ML20134B010
| ML20134B010 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/22/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20134B006 | List: |
| References | |
| NUDOCS 9701290217 | |
| Download: ML20134B010 (3) | |
Text
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Q NUCLEAR REEULATORY COMMISSION WASHINGTON, D.C. 2006H001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.113T0 FACILITY OPERATING LICENSE NO. NPF-6R ILLIN0IS POWER COMPANY. ET AL.
CLINTON POWER STATION. UNIT NO. 1 DOCKET NO. 50-461 1.0 INTRODUCTIO.H By letter dated August 15, 1996, and as supplemented on October 28 and November 15, 1996, and January 7, 1997, Illinois Power Company, the licensee, requested changes to the Clinton Power Station (CPS) Technical Specifications to incorporate the revised Safety Limit Minimum Critical Power Ratio (SLMCPR) as calculated by General Electric (GE) for CPS Cycle 7.
The need to change the SLMCPR resulted from the 10 CFR Part 21 condition reported by GE in their letter to the NRC dated May 24, 1996.
The requested changes would revise the SLMCPR from 1.07 to 1.09 for two recirculation loop operation and from 1.08 to 1.10 for single recirculation loop operation to support GE-10 fuel for CPS Cycle 7 operation.
The October 28, 1996, November 15, 1996, and January 7,1997 submittals provided clarifying information which did not affect the proposed no significant hazards determination as published in the Federal Register on September 11, 1996 (61 FR 47978).
2.0 EVALUATION In a March 27, 1996 telephone call, GE notified the NRC that the SLMCPR generically calculated in accordance with the GE Standard Application for Reactor Fuel (GESTAR II) may be nonconservative when applied to some actual core and fuel designs.
After meeting with the NRC, and in accordance with commitments made to the NRC, GE performed SLMCPR evaluations for all plants utilizing GE fuel and informed the affected plants of the results.
The affected plants were then instructed to establish administrative controls to ensure conformance with the revised safety limit.
Further review of this issue ;y GE resulted in the determination that this constituted a reportable condition per 10 CFR Part 21, as documented in the May 24, 1996, letter from GE to the NRC.
The SLMCPR is a specified acceptable fuel design limit as defined by General Design Criterion 10 of 10 CFR 50, Appendix A.
The SLMCPR is applied to ensure fuel cladding integrity is not lost as a result of over-heating.
The SLMCPR defines the minimum allowable critical power ratio (CPR) at which 99.9% of the fuel rods in the core are expected to avoid boiling transition during the most limiting anticipated operational occurrence (A00).
9701290217 970122 DR ADOCK 0500 1
By letter dated August 15, 1996, the licensee proposed revising CPS Technical Specification 2.1.1.2 to change the SLMCPR for two loop operation from 1.07 to 1.09 and single loop operation from 1.08 to 1.10. These new SLMCPR values were based on revised GE analysis performed for CPS Cycle 7 operation. The CPS cycle-specific fuel and core parameters used in this analysis included actual exposure-dependent rod power for R-factor distributions, and calculations made for several points in the operating cycle.
The staff review determined that the GE analysis include CPS cycle-specific parameters and was based on approved methodologies of GESTAR II (NEDE-240ll-P-5-11, Sections 1.1.5 and 1.2.5) and NED0-10985-A, January 1977, for both single and dual loop operation. The licensee's letters of October 28 and November 15, 1996, provided clarifying information of the analysis performed.
The licensee's letter of January 7,1997, modified Technical Specifications 2.1.1.2 and 5.6.5 to clearly indicate that the specified SLMCPR values are only applicable for Cycle 7 operation.
Based on our review, we conclude that the proposed changes to the SLMCPR are acceptable for CPS Cycle 7 operation because the new SLMCPR was developed with consideration of all the appropriate uncertainties and with considerable conservatism in the methodology.
In addition, the use of the approved methodology will ensure that values for Cycle 7 are determined such that all applicable design bases and safety limits are met. Operation beyond Cycle 7 will require separate, supporting analysis for the SLMCPR values.
3.0 STATE CONSULTATlDH In accordance with the Commission's regulations, the Illinois state official was notified of the proposed issuance of the amendment. The state official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
This 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 or changes a surveillance requirement. 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 (61 FR 47978). The amendment also changes record keeping or reporting requirements. Accordingly, the amendment met i the eligibility criteria for categorical uclusion set forth in 10 CFR 51.22(c)(9) and (c)(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 amendment.
5.0 CONCLUSION
The staff 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 wit 1 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:
T. Huang Date: January 22, 1997 1
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