ML20125C374
| ML20125C374 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/24/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20125C368 | List: |
| References | |
| NUDOCS 9212110165 | |
| Download: ML20125C374 (3) | |
Text
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WASHINGTON. D.C. 20666 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED 10 AMENDMENT NOS. 46 AND 35 TO FACILITY OPERATING LICENSE NOS. NPC-76 AND NPF-80 HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY j
CITY OF AUSTIN. TEXAS DOCKET NOS. 50-498 AND 50-499 S_0VTH TEXAS PROJECT. UNITS 1 AND 2 i
1.0 INTRODUCTION
By application dated October 12, 1990, Houston Lighting & Power Company, et.al., (the licensee) requested changes to the Technical Specifications a
(Appendix A to Facility Operating License Nos. NPF-76 and NPF-80) for the South Texas Project, Units 1 and 2.
The October 12, 1990 application was supplemented by letter dated January 24, 1991 and superseded by letters-of October 26, 1991 and June 16, 1992. The proposed changes would delete Tech-nical Specification (TS) Table 5.7-1 (Ccmponent Cycle or Transient Limits).
Cyclic / transient occurrences identified in the Updated Final Safety Analysis Report, Table 3.9-8, which include those listed in TS Table 5.7-1, would be tracked through administrative procedures. The change is intended to resolve discrepancies between Table 5.7-1 and the Updated Final Safety Analysis Report (UFSAR) which were previously identified by the staff during the 1988 review of the South Texas Project (STP) draft Technical Specifications (TS).
2.0 DISCUSSION AND EVALUATION Specification 5.7.1 of the STP TS states that, "The components identified in Table 5.7-1 are designed and shall be maintained within the_ cyclic or transient limits of Table 5.7-1."
This table lists cyclic and transient operating conditions which are assumed to occur over the service lifetime of the plant, and which are considered to be sufficiently severe or frequent to be of possible significance to the fatigue life of reactor coolant system (RCS) components. The licensee must monitor the occurrence of these cyclic / transient conditions to ensure that the components of the RCS are not subjected to conditions that are more severe than those which were considered in the component fatigue analyses which were performe ' to comply with Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Section III).
9212110165 921124 PDR ADOCK 05000498 P
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' During the review of the draft TS for STP Unit 2, the staff noted that the sip-a' UFSAR Table 3.9-8, " Summary of Reactor Coolant System Design Transients,"
lists more transients than does TS Table 5.7-1.
The staff was concerned that specifying and tracking only those cyclic and transient conditions listed in Table 5.7-1 would not provide adequate information to ensure that the components of the RCS-are maintained within the design bases.
Based on this concern, the staff requested that the Houston Lighting and Power Company provide justification for the adequacy of Table 5.7-1 as guidance for i
monitoring plant transients.
In response, the licensee committed to develop a plant procedure to ensure that the appropriate RCS cyclicaand transient i
occurrences are monitored.
The staff accepted the commitment in Supplement 6 of NUREG-0781, " Safety Evaluation Report Related to the Operation of South Texas Project, Unit 2" dated December 1988. By letter dated May 31, 1989, the licensee stated that Plant Engineering Procedure OPEP02-ZE-0001, Revision 1, had been implemented to ensure that all fatigue-significant transients. listed in TS Table 5.7-1 and UFSAR Table 3.9-8 were properly monitored.
The licensee proposed to delete TS Table 5.7-1, and augment TS Section 6, Administrative Controls, to include a component cyclic and transient limit program. The licensee irdicated that the component cyclic and transient limit program will be implemented by STP Plant Procedure OPEP02-ZE-0001, Revision 1.
In its submittal, the licensee stated that the proposed change is administrative, and will have no impact on plant operation or safety. The licensee further stated that.the proposed change is an improvement to the TS and consistent with the NRC policy for improving the TS (52 FR 3788, February i
6, 1987).
l The staff agrees that the current TS Table 5.7-1 does not provide a complete list of RCS cyclic / transient occurrences, &nd is inconsistent with the UFSAR.
The staff has reviewed the licensee's proposed change and supporting information, and finds that it is adequate to ensure that RCS fatigue-8 significant cyclic / transient occurrences are properly monitored. The removal of TS Tabic 5.7-1 in the manner described will not eliminate the licensee's i
responsibility to ensure that the cyclic / transient limits of the RCS are properly maintained, nor will it change the plant's design bases or operating procedures. The staff finds that the licensee's proposed amendment eliminates l
the discrepancy between TS Table 5.7-1 and the UFSAR and is an improvement to the current STP TS.
3.0
SUMMARY
l The staff has reviewed the licensee's proposed TS amendment for STP Units 1 and 2, and has determined that it is adequate to ensure proper monitoring of i
RCS fatigue-significant transients. The proposed change eliminates the discrepancy between TS Table 5.7-1 and the UFSAR, and thus it is an improvement to the current STP TS. Therefore, the staff finds that the proposed amendment is acceptable for STP Units 1 and 2.
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4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendment.
The State official had no comments.
5.0 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. The NRC staff has determined-that the 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 (55 FR 53072, 56 FR 66920, and 57 FR 47140).
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.
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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
M. McBrearty i
l Date:
November 24, 1992 l
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