ML16138A798
| ML16138A798 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/04/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML16138A799 | List: |
| References | |
| NUDOCS 9512120148 | |
| Download: ML16138A798 (3) | |
Text
0,e R REG&~
UNITED STATES NUCLEAR REGULATORY COMMISSION, WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 212 TO FACILITY OPERATING LICENSE DPR-38, AMENDMENT NO. 212 TO FACILITY OPERATING LICENSE NPF-47, AND AMENDMENT NO. 209 TO FACILITY OPERATING LICENSE DPR-55.
DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS 1. 2 AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287
1.0 INTRODUCTION
By letter dated September 1, 1995, as supplemented by letter dated November 15, 1995, Duke Power Company, (the licensee or DPC), submitted a request for changes to the Oconee Nuclear Station, Units 1, 2, and 3 Technical Specifications (TS).
The requested changes would revise TS 6.9.2 to'include references to updated or recently approved methodologies used to calculate cycle-specific limits contained in the Core Operating Limits Report (COLR).
The subject references have previously been reviewed and approved by the NRC staff. The November 15, 1995, letter provided clarifying information that did not change the scope of the September 1, 1995, application and the initial proposed no significant hazards consideration determination.
2.0 EVALUATION Specifically, the proposed amendments would add the following reports to the four reports listed in TS 6.9.2 as Items (1) through (4):
BAW-10162P-A, TACO3 Fuel Pin Thermal Analysis Computer Code, BAW Fuel Company, November, 1989.
The staff issued its evaluation of the Babcock & Wilcox (B&W) Topical Report BAW-10162P-A, "TACO3 - Fuel Pin Thermal Analysis Computer Code" by letter dated August 14, 1989, from A. C. Thadani, NRC, to J. H. Taylor, B&W. The revised TACO3 code, addressed by this evaluation, was developed to provide predictions of the thermal and mechanical performance of pressurized water reactor fuel rods experiencing variable power histories up to a particular burnup level.
The staff's review concluded that the Topical Report provided an acceptable basis for changes to the B&W TACO3 computer code.
9512120148 951204 PDR ADOCK 05000269 P
-2 BAW-10183P, Fuel Rod Gas Pressure Criterion, B&W Fuel Company, as approved by SER dated February, 1994.
The staff issued its evaluation of the Babcock & Wilcox Topical Report BAW-10183P, "Fuel Rod Gas Pressure Criterion" by letter dated February 22, 1994, from A. C. Thadani, NRC, to J. H. Taylor, B&W. The BAW-10183P report describes a fuel rod gas pressure criterion that the B&W Fuel Company (BWFC) would apply to existing fuel designs to allow the rod pressure to exceed system pressure under certain conditions. The staff's review concluded that the Topical Report provides an acceptable basis for the fuel rod gas pressure criterion for licensing applications.
By letter dated May 4, 1994, DPC requested that NRC review and approve the transfer of the fuel performance code TACO3 from the BWFC to DPC for reload licensing applications. The transfer includes the approved Topical Reports BAW-10162P-A and BAW-10183P, as approved. The NRC staff concluded, in a letter from H. N. Berkow, NRC, to M. S. Tuckman, DPC, dated April 3, 1995, that DPC has the technical capability to perform TACO3 analyses for reload licensing applications and therefore, the use of TACO3 by DPC for the Oconee Nuclear Station is acceptable.
The proposed revision in DPC's application of September 1, 1995, adds the references for the two methodology reports, BAW-10162P-A and BAW-10183P, as approved, to TS 6.9.2. On the basis of its review of the licensee's submittals summarized above, the NRC staff finds that this proposed revision to TS 6.9.2 is acceptable.
DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, August, 1994.
This report was approved for use on the Oconee Nuclear Station by letter dated August 8, 1994, from L. A. Wiens, NRC, to M. S. Tuckman, DPC. The Topical Report documents the development of the thermal hydraulic simulation models for the Oconee Nuclear Station using RETRAN-02 and VIPRE-01 computer codes and provided DPC's response to Generic Letter 83-11, "Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions." On these bases, the staff finds this proposed revision to TS 6.9.2, to add report DPC-NE-3000P-A, to be acceptable.
DPC-NE-2005P-A, Th rmal-Hydraulic Statistical Core Design Methodology, February, 1995.
The staff issued its evaluation of the Duke Power Company Topical Report DPC-NE-2005P-A, "Thermal-Hydraulic Statistical Core Design Methodology" by letter dated February 27, 1995, from G. M. Holahan, NRC, to H. B. Tucker, DPC.
This report documents the development of core thermal-hydraulic analysis based upon the statistical core design methodology using the VIPRE-01 computer code for the Catawba, McGuire, and Oconee Nuclear Stations. The staff concluded that the report is acceptable for referencing in license applications to the extent specified and under the limitations delineated in the report and the associated NRC evaluation. On these bases, the staff finds this proposed revision to TS 6.9.2, to add report DPC-NE-2005P-A, as approved, to be acceptable.
-3 In summary, the staff finds the proposed changes are acceptable because the use of the identified NRC-approved methodologies will ensure that the values for cycle-specific parameters are determined consistent with applicable design bases and safety limits, and assist safe operation of the facility.
It should be noted that Technical Specification 6.9.2 includes the statement:
"The approved methods to determine core operating limits given in TS 6.9.1 are specified in the Core Operating Limits Report (COLR)." The current COLR lists the topical reports used to calculate the core operating limits, but does not clearly specify which report is used to determine each operating limit. Also, the references in the COLR include some topical reports pertaining to fuel types not currently in use, but which may be used in the future. To meet the intent of the statement in TS 6.9.2 quoted above, the COLR should specify, for each fuel cycle, which topical reports and methodologies are used to calculate each core operating limit.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The Statel official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or 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 (60 FR 52928 dated October 11, 1995).
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendmen s..
5.0 CONCLUSION
The Commission has concuded, 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: S. S. Kirslis Date:
December 4, 1995