ML20117K480

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Safety Evaluation Supporting Amend 202 to License DPR-65
ML20117K480
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/04/1996
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20117K477 List:
References
NUDOCS 9609110324
Download: ML20117K480 (3)


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1 UNITED STATES 4

a NUCLEAR REGULATORY COMMISSION N

f WASHINGTON, D.C. 206S0001

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SAFETY EVALVATION BY THE OFFICE OF NVCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 202 TO FACILITY OPERATING LICENSE NO. DPR-65 NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY l

MILLSTONE NVCLEAR POWER STATION. UNIT N0. 2 i

DOCKET N0. 50-336 i

1.0 INTRODUCTION

By letter dated March 28, 1996, the Northeast Nuclear Energy Company, et al.

(the licensee) submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 2 (Millstone Unit 2), Technical Specifications (TSs).

The l

requested changes would change TS 3.7.7, " Sealed Source Contamination," and its Bases that modify the criteria for testing sealed sources for I

contamination and leakage. The changes are consistent with the testing criteria currently used at the Millstone Nuclear Power Station, Unit No. 3, the Haddam Neck Plant, and the Seabrook Station.

2.0 EVALUATION Currently, Section 3.7.7 of the TSs for Millstone Nuclear Power Station, Unit i

No. 2, states that "each sealed source containing radioactive material either in excess of those quantities of byproduct material listed in 10 CFR 30.71 or 0.1 microcuries, including alpha emitters, shall be free of 2 0.005 microcuries of removable contaminction." The quantities of byproduct material listed in 10 CFR 30.71 range from 0.1 to 1000 microcuries, depending on the particular radioisotope.

The licensee proposes to change the criteria for testing sealed sources for l

contamination and leakage at Millstone Unit 2 to the same as the criteria at Millstone Unit 3, the Haddam Neck Plant, and the Seabrook Station.

Specifically, the sealed sources that are required to be free of greater than or equal to 0.005 microcuries of removable contamination are those that will exceed "100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material." Although the proposed change increases the quantities of sealed source byproduct material that can be 96o9110324 960904 DR ADOCK 05000336 p

PDR

.. stored without requiring contamination and leak testing for some radionuclides, the actual radiological material content of a sealed source j

that will require routine leak testing is still small.

The proposed TS changes do not change the allowable leakage (less than 0.005 microcuries of i

removable contamination) for sealed sources. This allowable leakage is small and would not cause any significant radiation exposure to the workers or to the public. The area where the sealed sources are stored at the Millstone Unit 2, is routinely surveyed by Health Physics in accordance with Health Physics Department procedures and any significant leakage would be detected.

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As previously noted, the proposed changes to the TSs will make the criteria l

for testing sealed sources for contamination and leakage at Millstone Unit 2 l

the same as those at Millstone Unit 3, the Haddam Neck Plant, and the Seabrook Station. The TSs for sealed source contamination at these other plants have l

been previously approved by the staff.

Therefore, since the proposed changes are consistent with those previously approved and the changes do not modify the allowable leakage for sealed sources, the staff finds the licensee's i

proposed changes to the sealed source contamination TS 3.7.7 and supporting Bases to be acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The State official had no comments.

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4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The NRC 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 l

public comment on such finding (61 FR 20853). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR i

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.

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5.0 CONCLUSION

The Commission 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 l

defense and security or to the health and safety of the public.

I Principal Contributor:

C. Hinson Date: September 4, 1996 I

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