 445, 440 185

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3/4. 2. 5 DNB PPGUQfETERS ODE 1

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3/4 2-1 3/4 2-5 3/4 2-9 3/4 2-13 3/4 2-15 3/4 2-17 3/4 2-19 4

3 NSTRUMENT T 0 3/4.3.1 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-1 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation Movable Incore Detectors Seismic Instrumentation Meteorological Instrumentation Remote Shutdown Instrumentation Post-Accident Instrumentation Fire Detection Instrumentation Explosive Gas Monitoring Instrumentation......

3/4 3-34 3/4 3-38 3/4 3-38a 3/4 3-39 3/4 3-42 3/4 3-45 3/4 3-50 3/4 3-53 3 4 4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOIANT CIRCUIATION Startup and Power Operation...........................

3/4 4-1 COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. 4S, 402 185

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