ML17223A474
| ML17223A474 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/18/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17223A473 | List: |
| References | |
| NUDOCS 9001260272 | |
| Download: ML17223A474 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY TIlE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.
101AND 44 TO FACILITY OPERATING LICENSE NOS.
DPR-67 AND NPF-16 FLORIDA POWER
ST.
LUCIE PLANT, UNIT NOS.
1 AND 2 DOCKET NOS.
50-335 AND 50-389
- 1. 0 INTRODUCTION On September 27, 1985, the staff issued Generic Letter (GL) 85-19, "Reporting Requirerrents on Primary Coolant Iodine Spikes."
In GL 85-19 the staff recomITended that the primary coolant iodine spike reporting requirements could be reduced from a short-term report (such as Special Report or Licensee Event Report) to an item which is included in the Annual Report.
In addition, GL 85-19 also recomIn nded that the existing requirerrents to shut down a plant if coolant iodine 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 could be eliminated.
By letter dated February 21, 1989, Florida Power
& Light Company (the licensee) proposed to revise the St. Lucie Plant, Units 1 and 2
Technical Specifications (TS) Section 3.4.8 and the bases for these TS to conform to the recoIImIendations of GL 85-19.
2.0 EVALUATION The St.
Lucie Plant, Units 1 and 2 TS currently include ACTION requirements to be taken when the specific activity of the primary coolant exceeds certain limits.
The licensee proposes to include this information in the Annual Report.
This information is similar to that previously required in the Licensee Event Report, but has been changed to more clearly designate the results to be included from the specific activity analysis and to delete the information regarding fuel burnup by the core region.
In GL 85-19, the staff determined that the existing requirements to shut down a plant if coolant iodine 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 can be eliminated.
In the past decade the quality of nuclear fuel improved greatly and therefore the normal coolant iodine activity (absent iodine spiking) is well below the limit.
Appropriate actions would be taken long before accumulating 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> above the iodine activity limit.
Additionally, 10 CFR 50.72(b)(1)(ii) requires that the NRC be immediately notified of fuel cladding failures that exceed expected values or that are caused by unexpected factors.
Proper fuel management by the licensees and the existing reporting requirerrents would preclude ever approaching the limit.
For these reasons this TS limit is no longer considered necessary.
900126Ci272 900i i8 PDR APOCK 05000335 P
3.0 TECHNICAL FINDING Based on the above evaluation, and because the changes proposed by the licensee are in conformance with the recommendations of GL 85-19, the staff finds the proposed amendment acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments relate to changes in recordkeeping, reporting or administrative procedures or requirements.
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
5.0 CONCLUSION
We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date:
January 18, 1990 Princi al Contributor:
Jan A. Norris
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