ML16138A630
| ML16138A630 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/23/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A629 | List: |
| References | |
| NUDOCS 8807110303 | |
| Download: ML16138A630 (3) | |
Text
0 0UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.168 TO FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO.168 TO FACILITY OPERATING LICENSE DPR-47 AMENDMENT NO.165 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 June 1, 1987, and supplemented on November 24, 1987 (References 1 and 2) Duke Power Company (the licensee) requested amendments to the Technical Specifications (TS) of Facility Operating License Nos. DPR-38, OPR-47 and DPR-55 for the Oconee Nuclear Station, Units 1, 2, and 3. These amendments would revise the Station's common TS.
The proposed amendments would revise the LOCA-Limited Maximum Allowable Linear Heat Rate (Figure 3.5.2-16). These revisions would reflect NUREG-0630, Cladding Swelling and Rupture Models for LOCA Analysis and Babcock and Wilcox (B&W)
Owners Group Topical Report BAW-1915P, Bounding Analytical Assessment of NUREG-0630 models of LOCA kilowatt-per-foot limits with use of FLECSET.
A generic bounding assessment of the impact of NUREG-0630 on loss-of-coolant accident (LOCA) linear heat rate (LHR) limits has been performed for all core elevations consistent with B&W Emergency Core Cooling System (ECCS) Evaluation Model methods. The impact of NUREG-0630 was a reduction in LOCA LHR limits at the two-, four-and six-foot core elevations because of rupture time dependency of these elevations.
In an effort to reduce the NUREG-0630 impact, the B&W Owners Group has incorporated the benefits of using compensating models. B&W has evaluated the FLECHT-SEASET heat transfer correlation and modified it for B&W plant application. The modified correlation is modeled in the computer program "FLECSET."
BAW-1915P and BAW-10104, Revision 5 have been reviewed by the Commission and approved on October 5 and December 27, 1987 (References 3 and 4).
These reports provide the technical basis for these revisions. The models addressed in these reports are used to determine the LOCA-Limited Maximum Allowable LHR.
The proposed revision to Figure 3.5.2-16 reflects application of the new models.
6807110303 880623 PDR ADOCK 05000269 P
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- 2 The previously analyzed accident that is pertinent to this revision would be a large break loss-of-coolant accident. FLECSET is a B&W modified version of the FLECHT-SEASET reflood heat transfer correlation. Reflood heat transfer coefficients versus time were calculated using FLECSET and compared to those calculated by the present large break LOCA Evaluation Model (BAW-10104, Revision 3).
The FLECSET reflood heat transfer coefficients at the two-foot core elevation are higher than those calculated by the current Evaluation Model during the early stage of reflooding.. These higher reflood heat transfer coefficients allow the peak cladding temperature to turn over earlier in the transient.
2.0 EVALUATION The proposed TS revisions are to update the LOCA-Limited Maximum Allowable Linear Heat Rates reflecting the effects of the NUREG-0630 models and the analytical results with use of the FLECSET correlation (Reference 5).
We have reviewed the proposed TS changes and find that the proposed LOCA-Limited Maximum Allowable Linear Heat Rates are consistent with the calculated results presented in Table 3.2 of Reference 5, which had previously been approved by the Commission (Ref. 3) for licensing applications for the B&W lowered loop 15x15 fuel assembly plants including the Oconee plants. B&W performed the large break LOCA analyses to support the request of the TS revisions by using the modified ECCS Evaluation Model as described in the B&W topical report BAW-10104, Revision 5. On December 27, 1987, we generically approved the topical report BAW-10104, Revision 5. The staff also found the plant specific application of the B&W topical report BAW-10104, Revision 5 to the Oconee plants to be adequate and acceptable. Therefore, we conclude that the proposed TS revisions are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve a change in the installation or use of facility com ponents located within the restricted area as defined in 10 CFR Part 20. We have 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. Accordingly, the 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.
4.0 CONCLUSION
The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (53 FR17787 ) on May 18, 1988, and consulted with the state of South Carolina.
No public comments were received, and the state of South Carolina did not have any comments.
-3 We 'have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
5.0 REFERENCES
- 1. Letter from H. Tucker (Duke Power Co.) to NRC, dated June 1, 1987.
- 2.
Letter from H. Tucker (Duke Power Co.) to NRC, dated November 24, 1987.
- 3. Letter from A. Thadani (NRC) to C. Turk (B&WOG), "Acceptance for Referencing Topical Report BAW-1915 - Bounding Analytical Assessment cf NUREG-0630 Models on LOCA kw/ft Limits With Use of FLECSET,"
October 5, 1987.
- 4. Letter from A. Thadani (NRC) to C. Turk (B&WOG), BAW-10104, Revision 5, (B&W ECCS Evaluation Model) December 27, 1987.
- 5. J. Paljug, et al., "Bounding Analytical Assessment of NUREG-0630 Models on LOCA Kw/ft Limits With Use of FLECSET," BAW-1915, May 1986.
Principal Contributors: H. Pastis, PD#11-3/DRP-I/II S. Sun Dated:
June 23, 1988