ML20046C805
| ML20046C805 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/26/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20046C804 | List: |
| References | |
| NUDOCS 9308120199 | |
| Download: ML20046C805 (3) | |
Text
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k UNITED STATES r
NUCLEAR REGULATORY COMMISSION N
WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 81 TO FACILITY OPERATING LICENSE NO. NPF-49 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 DOCKET N0. 50-423
1.0 INTRODUCTION
By "B14378, Application for Amend to License NPF-49,revising TS Section 5.3.1 Re Design Features & Fuel Assemblies to Allow Use of ZIRLO Cladding in Fuel Assemblies for Consistency W/Wording in [[generic letter" contains a listed "[" character as part of the property label and has therefore been classified as invalid.,Suppl 1|letter dated March 15, 1993]], the Northeast Nuclear Energy Company, submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 3 Technical Specifications (TS).
The requested changes would allow (1) the use of ZIRLO fuel, (2) limited substitution of zirconium alloy or stainless steel filler rods for fuel rods, and (3) the use of three new approved analytical methods for Millstone 3.
The Westinghouse ZIRLO fuel was described in the topical report WCAP-12610
" VANTAGE + Fuel Assembly Reference Core Report," and was approved by the staff for irradiation up to 60,000 mwd /MTV rod average burnup.
The Hillstone 3 reload fuel design will allow removal of individual fuel rods from the assemblies that are found to be damaged or have the potential of cladding breach to be replaced by filler rods.
The reconstitution permits these fuel assemblies to be reused without the radiological consequences from the failed fuel rods.
The revised Technical Specification recognizes the acceptability of the use of reconstituted fuel assemblies provided that NRC-approved methodologies are used for safety analyses. The licensee also proposed the use of lead test assemblies in non-limiting core positions.
Our evaluation follows.
2.0 EVALUATI0B The staff approved the ZIRLO fuel design in a safety evaluation to the Westinghouse topical report WCAP-12610 " VANTAGE + Fuel Assembly Reference Core Report." Thus, the staff concludes that the use of ZIRLO fuel is acceptable
.for Millstone 3.
The licensee proposed filler rods of Zircaloy 4, ZIRLO, or stainless steel to replace damaged or failed fuel rods for reconstituting the fuel assemblies.
The licensee safety analyses of reconstitution will be performed according to the NRC-approved methodologies to comply with all safety design bases. The licensee also proposed the use of a limited number of lead test assemblies in non-limiting core positions for the purpose of completing representative testing of a new fuel design.
The licensee proposed Technical Specification 9308120199 930726 PDR ADOCK 05000423 P
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changes are consistent with the requirements described in the Supplement I to Generic Letter (GL) 90-02,
" Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications," ar.0 therefore are acceptable.
The licensee has proposed to revise Section 5.3.1 of the Technical Specifications by the following new paragraph:
The core shall contain 193 fuel assemblies.
Each fuel assembly shall consist of 264 zircaloy-4 or ZIRLO clad fuel rods with an initial 1
composition of natural uranium dioxide or a maximum nominal enrichment of 5.0 weight percent U-235 as fuel material.
Limited substitutions of zircaloy-4, ZIRLO or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assembly configurations shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by test or cycle-specific reload analyses to comply with all fuel safety design bases.
Each fuel rod shall have a nominal activa fuel length of 144 inches. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
Based on staff evaluation, we conclude that the above change is consistent with Supplement I to GL 90-02 and therefore the changes are acceptable.
The licensee has proposed to add the following three approved analytical methods to Section 6.9.1.6.b of the Technical Specifications:
9.
WCAP-10054-P-A, " Westinghouse Small Break ECCS Evaluation Model Using The NOTRUMP Code," August 1985 (W Proprietary).
(Methodology
{
for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
- 10. WCAP-10079-P-A, "NOTRUMP - A Nodal Transient Small Break and General Network Code," August 1985 (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
- 11. WCAP-12610, " VANTAGE + Fuel Assembly Report," June 1990 (W Proprietary.)
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
Since these three analytical methods have been approved by the staff, we I
conclude that these additions are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The State official had no comments.
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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.
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 (58 FR 19485). 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 the amendment will not be inimical to the common de7ense and security or to the health and safety of the public.
Principal Contributor:
S. Wu Date:
July 26, 1993 1
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