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| | number = ML091900724 | | | number = ML091900724 |
| | issue date = 08/05/2009 | | | issue date = 08/05/2009 |
| | title = Project, Units 1 and 2, Safety Evaluation for Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules | | | title = Safety Evaluation for Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules |
| | author name = Thadani M C | | | author name = Thadani M |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Halpin E D | | | addressee name = Halpin E |
| | addressee affiliation = South Texas Project Nuclear Operating Co | | | addressee affiliation = South Texas Project Nuclear Operating Co |
| | docket = 05000498, 05000499 | | | docket = 05000498, 05000499 |
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| ==1.0 INTRODUCTION== | | ==1.0 INTRODUCTION== |
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| By letter dated August 13, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082330456), STP Nuclear Operating Company (STPNOC or the licensee) submitted for the U.S. Nuclear Regulatory Commission (NRC) staff's review a request for revising the withdrawal schedules for two reactor pressure vessel (RPV) surveillance capsules (both are identified as Capsule X) for South Texas Project (STP), Units 1 and 2. The purpose of the licensee's submittal was to postpone the capsule withdrawal dates of the two units by one refueling cycle so that the RPV capsule withdrawal schedules would not coincide with the currently planned schedules for replacement of their RPV heads. The next set of withdrawals is scheduled to occur during Unit 1 refueling outage 15 (1 RE15) and Unit 2 refueling outage 14 (2RE 14). Under the proposed schedule, one capsule per unit will be withdrawn during refueling outages 1 RE16 and 2RE15, for STP, Units 1 and 2, respectively. | | By letter dated August 13, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082330456), STP Nuclear Operating Company (STPNOC or the licensee) submitted for the U.S. Nuclear Regulatory Commission (NRC) staff's review a request for revising the withdrawal schedules for two reactor pressure vessel (RPV) surveillance capsules (both are identified as Capsule X) for South Texas Project (STP), Units 1 and 2. The purpose of the licensee's submittal was to postpone the capsule withdrawal dates of the two units by one refueling cycle so that the RPV capsule withdrawal schedules would not coincide with the currently planned schedules for replacement of their RPV heads. The next set of withdrawals is scheduled to occur during Unit 1 refueling outage 15 (1 RE15) and Unit 2 refueling outage 14 (2RE 14). Under the proposed schedule, one capsule per unit will be withdrawn during refueling outages 1 RE16 and 2RE15, for STP, Units 1 and 2, respectively. |
| | | 2.0 REGULATORY REQUIREMENTS The surveillance programs for STP, Units 1 and 2 were implemented to monitor the induced changes in the mechanical and impact properties of the RPV materials. |
| ===2.0 REGULATORY===
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| REQUIREMENTS The surveillance programs for STP, Units 1 and 2 were implemented to monitor the induced changes in the mechanical and impact properties of the RPV materials. | |
| The surveillance programs were established in accordance with Appendix H to Title 10 of the Code of Federal Regulations Part 50 (10 CFR Part 50), "Reactor Vessel Material Surveillance Program Requirements." Appendix H to 10 CFR Part 50 requires licensees to monitor changes in the fracture toughness properties of ferritic materials in the RPV beltline region of light-water nuclear power reactors. | | The surveillance programs were established in accordance with Appendix H to Title 10 of the Code of Federal Regulations Part 50 (10 CFR Part 50), "Reactor Vessel Material Surveillance Program Requirements." Appendix H to 10 CFR Part 50 requires licensees to monitor changes in the fracture toughness properties of ferritic materials in the RPV beltline region of light-water nuclear power reactors. |
| The regulation states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the American Society for Testing and Materials (ASTM) Standard E185, "Standard Practice for Conducting Surveillance Enclosure | | The regulation states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the American Society for Testing and Materials (ASTM) Standard E185, "Standard Practice for Conducting Surveillance Enclosure |
Letter Sequence Approval |
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MONTHYEARML0919007242009-08-0505 August 2009 Safety Evaluation for Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Project stage: Approval 2009-08-05
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Category:Letter
MONTHYEARML24029A2752024-01-29029 January 2024 Request to Reschedule Evaluated Force-on-Force Drill IR 05000498/20230042024-01-29029 January 2024 Integrated Inspection Report 05000498/2023004 and 05000499/2023004 ML24024A1162024-01-24024 January 2024 STP Unit 2 Request for Information IR 05000498/20244042024-01-18018 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000498/2024404; 05000499/2024404 IR 05000498/20230032023-12-28028 December 2023 Acknowledgment of Reply to a Notice of Violation (NRC Inspection Report 05000498/2023003 and 05000499/2023003) ML23360A1692023-12-26026 December 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the South Texas Project Medical Services Drill Evaluated on August 31, 2023 NOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 ML23326A2592023-12-0505 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23339A1902023-12-0505 December 2023 Update Foreign Ownership, Control, or Influence (FOCI) IR 05000498/20234012023-12-0404 December 2023 Security Baseline Inspection Report 05000498/2023401 and 05000499/2023401 ML23324A0102023-11-16016 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A2282023-11-13013 November 2023 Integrated Inspection Report 05000498/2023003 and 05000499/2023003, and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23298A0002023-11-0101 November 2023 the Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 226 and 211 Related to Order Approving Indirect Transfer of Licenses and Conforming License Amendments ML23303A0782023-10-30030 October 2023 Submittal of Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments ML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) IR 05000498/20234032023-10-26026 October 2023 Material Control and Accounting Program Inspection Report 05000498/2023403 and 05000499/2023403 (Cover Letter) ML23317A1262023-10-12012 October 2023 South. Texas Project Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 26 ML23279A1382023-10-0505 October 2023 Responses to Requests for Additional Information Related to Application for Order Approving Indirect Transfer of Control of Licenses ML23271A1942023-10-0303 October 2023 Notification of Commercial Grade Dedication Inspection (05000498/2024013 and 05000499/2024013) and Request for Information ML23270B2592023-09-27027 September 2023 Update Foreign Ownership, Control, or Influence ML23263B1132023-09-20020 September 2023 Operator Licensing Examination Schedule Revision 1 IR 05000498/20243012023-09-0707 September 2023 Notification of NRC Initial Operator Licensing Examination 05000498/2024301; 05000499/2024301 IR 05000498/20233012023-09-0101 September 2023 NRC Examination Report 05000498/2023301 and 05000499/2023301 ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23236A6042023-08-24024 August 2023 Annual Dose Report for 2022 IR 05000498/20230052023-08-22022 August 2023 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023005 and 05000499/2023005) - Mid Cycle Letter ML23229A5262023-08-17017 August 2023 Inservice Inspection Summary Report - 1 RE24, ML23229A5892023-08-17017 August 2023 Voluntary Response to Regulatory Issue Summary (RIS) 2023-02, Scheduling Information for the Licensing of Accident Tolerant, Increased Enrichment, and Higher Burnup Fuels ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23228A2102023-08-15015 August 2023 Closure of Investigation (OI 4-22-19) ML23222A0322023-08-10010 August 2023 Report of Changes Made to Quality Assurance Program for Radioactive Material Packages ML23221A3002023-08-0909 August 2023 RE22 Inspection Summary Report for Steam Generator Tubinq, Rev. 1 (Epld L-2023-LRO-0029) ML23222A2792023-08-0909 August 2023 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) IR 05000498/20230022023-07-28028 July 2023 Integrated Inspection Report 05000498/2023002 and 05000499/2023002 ML23198A0532023-07-24024 July 2023 Request for Withholding Information from Public Disclosure ML23188A1612023-07-14014 July 2023 the Associated ISFSI - Notice of Consideration of Approval of Indirect Transfer of Licenses and Conforming Amendments and Opportunity to Request a Hearing (EPID L-2023-LLM-0004) - Letter ML23193A9932023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) ML23192A0482023-07-11011 July 2023 NRC Initial Operator Licensing Examination Approval 05000498/2023301; 05000499/2023301 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) ML23180A2822023-06-29029 June 2023 Operator Licensing Examination Schedule ML23177A2522023-06-26026 June 2023 Units 1, 2 & Independent Spent Fuel Storage Installation - Biennial Submittal of Technical Specification Bases Changes, Commitment Changes, 10 CFR 50.59 Evaluation Summary, and 10 CFR 72.48 Evaluation Summary ML23166B0802023-06-14014 June 2023 Update Foreign Ownership, Control, or Influence (FOCI) ML23163A1762023-06-12012 June 2023 Application for Order Approving Indirect Transfer of Control of Licenses 2024-01-29
[Table view] Category:Safety Evaluation
MONTHYEARML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) ML23279A0482023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Enclosure 4 -Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Nonproprietary Safety Evaluation) ML23015A0012023-02-0606 February 2023 Issuance of Amendment Nos. 225 and 210 to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML22300A2492022-12-0606 December 2022 Approval for Alternate Disposal Procedures for Very Low-Level Radioactive Material (EPID: L?2021?LLL?0022) ML22245A0012022-09-12012 September 2022 Relief from the Requirements of the ASME Code ML21319A3552021-12-0909 December 2021 Issuance of Amendment Nos. 224 and 209 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML21320A0022021-12-0808 December 2021 Issuance of Amendment Nos. 223 and 208 to Revise Technical Specification 3.6.3 and to Remove the Technical Specifications Index NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 22021-05-11011 May 2021 Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 ML21033A2392021-04-0808 April 2021 Issuance of Amendment Nos. 222 and 207 to Revise Technical Specifications to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML20253A0462020-09-29029 September 2020 Issuance of Amendment Nos. 220 and 205 to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML20227A3852020-09-0303 September 2020 Nonproprietary - Proposed Alternative RR-ENG-3-24 to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping ML20199M1622020-07-21021 July 2020 Proposed Alternatives PRR-01, PRR-02, PRR-03, and PRR-04 to the Requirements of the ASME OM Code (Epids L-2020-LLR-0007 to L-2020-LLR-0010) ML20141L6122020-05-28028 May 2020 Issuance of Amendment No. 219 to Revise Technical Specifications to Reduce Safety Injection Accumulators Minimum Pressures (Exigent Circumstances) ML19322A7192019-12-0909 December 2019 Issuance of Amendment Nos. 218 and 204 to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML19217A0602019-10-24024 October 2019 Issuance of Amendment Nos. 217 and 203 Revision to Technical Specification Tables to Change Terminology for the P-13 Permissive Interlock Description ML19213A1472019-08-20020 August 2019 Issuance of Amendment Nos. 216 and 202 Standby Diesel Generator Surveillance Requirements ML19142A3072019-08-13013 August 2019 Request for Relief Request RR-ENG-3-23 to Extend Volumetric Examination Interval for Reactor Vessel Closure Head Nozzles ML19067A2222019-06-0606 June 2019 Issuance of Amendment Nos. 215 and 201 Adoption of TSTF-522 Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML18303A2062018-11-0707 November 2018 Request for Relief from ASME Code to Extend the Inservice Inspection Interval for Category B-N-2 and B-N-3 Examinations ML18177A4252018-07-24024 July 2018 Relief from the Requirements of the Asme Code Regarding the Third 10-Year Inservice Inspection Interval ML18187A1492018-07-24024 July 2018 Relief Request RR-ENG-3-22 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML18159A2122018-07-19019 July 2018 Issuance of Amendment Nos. 214 and 200 Emergency Response Organization Time Augmentation and Staffing Chances to the Emergency Plan (CAC Nos. MG0024 and MG0025; EPID L-2017-LLA-0265) ML18128A3422018-06-0707 June 2018 Issuance of Amendment Nos. 213 and 199 to Revise TSs for Administrative Changes and to Relocate Fxy Exclusion Zones to the Colrs(Cac Nos. MG0253 and MG0254, EPID-L-2017-LLA-0300) ML17038A2232017-07-11011 July 2017 Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML17019A0022017-07-11011 July 2017 Safety Evaluation, Enclosure 3 to Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML16319A0102016-12-21021 December 2016 Issuance of Amendment No. 211, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16174A0912016-06-30030 June 2016 Relief Request RR-ENG-3-20, Use of ASME Code Case N-770-1, Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, for the Third 10-Year Inservice Inspection Interval ML16116A0072016-04-29029 April 2016 Issuance of Amendment Nos. 210 and 197, Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years ML15342A0032015-12-28028 December 2015 Issuance of Amendment Nos. 209 and 196, Adopt Technical Specification Task Force (TSTF)-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (CAC MF6178-MF6179) ML15343A1282015-12-11011 December 2015 Issuance of Amendment No. 208, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Unit 1 Cycle 20 (Emergency Circumstances) ML15209A6412015-09-22022 September 2015 Issuance of Amendment Nos. 207 and 195, Revise Updated Final Safety Analysis Report Table 15.6-17 to Correct Radiological Doses Resulting from Calculation Error Performed in Support of Amendments 182 and 169 ML15218A3672015-08-21021 August 2015 Relief Request RR-ENG-17, Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, Third 10-Year ISI Interval ML15201A1952015-08-20020 August 2015 Issuance of Amendment Nos. 206 and 194, Revise the Emergency Action Level Scheme to the NRC-endorsed Scheme Contained in NEI-99, Revision 6 ML15075A1462015-04-29029 April 2015 Issuance of Amendment Nos. 205 and 193, Request to Revise Technical Specification 3.3.1, Functional Unit 20, Reactor Trip Breakers, for Required Actions and Allowed Outage Times ML15049A1292015-02-27027 February 2015 Issuance of Amendment Nos. 204 and 192, Revise Technical Specification 6.9.1.6, Core Operating Limits Report, with Respect to Analytical Methods Used to Determine Core Operating Limits ML14339A1702015-02-13013 February 2015 Issuance of Amendment Nos. 203 and 191, Revise Fire Hazards Analysis Report and Fire Protection Program License Conditions Related to Alternate Shutdown Capability ML14281A0652015-01-29029 January 2015 Issuance of Amendment Nos. 202 and 190, Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date ML13221A0042013-09-0909 September 2013 Issuance of Amendment Nos. 201 and 189, Revise TS 5.0, Design Features, to Reflect Removal of Visitor'S Center Building and References to Emergency Operations Facility ML13142A1602013-06-0606 June 2013 Safety Assessment in Response to Information Request Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13008A5282013-04-25025 April 2013 Issuance of Amendment Nos. 200 and 188, Revise Technical Specification 3.3.3.6, Accident Monitoring Instrumentation ML13087A5172013-04-12012 April 2013 Relief Request RR-ENG-3-09, Request for Relief from ASME Code Requirements; Deferral of Code Repair of Essential Cooling Water System Piping Until April 2013 Refueling Outage ML13004A3392013-03-12012 March 2013 Relief Request RR-ENG-3-10, Reactor Pressure Vessel Head Flange O-Ring Leakoff Lines Non-Destructive Examination, for the Third 10-Year Inservice Inspection Interval ML13007A1362013-01-31031 January 2013 Review of Operations Quality Assurance Plan, Revision 20 ML12243A3432012-09-10010 September 2012 RR RE-ENG-3-04 to Apply Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Requirements for Examination of Class 1 and 2 Piping Welds ML12235A3472012-08-28028 August 2012 Relief Request RR-ENG-3-06 from ASME Code Requirements for Leak Testing Boundaries of Class 1 Pressure-Retaining Components, Third 10-Year Inservice Inspection Interval (TAC ME7053-ME7054) ML12201A2562012-08-16016 August 2012 Relief Request RR-ENG-3-08, Deferral of Code Repair of Flaws in U2 Essential Cooling Water Class 3 Piping Until Restart from Current Refueling Outage Scheduled for Mid-April 2012 ML12152A2452012-08-14014 August 2012 Issuance of Amendment Nos. 199 and 187, Revise Applicability of Risk-Managed Technical Specifications (TS) to TS 3.7.7, Control Room Makeup and Cleanup Filtration System ML1124402222011-11-17017 November 2011 Issuance of Amendment Nos. 198 and 186, Revise Technical Specifications 5.3.1 and 6.9.1.6 to Allow Fuel Assemblies with Optimized Zirlo Cladding ML1126500712011-10-14014 October 2011 Relief Request RR-ENG-3-05, from Requirements for Ultrasonic Examination of Reactor Pressure Vessel Shell-to-Flange Welds for Third 10-Year Inservice Inspection ML1118605352011-07-29029 July 2011 Relief Request RR-ENG-2-55 from ASME Code Requirements for Weld Examinations, Second 10-Year Inservice Inspection Interval 2023-02-06
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 5, 2009 Mr. Edward D. Halpin Chief Nuclear Officer STP Nuclear Operating Company South Texas Project P. O. Box 289 Wadsworth, TX 77483 SOUTH TEXAS PROJECT 1 AND 2: SAFETY EVALUATION FOR REVISION TO REACTOR PRESSURE VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULES (TAC NOS. ME1409 AND ME1410)
Dear Mr. Halpin:
By letter dated August 13, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082330456), STP Nuclear Operating Company (the licensee) submitted for U.S. Nuclear Regulatory Commission (NRC) staff review and approval of a request for revising the withdrawal schedules for the two reactor pressure vessel (RPV) surveillance capsules (both are identified as Capsule X) for South Texas Project (STP), Units 1 and 2. The purpose of the licensee's submittal was to postpone the capsule withdrawal dates for the two units by one refueling cycle so that the RPV capsule withdrawal schedules would not coincide with the schedules for replacement of the respective RPV heads. Under the proposed schedule, one capsule per unit will be withdrawn during refueling outages 1RE16 and 2RE15, for STP, Units 1 and 2, respectively.
Based on its review of the licensee's request, the NRC staff concludes that the proposed revision to withdrawal schedules for the STP, Units 1 and 2 capsules continues to meet the requirements of the American Society for Testing and Materials Standard E185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," and Appendix H to Title 10 of Code of Federal Regulations Part 50, "Reactor Vessel Material Surveillance Program Requirements." Therefore, the NRC staff finds the proposed modified capsule withdrawal schedules for STP, Units 1 and 2 are acceptable.
The NRC staff's safety evaluation is enclosed.
E. Halpin -2 If you have any questions, please contact me at 301-415-1476 or by email at mohan.thadani@nrc.gov.
Sincerely, Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
As stated cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE REVISION 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 August 13, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082330456), STP Nuclear Operating Company (STPNOC or the licensee) submitted for the U.S. Nuclear Regulatory Commission (NRC) staff's review a request for revising the withdrawal schedules for two reactor pressure vessel (RPV) surveillance capsules (both are identified as Capsule X) for South Texas Project (STP), Units 1 and 2. The purpose of the licensee's submittal was to postpone the capsule withdrawal dates of the two units by one refueling cycle so that the RPV capsule withdrawal schedules would not coincide with the currently planned schedules for replacement of their RPV heads. The next set of withdrawals is scheduled to occur during Unit 1 refueling outage 15 (1 RE15) and Unit 2 refueling outage 14 (2RE 14). Under the proposed schedule, one capsule per unit will be withdrawn during refueling outages 1 RE16 and 2RE15, for STP, Units 1 and 2, respectively.
2.0 REGULATORY REQUIREMENTS The surveillance programs for STP, Units 1 and 2 were implemented to monitor the induced changes in the mechanical and impact properties of the RPV materials.
The surveillance programs were established in accordance with Appendix H to Title 10 of the Code of Federal Regulations Part 50 (10 CFR Part 50), "Reactor Vessel Material Surveillance Program Requirements." Appendix H to 10 CFR Part 50 requires licensees to monitor changes in the fracture toughness properties of ferritic materials in the RPV beltline region of light-water nuclear power reactors.
The regulation states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the American Society for Testing and Materials (ASTM) Standard E185, "Standard Practice for Conducting Surveillance Enclosure
-2 Tests for Light-Water Cooled Nuclear Power Reactor Vessels," that is current on the issue date of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) to which the reactor vessel was purchased.
Later editions of ASTM E185 may also be used including those editions through 1982 (ASTM E185-82).
NUREG-1801, "Generic Aging and Lessons Learned (GALL) Report," provides additional guidance concerning the development of surveillance programs to accommodate the 60-year extended period of operation if license renewal is pursued. The RPV surveillance programs for STP, Units 1 and 2, are based on ASTM E185-73. However, their current surveillance capsule withdrawal schedules have been developed in accordance with ASTM E185-82. 3.0 TECHNICAL EVALUATION The licensee's RPV surveillance programs for STP, Units 1 and 2, are based on the ASTM E185-73 standard, and the surveillance capsule withdrawal schedules are in accordance with ASTM E185-82. ASTM E185-82 recommends that a surveillance program provide three surveillance capsules if the predicted transitional temperature shift NDT) at vessel inside surface is less than 100 degrees Fahrenheit (OF). The licensee stated in the submittal that the STP, Units 1 and 2 surveillance programs fall into this category.
The staff verified this based on a survey of the NRC's Reactor Vessel Integrity Database which indicated that the bounding NDT value for the STP, Units 1 and 2 beltline materials for 32 effective full power years (EFPYs) is approximately 58.5 of. So far, three capsules have been withdrawn from each STP RPV, and three capsules remain in each RPV. The last withdrawn capsules have neutron fluence values equivalent to 33.84 EFPYs for the Unit 1 RPV and 30.93 EFPYs for the Unit 2 RPV, meeting the ASTM E185-73 requirement, and meeting effectively the ASTM E185-82 requirement for the equivalent vessel neutron fluence value for the last capsule of each STP unit. Hence, the staff agrees with the licensee that no further samples are needed to support the 40-year operation of STP, Units 1 and 2. STPNOC has stated its intention to submit an application to extend the operating licenses for STP, Units 1 and 2, for an additional 20 years for a license renewal authorization for 60 years of operation.
As such, each unit's Capsule X will qualify operation for 60 years, and the remaining two capsules from each unit will be kept as spares until a determination for disposal is made. The estimated neutron fluence values for each Capsule X at the proposed withdrawal dates are 4.37 X 10 19 n/cm 2 (E > 1.0 million electron volts (MeV)) for Unit 1 and 4.18 X 10 19 n/cm 2 (E > 1.0 MeV) for Unit 2, or equivalently, 59.04 EFPYs for the Unit 1 and Unit 2 RPVs. The irradiated RPV material information from each unit's Capsule X, which is the subject of the present submittal for capsule withdrawal schedule deferral, is intended to support the extended period of operation for STP, Units 1 and 2. Based on the above, the staff has concluded that the proposed withdrawal schedules for Capsule X for each STP unit is consistent with 10 CFR Part 50, Appendix H requirements because it meets the ASTM E185-73 recommendation and effectively meets the ASTM E185-82 recommendation.
-3
4.0 CONCLUSION
Based on its review of the licensee's submittal, the NRC staff concludes that the proposed withdrawal schedules for the STP, Units 1 and 2 capsules continue to meet the requirements of the ASTM Standard E185-82, and Appendix H to 10 CFR Part 50 and is acceptable for implementation.
The licensee must revise the material surveillance program capsule withdrawal schedule in the Updated Final Safety Analysis Report (Section 5.0 and Table 16.1-2) for STP, Units 1 and 2, with only changes approved in this safety evaluation.
The Commission has concluded, based on the considerations discussed above regarding the revised RPV materials surveillance capsule program withdrawal schedule, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by the revised withdrawal schedule, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the revised withdrawal schedule will not be inimical to the common defense and security or to the health and safety of the public. In addition, the NRC staff finds that the revised withdrawal schedule for RPV material surveillance Capsule X, which is consistent with the current license for operation of 40 years, allows future RPV withdrawals of material surveillance capsules to obtain RPV data with estimated fluence values greater than 40 years. However, this safety evaluation does not provide a determination on the material surveillance program for any period of extended operation for STP, Units 1 and 2. The NRC staff will evaluate the applicability of the withdrawal schedule for the extended period of operation once the licensee has submitted a license renewal application.
Principal Contributor:
S. Sheng Date: August 5, 2009 E. Halpin -2 If you have any questions, please contact me at 301-415-1476 or by email at mohan.thadani@nrc.gov.
Sincerely, IRN Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMSouthTexas Resource Resource RidsOgcRp Resource RidsRgn4MailCenter Resource SSheng, NRRIDCI/CVIB ADAMS Accession No. ML091900724
- SE memo dated OFFICE NRR/LPL4/PM NRRlLPL4/LA DCI/CVIB/BC NRR/LPL4/BC NRRlLPL4/PM NAME MThadani JBurkhardt MMitchell*
MMarkley MThadani DATE 7/22/09 7/21/09 7/8109 8/5/09 8/5/09 OFFICIAL RECORD COPY