ML20248C320
| ML20248C320 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/28/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248C303 | List: |
| References | |
| NUDOCS 8910030423 | |
| Download: ML20248C320 (3) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO."70 TO FACILITY OPERATING LICENSE NO. DPR-22 NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT l
DOCKET NO. 50-263
1.0 INTRODUCTION
By letter dated July 26, 1989 (Ref. 1), Northern States Power Company (the licensee) proposed changes to the Technical Specifications (TSs) for the Monticello Nuclear Generating Plant (Monticello).
The proposed changes would modify specifications having cycle-specific parameter limits by replacing the values of those limits with a reference to the Core Operating Limits Report (COLR) for the values of those limits.
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 TSs.
Guidance on the proposed changes was developed by the NRC on the basis of the review of a lead plant proposal submitted on the Oconee plant docket by Duke Power Company.
This guidance was provided to all power reactor licensees and applicants by Generic Letter 88-16, dated October 4, 1988 (Ref. 2).
2.0 EVALUATION The licensee's proposed changes to the TSs are in accordance with the guidance provided by Generic Letter 88-16 and are addressed below.
(1) The Definition section of the TSs 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 iadividual 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.C.2.a The Rod Block Monitor operability requireirents for this specification are provided in the COLR.
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, (b) Specification 3.2.C.1 (Item 4.a and Note 8 of Table 3.2.3) i The Rod Block Monitor upscale trip settings for this specification are provided in the COLR.
(c) Specification 3.11.A The Maximum Average Planar Linear Heat Generation Rate limits for this specification are provided in the COLR.
(d) Specification 3.11.B The Linear Heat Generation Rate limits for this specification are provided in the COLR.
(e) Specification 3.11.C The Minimum Critical Power Ratio limits for this specification are provided in the COLR.
The bases of affected specifications have been modified by the licensee to l
include appropriate reference to the COLR.
Based on our review, we conclude that the changes to these bases are acceptable.
(3) Specification 6.7.A.7 was added to the reporting requirements of the Administrative Controls section of the TSs. This specification requires
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that the COLR be submitted, upon issuance, to the NRC Document Control j
Desk with copies to the Regional Administrator and Resident Inspector.
The report provides the values of cycle-specific parameter limits that are applicable for the current fuel cycle.
Furthermore, this specification requires that the values of these limits be established using NRC-approved i
methodology and be consistent with all applicable limits of the safety l
analysis. The approved methodologies are the following:
NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latestapprovedversion)
NSPNAD-8608-A, " Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant" (latest approved version)
NSPNAD-8609-A, " Qualification of Reactor Physics Methods for Application toMonticello"(latestapprovedversion)
Finally, the specification requires that all changes in cycle-specific parameter limits be documented in the COLR 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 licensee 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 the TSs. Because plant operation continues to be limited in accordance with the values of cycle-specific parameter limits that are established using i
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. i an NPC-approved methodology, 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 I
acceptable.
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
This amendment involves changes in recordkeeping, reporting, or administrative procedures or requirements and changes requirements with respect to the use of facility components located within the restricted are as defined in 10 CFR Part
- 20. We have determined that the amendment involves no significant increase in the amounts, and no significant change in the types of any effluent that maybe released offsite and that there is no significant increase in individual or cumulative radiation exposure. The staff has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public connent on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(a)and(10).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
S We have 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) issuance of this amer.dment will not be inimical to the connon defense and security or to the i
health and safety of the public.
5.0 REFERENCES
1.
Letter from Thomas M. Parker (HSP) to NRC, dated July 26, 1989.
2.
Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits from Technical Specifications," dated October 4,1988.
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Principal Contributor:
D. Fieno Dated: September 28, 1989 I
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