ML20056D694
| ML20056D694 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/28/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056D693 | List: |
| References | |
| NUDOCS 9308170335 | |
| Download: ML20056D694 (2) | |
Text
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. UNITED STATES
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j NUCLEAR REGULATORY COMMISSION
}W WASHINGTON. D C. 20556-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.113 TO FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 DOCKET NO. 50-395
1.0 INTRODUCTION
By letter dated October 6,1992, South Carolina Electric & Gas Company (the licensee) submitted a request for changes to the Virgil C. Summer Nuclear Station, Unit No.1 (Summer Station) Technical Specifications (TS). The proposed changes would modify Figures 3.4-2 and 3.4-3 to TS 3/4.4.9, Pressure / Temperature Limits, Reactor Coolant System, and remove Table 4.4-5, " Reactor Vessel Material Surveillance Program - Withdrawal Schedule," and the reference to this table in Surveillance Requirement 4.4.9.1.2.
The requested changes to the Pressure / Temperature (P/T) limits would provide new heatup and cooldown curves based on the analysis of specimen X of the Summer Station radiation surveillance program.
The request to remove Table 4.4-5 is based on the guidance of Generic Letter 91-01 (GL 91-01), " Removal of the Schedule for Withdrawal of Reactor Vessel Material Specimens from Technical Specifications."
2.0 EVALUATION P/T Limit Curves Throughout the life of the reactor vessel, material irradiation surveillance specimens are removed and examined to determine changes in material properties.
The results of the examination of these specimens may warrant a change to the heatup and cooldown curves (P/T limit curves) associated with the reactor vessel.
Strict adherence to proper heatup and cooldown curves is necessary to ensure vessel integrity under normal and transient conditions.
In accordance with the TS for Summer Station, surveillance specimen X was removed during refueling outage 5.
Analysis of this specimen has indicated that a change to the P/T limit curves is appropriate.
In effect, the changes to the curves increase the reference transition temperature by approximately 10*F.
The calculations performed in the development of the proposed P/T curves were made using the guidance of Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials," and Appendix G to 10 CFR Part 50, " Fracture Toughness Requirements." The staff has reviewed the proposed changes and has 9308170335 930728 PDR ADOCK 05000395 p
. determined that they continue to provide conservative limits on the reactor coolant system pressure and temperature in accordance with the requirements of Section V of Appendix G to 10 CFR Part 50. The changes are, therefore, acceptable.
Removal of Schedule The capsule removal schedule states that during reactor vessel life various material samples will be removed for testing. The capsule removal schedule is controlled by Appendix H to 10 CFR Part 50. The licensee has committed to place the capsule withdrawal schedule in the Final Safety Analysis Report.
Removal of this schedule has no impact on plant safety, is in accordance with the guidance of Generic Letter 91-01, and is, therefore, acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of South Carolina official was notified of-the proposed issuance of the t.mendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes the Surveillance Requirements. The NRC staff has determined that the l
amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (57 FR 55500). Accordingly, the amendment meets 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 the amendment.
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 1
the amendment will not be inimical to the common defense and security or to the health and safety of the puulic.
Principal Contributor:
G. Wunder 1
i Date: July 28, 1993 i
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