ML17332A948

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Amends 201 & 186 to Licenses DPR-58 & DPR-74,respectively, Deleting TS Section & Tables Titled Conponent Cyclic or Transient Limits & Relocate Info to Updated Final Safety Analysis Rept
ML17332A948
Person / Time
Site: Cook  
Issue date: 09/28/1995
From: John Hickman
NRC (Affiliation Not Assigned)
To:
Shared Package
ML17332A949 List:
References
NUDOCS 9510050013
Download: ML17332A948 (21)
v • d • e


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 201 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 12, 1993 and supplemented November 18,

1994, May 30,
1995, and August 8,
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;

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 gk 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.

'75i00500f3 950928 PDR ADOCK 050003i5 I

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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.

201

, 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, with full implementation within 45 days.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 28, 1995 ohn B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

2O1 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 XV 5-9 5-10 5-11 5-12 6-13 6-20 INSERT XV 5-9 5-10 6-13 6-20

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9 COOK NUCLEAR HANT - UNIT 1 AMENDMENT NO. 389, ~ 201

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ESIGN

~CAl'ACT 5.6.4 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies.

7 SE S IC CLASSI C TION 5.7.1 Those structures, systems and components identified as Category I Items in the FSAR shall be designed and maintained to the original design provisions contained in the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

8 METEROLOGICAT.

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0 5.8.1 The meterological tower shall be located as shown on Figure 5.1-3.

COOK NUCLEAR PLANT - MIT 1 5-9 AHENDMENT NO

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6.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.

b.

Deleted.

c.

Deleted.

d.

PROCESS CONTROL PROGRAM implementation.

e.

OFFSITE DOSE CALCULATIONMANUALimplementation.

f.

Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.

Component Cyclic or Transient Limits program, which provides controls to track the UFSAR, Section 4.1, cyclic and transient occurrences to ensure that components are maintained within the limits.

6.8.2 Each procedure and administrative policy of Specification 6.8.1 above, and changes thereto, including temporary changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above.

6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples foriodines and particulates under accident conditions. The program willinclude the following:

a.

Training of personnel, b.

Procedures for sampling and analysis, Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEARPLANT-UNIT1 Page 6-13 AMENDMENTVl, 4$4, 489, 4',

201

CO 6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

h.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environment.

e.

Records of transient or operational cycles for those facility components identified in the Updated Final Safety'Analysis Report.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members 'of the Plant Staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the QA Manual.

j.

Records of reviews performed for changes made to procedures or equipment or review of tests and experiments pursuant to 10 CFR 50.59.

m.

Records of meetings of the PNSRC and the NSDRC.

Records of radioactive shipments.

Records of the service lives of hydraulic snubbers including the date at which service life commences and associated installation and maintenance records.

1 Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6 TATTON PRO CT ON 0

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

COOK NUCLEAR PIANT - UNIT 1 6-20 AMENDMENT NO. 80, 454, ~

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&4001 DIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 186 License No.

DPR-74 l.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated November 12, 1993 and supplemented November 18,

1994, Hay 30,
1995, and August 8,
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

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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 ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.

186

, 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, with full implementation within 45 days.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 28, 1995 Mohn B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

T ACHMENT TO LICENSE AMENDMENT NO.

186 ACILITY 0 TING 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.

REMOV XV 5-9 5-10 5-11 5-12 6-13 6-20 INSERT XV 5-9 5-10 6-13 6-20

INDEX S

G ES HAEC'~ON Exclusion Area..................

Low Population Zone

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DESIGN FEATURES CRITICALITY NEW FUEL 5.6.2.1 The new fuel pit storage racks are designed and shall be maintained with a nominal 21-inch center-to-center distance between new fuel assemblies such that ~ will not exceed 0.98 when fuel assemblies are placed in the pit and aqueous foam moderation is assumed.

F 6.2.2 Fuel stored in the new fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows'escri.

tion 1)

Westinghouse 15 x 15 STD 15 x 15 OFA 2)

Exxon/ANF 15 x 15 3)

Westinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 VS 4)

Exxon/ANF 17 x 17 Maximum Nominal Fuel Assembly Enrichment Wt. 't 235U 4.55 3.50 4.55 4.23 DRAINAGE 5.6.3 CAPACITY The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 629'".

5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies.

COOK NUCLEAR PLANT -UNIT 2 5-9 AMENDMENT NO 5k,'+3'g

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6.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, Februaty 1978.

b.

Deleted.

c.

Deleted.

d.

PROCESS CONTROL PROGRAM implementation.

e.

OFFSITE DOSE CALCULATIONMANUALimplementation.

f.

Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.

Component Cyclic or Transient Limits program, which provides controls to track the UFSAR, Section 4.1, cyclic and transient occurrences to ensure that components are maintained within the limits.

6.8.2 Each procedure and administrative policy of Specification 6.8.1 above, and changes thereto, including temporaty changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above.

6.8.3 Aplant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions. The program will include the following:

a.

Training of personnel, b.

Procedures for sampling and analysis, c.

Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEAR PLANT-UNIT2 Page 6-13 AMENDMENTA, 438, 47$, kVS, 186

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6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environment.

e.

Records of transient or operational cycles for those facility components identified in the Updated Final Safety Analysis Report.

f.

Records of reactor tests and experiments.

h.

Records of training and qualification for current members of the Plant Staff.

Records of in-service inspections performed pursuant to these Technical Specifications.

Records of Quality Assurance activities required by the QA Manual.

Records of reviews performed for changes made to procedures or equipment or review of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PNSRC and the NSDRC.

1.

Records of radioactive shipments.

m.

Records of the service lives of hydraulic snubbers including the date at which service li,fe commences and associated installation and maintenance records.

n.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6 11 RAD A ION PROTECTION PROG Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

COOK NUCLEAR PIANT - UNIT 2 6-20 AMENDMENT NO. M, 438, 456 186

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