ML17292B632

Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO

ML17292B632
Person / Time
Site:	Columbia
Issue date:	04/07/1999
From:	Galen Smith WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17292B633	List: ML17292B632 ML17292B634
References
GO2-99-064, GO2-99-64, NUDOCS 9904150198
Download: ML17292B632 (11)

Text

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REGULAT . INFORMATION DISTRIBUTIO SYSTEM (RIDS)

ACCESSION NBR:9904150198 "'OC.DATE: 99/04/07 NOTARIZED: YES DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUIFT N2&'.E AUTHOR AFFILIATION SMITH,G.O. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Application for amend to license NPF-21,rec(uesting mod to MCPR safety limits by 990930 to allow continued power operation at plant following restart from R-14 RFO.

DISTRIBUTION CODE: ZOOID COPIES RECEIVED:LTR i ENCL J SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 CUSHING,J 1 INTERNAL: ACRS 1 1 FILE CENTER 01 1 NRR/DE/EEIB 1 1 /DX*/R 1 1 hRR/DE/EMEB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB NUDOCS-ABSTRACT 1

1 1

1 NRR/SPSB JUNG,I OGC/HDS3 1

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N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COP1ES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 14

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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 April 7, 1999 GO2-99-064 Docket No. 50-397 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

WNP-2 OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT MINIMUMCRITICALPOWER RATIO SAFETY LIMITS

References:

1) Letter ABBWP-99-015 dated February 19, 1999, R Matheny (ABB) to RA Vopalensky (Supply System), "WNP-2 Cycle 15 Safety Limit Minimum Critical Power Ratio for SVEA-96 Fuel Based on Reference Core"

2) CE NPSD-844-P, "WNP-2 Cycle 15 Reference Core Reload Design Report",

January 1999

3) CENPD-300-P-A, "Reference Safety Report for Boiling Water Reactor Reload Fuel", July 1996

4) ANFB Critical Power Correlation Uncertainty for Limited Data Sets, ANF-1125(P)(A), Supplement 1, Appendix D, Siemens Power Corporation-Nuclear Division, July 1998

5) Letter KVW:98:148 dated July 8, 1998, KV Walters, (Siemens Power Corporation), to RA Vopalensky (Supply System), "MCPR Safety Limit Reanalysis for WNP-2 Cycle 11" 990%i 50i98 990407 PDR ADQCK 05000397 P PDR

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REQUEST FOR AME~ENT MIRMIIMCRISICALECWER RATIO SASESS LIMISS Page 2 In accordance with the Code of Federal Regulations, Title 10, Parts 50.59, 50.90, and 2.101, the Supply System hereby submits a request for amendment of the WNP-2 Operating License.

Specifically, the Supply System is requesting modification of the minimum critical power ratio safety limits by September 30, 1999. Approval of the proposed change is necessary to allow continued power operation at WNP-2 following restart from the R-14 refueling outage.

Asea Brown Boveri (ABB) has completed an evaluation of the ABB SVEA-96 Safety Limit Minimum Critical Power Ratio (SLMCPR) for WNP-2 Cycle 15 (Reference 1). This evaluation is based on the reference core loading pattern and state point depletion strategy in Reference 2. The NRC approved methodology documented in CENPD-300-P-A, "Reference Safety Report for Boiling Water Reactor Reload Fuel", July 1996 (Reference 3) was utilized for this evaluation. The evaluation of the ABB SVEA-96 SLMCPR, as a function of cycle exposure, established values late in Cycle 15 that provide conservative two loop and single loop SLMCPRs of 1.10 and 1.12, respectively, which can be used to represent the entire cycle.

NRC approved methodology (Reference 3) assumes that the SLMCPR for the non-ABB resident fuel is unchanged &om the last cycle for which it was evaluated by its supplier. The ATIUUM-9Xfuel was last evaluated by Siemens Power Corporation (SPC) for Cycle 11 (Reference 5) using the additive constant uncertainty for ATRIUM-9Xfuel of 0.0201 which is contained in the NRC safety evaluation approval of Reference 4. With the approval of Reference 4, it is now appropriate to recalculate the SLMCPRs. Based upon the NRC approved additive constant of uncertainty of 0.0201, as documented in Reference 5, at least 99.9/0 of the SPC ATRIUM-9X fuel rods are expected to avoid boiling transition with a SLMCPR of 1.10 during two loop operation and 1.11 during single loop operation.

In summary, this proposed change will establish the SLMCPR for SPC ATRIUM-9Xfuel at 1.10 for two recirculation loop operation or 1.11 for single recirculation loop operation. This fuel is co-resident with ABB fuel at WNP-2. The SLMCPR for ABB SVEA-96 fuel shall be 1.10 for two recirculation loop operation or 1.12 for single recirculation loop operation.

Additional information has been attached to this letter to complete the Supply System's amendment request. Attachment 1 provides a detailed description of the proposed changes. Attachment 2 summarizes the proposed changes and provides marked up pages of the Technical Specifications. describes an evaluation of the proposed changes in accordance with 10CFR50.92(c) and concludes they do not result in a significant hazards consideration. Attachment 4 provides the Environmental Assessment Applicability Review and notes that the proposed change meets the eligibility criteria for a categorical exclusion as set forth in 10CFR51.22(c)(9). Therefore, in accordance with 10CFR51.22(b), an environmental assessment of the change is not required. submits the typed Technical Specification pages as proposed by this amendment.

This request for an amendment has been reviewed and app'roved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board. In accordance with 10CFR50.91, the state of Washington has been provided a copy of this letter.

REQUEST FOR AME NT MINIMUMCRITICAL WER RATIO SAFETY LIMITS Page 3 Should you have any questions or desire additional information regarding this matter, please contact me or P. J. Inserra at (509) 377-4147.

Respectfu I, pQ

785 psig and core flow h 10/0 rated core flow: The MCPR for ATRIUM-9Xfuel shall be > 1.10 for two recirculation loop operation or > 1.11 for single recirculation loop operation. The MCPR for ABB SVEA-96 fuel shall be > 1.10 for two recirculation loop operation or > 1.12 for single recirculation loop operation. Reference 9 [ANFB Critical Power Correlation Uncertainty for Limited Data Sets, ANF-1125(P)(A), Supplement 1, Appendix D, Siemens Power Corporation - Nuclear Division, July 1998] is added to Technical Specification 5.6.5 list of COLR References (page 5.0-21) (see attached page markup). ~ (Information Only) BASES Section 2.1.1.1 FUEL CLADDING INTEGRITY (page B 2.0-2) is changed to add new Reference 7 (see attached page markup). ~ (Information Only) BASES Section 2.1.1.2 MCPR (page B 2.0-3) is changed to delete the use of an interim additive constant uncertainty for the SPC ATRIUM-9Xfuel for Cycle 14 by deleting the following sentence (see attached page markup): Reference 7 describes the interim use of increased ANFB additive constant uncertainty for the SPC ATRIUM-9Xfuel during Cycle 14. ~ (Information Only) BASES REFERENCES (page B 2.0-5) is changed to delete old Reference 7 and add new Reference 7 (see attached page markup):

7. ANFB Critical Power Correlation Uncertainty for Limited Data Sets, ANF-1125(P)(A), Supplement 1, Appendix D, Siemens Power Corporation-Nuclear Division, July 1998.