ML20134P933
| ML20134P933 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/03/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134P922 | List: |
| References | |
| NUDOCS 8509090101 | |
| Download: ML20134P933 (2) | |
Text
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UNITED STATES g
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SAFETY EVALUATION BY THE OFFICF 0F MUCLEAR REACTOR REGULATION C
SUPPORTING AMENDMENT NO. 66 TO FACILITY OPEPATING LICENSE NO. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY
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HADDAM NECK PLANT DOCKET NO. 50-213
1.0 INTRODUCTION
i By letter dated May 2,1983, the Connecticut Yankee Atomic Power Company (CYAPCO) submitted a reouest for changes to the Haddam Neck Plant Technical Specifications.
This amendment r'odi#ies the Technical Specifications to:
(1) add post-accident instrumentation headings to Sections 3 and 4 of the index; (2) add new limiting conditions for operation and surveillance requirements for post-accident instrumentation, and (3) add requirements for a special report l
if pcst-accident instrumentation is unavailable.
l i
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal 2
Register on October 26, 1983 (48 FR 49581). No comments or requests for hearing were received.
2.0 EVALUATION The staff has reviewed the proposed post-accident instrunentation criteria in the Haddam Neck Technical Specifications. The proposed technical i-specifications for the containment high radiation monitor and the stack wide range noble gas monitor provide the capability to detect and measure the radiation levels within the containment and to monitor the releases from the plant stack during or following an accident. Because these monitors are required for post-accident assessments, these specifications are necessary to ensure the operability of the high rance containment radiation monitors and wide-range stack noble gas monitors.
The staff has reviewed the proposed technical specifications for the containment high radiation monitor and concludes that the requirement, range, response, special calibration, etc., are in compliance with Table II.F.1-3 of MUP.EG-0737, " Clarification of the TMI Action Plan Requirements." The staff has also reviewed the proposed technical specification for the stack wide-range noble gas nonitor and concluded that the proposed specification is in compliance with Table 3 of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant conditions During and Following an Accident."
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i Based upon the above discussion, the staff concluded that the proposed amendment is in compliance with the requirements of NUREG-0737 and Regulatory Guide 1.97 and is, therefore, acceptable.
The licensee also requested a change in the title of the individual who is to receive the special reports required by T.S. 6.9.3 from Director of the Office of Inspection and Enforcement Regional Office to the Pegional Administrator of the Regional Office. We have reviewed this proposed administrative change and concluded that it reflects the proper titles under the current NRC organization and is therefore acceptable.
4 3.0 ENVIRONMENTAL CO.NSIDERATION l
This amendment involves a change in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and/or changes to the surveillance requirements. The staff has detemined 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 i
or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this amerdment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.?2(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuarce of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Comission's regulations i
and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ACKNOWLEDGEMENT This Safety Evaluation has been prepared by J. Minns of the Radiological Assessment Branch and R. Fell of the Meterological and Effluent Treatment i
Systems Branch.
Dated:
September 3,1985.
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