ML17228B121
| ML17228B121 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/25/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17228B120 | List: |
| References | |
| NUDOCS 9505040096 | |
| Download: ML17228B121 (3) | |
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SAF UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 A U IO BY TH OFFIC UC EA RE CTO REGULATION R
TO AMENDM N OS 135 ND 74 TO FACIL TY 0 ERATING LICENSE NO.
DPR-6 AND NO. NPF-16 POWRAD IGH CO A
S LUCIE PLANT UNIT NOS.
1 AND 2 D CK T NOS. 50-335 AND 50-389
- 1. 0 INTRODUCTION By letter dated May 23, 1994, Florida Light 5 Power Company (FPL) submitted a
request for license amendments to change the St. Lucie Generating Station, Units 1 5 2, Technical Specifications (TS).
The amendments would relocate the Seismic Monitoring Instrumentation (SMI) Limiting Conditions for Operation (LCO) 3.3.3.3, the Surveillance Requirements (SR) 4.3.3.3. 1, and 4.3.3.3.2, and the associated Tables 3.3-7 and 4.3-4, and Bases 3/4.3.3.3 contained in the TS, to the Updated Final Safety Analysis Report (UFSAR).
2.0 BACKGROUND
Section 182a of the Atomic Energy Act (the "Act") requires applicants for nuclear power plant operating licenses to state technical specifications to be included as part of the license.
The Commission's regulatory requirements related to the content of technical specifications are set forth in 10 CFR 50.36.
That regulation requires that the TS include items in five specific categories, including (1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
However, the regulation does not specify the particular requirements to be included in a plant's TS.
The Commission has provided guidance for the contents of TS in its "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors"
("Final Policy Statement" ),
58 Fed.
Reg.
39132 (July 22, 1993), in which the Commission indicated that compliance with the Final Policy Statement satisfies Section 182a of the Act.
In particular, the Commission indicated that certain items could be relocated from the TS to licensee-controlled documents, consistent with the standard enunciated in Portland General Electric Co. (Trojan Nuclear Plant),
ALAB-531, 9 NRC 263, 273 (1979).
In that
- case, the Atomic Safety and Licensing Appeal Board indicated that "technical specifications are to be reserved for those matters as to which the imposition 9505040096 950425 PDR ADQCK 05000335 P
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2 of rigid conditions or limitations upon reactor operations is deemed necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety."
The "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (FPSTSI) published by the NRC ln the ~ader I Ibeeister on July 22, 1993 (58 FR 39132) discusses revised criteria for defining the scope of the TS as required by 10 CFR 50.36.
In particular, the FPSTSI enumerates four cy iteria that delineate the classes of technical material that should be included in the TS.
The four criteria state:
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restriction that is an initial condition of a Design Basis Accident or Transient analysis that either assumes the failure of, or presents a
challenge to the integrity of a fission product barrier.
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Design Basis Accident or Transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
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- 3. 0 EVALUATION The staff has reviewed the request for relocation of the TS LCO 3.3.3.3, the SR 4.3.3.3, and associated Tables 3.3-7 and 4.3-4, and Bases 3/4.3.3.3 for Seismic Monitoring Instrumentation from the Technical Specifications contained in the TS sections 3.3.3.3 and 4.3.3.3 to the UFSAR.
The requirements described in the affected sections of the TS will be maintained in the UFSAR and any subsequent changes to the UFSAR or equivalent controlled documents, related to these instruments, will be made in accordance with 10 CFR 50.59.
The request was evaluated utilizing the four criteria set forth in the above NRC FPSTSI.
The proposed amendment does not involve changes in the way the plant will be operated, maintained, or tested.
Appendix A to 10 CFR Part 100 requires that SMI be provided to promptly determine the severity of any earthquake-induced ground motion affecting the plant and evaluate its effects on the plant, including initiating shutdown procedures if certain specified ground motion criteria have been exceeded.
However, the SKI are not considered part of the accident analysis as outlined by the NRC FPSTSI criteria I through 4, nor do they affect the margin of safety of the plant.
In conclusion, the above relocated requirements relating to Seismic Monitoring Instrumentation are not required to be in the TS under 10 CFR 50.36 or 182a of the Atomic Energy Act,'nd are not required to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety.
- Further, they do not fall within any of the four criteria set forth in the Commission's Final Policy Statement, discussed above.
In addition, the Staff finds that sufficient regulatory controls exist under 10 CFR 50.59 to assure continued protection of the public health and safety Accordingly, the staff has concluded that these requirements may be, relocated from the TS to the Licensee's UFSAR On this basis, the staff concludes that TS LCO 3 ' ' ',
TS SR 4 ' ' ', Tables 3.3-7 and 4.3-4 the Bases for TS 3/4.3.3.3 may be relocated to the UFSAR Any future changes to the SMI requirements will be controlled by 10 CFR 50.59
- 4. 0 STATE CONSULTATION Based upon the written notice of the proposed amendments, the Florida State official had no comments'.0 ENVIRONNENTAL CONSIDERATION These amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
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 (59 FR 34664)
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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.
- 6. 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:
G ~ Giese-Koch Date: April 25, 1995