ML17352A412
| ML17352A412 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/11/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17352A409 | List: |
| References | |
| NUDOCS 9402010399 | |
| Download: ML17352A412 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFET LU TION BY THE OFFICE OF NUCLEAR REACTOR REGUL TION RE AT D TO AMENDMENT NO.
1 8 TO F CILITY OPERATING LICENSE NO.
DPR-31 AND AMENDMENT NO.
1 270 FACILITY OPERATING LICENSE NO.
DPR-41 FLORIDA POWER AND LIGHT COMPANY TURK Y POINT UNIT NOS.
3 AND 4 DOCKET NOS. 50-250 AND 50-251
- 1. 0 INTRODUCTION By "L-93-241, Application for Amend to Licenses DPR-31 & DPR-41 Revising Surveillance Requirement 4.6.1.2a & Associated Bases to Conform w/NUREG-1431,Standard Ts,[[Manufacturer" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Plants,Rev 0|letter dated October 4, 1993]], Florida Power 8I Light Company (FPL or the licensee) proposed license amendments to change the Technical Specifications (TS) for the Tur key Point Nuclear Generating Units 3 and 4 (Turkey Point or the facility).
The proposed amendments would revise the surveillance test schedule in TS 4.6. 1.2a and the associated Bases for performing Type A tests which determine the overall integrated containment leakage rate.
The licensee proposed these amendments to provide for operational flexibilityby matching the test schedule with the longer fuel cycle lengths and longer refueling outages in which major plant modifications are generally implemented.
The proposed TS wording would be consistent with the standard TS for Westinghouse Plants (NUREG-1431).
- 2. 0 EVALUATION 10 CFR 50 Appendix J, Section III, paragraph D states "...three Type A tests shall be performed, at approximately equal intervals during each 10-year service period.
The third test of each set shall be conducted when the plant is shutdown for the 10-year plant inservice inspections."
Consistent with the test interval (three tests within 10 years) set forth in 10 CFR 50 Appendix J, the existing TS 4.6.2. la states:
Three Type,A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at a pressure not less than Pa, 49.9 psig, during each 10-year service period.
The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
The specific test schedule, at 40 + 10 month intervals, in the TS does not accommodate longer fuel cycle lengths and longer refueling outages in which major plant modifications are implemented.
To avoid unnecessary future TS change requests when the fuel cycle does not match the 40 + 10 month TS required interval, the licensee proposed to revise TS 4.6.1.2a t'o read:
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Type A test shall be performed in accordance with 10 CFR 50 Appendix J, as modified by approved exemptions.
TS Bases 3/4.6 will also be revised to reflect the proposed TS changes.
The staff has evaluated the proposed TS changes which are summarized below.
NUREG-1431, Standard Technical Specifications, Westinghouse
- Plants, dated September
- 1992, includes guidance for the performance of Type A tests in accordance with 10 CFR 50 Appendix J.
The proposed TS wording is consistent with NUREG-1431.
The licensee will continue to perform three Type A tests, at approximately three equal intervals, as required by 10 CFR Appendix J and any change to the leak tests will be accomplished only by means of an NRC-approved exemption request to 10 CFR 50 Appendix J.
In a discussion with the staff regarding the proposed TS change, the licensee clarified that consistent with the existing TS, the Type A test will be performed at a pressure not less than Pa, 49.9 psig.
The licensee agreed to reflect this clarification of test pressure in the TS.
Accordingly the licensee's original proposed TS wording in its October 4, 1993 submittal will be revised to read:
Type A test shall be performed at a pressure not less than Pa, 49.9 psig, in accordance with 10 CFR 50 Appendix J, as modified by approved exemptions.
/
As a result, the staff finds the proposed TS changes (as revised) acceptable.
3.0 STATE CONSULTATION
Based upon the written notice of the proposed amendments, the Florida State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION The amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
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 (58 FR 59748).
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.
5.0 CONCLUSION
Based on the staff evaluation in Section 2.0 above, the staff concludes that the proposed Technical Specifications changes are acceptable.
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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principle Contributor:
L. Raghavan, PDII-2, DRPE Date:
January 11, 1994
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