ML112440222
| ML112440222 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/17/2011 |
| From: | Balwant Singal Plant Licensing Branch IV |
| To: | Halpin E South Texas |
| Singal, Balwant, 415-3016, NRR/DORL/LPL4 | |
| References | |
| TAC ME5238, TAC ME5239 | |
| Download: ML112440222 (22) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 17, 2011 Mr. Edward D. Halpin President and Chief Executive Officer!
Chief Nuclear Officer STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483 SUB.JECT: SOUTH TEXAS PROJECT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: USE OF OPTIMIZED ZIRLOTM FUEL ROD CLADDING MATERIAL (TAC NOS. ME5238 AND ME5239)
Dear Mr. Halpin:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 198 to Facility Operating License No. NPF-76 and Amendment No. 186 to Facility Operating License No. NPF-80 for the South Texas Project, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 21,2010.
The amendments revise TS 5.3.1, "FUEL ASSEMBLIES," by adding Optimized ZIRLOTM fuel rods to the fuel matrix in addition to Zircaloy or ZIRLOTM fuel rods that are currently in use. The amendments also add a reference to an NRC-approved VVestinghouse Electric Company LLC topical report regarding Optimized ZIRLOTM to TS Section 6.9.1.6, "Core Operating Limits Report (COLR)."
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
~ ~~ '--, t*s-", \A,~O Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosures:
- 1. Amendment No. 198 to NPF-76
- 2. Amendment No. 186 to NPF-80
- 3. Safety Evaluation cc w!encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 198 License No. NPF-76
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by STP Nuclear Operating Company (STPNOC)*
acting on behalf of itself and for NRG South Texas LP, the City Public Service Board of San Antonio (CPS), and the City of Austin, Texas (COA) (the licensees), dated December 21,2010, complies with the standards and req uirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and Oi) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- STPNOC is authorized to act for NRG South Texas LP, the City Public Service Board of San Antonio, and the City of Austin, Texas, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
Enclosure 1
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 198, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. STPNOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-76 and the Technical SpeCifications Date of Issuance: November 17, 2011
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 SOUTH TEXAS PROJECT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 186 License No. NPF-80
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by STP Nuclear Operating Company (STPNOC)*
acting on behalf of itself and for NRG South Texas LP, the City Public Service Board of San Antonio (CPS), and the City of Austin, Texas (COA) (the licensees), dated December 21,2010, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- STPNOC is authorized to act for NRG South Texas LP, the City Public Service Board of San Antonio, and the City of Austin, Texas, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
Enclosure 2
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment. and Paragraph 2.C.(2) of Facility Operating License No. NPF-80 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A. as revised through Amendment No. 186. and the Environmental Protection Plan contained in Appendix B. are hereby incorporated in the license. STPNOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley. Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-80 and the Technical Specifications Date of Issuance: November 17, 2011
AnACHMENT TO LICENSE AMENDMENT NOS. 198 AND 186 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-498 AND 50-499 Replace the following pages of the Facility Operating Licenses, Nos. NPF-76 and NPF-80, and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Operating License No. NPF-76 REMOVE INSERT
-4 Facility Operating License No. NPF-80 REMOVE INSERT
-4 Technical Specifications REMOVE INSERT 5-6 5-6 6-16 6-16
SOUTH TEXAS LICENSE -4 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 198, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. STPNOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Not Used (4) Initial Startup Test Program (Section 14, SER)*
Any changes to the Initial Test Program described in Section 14 of the Final Safety Analysis Report made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(5) Safety Parameter Display System (Section 18, SSER No. 4)*
Before startup after the first refueling outage, HL&P{**J shall perform the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to issues as described in Section 18.2 of SER Supplement 4.
(6) Supplementary Containment Purge Isolation (Section 11.5, SSER NO.4)
HL&P shall provide, prior to startup from the first refueling outage, control room indication of the normal and supplemental containment purge sample line isolation valve position.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
- The original licensee authorized to possess, use and operate the facility was HL&P.
Consequently, historical references to certain obligations of HL&P remain in the license conditions.
Amendment No. 198
-4 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 186 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. STPNOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Not Used (4) Initial Startup Test Program (Section 14. SR)*
Any changes to the Initial Test Program described in Section 14 of the Final Safety Analysis Report made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(5) License Transfer Texas Genco, LP shall provide decommissioning funding assurance, to be held in decommissioning trusts for South Texas Project, Unit 2 (Unit 2) upon the direct transfer of the Unit 2 license to Texas Genco, LP, in an amount equal to or greater than the balance in the Unit 2 decommissioning trust immediately prior to the transfer. In addition, Texas Genco, LP shall ensure that all contractual arrangements referred to in the application for approval of the transfer of the Unit 2 license to Texas Genco, LP to obtain necessary decommissioning funds for Unit 2 through a non-bypassable charge are executed and will be maintained until the decommissioning trusts are fully funded, or shall ensure that other mechanisms that provide equivalent assurance of decommissioning funding in accordance with the Commission's regulations are maintained.
(6) License Transfer The master decommissioning trust agreement for Unit 2, at the time the direct transfer of Unit 2 to Texas Genco, LP is effected and thereafter, is subject to the following:
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 186
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies. Each fuel assembly shall consist of a matrix of zircaloy, ZIRLO', or Optimized ZIRLO' clad fuel rods with an initial composition of natural or sli~htly enriched uranium dioxide as fuel material. Limited substitutions of zirconium alloy, ZIRLO M, or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 158.9 inches of absorber material. The absorber material within each assembly shall be silver-indium-cadmium or hafnium. Mixtures of hafnium and silver-indium cadmium are not permitted within a bank. All control rods shall be clad with stainless steel tubing.
5.4 (NOT USED) 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological towers shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE 5.6.1 CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
SOUTH TEXAS - UNITS 1 & 2 5-6 Unit 1 - Amendment No. 2,10,16,43, 61,65,89,92,98, 104, 198 Unit 2 - Amendment No. 2,6,32,50 54,76,79,85, 91, 186
6.0 ADMINISTRATIVE CONTROLS 6.9 Reporting Requirements 6.9.1.6b (continued)
- 5. Westinghouse letter NS-TMA-2198, T.M. Anderson (Westinghouse) to K.
Kniel (Chief of Core Performance Branch, NRC) January 31, 1980
Attachment:
Operation and Safety Analysis Aspects of an Improved load Follow Package.
(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control). Approved by NRC Supplement No.4 to NUREG-0422, January 1981. Docket Nos. 50-369 and 50-370.)
- 6. NUREG-0800, Standard Review Plan, U. S. Nuclear Regulatory Commission. Section 4.3, Nuclear Design. July 1981. Branch Technical Position CPB 4.3-1. Westinghouse Constant Axial Offset Control (CAOC).
Rev. 2, July 1981.
(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Contro!).)
- 7. WCAP-10266-P-A. Rev. 2. WCAP-11524-NP-A Rev. 2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code,"
Kabadi, J.N .* et al.. March 1987; including Addendum 1-A, "Power Shape Sensitivity Studies," December, 1987 and Addendum 2-A, "BASH methodology Improvements and Reliability Enhancements," May 1988.
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor) 8.1 WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report,"
April 1995 0!::l.. Proprietary) 8.2 WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRlO', July 2006 0!::l.. Proprietary)
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor)
- 9. CENPD-397-P-A, Revision 01, "Improved Flow Measurement Accuracy Using Crossflow Ultrasonic Flow Measurement Technology," May 2000.
(Methodology for operating at a RATED THERMAL POWER of 3,853 Mwt)
- 10. WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOl Moderator Temperature Coefficient Measurement," March 1997 0!::l.. Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient)
- 11. WCAP 12472-P-A, "BEACON Core Monitoring and Operations Support System," August 1994 0!::l.. Proprietary)
(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor)
(continued)
SOUTH TEXAS - UNITS 1 & 2 6-16 Unit 1 -Amendment No.138, 151, 175, 198 Unit 2 - Amendment No 127, 139, 163, 186
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 198 AND 186 TO FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 STP NUCLEAR OPERATING COMPANY, ET AL.
SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499
1.0 INTRODUCTION
By letter dated December 21, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML103630408), STP Nuclear Operating Company (STPNOC, the licensee), submitted a license amendment request (LAR) for Technical Specification (TS) revisions and an exemption for South Texas Project (STP), Units 1 and 2. The proposed TS changes would revise TS 5.3.1, "FUEL ASSEMBLIES," by adding Optimized ZIRLOTM fuel rods to the fuel matrix in addition to Zircaloy or ZIRLOTM fuel rods that are currently in use as an acceptable cladding material. The amendments would also add a reference to a previously U.S. Nuclear Regulatory Commission (NRC)-approved Westinghouse Electric Company LLC (Westinghouse) topical report (TR) regarding Optimized ZIRLOTM to Section 6.9.1.6, "Core Operating Limits Report (COLR)." In its letter dated December 21,2010, the licensee also requested an exemption from the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46, "Acceptance criteria for emergency core cooling systems [ECCS] for light-water nuclear power reactors," and Appendix K to 10 CFR 50, "ECCS EVALUATION MODELS," to allow the use of fuel rods clad with Optimized ZIRLOTM alloy for future reload applications. The request for exemption is addressed by a separate licensing action under Technical Assignment Control (TAC) Nos. ME5365 and ME5366.
The Optimized ZIRLOTM cladding, manufactured by Westinghouse, is a new version of the ZIRLOTM material and was approved in TR Addendum 1-A to WCAP-12610-P-A and CENPD-404-P-A, entitled "Optimized ZIRLO," for Westinghouse and Combustion Engineering (CE) fuel designs (References 1 and 2). The fuel rod burnup limits were approved to a peak rod average of 62,000 megawatt days per metric ton unit (MWd/MTU) for Westinghouse fuel and 60,000 MWd/MTU for CE fuel. However, the NRC staff requires that licensees using the Optimized ZI RLO ' cladding material comply with the conditions and limitations listed in the NRC staff safety evaluation (SE) dated June 10, 2005 (Reference 1).
Enclosure 3
-2
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," allow a licensee to amend or change the original license applications. The regulations in 10 CFR 50.92, "Issuance of amendment," specify that the NRC staff will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate in determining whether an amendment will be issued to the applicant In its letter dated December 21, 2010, the licensee requested a license amendment to add Optimized ZIRLOTM as an acceptable fuel rod cladding material in the TSs.
By letter dated June 10,2005 (Reference 1), the NRC staff issued an SE approving Addendum 1 to Westinghouse TR WCAP-12610-P-A and CENPD-404-P-A, "Optimized ZIRLOTM," wherein the NRC staff approved the use of Optimized ZIRLOTM as an acceptable fuel cladding material. The NRC staff approved the use of Optimized ZIRLOTM as a fuel cladding material based on:
- 1) similarities to standard ZIRLOTM,
- 2) demonstrated material performance, and
- 3) a commitment to provide irradiated data and validate fuel performance models ahead of burnups achieved in batch application.
The NRC staffs SE for Optimized ZIRLOTM includes 10 conditions and limitations for its use.
By letter dated October 28,2011 (ADAMS Accession No. ML112420611), the NRC staff granted an exemption from specific requirements of 10 CFR 50.46 and Appendix K to 10 CFR 50, for STP, Units 1 and 2, to allow the use of Optimized ZIRLOTM for fuel rod cladding.
3.0 TECHNICAL EVALUATION
On June 10, 2005, the NRC staff issued an SE for Addendum 1 to TR WCAP-12610-P-A and CENPD-404-P-A for Optirnized ZIRLOTM (Reference 1). In the SE, the staff concluded that:
Based upon demonstrated material performance in Addendum 1 and in response to RAts [requests for additional information] (References 2, 3, and 4) 1 and the irradiated database, the NRC staff has approved Optimized ZIRLOTM for full batch implementation.
Refers to the references in the NRC staff evaluation dated June 10, 2005.
-3 In addition, the NRC staff concluded in its SE that:
The NRC staff reviewed the effects of Optimized ZIRLOTM using the appropriate fuel design requirements of [Standard Review Plan 2 ] SRP 4.2 and 10 CFR Part 50, Appendix A, General Design Criteria and found that the TR provided reasonable assurance that under both normal and accident conditions, Westinghouse and CE fuel assembly designs implementing Optimized ZI RLO '
fuel cladding would be able to safely operate and comply with NRC regulations.
The NRC staff's SE also stated that licensees referencing Addendum 1 to the TR to implement Optimized ZIRLOTM must ensure compliance with 10 conditions as specified in the SE. The licensee has documented its compliance with these 10 conditions and limitations in its application dated December 21,2010, and has committed to ensuring compliance with them for future fuel reloads.
3.1 Conditions and Limitations 3.1.1 Condition 1 Condition 1: Until rulemaking to 10 CFR Part 50 addressing Optimized ZIRLOTM has been completed, implementation of Optimized ZIRLOTM fuel clad requires an exemption from 10 CFR 50.46 and 10 CFR Part 50 Appendix K.
The licensee's application dated December 21,2010, included the request for exemption from 10 CFR 50.46 and 10 CFR Part 50 Appendix K. By letter dated October 28, 2011, the NRC staff approved an exemption from specific requirements of 10 CFR 50.46 and Appendix K to 10 CFR 50 for STP, Units 1 and 2, to allow the use of Optimized ZIRLOTM for fuel cladding. The NRC staff concludes that the approach is acceptable.
3.1.2 Condition 2 Condition 2: The fuel rod bumup limit for this approval remains at currently established limits:
62 GWdlMTU [gigawatt days per metric ton unit] for Westinghouse fuel designs and 60 GWdlMTU for CE fuel designs.
In its application dated December 21, 2010, the licensee stated that the maximum fuel rod burnup limit for Westinghouse fuel designs including Optimized ZIRLOTM continues to be 62 GWd/MTU. The NRC staff concludes that this is acceptable.
2 NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," March 2007 (ADAMS Accession No. ML070660036).
-4 3.1.3 Condition 3 Condition 3: The maximum fuel rod waterside corrosion, as predicted by the best-estimate model, will [proprietary limits included in TR and proprietary version of SE] of hydrides for aI/
locations of the fuel rod.
In its application dated December 21,2010, the licensee stated that the licensee will confirm the corrosion and hydrogen pickup using the Optimized ZIRLOTM cladding meet the design limits as part of the core reload design process. Based on the licensee's core reload design process, the NRC staff concludes that this is acceptable.
3.1.4 Condition 4 Condition 4: All the conditions listed in previous NRC SE approvals for methodologies used for standard ZIRLOTM and Zircaloy-4 fuel analysis will continue to be met, except that the use of Optimized ZIRLOTM cladding in addition to standard ZIRLOTM and Zircaloy-4 cladding is now approved.
In its application dated December 21,2010, the licensee stated that it will continue to meet all conditions associated with approved methods for the Optimized ZIRLOTM fuel design as part of the core reload design process. Based on the licensee's core reload design process, the NRC staff concludes that this is acceptable.
3.1.5 Condition 5 Condition 5: All methodologies will be used only within the range for which ZIRLOTM and Optimized ZIRLOTM data were acceptable and for which the verifications discussed in Addendum 1 and responses to RAls were performed.
In its application dated December 21, 2010, the licensee stated that it will make sure that the reload methodologies will be consistent with the approach including conditions and limitations accepted in the approved topical report Addendum 1-A to WCAP-12610-P-A and CENPD-404-P-A, "Optimized ZIRLOTM ," as part of the core reload design process. Based on the licensee's core reload design process, the NRC staff concludes that this is acceptable.
-5 3.1.6 Condition 6 Condition 6: The licensee is required to ensure that Westinghouse has fulfil/ed the fol/owing commItment: Westinghouse shall provide the NRC staff with a letter(s) containing the following information (Based on the schedule described in response to RAI #3) [Reference 3/:
- a. Optimized ZIRLOTM LTA [lead test assembly] data from Byron, Calvert Cliffs, Catawba, and Millstone.
- i. Visual ii. Oxidation of fuel rods iii. Profilometry iv. Fuel rod length
- v. Fuel assembly length
- b. Using the standard and Optimized ZIRLOTM database including the most recent L TA data, confirm applicability with currently approved fuel performance models (e.g., measured vs. predicted).
In its application dated December 21, 2010, the licensee indicated that Westinghouse has provided the NRC staff a number of LTA data and models (References 3, 4,5,6, and 7). The data provided, but were not limited to, the information described in the Condition 6.a.
Westinghouse will continue to evaluate the applicability and adequacy of the fuel performance models for the Optimized ZIRLOTM fuel design. Confirmation of the approved models' applicability up through the projected end of cycle burnup for the Optimized ZIRLOTM fuel rods must be completed prior to their initial batch loading and prior to the startup of subsequent cycles. As described in the licensee's Regulatory Commitment No. 10-24696-03 (listed in Section 4.0 of this SE), until the commitment is complete, the licensee will confirm that, as higher burnups/fluencies are achieved for Optimized ZIRLOTM clad fuel rods, the requirements of this condition are met as it applies to STP, Units 1 and 2.
Based on the LTA references and the commitment, the NRC staff concludes that this is acceptable.
3.1.7 Condition 7 Condition 7: The licensee is required to ensure that Westinghouse has fulfilled the following commitment: Westinghouse shall provide the NRC staff with a letter containing the following information (based on the schedule described in response to RAI #11 [Reference 3/):
- a. Vogtle growth and creep data summary reports.
3 Refers to the references in the NRC staff evaluation dated June 10, 2005.
- 6
- b. Using the standard ZIRLOTM and Optimized ZIRLOTM database including the most recent Vogtle data, confirm applicability with currently approved fuel performance models (e.g., level of conservatism in W rod pressure analysis, measured vs. predicted, predicted minus measured vs. tensile and compressive stress).
Westinghouse has provided the NRC staff a number of LTA data and models including the Vogtle results (References 3. 4. 5,6. and 7). The data provided. but were not limited to, the information described in the Condition 7.a.
In its application dated December 21, 2010, the licensee indicated that the data from three cycles of operation had been evaluated and that the updated creep model had been used to predict the growth and creep in fuel rod performance. The licensee provided the favorable results to the NRC staff (Reference 7). Confirmation of the approved models' applicability up through the projected end of cycle burnup for the Optimized ZIRLOTM fuel rods must be completed prior to their initial batch loading and prior to the startup of subsequent cycles. As described in the Regulatory Commitment No. 10-24696-04 (listed in Section 4.0 of this SE), until the commitment is complete, the licensee will confirm that the requirements of this condition are met as it applies to STP, Units 1 and 2.
Based on the LTA references and the commitment, the NRC staff concludes that this is acceptable.
3.1.8 Condition 8 Condition 8: The licensee shall account for the relative differences in unirradiated strength (YS
[yield strength] and UTS [ultimate tensile strength]) between Optimized ZIRLOTM and standard ZIRLOTM in cladding and structural analyses until irradiated data for Optimized ZIRLOTM have been collected and provided to the NRC staff.
- a. For the Westinghouse fuel design analyses:
- i. The measured, unirradiated Optimized ZIRLOTM strengths shall be used for beginning-of-life (BOL) analyses.
ii. Between BOL up to a radiation f1uence of 3.0 x 1tY1 nlcm 2 (E > 1MeV),
pseudo-irradiated Optimized ZIRLOTM strength set equal to linear interpolation between the following two strength level points: At zero f1uence, strength of Optimized ZIRLOTM equal to measured strength of Optimized ZIRLOTM and at afluence of 3.0 x 1tY1 nlcm 2 (E > 1MeV),
irradiated strength of standard ZIRLOTM at the fluence of 3.0 x 1tY1 nlcm 2 (E > 1Me V) minus 3 ksi.
-7 iii. During subsequent irradiation from 3.0 x 1(jl nlcm 2 up to 12 X 1(jl nlcm 2 ,
the differences in strength (the difference at a f/uence of 3 x 1(jl nlcm 2 due to tin content) shall be decreased linearly such that the pseudo irradiated Optimized ZIRLOTM strengths will saturate at the same properties as standard ZIRLOTM at 12 x 1c1 1 nlcm2.
- b. For the CE fuel design analyses, the measured, unirradiated Optimized ZIRLOTM strengths shall be used for all f/uence levels (consistent with previously approved methods).
In its application dated December 21,2010, the licensee stated that the relative differences in unirradiated strength between Optimized ZIRLOTM and standard ZIRLOTM in cladding and structural analyses will be accounted for until irradiation data for Optimized ZIRLOTM is accepted by the NRC staff. Analysis of Optimized ZIRLOTM clad fuel rods will use the YS and UTS as modified per Conditions B.a.i, B.a. ii, and B.a.iii until such time that irradiation data for Optimized ZIRLOTM strengths are collected and provided to the NRC staff. As described in the Commitment No.1 0-24696-05, until the values are accepted by the staff, the licensee will confirm that the requirements of this condition are met as it applies to STP, Units 1 and 2. The licensee stated that Condition B.b is not applicable because STP, Units 1 and 2 are Westinghouse fuel design plants.
Based on the commitment, the NRC staff concludes that this is acceptable.
3.1.9 Condition 9 Condition 9: As discussed in response to RAI #21 (Reference 3t, for plants introducing Optimized ZIRLOTM that are licensed with LOCBART or STRIKIN-II and have a limiting PCT
[peak cladding temperature] that occurs during blowdown or early ref/ood, the limiting LOCBART or STRIKIN-/I calculation will be rerun using the specified Optimized ZIRLOTM material properties. Although not a condition of approval, the NRC staff strongly recommends that, for future evaluations, Westinghouse update all computer models with Optimized ZIRLOTM specific material properties.
In its application dated December 21,2010, the licensee stated that a LOCBART calculation using the Optimized ZIRLOTM specific material models was not required because the approved peak clad temperature occurred during the late reflood, unlike the blowdown or early reflood, of a large break loss-of-coolant accident (LOCA). In addition, the STP units are not licensed with STRIKIN-II. Therefore, this condition does not apply to the STP, Units 1 and 2.
Based on the technical assessment, the NRC staff concludes that this is acceptable.
4 Refers to the references in the NRC staff evaluation dated June 10, 2005,
- 8 3.1.10 Condition 10 Condition 10: Due to the absence of high temperature oxidation data for Optimized Z/RLOTM, the Westinghouse coo/ability limit on PCT during the locked rotor event shall be {proprietary limits included in TR and proprietary version of SEj.
In its application dated December 21,2010, the licensee stated that the locked rotor event will be assessed against this coolability limit for the Optimized ZIRLOTM fuel design as part of the core reload design process. Based on the licensee's core reload design process, the NRC staff considers that this condition is met by the licensee.
Based upon the information provided, the NRC staff concludes that the licensee's response, as discussed above, meets the requirements of all SE Conditions and Limitations for STP, Units 1 and 2. Therefore, the NRC staff concludes that the Optimized ZIRLOTM fuel design is acceptable for use in STP, Units 1 and 2, to a peak rod average burnup limit of 62 GWD/MTU.
3.2 TS Revisions 3.2.1 Section 5.3.1, "FUEL ASSEMBLIES" In its letter dated December 21,2010, the licensee proposed to add Optimized ZIRLOTM as an acceptable fuel rod cladding material. The revised TS reads as follows (the proposed change is underlined):
" ... Each assembly shall consist of a matrix of zircaloy, ZI RLO TM, or Optimized ZIRLOTM clad fuel rods ... "
Based on the approved Optimized ZIRLOTM fuel, the NRC staff concludes that the proposed revision to the TSs is acceptable for STP, Units 1 and 2.
3.2.2 Section 6.9.1.6.b, "Core Operating Limits Report (COLR)"
In its letter dated December 21, 2010, the licensee proposed to add the approved Westinghouse TR Addendum 1-A to WCAP-12610-P-A and CENPD-404-P-A, "Optimized ZIRLO," to the list of references in the COLR. Existing reference 8 will be renumbered as 8.1 and the new reference to WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOTM," July 2006, will be added as reference 8.2. Based on the approved TR, the NRC staff concludes that this revision is acceptable for STP, Units 1 and 2.
3.3 Summary of Technical Evaluation The NRC staff has reviewed the proposed amendment of the TS. Based on the evaluation set forth above, the NRC staff concludes that the Optimized ZIRLOTM fuel design is acceptable to a peak rod average burnup limit of 62 GWd/MTU and the associated TS revisions are acceptable.
- 9 4.0 REGULATORY COMMITMENTS In its letter dated December 21,2010, the licensee made the following regulatory commitments and indicated that these commitments will be implemented prior to the loading of the fuel rods with Optimized ZIRLOTM cladding:
Regulatory Commitment No. Description of the Regulatory Commitment 10-24696-03 Lead Test Assembly (LTA) measured data and favorable results from visual examinations of once, twice, and thrice-burned LTAs confirm, for three cycles of operation, that the current fuel performance models are applicable for Optimized ZIRLOTM clad fuel rods. Westinghouse will continue to provide additional data from the Optimized ZIRLOTM LTA programs to the NRC as it becomes available. Confirmation of the approved models' applicability up through the projected end of cycle burnup for the Optimized ZIRLOTM fuel rods must be completed prior to their initial batch loading and prior to the startup of subsequent cycles.
Until the commitment is complete, STPNOC will confirm that, as higher burnups/fluences are achieved for Optimized ZIRLOTM clad fuel rods, the requirements of this condition are met as it applies to STP, Units 1 and 2.
10-24696-04 Data from three cycles of operation have been evaluated and the fuel rod creep models from fuel rod design codes have been used to predict growth and creep performance of the samples. This information was provided to the NRC in the most recent informational letter 0!i.. LTR NRC-10-43) dated July 26,2010. Confirmation of the approved models' applicability up through the projected end of cycle burnup for the Optimized ZIRLOTM fuel rods must be completed prior to their initial batch loading and prior to the startup of subsequent cycles. Until the commitment is complete, STPNOC will confirm that the requirements of this condition are met as it applies to STP, Units 1 and 2.
10-24696-05 The relative differences in unirradiated strength (YS and UTS) between Optimized ZIRLOTM and standard ZIRLOTM in cladding and structural analyses will be accounted for until irradiation data for Optimized ZIRLOTM is accepted by the NRC staff. Analysis of Optimized ZIRLOTM clad fuel rods will use the yield strength and Ultimate tensile strength as modified per Conditions B.a.i, B.a. ii, and B.a. iii until such time that irradiation data for Optimized ZIRLOTM strengths are collected and provided to the NRC. Until the values are accepted by the NRC, STPNOC will confirm that the requirements of this condition are met as it applies to STP, Units 1 and 2.
The NRC staff reviewed the commitments made by the licensee and concludes that these commitments are acceptable.
- 10
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to 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 amendments 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 exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on April 5, 2011 (76 FR 18804). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
7.0 CONCLUSION
The Commission has 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) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
8.0 REFERENCES
- 1. Berkow, H. N., U.S. Nuclear Regulatory Commission, letter to J. A Gresham, Westinghouse Electric Company, "Final Safety Evaluation for Addendum 1 to Topical Report WCAP-12610-P-A and CENPD-404-P-A, 'Optimized ZIRLOTM' (TAC No.
MB8041)," dated June 10, 2005 (ADAMS Accession No. ML051670395).
- 2. Gresham, J. A, Westinghouse Electric Company LLC, letter to U.S. Nuclear Regulatory Commission, "Issuance of Approved Version of WCAP-1261 O-P-A & CENPD-404-P-A, Addendum 1-A (Proprietary)IWCAP-14342-A & CENPD-04-NP-A, Addendum 1-A (Non Proprietary) 'Optimized ZIRLOTM'," dated July 10. 2006 (ADAMS Accession Nos.
ML062080563 and ML062080569).
- 3. Gresham, J. A, Westinghouse Electric Company LLC, letter to U.S. Nuclear Regulatory Commission, "SER Compliance with WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A 'Optimized ZIRLOTM' (Proprietary/Non-proprietary)," dated January 4, 2007 (not publicly available - proprietary).
- 11
- 4. Gresham, J. A, Westinghouse Electric Company LLC, letter to U.S. Nuclear Regulatory Commission, "SER Compliance with WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A 'Optimized ZIRLOTM' (Proprietary/Non-Proprietary)," dated November 6, 2007 (ADAMS Accession No. ML073130555).
- 5. Gresham, J. A, Westinghouse Electric Company LLC, letter to U.S. Nuclear Regulatory Commission, "SER Compliance with WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A 'Optimized ZIRLOTM' (Proprietary/Non-Proprietary)," dated February 5, 2008 (ADAMS Accession Nos. ML080390494).
- 6. Gresham, J. A, Westinghouse Electric Company LLC, letter to U.S. Nuclear Regulatory Commission, "SER Compliance with WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A 'Optimized ZIRLOTM' (Proprietary/Non-Proprietary)," dated December 30, 2008 (not publicly available - proprietary).
- 7. Gresham, J. A, Westinghouse Electric Company LLC, letter to U.S. Nuclear Regulatory Commission, USER Compliance ofWCAP-12610-P-A & CENPD-404-P-A Addendum 1-A
'Optimized ZIRLOTM' (Proprietary/Non-Proprietary)," dated July 26,2010 (ADAMS Accession Nos. ML102140213 and ML102140214).
Principal Contributor: Shih-Lang Wu, NRR/DSS/SNPB Date: November 17, 2011
November 17. 2011 Mr. Edward D. Halpin President and Chief Executive Officerl Chief Nuclear Officer STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth.TX 77483
SUBJECT:
SOUTH TEXAS PROJECT. UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: USE OF OPTIMIZED ZIRLOTM FUEL ROD CLADDING MATERIAL (TAC NOS. ME5238 AND ME5239)
Dear Mr. Halpin:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 198 to Facility Operating License No. NPF-76 and Amendment No. 186 to Facility Operating License No. NPF-80 for the South Texas Project. Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 21,2010.
The amendments revise TS 5.3.1, "FUEL ASSEMBLIES," by adding Optimized ZIRLOTM fuel rods to the fuel matrix in addition to Zircaloy or ZIRLOTM fuel rods that are currently in use. The amendments also add a reference to an NRC-approved VVestinghouse Electric Company LLC topical report regarding Optimized ZIRLOTM to TS Section 6.9.1.6. "Core Operating Limits Report (COLR)."
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, IRA!
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosures:
- 1. Amendment No. 198 to NPF-76
- 2. Amendment No. 186 to NPF-80
- 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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