ML17348B376
| ML17348B376 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/07/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17348B375 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9202110366 | |
| Download: ML17348B376 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 151 TO FACILITY OPERATING LICENSE NO.
DPR-31 AND AMENDMENT NO 146 TO FACILITY OPERATING LICENSE NO DPR 41 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNIT NOS.
3 AND 4 DOCKET NOS.
50-250 AND 50-251
1.0 INTRODUCTION
By letter dated September 17, 1991, Florida Power and Light Company (FPL, the licensee) proposed to amend Facility Operating Licenses DPR-31 and DPR-41 for Turkey Point Units 3 and 4, respectively.
These amendments would remove the present surveillance requirements for snubbers in the Technical Specifications (TS) for both units and replace them with the alternative requirements contained in Generic Letter 90-09, "Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions."
- 2. 0 EVALUATION The snubber visual examination schedule in the existing TS is based on the permissible number of inoperable snubbers found during the visual examination.
Because the existing snubber visual examination schedule is based only on the absolute number of inoperable snubbers found during the visual examinations irrespective of the total population of snubbers, licensees with a large snubber population find the visual examination schedule excessively restrictive.
The purpose of the alternative visual examination schedule is to allow the licensee to perform visual examinations and corrective actions during plant outages without reduction of the confidence level provided by the existing visual examination schedule.
The new visual examination schedule specifies the permissible number of inoperable snubbers for various snubber populations.
The basic examination interval is the normal fuel cycle, up to 24 months.
This interval may be extended to as long as twice the fuel cycle, or reduced to as small as two-thirds of the fuel cycle, depending on the number of unacceptable snubbers found during the visual examination.
The examination interval also may vary by +25 percent to coincide with the actual outage.
In the event one or more snubbers are found inoperable during a visual examination, the Limiting Conditions for Operation (LCO) in the present TS require the licensee to restore or replace the inoperable snubber(s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the attached system inoperable and follow the appropriate action statement for that system.
This LCO will remain 9202110366 920207 PDR ADOCN 05000250 PDR ~
in the TS.
However, the permissible number of inoperable snubber(s) and the subsequent visual examination interval will now be determined in accordance with the new visual examination schedule (Table 4.7-2 of Generic Letter 90-09 dated December 11, 1990).
As noted in the guidance for this line-item TS improvement, certain corrective actions may have to be performed depending on the number of inoperable snubbers found.
All requirements for corrective actions and evaluations associated with the use of the visual examination schedule and stated in the footnotes 1 through 6 (Table 4.7-2 of Generic Letter 90-09) shall be included in the TS.
The licensee has proposed changes to Specification 3/4.7.6 for Units 3 and 4
that are consistent with the guidance provided in Generic Letter 90-09 for the replacement of the snubber visual examination schedule with Table 4.7-2 (including footnotes 1 through 6) of Generic Letter 90-09.
For that reason, and also because the alternative requirements will result in a reduced occupational radiological exposure to the plant personnel, the staff finds the proposed changes 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
These amendments change surveillance requirements.
The NRC 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 (56 FR 55947).
Accordingly, these 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 these amendments.
5.0 CONCLUSION
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 Colhmission'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.
Principal Contributor:
R. Auluck Date:
February 7,
1992