ML20248E259
| ML20248E259 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 03/28/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248E244 | List: |
| References | |
| NUDOCS 8904120182 | |
| Download: ML20248E259 (2) | |
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UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20565 4,.....,o SAFET) EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 26 TO FACILITY OPERATING LICENSES NOS. NPF-37 AND NPF-66 BYRON STATION, UNITS 1 AND 2 DOCKET NOS. 50-454 AND 50-455 AND SUPPORTING AMENOMENT NO. 15 TO FACILITY OPERATING LICENSES NOS. NPF-72 AND NPF-77 BRAIDWOOD STATION UNITS 1 AND 2 DOCKET NOS. 50-456 AND 50-457
1.0 INTRODUCTION
By letter dated December 12, 1988, Commonwealth Edison Company proposed changes to the Technical Specifications (TS) for Byron Station, Units 1 and 2,-
and Braidwood Station, Units 1 and 2.
The proposed changes would modify-specifications having cycle-specific Fxy limits by replacing the values of those limits with a reference to the Operating Limits Report for the values of those limits. The proposed changes also include the addition of Operating Limits Report to the. Definitions Section and to the reporting requirements of the Administrative Controls Section of TS. Guidance on the proposed changes was developed by NRC on the basis of the review of a lead-plant proposal submitted on the Oconee Plant docket that was endorsed by the Babcock and Wilcox Owners Group. This guidance was provided to ell power reactor licensees and epplicants by Generic Letter 88-16, dated October 4,1988. The December 12, 1988 letter supersedes a previously proposed amendment dated July 11, 1988.
2.0 EVALUATION The licensee's proposed changes to the TS are in accordance with the guidance provided by Generic Letter 88-16 and are addressed below.
i (1) The Definitions Section of the TS was modified to include a definition of i
the Operating Limits Report that requires cycle / reload-specific parameter limits to be establised on a unit-spacific basis in accordance with NRC -
approved methodology that maintains the limits of the safety analysis.
The definition notes that plant operation within these limits is addressed by individual specifications.
(2) Specification 4.2.2.2.e was revised to replace the values of cycle-specific Fxy limits with a reference to the Operating Limits Report that provides these limits.
8904120182 890328 PDR ADOCK 05000454 P
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2 (3) Specification 6.9.1.9 was changed in the reporting requirements of the j
Administrative Controls.Section of the TS. This specification requires that the Operating Limits Report be submitted, upon issuance, to the NRC-Document Control Desk with copies to the Regional Administrator and 1
Resident Inspector. The report provides the values of cycle-specific parameter limits that are applicable for the current fuel cycle.
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Furthermore, this specification requires that the values of these limits j
be established using the NRC-approved methodology in Topical Report NFSR-0016,'" Benchmark of PWR Nuclear Design Methods" dated July M3 and consistent with all applicable limits of the safety analysis. Finally, the specification requires that all changes in cycle-specific parameter limits be documented in the Operating Limits Report before each reload cycle or remaining part of a reload cycle and submitted upo, issuance to NRC, prior to operation with the new parameter limits.
On.the basis of the review of the above items, the NRC staff concludes that the licensee provided an acceptable response to those items as addressed in the NRC guidance in Generic Letter 88-16 on modifying cycle-specific Fxy limits in TS. Because plant operation continues to be limited in accordance with the values of cycle-specific parameter limits that are established using an NRC-approved methodology, the NRC staff concludes that this change is administrative in nature and there is no imp:ct on plant safety as a consequence. Accordingly, the staff finds the proposed changes acceptable, n
3.0' ENVIRONMENTAL CONSIDERATION These amendments involve changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR l
51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance L
of these amendments.
4.0. CONCLUSION On the basis of the considerations discussed above, the NRC staff concludes 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)theissuanceoftheseamendmentswillbeinimicaltothecommon defense and security or to the health and safety of the public.
Principal Contributors: Daniel B. Fieno, SRXB/ DEST Thomas G. Dunning, OTSB/DOEA Leonard N. 01shan, PDIII-2/DRSP Dated: March 28, 1989 l
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