ML20012C392
| ML20012C392 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/13/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012C390 | List: |
| References | |
| GL-88-16, NUDOCS 9003210181 | |
| Download: ML20012C392 (4) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N05. 92 AND 85 TO FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-282 AND 50-306
1.0 INTRODUCTION
By letter dated November 17, 1989, (Ref. 1), Northern States Power Company (the licensee) proposed changes to the Technical Specifications (TS) for Prairie Island Nuclear Generating Plant, Unit Nos. 1 and-2.
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).
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.
Gu,idance 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 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 TS are in accordance with the guidance provided by Generic Letter 88-16 and are addressed below.
2.1 - The Definitions 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 l_imits is addressed by individual specifications.
2.2 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 3.10.B.1, 3.10.B.2 and 3.10.B.3 Power distribution parameters (the heat flux hot channel factor RIP limit (F0' ), the nuclear enthalpy rise hot channel factor limit RTP (F
, PFDH, the normalized function that limits the heat flux hoi *b$nNe)lfactoraxiallyK(Z),andthetransientaxialxenon factor V(Z) for these specifications are specified in the COLR.
The 9003210181 900313 P,DR ADOCK 0500 g,
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. I high neutron flux trip set point reduction factor, which is used when the nuclear enthalpy rise hot channel factor exceeds its limit, for Specification 3.10.B.3 is also specified in the COLR.
(b) Specification 3.10.B.4 through 3.10.B.9 The axial flux difference limits and target band for these specifications are specified in the COLR.
(c) Specification 3.10.0 Shutdown and control bank insertion limits for this specification are specified in the COLR.
(d) Specification 3.10.J The reactor coolant system flow limit for this specification is specified in the COLR.
The bases of affected specifications have been modified by the licensee to include appropriate reference to the COLR.
Based on our review, we conclude that the changes to these bases are acceptable.
2.3 Specification 6.7.A.6 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 Des'k with copies to the Regiona) Administrator and Resident Inspector.
The report provides the values of cycle-specific parameter 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 consistent with all applicable limits of the safety analysis.
The approved methodologies are the following:
(a) NSPNAD-8101-A, " Qualification of Reactor Physics Methods for Application of PI Units" (latest approved version).
(b) NSPNAD-8102-A, " Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units" (latest, approved version).
(c) WCAP-9272-P-A, " Westinghouse-Reload Safety Evaluation Methodology,"
July 1985.
(d) WCAP-10054-P-A, " Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code" August 1985.
(e) WCAP-10924-P-A, " Westinghouse Large-Break LOCA Best-Estimate Methodology" December 1988.
(f) XN-NF-77-57(A), XN-NF-77-57, Supplement 1 (A), " Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II," May 1981.
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. Fire 11y, 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. These administrative changes do not in any way alter the action noticed or affect the inteal determination.
On 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 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 these changes are adminis-trative in nature'and there is no impact on plant safety as a consequence.
Accordingly, the staff finds that the proposed changes are acceptable.
As part of the implementation of Generic Letter 88-16, the staff has also reviewed a sample COLR that was provided by the licerisee. On the basis of this review, the staff concludes that the format and content of the sample COLR are acceptable. However, the staff requires that separate COLRs be issued for each Prairie Island Unit. This matter was discussed and agreed with by the licensee.
The licensee also proposed a number of Technical Specification changes that are l
net part of the changes needed to implement Generic Letter 88-16. The staff inadvertently omitted from the notice the deletion of the TS 3.10.D.3 I
concerning rod insertion limits, a provision that was applicable to the first fuel cycle only and has no effect en any subsequent fuel cycles for both units.
The other administrative change appear in TS 3.10.B.7(a) where word "its" l
is replaced with the word "the".
This is an editorial change which does not change the restrictive level or the intent of the specification.
These 6dministrative changes do not significantly alter the action noticed or affect the initial determination. These changes are administrative in nature and, therefore, we conclude that they are acceptable.
3.0 ENVIR0lmENTAL CONSIDERATION These amendments involve changes to requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20, and changes recordkeeping, reporting, or administrative procedures or requirements. The staff has determined that the arrendments involve 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 expcsure. The Commission has previously issued a proposed finding that the amendements involve no significant hazards, and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9)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 these amendments.
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-4 4;0 CONCLUSION Wehaveconcluded,basedontheconsiderationsdiscussedabove,that(1)there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendrents will not be inimical to the common defense and (3) security or to the health and safety of the public.
5.0 REFERENCES
1.
Letter from Thomas M. Parker (NSP) to NRC, dated November 17 1989.
2.
Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits from Technical Specifications," dated October 4, 1988.
Principal Contributor: Daniel Fieno Dated: March 13, 1990-
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