ML20087A179
| ML20087A179 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/27/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20087A173 | List: |
| References | |
| NUDOCS 9508040215 | |
| Download: ML20087A179 (3) | |
Text
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?q UNITED STATES NUCLEAR REGULATORY COMMISSION f
If WASHINGTON. D.C. 20666-0001 l
i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 202 TO FACILITY OPERATING LICENSE NO. DPR-32 i
l AND AMENDMENT N0. 202 TO FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281
1.0 INTRODUCTION
By l' <Mr dated November 29, 1994, the Virginia Electric and Power Company (the onsee) proposed changes to the Technical Specifications (TS) for the Surr3 6 nr Station, Units 1 and 2 (SPS-l&2).
The proposed changes would alls the use of ZIRLO material for fuel cladding for SPS-l&2. The 1
Westinghouse ZIRLO fuel was described in the topical report WCAP-12610 l
" VANTAGE + Fuel Assembly Reference Core Report," and was approved by the NRC staff for irradiation up to 60,000 mwd /MTV rod average burnup. Two demonstration or lead test assemblies of ZIRLO-clad fuel have successfully completed two cycles of operation in the North Anna, Unit I core. The staff's t
evaluation is presented below.
2.0 DISCUSSION j
The NRC staff approved the ZIRLO fuel design in a Safety Evaluation dated July 1,1991, for the Westinghouse topical report WCAP-12610 " VANTAGE + Fuel Assembly Reference Core Report." The NRC staff also approved Loss-of-Coolant Accident (LOCA) methodologies in a Safety Evaluation dated October 9,1991, for the Westinghouse topical reports WCAP-12610, Appendix F, "LOCA NOTRUMP I
Evaluation Model:
ZlRLO Mcdifications," and Appendix G, "LOCA Plant Specific Accident Evaluation."
la addition, the NRC staff also approved the ZIRLO growth model as discussed in a Safety Evaluation dated September 15, 1994, for the Westinghouse Topical Report WCAP-12610, Appendix B, Addendum 1, " Extended Burnup fuel Design Methodology and ZIRLO Fuel Performance Models."
3.0 TECHNICAL SPECIFICATION CHANGES (Section 5.3.A.1)
The reactor core contains approximately 176,200 lbs of uranium dioxide in the form of slightly enriched uranium dioxide pellets. The pellets are encapsulated in Zircaloy-4 or ZIRLO tubing to form fuel rods. All fuel rods are pressurized with helium during fabrication. The reactor core is made up of 157 fuel assamblies.
Each fuel assembly contains 204 fuel rods except for fuel assemblies which may be reconstituted to replace leaking fuel rods with i
non-fueled rods (e.g. zircaloy or stainless steel).
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' 4.0 EVALUATION The only substantial change to the TS proposed by this amendment is to allow the use of fuel clad with ZIRLO. The use of ZIRLO does not, in itself, change the mechanical, nuclear, or thermohydraulic characteristics of the fuel. The staff finds that the use of ZIRLO will cause no appreciable increase in the consequences of any non-LOCA accident; furthermore, the staff finds that the i
LOCA safety analysis described in Appendices F and G of WCAP-12610 shows that ZIRLO clad fuel is acceptable for use at Surry Power Station.
The staff finds, therefore, that the proposed changes are acceptable.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments.
The State official had no comment.
6.0 ENVIRONMENTAL CONSIDERATION
l 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 l
Part 20.
The NRC staff has determined that the amendments involve no i
significant increase in the amounts, and no significant change in the types, i
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 (60 FR 508). 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.
i
7.0 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 these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
B. Buckley i
Date:
July 27,1995 i
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