GO2-99-064, 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: |
| References | |
| GO2-99-064, GO2-99-64, NUDOCS 9904150198 | |
| Download: ML17292B632 (11) | |
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CATEGORY 1 REGULAT INFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCESSION NBR:9904150198
"'OC.DATE: 99/04/07 NOTARIZED: YES FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 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:
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N NOTE TO ALL "RIDS" RECIPIENTS:
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968
~ Richland, Washington 99352-0968 April7, 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 RATIOSAFETY 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 forWNP-2 Cycle 11" 990%i 50i98 990407 PDR ADQCK 05000397 P
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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 followingrestart from the R-14 refueling outage.
Asea Brown Boveri (ABB) has completed an evaluation ofthe ABB SVEA-96 Safety LimitMinimum 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 ofcycle 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 of0.0201 which is contained in the NRC safety evaluation approval ofReference 4. With the approval ofReference 4, it is now appropriate to recalculate the SLMCPRs. Based upon the NRC approved additive constant ofuncertainty of0.0201, as documented in Reference 5, at least 99.9/0 of the SPC ATRIUM-9Xfuel 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 willestablish 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.
summarizes the proposed changes and provides marked up pages of the Technical Specifications. describes an evaluation ofthe proposed changes in accordance with 10CFR50.92(c) and concludes they do not result in a significant hazards consideration. 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 ofWashington has been provided a copy ofthis 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 CLADDINGINTEGRITY (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 followingsentence (see attached page markup): Reference 7 describes the interim use ofincreased ANFB additive constant uncertainty forthe 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.