ML17227A306
| ML17227A306 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/25/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17227A305 | List: |
| References | |
| NUDOCS 9202280060 | |
| Download: ML17227A306 (4) | |
Text
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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 NOS.
3 AND 5
TO FACILITY OPERATING LICENSE NO.
DPR-67 AND NO. NPF-16 FLORIDA POWER AND LIGHT COMPANY ET AL.
ST.
LUCIE PLANT UNIT NOS.
1 AND 2 DOCKET NOS.
50-335 AND 50-389
- 1. 0 INTRODUCTION By letter dated December 17, 1991, the Florida Power
- 5. Light Company (FPL, the licensee),
proposed a change to the Technical Specifications (TS) for the St.
Lucie Plant, Units 1 and 2.
The proposed change removes TS Table 4.4-5 which provides the schedule for reactor vessel material specimen withdrawal.
The proposed change also removes any references to Table 4.4-5.
Guidance on the proposed TS change was provided by Generic Letter 91-01, dated'January 2,
1991, to all holders of operating licenses or construction permits for nuclear power reactors.
- 2. 0 EVALUATION Technical Specification 3/4;4.9, "Pressure/Temperature Limits," contains a limiting condition for operation for the Reactor Coolant System (RCS) that limits the rate of change in temperature and pressure to values consistent with the fracture toughness requirements of the American Society of Mechanical Engineers (ASME) Code and Appendix G to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50).
Changes in the values of these limits are necessary because the fracture toughness properties of ferritic materials in the reactor vessel change as a function of the reactor operating time (neutron fluence).
For this reason, the TS include a surveillance requirement, TS 4.4.9. Ic for Unit 1 and 4.4.9. 1.2 for Unit 2, to require the removal and examination of the irradiated specimens of reactor vessel material.
The licensee examines the specimens to determine the changes in material properties in accordance with the requirements of Appendix H to 10 CFR Part 50.
Table 4.4-5 identifies the material specimens and specifies the schedule removal of each specimen.
The removal of the schedule for withdrawing material specimens from the TS will eliminate the necessity of a license amendment to make changes to this schedule.
- However,Section I.B.3 of Appendix H to 10 CFR Part 50 requires the submittal of a proposed withdrawal schedule for material specimens to the U.S.
Nuclear Regulatory Commission (NRC) and approval by the NRC before 92022800b0 920225(
PDR ADOCK 05000335 P
implementation.
- Hence, adequate regulatory controls exist to control changes to this schedule without the necessity of subjecting it to the license amendment process by including it in TS.
The licensee has already incorporated the reactor vessel material withdrawal schedules in the Updated Final Safety Analysis Reports (UFSARs).
In addition, the licensee will include any subsequent NRC-approved revisions to this schedule in an update of the UFSARs.
The inclusion of the withdrawal schedule in the UFSARs provides a source for this information that is readily available as a reference for NRC inspectors and other staff use.
Finally, the surveillance requirements for removing material specimens and the Bases section for this specification remain unchanged except for the removal of the references to Table 4.4-5 from the TS.
The NRC has reviewed this matter and finds that the proposed changes to the TS for St. Lucie Plant, Units 1 and 2
are 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 involve a change to a surveillance requirement.
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 these amendments involve no significant hazards consideration and there has been no public comment on such finding (57 FR 2594).
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.
r, l '
- 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 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.
Principal Contributor:
T.
G. Dunning Date:
February 25, 1992