ML20211M442
| ML20211M442 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/08/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211M441 | List: |
| References | |
| TAC-60423, TAC-60424, NUDOCS 8612170270 | |
| Download: ML20211M442 (3) | |
Text
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UNITED STATES 3
NUCLEAR REGULATORY COMMISSION
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO APENDMENT N0.66 TO FACILITY OPERATING LICENSE NPF-9 AND ANENDNENT Nb. 47 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY DOCKET NOS. 50-369 AND 50-370 McGUIRE NUCLEAR STATI0rl, UNITS 1 AND 2 INTRODUCTION By letter dated Decenber 13, 1985, the Duke Power Company proposed changes to the Technical Specifications for the McGuire Nuclear Station, Units Nos. I and 2 j
that would involve: (1) a revision to the reporting requirements related to primary coolant iodine spikes, (2) the deletion of existing Technical Specifi-cations (TS) requirements to shut down the facility if coolant icdfre activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month period, and (3) a clarification of the sampling technique to allow analysis of a non-degassed reactor coolant system (RCS) sample for determination of total specific activity. The proposed changes in items (1) and (2) are in accordance with NRC Generic Letter No.
85-19 dated September 27, 1985.
EVALUATION Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes, is part of an ongoing effort to delete unnecessary reporting requirements.
It has been determined that reporting requirements related to primary coolant specific activity levels, specifically iodine spikes, can be reduced from a short term report to an item to be included in the Annual Report.
It has also been detennined that existing shutdown requirements based on exceeding the primary coolant iodine activity limits for an accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> are no longer necessary. This is based on an improvement in the quality of nuclear fuel over the past 10 years and the fact that appro-priate actions would be initiated long before approaching the limit as currently specified.
Generic Letter 85-19 reports these findings and presents revel Technical Specifications in Standard Technical Specification format which reflect these fi r.di r,g s. Duke Power Company has proposed amending the McGuire Units 1 and 2 Technical Specifications to match the medel Technical Specifications presented.
We find the revisions to the reporting requirements and the deletion of re-quirements to shut down the facility if coolant icdire activity limits are exceeded for 800 hnurs in a 12 month period to be consistent with the Generic Letter and model Technical Specifications and, therefore, to be acceptable.
8612170270 861208 PDR ADOCK 05000369 P
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-2 The licensee has proposed to change the Techniccl Specifications to allow the use of a new analysis technique to cuantify reactor coolant system activity.
The present Technical Specifications require the taking of a pressurized sample of reactor coolant, degassing the sample, and analyzing the gas and the liquid separately. The results of the two analyses are then added to detcrnine the gross radioactivity. The proposeo change would permit analyzing c pressurized sample that had not been oegassed. This approach is viewed es being more desirable because it reduces occupational radiation exposures.
Data sub-mitted by the licensee indicate that the single analysis method nwets regulatory requiren:ents, and therefore, the proposed change to the Technical Specificctions allowing its use is acceptable.
ENVIRONMENTAL CONSIDERATI0fl These amendments involve changes to the installation or use of facility con-cenents located within the restricted area as defined in 10 CFR Part 20 cr.d charges in reporting or administrative procedures or requirements. The staff has determired 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 exposure. The NRC staff bcs rede a determination that the amendments involve no significant hazards consideration, and there has been no public comment on such finding.
Accordingly, the amendments meet either the eligibility criteria for catecorical exclusion set forth in 10 CFR 51.22(c)(9)or(c)(10). Fursuart to 10 CFR 51.22(b) no environn: ental impact statement or environnental assessment need be prepared fr connection with the issuance of these amendments.
CONCLUSION The Con. mission made a proceseo determination that the amendments involve no significant hazards consideration which was published fr the Federal Register (51 FR 30571) cn tugust 27, 1986, and consulted with the state of North Carolina.
No public connents were received, and the state of f:crth Carolina did not have any comnents.
We hive concluded, baseo on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will rot be eodangereo by operation in the proposed carrer, and (2) such activities will be conducted in compliance with the Conraission's regulations, and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
C. Willis H. Gilpin D. Wigginton Dated: December 8, 1986 a
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- i DATED. December 8, 1986 AMEliLMENT f40.66 TO FACILITY CFERATING LICENSE NPF McGuire fluclear Station, Unit 1 AliEh0HENT NO.47 TO FACILITY OPERATING LICENSE NPF McGuire Nuclear Station, Unit 2 DISTRIBUTION:-
DocketFIIe50Z369/370?
NRC PDR Local PDR PRC System NSIC PWR#4 R/F B. J. Youngblood R/F M. Duncan D. Hood H. Thorapson OGC/Bethesda J. Partlow B. Grimes E. Jordan L. Harmon
- 11. Jones T. Barnhart (8)
ACRS (10)
OPA LFMB N. Thompson E. Butcher C. Willis H. Gilpin