ML20093C964

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Safety Evaluation Supporting Amends 76 & 102 to Licenses DPR-71 & DPR-62,respectively
ML20093C964
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 09/22/1984
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20093C961 List:
References
NUDOCS 8410110021
Download: ML20093C964 (2)


Text

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UNITED STATES j'j l'i NUCLEAR REGULATORY COMMISSION j

WASHINGTON. D. C. 20551

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0.

76 TO FACILITY LICENSE NO. DPR-71 AND AMENDMENT NO.102 TO FACILITY LICENSE NO. DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 1.0 In+roduction By letter dated May 10, 1984 as supplemented June 18, 1984 the Carolina Power & Light Company (the licensee) submitted proposed changes to the Technical Specifications appended to Facility Operating) License Nos. DPR-71 and DPR-62 for the Brunswick Steam Electric Plant (BSEP. Units 1 and 2.

The proposed amendments would revise the Technical Specifications (TS) 4.4.3.1.b and 4.4.3.2a to incorporate changes in instrument tag numbers.

The integrated drywell floor equipment drain leakage detection system has been replaced with a system consisting of two separate components.

Separate instrument numbers are needed for each components, which results in new instrument numbers to be added. The balance of the changes are editorial revisions to make nomenclature consistent with the Standard Technical Specifications for BWR, NUREG-0123, Rev. 3 and to correct three typographical errors.

The proposed changes are administrative and editorial revisions to Brunswick Technical Specifications 4.1.3.7, 3.3.4, 3.6.6.1, 4.6.6.1, 3.4.3.1, 4.4.3.1, 3.4.3.2 and 4.4.3.2.

2.0 Evaluation

The proposed administrative and editorial revisions to Brunswick Technical Specifications are discussed below:

Technical Specification 4.1.3.7 is corrected to refer to Technical Specification 4.1.3.1.2 for surveillance requirements, not Technical Specification 4.1.3.1.

Technical Specification 3.3.4 is corrected to reference the proper table. Table number 3.3.4-1 changed to 3.3.4-2 (Unit 1 only).

Technical Specification 3/4.6.6.1 is corrected to refer to the proper Regulatory Guide and to make it more closely confonn to the Standard l

Technical Specifications.

In Unit 1 Technical Specifications an I

expired one-time exemption to the surveillance interval is deleted.

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Technical Specification 3/4.4.3.1 is revised to make the nomenclature consistent with BWR standard Technical Specifications, to incorporate changes in instrument tag numbers and to correct incorrect instrument numbers.

Technical Specification 3/4.4.3.2 is revised to make the nomenclature consistent with standard Technical Specifications, for BWRs, NUREG-0123, Rev. 3 to incorporate changes in instrument tag numbers and to correct incorrect instrument number.

We have reviewed the licensee's submittal consisting of the proposed Technical Specification changes and the associated justification for their change and we have determined that the proposed changes are administrative and editorial and that safe operation can be accomplished with these changes.

Based on our review we conclude that the proposed changes to the Technical Specifications are acceptable.

3.0 Environmental Considerations, The amendments involve changes in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The staff has determined that the amendments involve 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 amendments involve no significant hazards consideration and there has been no public comment on such finding.

Accordingly, the amendments meet 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 amendments.

4.0 Conclusions We have 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 Commission's regulations and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

M. Sinkule, Region II Dated: September 22, 1984