ML17284A632
| ML17284A632 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/29/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17284A631 | List: |
| References | |
| NUDOCS 9806040039 | |
| Download: ML17284A632 (8) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-&01 LATEDT END E
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By letter dated December 4, 1997, as supplemented by letters dated January 28, 1998, March 3, 1998, March 9, 1998, and April24, 1998, the Washington Public Power Supply System (the Supply System, or the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. NPF-21) for the WPPSS Nuclear Project No. 2.
The proposed changes would revise the technical specifications (TS) to permit the continued use of the existing Siemens Power Corporation minimum critical power ratio (MCPR) safety limits for WNP-2 Fuel Cycle 14 and changes the ASEA Brown Boveri (ABB) MCPR safety limit for single loop operation from 1.08 for Cycle 13 to 1.09 for Cycle 14 The March 3, 1998, March 9, 1998, and April24, 1998, supplemental letters provided additional clarifying information and did not change the staffs original no significant hazards consideration determination published in the ~Fed gJ Hagi.~tr on January 14, 1998 (63 FR 2284).
2.0 V
AT The proposed revisions to the Technical Specifications are described below.
2.1 TS 2.1.1.2 The following changes are proposed for TS 2.1.1."2, Safety LimitMCPR (SLMCPR):
(1)
"For all other fuel, the MCPR" is changed to "The MCPR for the ABB SVEA-96 fuel",
(2)
"1.08" is changed to "1.09" for the MCPR for single recirculation loop operation, and (3)
"13 only" is changed to "14" for the cycle number for the MCPR limits for the
'TRIUM-9X fuel.
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I For the Cycle 14 SLMCPR analyses, the licensee has justified its bases, assumptions, and codes used for the SLMCPR analyses for ABB SVEA-96 fuel to support the TS change for the single loop operation (Reference 1). The two loop and single loop SLMCPRs for the ABB SVEA-96 fuel in WNP-2 Cycle 14 are determined using the reference core loading pattern and state point depletion strategy in the WNP-2 Cycle 14 Reload Design Report (Reference 2) and the approved methodologies including CENPD-300-P-A (Sections 5.3.2.1, 5.3,2.2 and 5.3.2.3)
(Reference 3). The treatment of SLMCPR in mixed cores involving non-ABB fuel follows the procedures described in Section 5.3.2.2 of Reference 3. ABB has evaluated the cycle dependent SVEA-96 SLMCPR for WNP-2 Cycle 14 and the results show that the Cycle 14 SLMCPRs are 1.07 for two loop operation and 1.09 for single loop operation.
The proposed change of the single loop SLMCPR value is needed because the calculated results are about 0.006 greater for Cycle 14 than that for Cycle 13. This is because the assembly radial power distribution used for Cycle 14 has a slightly greater number of assemblies close to the peak assembly power than that for Cycle 13. The interim SLMCPR values for the ATRIUM-9Xfuel were determined by Siemens Power Corporation (SPC) to be 1.13 for two loop operation and 1.14 for single loop operation using NRC approved methodology and an additive constant uncertainty (ACU) of 0.029 for Cycle 13. This is continuously valid for Cycle 14 operation since the thrice-burned ATRIUM-9Xfuel for Cycle 14 will have much lower peak uncontrolled bundle power than that for the fresh ATRIUM-9Xfuel. Also, the calculation of delta CPR includes the application of a conservative adder as described in the Operating License condition imposed by Amendment 151 (Reference 4). Based on our review of the licensee's submittals (References.
1, 5, 6, and 7), the staff finds that the proposed TS change for the single loop SLMCPR of 1.09 for SVEA-96 fuel in Cycle 14 operation is acceptable because the proposed changes will ensure that the fuel design safety criteria, that more than 99.9 percent of the fuel rods avoid transition boiling during normal operation as well as anticipated operational occurrences, is met.
The wording changes from "forall other fuel, the MCPR" to "The MCPR for the ABB SVEA-96 fuel" and from cycle "13 only" to "14" reflect the applicability for WNP-2 Cycle 14 operation and that fuel design safety criteria willbe met. Therefore, the proposed changes are acceptable.
2.2 Bases 2.1.1.2 The proposed change to the Bases is merely to change the Cycle number from "13" to "14" to reflect the applicability of the interim use of increased ANFB additive constant uncertainty for the SPC ATRIUM-9Xfuel to Cycle 14. This change is consistent with the change to TS 2.1.1.2.
2.3 TS 5.6.5, Core Operating Limits Report The following analytic methods used to determine core operating limits are no longer used and are being deleted from the TS:
a.
5.6.5.2, "NRC Approval of ANFB Additive Constants for ANF 9x9 9x BWR Fuel," dated November 14, 1996.
b.
5.6.5.4, XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986.
l Il c.
5.6.5.7, NEDE-24011 P A 10 US, "General Electric Standard Application for Reactor Fuel," U.S., Supplement, March 1991.
d.
5.6.5.10, EMF-CC-074(P)(A), "Volume 1 STAIF A Computer Program for BWR Stability in the Frequency Domain, Volume 2 STAIF A Computer Program for BWR Stability in the Frequency Domain, Code Qualification Report," July 1994.
The remaining methods have been renumbered for continuity in the TS.
The proposed deletions and renumbering to the list of approved methodologies in TS 5.6.5.b are acceptable since these changes are appropriate to reflect the methodologies necessary for Cycle 14 specific operating limits in TS 5.6.5.a.
Based on the review, as discussed above, the staff concludes that the proposed TS revisions are acceptable for WNP-2 Cycle 14 application.
3.0 REFERENCES
1.
Letter (GO2-98-042) from D. W. Coleman to USNRC, "WNP-2 Operating License NPF-21 Request for Amendment Submittal of Additional Information," March 3, 1998.
2.
Attachment 1 to Letter dated April24, 1998, transmitting Supply System Report WNP2-FTS-148, "WNP-2 Cycle 14 Reload Design Report."
3.
CENPD-300-P-A, "Reference Safety Report for Boiling Water Reactor Reload Fuel," July 1996.
4.
Letter USNRC to J. V. Parrish transmitting Amendment No. 151 to Facility Operating License No. NPF-21 dated July 3, 1997.
5.
Letter (GO2-97-219) from P. R. Bemis to USNRC, "WNP-2 Operating License NPF-21 Request for Amendment Minimum Critical Power Ratio Safety Limits," December 4, 1997.
6.
Letter (GO2-98-049) from P. R. Bemis to USNRC, "WNP-2 Operating License NPF-21 Request for Amendment of SLMCPR - Modification of Request," March 9, 1998.
7.
Letter (GO2-98-063) from D. W. Coleman to USNRC, "WNP-2 Operating License NPF-21 Request for Amendment Submittal of Additional Information," April 24 1998.
4.0 In accordance with the Commission's regulations, the Washington State officialwas notified of the proposed issuance of the amendment.
The State official had no comments.
li 5.0 NV ON E
L SI E A ION The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no signifi-cant 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 exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FR 2284). Accordingly, the amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). This amendment also involves changes in recordkeeping, reporting, or administrative procedures or requirements.
Accordingly, with respect to these items, the amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 0). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in,connection with the issuance of the amendment.
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c The Commission has concluded, based on the considerations discussed, above, that (1) there is reasonable assurance that the health and safety of the public willnot be endangered by operation in the proposed manner, (2) such activities willbe conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: T. Huang Date:
May 29, 1998