ML17332A838

Safety Evaluation Supporting Amend 196 to License DPR-58

ML17332A838
Person / Time
Site:	Cook
Issue date:	07/06/1995
From:	Office of Nuclear Reactor Regulation
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ML17332A837	List: ML17332A836 ML17332A838
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NUDOCS 9507120391
Download: ML17332A838 (6)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON' C

2055&4001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.

TO FACILITY OPERATING LICENSE NO. DPR-58 INDIANA MICHIGAN POWER COMPANY DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 DOCKET NO. 50-315

1. 0 INTRODUCTION By letter dated March 17, 1995, the Indiana Michigan Power Company (the licensee) requested an amendment to the Technical Specifications (TS) appended to Facility Operating License No.

DPR-58 for the Donald C.

Cook Nuclear Plant, Unit No.

1.

The proposed amendment would revise TS 4.6. 1.2.a to provide a

one-time extension of the required test interval for overall integrated containment leak rate tests (Type A tests).

TS 4.6. 1.2.a requires that three Type A tests be conducted at 40 plus or minus 10-month intervals during each 10-year service period, and that the third test of each set of three be conducted during the shutdown for the 10-year plant inservice inspection.

Part 50 of Title 10 of the Code of Federal Regulations (CFR), Appendix J,Section III.D.1, requires that a set of three approximately equally spaced Type A tests be performed during each 10-year service period, and that the third test of each set be conducted during the plant shutdown for the 10-year plant inservice inspection.

The licensee has proposed that the following be added to the TSs as a footnote to TS 4.6.1.2.a:

"A one-time extension of the test interval is allowed for the third Type A test of the second 10-year service period originally scheduled to be performed at the end of Cycle 14.

The test will be performed prior to unit restart following the refueling outage that will follow the end of Cycle 15."

2. 0 EVALUATION The surveillance requirement in D.C.

Cook TS 4.6. 1.2 currently states:

"The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:

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Types A, 8, and C (Overall Integrated and Local Combined Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions."

These tests are performed to assure that leakage through the primary reactor containment and systems and components penetrating primary containment shall not exceed allowable leakage rate values as specified in the TS and to assure that periodic surveillance of reactor containment penetrations and isolation valves is performed so that proper maintenance and repairs are conducted.

The licensee has stated that the results from the last three Type A tests demonstrate the as-found leakage rates were well below the acceptance limits established in 10 CFR Part 50, Appendix J and the TS.

Appendix J and the TS require that the as-found leak rate be less than L

(0.25 wtX/day) and that the as-left leak rate be less that 75X of L, (0.8716 wtX/day).

The as-found leak rates for the last three Type A tests were 0.10567, 0.05550, and 0.08716 wtX/day, respectively.

The results of these Type A tests showed that the integrated leakage of primary containment was less than 50

% of the allowable leak rate, including penalties associated with the Type B and C testing program.

In addition, for the last 3 tests the contribution of Type B and C

test penalties to the as-found leak rate was 81X, 49%,

and 9%, respectively.

These results demonstrate the licensee's efforts in limiting containment penetration leak rates over the past 10 years.

These Type B and C tests will continue to be performed at the frequency required by the TS with repairs being performed as necessary.

The demonstrated operability of these penetrations will provide added assurance that overall containment leakage remains satisfactory.

The licensee also indicated that the general visual inspection of all accessible interior surfaces of the steel liner plate and exterior surfaces of the containment concrete wall, required by TS to be performed prior to a Type A test, will still be performed during the 1995 refueling outage.

The purpose of this inspection is to detect any evidence of structural deterioration (corrosion or deformation of the steel liner and spalling and cracking of the concrete) which may affect the containment structural integrity or its leak tightness.

Modifications which could alter the containment structure are subject to the licensee's 10 CFR 50.59 review process and any unplanned modifications to the containment prior to the next scheduled Type A test would be subject to the special testing requirements of 10 CFR Part 50, Appendix J, Section IV.A.

However, no modifications to the containment boundary are planned for 1995 or 1996.

Based on the past Type A test results, the continued Type B and C testing, and the visual inspection to be performed, the staff finds that the proposed amendment for a one-time extension of the required test interval for Type A

tests would not adversely affect plant safety and is, therefore, acceptable.

Cond'urrently, by separate correspondence, the Commission has granted a one-time schedular exemption to allow an extension of one cycle for the performance of the 10 CFR Part 50, Appendix J, Type A test, provided that the general containment inspection is performed.

3.0 STATE CONSULTATIO In accordance with the Commission s regulations, the Michigan State official was notified of the proposed issuance of the amendments.

The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes surveillance requirements.

The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released

offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a

proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (60 FR 20519).

Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

John Hickman Date:

Quly 6, 1995

DATED:

AMENDMENT NO. i 96 TO FACILITY OPERATING LICENSE NO DPR-58-D C

COOK-UNIT I L Docket File,'UBLIC PDIII-I Reading E.

Adensam (e-mail)

D. Hannon C. Carpenter C. Jamerson J.

Hickman (2)

OGC-WF G. Hill (2)

C. Grimes R. Barrett ACRS (4)

OPA OC/LFDCB W. Kropp, RIII SEDB cc:

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