ML20005E776
| ML20005E776 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/22/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005E772 | List: |
| References | |
| GL-88-16, NUDOCS 9001110040 | |
| Download: ML20005E776 (3) | |
Text
l
[,[)
jo,,
UNITED STATES g
NUCLEAR REGULATORY COMMISSION 5
,t WA$HINGTON D C.20555 i
%,,.... +,5 r
1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 28 TO FACILITY OPERATING LICENSE NO. NPF-62 CLINTON POWER STATION, UNIT NO. 1 ILLINOIS POWER COMPANY ET AL.
DOCKET NO. 50-461
1.0 INTRODUCTION
By letter dated June 12,1989 (Ref.1), as amended by letter dated August 17, 1989 (Ref. 2), Illinois Power Company, et 31., (the licensees) proposed changes to the Technical Specifications (TS) for the Clinton Power Station.
The proposed changes would modify specifications having cycle-specific parameter limits by replacing the values of those limits with a reference totheCoreOperatingLimitsReport(COLR)forthevaluesofthoselimits.
The proposed changes also include the addition of the COLR to the Definitions Section and to the reporting requirements of the Administrative Controls Section of the TS. Guidance on the proposed changes was developed by NRC on the basis cf the review of a lead-plant proposal submitted on the Oconee plant docket by Duke Power Company. This guidance wcs provided to all power reactor licensees and applicants by Generic Letter 88-16, dated October 4,1988(Ref.3).
2.0 EVALUATION The licensees' praposed changes to the TS are in accordance with the guidance providtJ by Generic Letter 88-16 and are addressed below.
(1) The Definition Section of the TS was modified to include a definition of the Core Operating Limits Report that requires cycle / reload-specific parameter limits to be established on a unit-specific basis in accordance with an 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) The following specifications were revised to replace the values of cycle-specific parameter limits with a reference to the COLR that provides these limits.
(a) Specification 3.2.1 TheAveragePlanarLinearHeatGenerationRate(APLHGR) limits, the flow dependent MAPLHGR factor MAPFAC, and the power f
dependent MAPFAC for this specification are provided in the COLR.
p 00bEl $$$$$$e, n
1
e.
4
.p s
[
~ r
-(b) Specification 3.2.3 TheMinimumCriticalPowerRatio(MCPR)limitsMCPR and MCPR f
P for this specification are provided in the COLR (c) Specification 3.2.4 L
The Linear Heat Generation Rate (LHGR) limits for this specification are provided in the COLR.
The Bases of affected specifications have been modified by the licensee to include a)propriate reference to the COLR.
Based on our review, we conclude t1at_the :.hanges to thcsc Bases are acceptable.
(3) Specification 6.9.1.9 was added to the reporting requirements of the
' Administrative Controls Section of the TS. This specification requires that the COLR be submitted, upon issuance, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. The report provides the values of cycle-specific paranieter limits that are applicable for the current fuel cycle.
Furthermore, these specifications require that the values of these limits be established using NRC approved methodologies and be consis-tent with all applicable limits of the safety analysis. The approved methodologies are the fclicwing:
(a) " General Electric Standard Application for Reactor fuel
-(GESTAR II)," NEDE-24011-P-A (latest approved version).
(b) " Maximum Extended Operating Domain and Feedwater Heater Out-of-Service Analysis for Clinton Power Station,"
NEDC-31546P, August 1988.
Finally, the specification requires that all changes in cycle-specific parameter limits be documented in the CCLR before each reload cycle or remaining part of a reload cycle and submitted upon 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 licensees provided an acceptable response to those items as addressed in the NRC guidance in Generic Letter 88-16 on modifying cycle-specific parameter limits in TS.
Because plant operation continues to be limited in accordance with the values of cycle-specific parameter limits that are established using NRC approved methodologies, the NRC staff concludes that this change is administrative in nature and there is no impact on plant safety as a consequence. Accordingly, the staff finds that the proposed changes are acceptable.
{,
.o o
- 0 As part of the implementation of Generic Letter 88-16, the staff has also reviewed a sample COLR that was provided by the licensee. On the basis of this review, the staff concludes that the format and content of the sample COLR are acceptable.
3.0 ENVIRONMENTAL-CONSIDERATION Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and finding of no significant impact has been prepared and published (54 FR 52474) in the Federal Register on December 21, 1989. Accordingly, based upon the environmental assessment, the Commission had determined that the issuance of this amendment will not have a significant effect on the quality of the human environment and that no environmental impact statement need be prepared.
4.0 CONCLUSION
S The Commission has issued a Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing which was published in the Federal Register (54 FR 31900) on August 2, 1989.
No petition to intervene or request for hearing has been filed on this action.
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 preposed manner, and (2) such activities will be conducted in compliance with the Connission's regulations, and issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 REFERENCES
1.
Letter (U-601465) from J.S. Perry (IPC)(to NRC, dated June 12, 1989.
2.
Letter (U-601499) from D.L. Holtzscher IPC) to NRC, dated August 17, 1989.
3.
Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits from Technical Specifications," dated October 4,1988.
Principal Contributor:
Daniel Fieno, SRXB l
Dated: December 22, 1989