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Category:Letter type:NOC
MONTHYEARNOC-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 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) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003761, Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-09-10010 September 2020 Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic NOC-AE-20003760, Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal2020-09-0808 September 2020 Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal 2023-07-11
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22138A2022022-04-28028 April 2022 Submittal of Revision 21 to Updated Final Safety Analysis Report ML22140A0812022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22140A0792022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML22140A0692022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML22140A0712022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22140A0772022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (Redacted) ML22140A0672022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses (Redacted) ML22140A0612022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems (Redacted) ML22140A0562022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22140A0642022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 1, Responses to NRC Questions ML22140A0682022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22140A0752022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Controlled Drawings, Part 4 of 4 (Redacted) ML22140A0652022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22140A0622022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Controlled Drawings, Part 3 of 4 ML22140A0732022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Controlled Drawing Manual Cross-Reference ML22140A0782022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22140A0802022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML22140A0762022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 19A, License Renewal ML22140A0582022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Controlled Drawings, Part 2 of 4 (Redacted) ML22140A0742022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Controlled Drawings, Part 1 of 4 ML22140A0592022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML22140A0702022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML22140A0662022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features (Redacted) ML22140A0602022-04-28028 April 2022 1 to Updated Final Safety Analysis Report, List of Effective Pages ML20133J9402020-04-29029 April 2020 Updated Final Safety Analysis Report, Revision 20, STP Controlled Drawing List ML20133J9332020-04-29029 April 2020 Submittal of Updated Final Safety Analysis Report, Revision 20 ML20133J9392020-04-29029 April 2020 Updated Final Safety Analysis Report, Revision 20, List of Effective Pages ML20133J9432020-04-29029 April 2020 Updated Final Safety Analysis Report, Revision 20, STP Controlled Drawing. (Part 3 of 4) ML20133J9382020-04-29029 April 2020 Updated Final Safety Analysis Report, Revision 20. (Part 5 of 5, Response to NRC Questions) ML20133J9422020-04-29029 April 2020 Updated Final Safety Analysis Report, Revision 20, STP Controlled Drawing. (Part 2 of 4) (Redacted) ML20133J9442020-04-29029 April 2020 Updated Final Safety Analysis Report, Revision 20, STP Controlled Drawing. (Part 4 of 4) (Redacted) ML20133J9412020-04-29029 April 2020 Updated Final Safety Analysis Report, Revision 20, STP Controlled Drawing. (Part 1 of 4) ML18130A0342018-04-30030 April 2018 Project, Units 1 and 2, Submittal of Updated Final Safety Analysis Report, Revision 19 ML18130A0472018-04-30030 April 2018 Project, Units 1 and 2, Updated Final Safety Analysis Report, Revision 19, Controlled Drawing, Part 2 NOC-AE-18003568, Updated Final Safety Analysis Report, Revision 19, Controlled Drawing, Part 42018-04-30030 April 2018 Updated Final Safety Analysis Report, Revision 19, Controlled Drawing, Part 4 ML18130A0482018-04-30030 April 2018 Project, Units 1 and 2, Updated Final Safety Analysis Report, Revision 19, Controlled Drawing, Part 3 ML18130A0452018-04-30030 April 2018 Project, Units 1 and 2, Updated Final Safety Analysis Report, Revision 19, Controlled Drawing Manual Cross-Reference ML18130A0462018-04-30030 April 2018 Project, Units 1 and 2, Updated Final Safety Analysis Report, Revision 19, Controlled Drawing, Part 1 ML16207A6652016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 3.6.2, Figure 3.6.2-1 to Figure 3.6.2-8 ML16207A6392016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 15.B, Figure 15.B-2 to 15.B-3 ML16207A6242016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 11.4, Figure 11.4-1 to 11.4-3 ML16207A6472016-04-28028 April 2016 Revision 18 to Updated Safety Analysis Report, Section 2.1, Figure 2.1-1 Through Figure 2.1-13 ML16207A6182016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 10.3, Figure 10.3-1 to Figure 10.3-5 ML16207A6302016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 15.0-1, Figure 15.0-1A to 15.0-31 ML16207A6892016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 7.3, Figure 7.3-1 to Figure 7.3-29 ML16207A6332016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 15.3, Figure 15.3-1 to 15.3-20 ML16207A6492016-04-28028 April 2016 Revision 18 to Updated Safety Analysis Report, Section 2.3, Figure 2.3-1 Through Figure 2.3-18 ML16207A5612016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML16207A6902016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 7.4, Figure 7.4-1 to Figure 7.4-13 ML16207A6992016-04-28028 April 2016 Revision 18 to Updated Final Safety Analysis Report, Section 8.3, Figure 8.3-1 to Figure 8.3-14 2022-04-28
[Table view] |
Text
TREAT AS INFORMATION
Nuclear Operating Company 4N W mw _____1" Soath 7s Nqed EkrlcftE an- SngtaStio PO. &289 WidmdA, Trn 7483)
May 9, 2005 NOC-AE-05001884 STI: 31881185 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Proposed Change to the Wording of UFSAR Section 13.7
References:
- 1. Letter, J. A. Zwolinski to W. T. Cottle, "South Texas Project Units I and 2 -
Safety Evaluation on Exemption Requests from Special Treatment Requirements of 10 CFR Parts 21, 50, and 100 (TAC Nos. MA6057 and MA6058)," dated August 3, 2001
- 2. 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors: Final Rule," dated November 22, 2004 As the industry's prototype pilot for the 10 CFR 50.69 rule-making effort, STP Nuclear Operating Company (STPNOC) is proposing a change to Updated Final Safety Analysis Report (UFSAR) Section 13.7.4.2 concerning the periodicity of the feedback and corrective action activities. STPNOC considers that the proposed change could be viewed as a decrease in effectiveness of the evaluation and assessment process per UFSAR Section 13.7.5.2.c.
Therefore, STPNOC is seeking prior NRC review and approval of the proposed change per UFSAR Section 13.7.5.2.e.
Based on differences in the feedback assessment periodicities as approved by the NRC between the STP approach (Reference 1) and the industry approach (Reference 2), STPNOC requests a change in the feedback periodicity in UFSAR Section 13.7.4.2 to "at least once every two refueling outages." The justifying basis supporting the proposed change and a markup of the proposed change are provided in the enclosed attachments.
NOC-AE-05001884 Page 2 of 3 STPNOC considers the proposed change to be technically justified and consistent with a risk-informed, performance-based approach to implement the approved Exemption from certain special treatment requirements. However, since the proposed change could be viewed as a decrease in the effectiveness of the evaluation and assessment process per STP UFSAR Section 13.7.5.2.c, prior NRC review and approval is requested. STPNOC requests approval of the proposed UFSAR change by July 29, 2005.
There are no commitments in this letter.
If there are any questions regarding this request, please contact Scott. Head at (361) 972-7136 or me at (361) 972-7849.
E. D. Halpin Vice President, Oversight ges Attachments:
- 1. Description of Change and Supporting Basis
- 2. Annotated UFSAR Page
NOC.AE-05001884 Page 3 of 3 cc:
(paper copy) (electronic copy)
Bruce S. Mallett A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 David H. Jaffe Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission C. M. Canady Jack A. Fusco City of Austin Michael A. Reed Electric Utility Department Texas Genco, LP 721 Barton Springs Road Austin, TX 78704 C. A. Johnson AEP Texas Central Company Richard A. Ratliff C. Kirksey Bureau of Radiation Control City of Austin Texas Department of State Health Services 1100 West 49th Street Jon C. Wood Austin, TX 78756-3189 Cox Smith Matthews Jeffrey Cruz J. J. Nesrsta U. S. Nuclear Regulatory Commission R. K. Temple P. O. Box 289, Mail Code: MN116 E. Alarcon Wadsworth, TX 77483 City Public Service
NOC-AE-05001884 Attachment 1 Description of Change and Supporting Basis
NOC-AE-05001884 Attachment 1 Description of Change and Supporting Basis
1.0 Background
The South Texas Project (STP) was granted an exemption from certain special treatment requirements of 10 CFR Parts 21, 50, and 100 as stated in Reference 1. The scope of the exemption and the associated commitments are contained in STP UFSAR Section 13.7.
This section also provides allowances for making changes to UFSAR Section 13.7 with and without prior NRC review and approval. In addition, NRC recently approved 10 CFR 50.69 (Reference 2) which largely mirrors the STP exemption allowances; however, in certain instances, 10 CFR 50.69 permits broader allowances than the approved STP exemption.
In an effort to maintain consistency in the implementation approach with industry's 10 CFR 50.69 activities, STP Nuclear Operating Company (STPNOC) proposes a change to the wording of UFSAR Section 13.7.4.2 to be more consistent with the NRC approved wording of 10 CFR 50.69(e)(1) which states:
The licensee shall review changes to the plant, operational practices, applicable plant and industry operational experience, and as appropriate, update the PRA and SSC categorization and treatment processes. The licensee shall perform this review in a timely manner but no longer than once every two refueling outages.
2.0 References
- 1. Letter, J. A. Zwolinski to W. T. Cottle, "South Texas Project Units 1 and 2 -
Safety Evaluation on Exemption Requests from Special Treatment Requirements of 10 CFR Parts 21, 50, and 100 (TAC Nos. MA6057 and MA6058)," dated August 3, 2001
- 2. 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors:
Final Rule," dated November 22, 2004
NOC-AE-05001884 Attachment 1 Page 2 of 3 3.0 Description of Change The current wording in STP UFSAR Section 13.7.4.2 which is comparable to the 10 CFR 50.69(e)(1) wording states the following:
STP has feedback and corrective action processes to ensure that equipment performance changes are evaluated for impact on the component risk categorization, the application of special treatment, and other corrective actions.
At least once per cycle, performance data is compiled for review, which is performed for each system that has been categorized in accordance with Section 13.7.2. Performance and reliability data are generally obtained from sources such as the Maintenance Rule Program and Operating Experience Review.
STPNOC requests a change in the feedback periodicity in UFSAR Section 13.7.4.2 to 'at least once every two refueling outages' rather than the current 'at least once per cycle'.
The justifying basis supporting this proposed change is provided below. A markup of the proposed change is provided in Attachment 2.
4.0 Basis Supporting the Requested Change STPNOC considers the proposed change to be technically justified and consistent with a risk-informed, performance-based approach to implement the approved exemption from certain special treatment requirements for the following reasons:
- 1. The NRC has already approved a feedback assessment review period of 'no longer than once every two refueling outages', per 10 CFR 50.69(e)(1), for all industry users that voluntarily adopt 10 CFR 50.69. The proposed change would add consistency between the approved STP approach and 10 CFR 50.69.
- 2. STPNOC has a robust categorization and feedback process that has been extensively reviewed by the NRC. The proposed change would not alter the categorization or feedback methodology; rather, the change is procedural in nature, and would only alter the frequency of the formal reviews.
- 3. The STP periodic review process (feedback process) is proceduralized to ensure consistency in review methodology from one review period to another. This demonstrated process will be unaffected by the proposed change.
- 4. The STP PRA Model updates occur on a once-per-36 month basis. The proposed change to the periodic review frequency would better align the performance review periodicity with the scheduled PRA Model updates.
NOC-AE-05001884 Attachment 1 Page 3 of 3
- 5. There is nothing stated in UFSAR Section 13.7 or in the NRC Safety Evaluation Report for the exemption that assigns any particular importance to the 'at least once per cycle' feedback assessment frequency or that would be inconsistent with extending this period to "at least once every two refueling outages."
- 6. STPNOC has completed three periodic review cycles to date per UFSAR Section 13.7.4.2. STPNOC has noted that performance changes due to reductions in special treatment requirements (if any are noted) are not readily discemable for several cycles. The proposed change would be more reflective of a risk-informed, performance-based approach.
- 7. STPNOC continues to emphasize a real-time assessment of potential changes in component performance, system design changes, PRA updates, and operating experience insights into possible categorization and treatment changes. The experience to date demonstrates that the PRA Group, Operations, Systems Engineering, Design Engineering, and the Operating Experience Group readily provide insights into changes in component performance, design, modeling, operating experience, etc to the Working Group (same as industry's Integrated Decision-making Panel (IDP)). The proposed change would not alter the emphasized real-time assessment of these types of changes as they are noted.
- 8. The STP Working Group meets frequently which provides numerous opportunities for performance feedback to occur. The Working Group is supported by personnel representing Operations, Systems Engineering, PRA, Licensing, Maintenance, Quality, Design Engineering, Operating Experience, and Maintenance Rule.
Considering the above justifications, STPNOC requests NRC approval of the proposed change to UFSAR Section 13.7.4.2.
5.0 Conclusions STPNOC considers the proposed change to be technically justified and consistent with a risk-informed, performance-based approach to implement the approved exemption from certain special treatment requirements. However, since the proposed change could be viewed as a decrease in the effectiveness of the evaluation and assessment process per STP UFSAR Section 13.7.5.2.c, STPNOC seeks prior NRC review and approval.
STPNOC is currently scheduled to begin the next series of periodic reviews in third quarter 2005. Therefore, STPNOC requests approval of the proposed UFSAR change by July 29, 2005.
A markup of the proposed change is provided in Attachment 2.
NOC-AE-05001884 Attachment 2 Annotated UFSAR Page
STPEGS UFSAR Procedures provide for the qualification, training, and certification of personnel. STPNOC considers vendor recommendations in the training, qualification, and certification of personnel.
STPNOC may use an alternative to these recommendations if there is a basis for continued effective training of personnel. The basis does not need to be documented.
For qualification, training, and certification of personnel, STPNOC uses standards required by the State of Texas and national consensus commercial standards used at STP consistent with STPNOC's normal commercial and industrial practices. STPNOC does not need to itemize the standards in use at STP or to perform an evaluation of all national consensus standards.
Documentation, reviews, and record retention requirements for completed work activities are governed by Station procedures.
Planned changes to, or elimination of, commitments described in the UFSAR or other licensing bases documentation that address issues identified in NRC generic communications (e.g., generic letters or bulletins), NRC orders, notices of violation, etc. related to safety-related LSS and NRS SSCs will be evaluated in accordance with an NRC-endorsed commitment change process.
13.7.3.3.8 Configuration Control Process. The Station's configuration control process is controlled through approved procedures and policies. The design control process ensures that the configuration of the Station is properly reflected in design documents and drawings.
13.7.4 Continuing Evaluations and Assessments 13.7.4.1 Performance Monitoring. STP has performance monitoring processes that include the following:
- Maintenance Rule Program - Specific performance criteria are identified at the plant, system, or train level. Regardless of their risk categorization, components that affect MSS or HSS functions will be monitored and assessed in accordance with plant, system and/or train performance criteria.
- Corrective Action Program - Condition reports document degraded equipment performance or conditions, including conditions identified as a result of operator rounds, system engineer walk-downs, and corrective maintenance activities.
- STP collects indicators from the performance of plant activities, such as corrective maintenance, installation of modifications, and conduct of testing.
13.7.4.2 Feedback and Corrective Action. STP has feedback and corrective action processes to ensure that equipment performance changes are evaluated for impact on the component risk categorization, the application of special treatment, and other corrective actions.
At least once per eyele every two refueling outages, performance data is compiled for review, which is performed for each 13.7-13 Revision 12