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Category:Letter
MONTHYEARIR 05000400/20240112024-09-10010 September 2024 NRC Inspection Report 05000400/2024011 IR 05000400/20240052024-08-26026 August 2024 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400-2024005) Rev 1 ML24059A4252024-08-14014 August 2024 Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications ML24213A0522024-08-0202 August 2024 Issuance of Amendment No. 201 to Extend Completion Time of Inoperable Reactor Coolant System Accumulator Using Consolidated Line Item Improvement Process ML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000400/20240022024-07-29029 July 2024 – Integrated Inspection Report 05000400/2024002 ML24170A7312024-07-29029 July 2024 – Exemption from the Requirements of 10 CFR 50.55a(H)(2) Using the Risk-Informed Process for Evaluations Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000400/20243022024-06-27027 June 2024 – NRC Operator Licensing Examination Approval 05000400/2024302 IR 05000400/20244012024-06-25025 June 2024 – Security Baseline Inspection Report05000400/2024401 ML24162A1372024-06-24024 June 2024 – Regulatory Audit Summary Related to the Review of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2)(EPID L-2024-LLE-00040) ML24136A1382024-05-20020 May 2024 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2024011) and Request for Information (RFI) ML24116A2592024-05-14014 May 2024 Staff Evaluation Related to Aging Management Plan and Inspection Plan for Reactor Vessel Internals ML24127A1592024-05-0808 May 2024 – Notification of Licensed Operator Initial Examination 05000400/2024302 IR 05000400/20240012024-05-0505 May 2024 Integrated Inspection Report 05000400/2024001 ML24100A0912024-04-10010 April 2024 Operator License Examination Report ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) IR 05000400/20230062024-02-28028 February 2024 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2023006 ML24032A2632024-02-23023 February 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0044 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000400/20243012024-02-21021 February 2024 – NRC Operator Licensing Examination Approval 05000400/2024301 IR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition 2024-09-10
[Table view] Category:Meeting Summary
MONTHYEARML24124A0342024-05-0101 May 2024 Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris ML24011A1652024-02-12012 February 2024 December 11, 2023, Summary of Meeting with Duke Energy to Discuss a Shearon Harris Nuclear Power Plant, Unit 1 Planned Exemption Request Related to Turbine Control System and Reactor Protection System Circuitry ML23157A3202023-06-26026 June 2023 Summary of April 26, 2023, Meeting with Duke Energy to Discuss a Shearon Harris Nuclear Power Plant, Unit 1 Planned License Amendment Request Related to Turbine Control System and Reactor Protection System Circuitry ML23151A1232023-05-31031 May 2023 Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Shearon Harris Nuclear Plant ML22167A1852022-06-30030 June 2022 Summary of June 6, 2022, Meeting with Duke Energy to Discuss Shearon Harris Nuclear Power Plant, Unit 1 Closeout of Generic Safety Issue (GSI) 191 ML22129A0062022-05-10010 May 2022 Summary of April 20, 2022, Meeting with Duke Energy Progress, LLC, to Discuss Proposed License Amendment Request to Revise Reactor Coolant System Pressure Isolation Valve Operational Leakage Surveillance Requirement Frequency (L-2022-LRM 00 ML22130A0302022-05-0909 May 2022 Summary of Public Meeting on 2021 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20220350 ML21341A5542021-12-29029 December 2021 Summary of November 29, 2021, Meeting with Duke Energy Progress, LLC and Duke Energy Carolinas, LLC to Discuss a Planned License Amendment Request to Relocate ML21172A2672021-08-13013 August 2021 Regulatory Audit Summary Related to the Review of LAR to Revise 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative Seis ML21131A1472021-05-11011 May 2021 Public Meeting Summary 2020 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20210385 ML20136A2222020-05-15015 May 2020 Har - Bru 2019 Aam Meeting Summary ML19331A8062020-01-29029 January 2020 Summary of November 13, 2019 Closed Meeting with Duke Energy Carolinas, LLC and Duke Energy Progress, LLC, to Discuss Security-Related Information for Its Licensed Facilities ML19329A0232019-11-27027 November 2019 Summary of October 29, 2019 Conference Call with Duke Energy Progress, LLC Regarding the Fall 2019 Steam Generator Tube Inspections ML19241A2902019-09-24024 September 2019 Summary of August 22, 2019, Meeting with Duke Energy Progress, LLC Proposed License Amendment Request to Adopt Risk-Informed Completion Times ML19220A6702019-08-26026 August 2019 Summary of August 7, 2019, Meeting with Duke Energy Progress, LLC and Duke Energy Carolinas, LLC to Discuss a Proposed License Amendment Request for a Common Emergency Plan ML19113A0652019-05-14014 May 2019 Summary of Meeting with Duke Energy to Discuss Proposed License Amendment Request for Shearon Harris, Unit 1, Technical Specification Changes Associated with Departure from Nucleate Boiling Ratio Safety Limit ML19120A1342019-05-0606 May 2019 3/15/19 Summary of Public Meeting with Nuclear Entergy Institute, Duke Energy, and Southern Nuclear Operating Company Post-Pilot Implementation of Tornado Missile Risk Evaluator Methodology at Vogtle, Units 1 and 2 and Shearon Harris, Unit ML19123A3522019-05-0202 May 2019 Public Meeting Summary - Shearon Harris Nuclear Plant, Docket No. 50-400 ML19087A0622019-04-11011 April 2019 Summary of March 25, 2019, Public Teleconference with Duke Energy to Discuss the Request for Additional Information Response Regarding the Proposed Alternative to the Depth Sizing Qualification Requirement (Duke Energy Fleet Relief Request ML18352A3572019-01-0808 January 2019 Summary of Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Request for Shearon Harris Nuclear Power Plant, Unit 1, Regarding Emergency Plan Changes ML18361A6712019-01-0808 January 2019 Summary of Meeting with Duke Energy Progress, LLC to Discuss License Amendment Request for Shearon Harris Unit 1, Regarding 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, ML18355A8142019-01-0707 January 2019 Summary of December 20, 2018, Teleconference Meeting with Duke Energy Progress, LLC to Discuss a Proposed License Amendment Request for Shearon Harris Unit 1, Regarding a Risk-Informed Essential Services Chilled Water System TS ML18094A2632018-08-17017 August 2018 Summary of 01/18/2018, Public Meeting with Nuclear Energy Institute, Duke Energy, Southern Nuclear Operating Co., Entergy Operations, Inc. to Discuss Development of Tornado Missile Risk Evaluator Methodology ML18109A0912018-04-19019 April 2018 Summary of 2017 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant, Docket No. 50-400 ML18088A0732018-04-0303 April 2018 March 27, 2018, Summary of Presubmittal Meeting with Duke Energy Progress, LLC to Discuss a Proposed Relief Request for Shearon Harris Nuclear Power Plant, Unit 1 ML18064A1332018-03-19019 March 2018 Summary of February 27, 2018, Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Request for Shearon Harris Nuclear Power Plant, Unit 1, Regarding Emergency Plan Emergency Action Level Scheme Changes (L-2017-LRM-00 ML17340A1302017-12-22022 December 2017 Summary of November 29, 2017, Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Requests to Implement the Requirement of 10 CFR 50.69 at Brunswick, Shearon Harris, and H. B. Robinson ML17340A0612017-12-0808 December 2017 11/8/17 Summary of Teleconference with Entergy Operations, Inc., Tornado Missile Risk Evaluator with Applicability to Submittals from Duke Energy and Southern Nuclear Operating Co, Inc. ML17244A0742017-09-28028 September 2017 8/17/2017 Summary of Public Meeting with Nuclear Energy Institute and Licensees to Discuss the Tornado Missile Risk Evaluation Tool for Grand Gulf, Shearon Harris, and Vogtle, Units 1 and 2 ML17257A0992017-09-26026 September 2017 Summary of Public Meeting with Nuclear Energy Institute and Licensees to Discuss the Tornado Missile Risk Evaluation Tool for Grand Gulf, Shearon Harris, and Vogtle, Units 1 and 2 ML17223A1212017-08-17017 August 2017 Summary of August 3, 2017, Meeting with Duke Energy Progress, LLC on Proposed License Amendment Request to Implement Fuel Reload Design Methodology Reports for Shearon Harris and H. B. Robinson ML17145A3142017-05-25025 May 2017 EOC Meeting Summary ML16286A0152016-11-0101 November 2016 Summary Of September 29, 2016, Duke Energy Progress, LLC. To Discuss Proposed License Amendment Request Regarding Shearon Harris Nuclear Power Plant, Unit 1, BWR Storage Rack Inserts And The Spent Fuel Pool Criticality Analysis (CAC No. MF8327) ML16235A2382016-10-17017 October 2016 Summary of the July 12-13, 2016 Audit Supporting the U.S. Nuclear Regulatory Commission Review of DPC-NE-1008-P, Nuclear Design Methodology Using CASMO-5/SIMULATE-3 for Westinghouse Reactors ML16125A0992016-05-20020 May 2016 Summary of May 2, 2016, Meeting with Duke Energy Progress, Inc. to Discuss Fuel Reload Design Methodology Reports and Proposed Supplement to a License Amendment Request Regarding Shearon Harris and H.B. Robinson ML16134A1552016-05-12012 May 2016 Public Meeting Summary - 2015 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant ML16112A3772016-04-25025 April 2016 Summary of Meeting with Duke Energy Progress, Inc. to Discuss the Shearon Harris Nuclear Plant, Unit 1, TSTF-425 LAR Request for Additional Information Reponses ML16034A5242016-03-11011 March 2016 Summary of February 1, 2016, Pre-submittal Meeting with Duke Energy Regarding Consolidation of Emergency Operations Facilities ML16035A4802016-02-12012 February 2016 Jsc Meeting Summary Attachment ML15280A2532015-11-25025 November 2015 Summary of Mtg. with Duke Energy Progress Inc. to Discuss Fuel Reload Design Methodology Reports & Proposed License Amendment Request Shearon Harris Nuclear Power Plant Unit 1 and H.B. Robinson Steam Electric Plant Unit No. 2 (MF6701/MF6702 ML15202A4752015-09-24024 September 2015 Summary of Meeting with Duke Energy Progress, Inc. to Discuss Shearon Harris Nuclear Power Plant, Unit 1, Proposed License Amendment Request Regarding Technical Specifications for the Pressurizer and Main Steam Line Safety Valves (MF6233) ML14129A3352014-05-0909 May 2014 Summary of Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear Plant ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13204A2672013-09-27027 September 2013 07/09/13 Summary of Meeting with Duke Energy Regarding a Nonconservative Technical Specification Loss of Offsite Power Voltage Setpoint License Amendment Request ML13218B3692013-09-27027 September 2013 7/30/2013 - Summary of Meeting with Duke Energy Regarding a Change to the Emergency Response Facility Activation Timeliness and Criteria ML13225A2932013-08-12012 August 2013 7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop ML13171A3292013-06-20020 June 2013 Public Meeting Summary, Category 3, NRC Special Inspection on Reactor Vessel Head Nozzle Repair of Shearon Harris Nuclear Plant ML13155A1052013-06-12012 June 2013 May 2, 2013, Summary of Meeting with Duke Energy Concerning the Relocation of the Emergency Operating Facilities ML13151A2262013-05-30030 May 2013 Meeting Summary - Category 1 Public Meeting Annual Assessment - Shearon Harris Nuclear Plant - Docket 50-400 ML12277A0252012-11-0202 November 2012 10/2/12 Summary of Meeting with Duke Energy Carolinas to Discuss Nonconservative Technical Specifications License Amendment Requests 2024-05-01
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OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET Date Printed: Nov 13, 2008 08:00 PAPER NUMBER: ACTION OFFICE: AUTHOR: AFFILIATION:
ADDRESSEE:
SUBJECT:
LTR-08-0587 LOGGING DATE: 11/12/2008 EDO William Shack DEDMRT ACRS DEDR DEDCM Dale Klein AO Summary Report-55th meeting of the ACRS, October 2-3, 2008, and other related activities of the Committee ACTION: DISTRIBUTION:
LETTER DATE: ACKNOWLEDGED SPECIAL HANDLING: NOTES: FILE LOCATION: Appropriate RF 11/12/2008 No ADAMS DATE DUE: DATE SIGNED:~UC4 ~O V7 e-bS,4 secy-ot' UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 -0001 November 5, 2008 The Honorable Dale E. Klein Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
SUBJECT:
SUMMARY
REPORT -556th MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, OCTOBER 2-3, 2008, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE
Dear Chairman Klein:
During its 556th meeting, October 2-3, 2008, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports, letters, and memoranda:
REPORTS Reports to Dale E. Klein, Chairman, NRC, from William J. Shack, Chairman, ACRS:* Report on the Safety Aspects of the License Renewal Application for the Shearon Harris Nuclear Power Plant, Unit 1, dated October 16, 2008 Status of Resolution of Generic Safety Issue-191, "Assessment of Debris Accumulation on PWR Sump Performance," dated October 22, 2008 LETTERS Letter to R. W. Borchardt, Executive Director for Operations, NRC, from William J. Shack, Chairman, ACRS: Interim Letter 5: Chapters 19 and 22 of the NRC Staffs Safety Evaluation Report with Open Items Related to the Certification of the ESBWR Design, dated October 29, 2008 Letter to Dr. Brian Sheron, Director, Office of Nuclear Regulatory Research, NRC, from William J. Shack, Chairman, ACRS: ACRS Assessment of the Quality of Selected NRC Research Projects -FY 2008, dated October 22, 2008 MEMORANDA Memoranda to R. W. Borchardt, Executive Director for Operations, NRC, from Edwin M. Hackett, Executive Director, ACRS: Proposed Interim Staff Guidances COL/ESP-ISG-004 and DC/COL-ISG-07, dated October 8, 2008 Draft Final Revision to Regulatory Guides 1.114 and 3.11, dated October 8, 2008 Withdrawal of Regulatory Guide 6.8, "Identification Plaque For Irretrievable Well-Logging Sources," dated October 8, 2008 HIGHLIGHTS OF KEY ISSUES 1. License Renewal Application for the Shearon Harris Nuclear Power Plant, Unit 1 The Committee met with representatives of the Carolina Power & Light Company (CP&L) (the applicant) and the NRC staff to discuss the license renewal application (LRA) for the Shearon Harris Nuclear Power Plant (HNP), Unit 1, and the associated NRC staff's final Safety Evaluation Report (SER). The operating license for HNP, Unit 1 expires on October 24, 2026. The applicant has requested approval for continued operation for a period of 20 years beyond the current license expiration date.In the final SER, the staff documented its review of the license renewal application and other information submitted by CP&L and obtained during the audits and an inspection conducted at the plant site. The staff reviewed the completeness of the applicant's identification of structures, systems, and components (SSCs) that are within the scope of license renewal; the integrated plant assessment process; the applicant's identification of the plausible aging mechanisms associated with passive, long-lived components; the adequacy of the applicant's aging management programs; and the identification and assessment of time-limited aging analyses requiring review.The applicant addressed the open item, which is related to the scoping classification of feedwater regulating valves and bypass valves. HNP included these valves in the LRA within the scope of license renewal per the criteria of 10 CFR 54.4(a) (2), because it's believed that these valves are nonsafety-related components.
However, the staff initially believed that these valves perform main feedwater isolation function under certain postulated transients and fulfill a safety-related function; therefore, these valves should be included within the scope under 10 CFR 54.4(a) (1). The applicant pointed out a past NRC precedence which allowed credit be taken for the backup nonsafety-related components to mitigate the consequences of a main steamline break inside containment.
The staff agreed with the applicant's assessment and determined that the feedwater regulating and bypass valves are properly categorized as nonsafety-related components, and that the requirements of 10 CFR 54.4(a) (2) apply to these Valves. The applicant also discussed electrical manholes issue. The applicant described the cable design, manhole inspection program, historical operating experience, and corrective actions.The staff described its review of the applicant's scoping, screening, aging management programs, time-limited aging analyses, and the resolution of the open item, described above.The staff concluded that the requirement of 10 CFR 54.29(a) has been met. Committee Action The Committee issued a report to the NRC Chairman on this matter, dated October 16, 2008.The Committee concluded that the programs established and committed to by the applicant to manage age-related degradation provide reasonable assurance that the HNP, Unit 1 can be operated in accordance with the current licensing basis for the period of extended operation without undue risk to the health and safety of the public. The Committee recommended that the CP&L application for renewal of the operating license for HNP, Unit 1 be approved.
In addition, the Committee recommended that prior to entering the period of extended operation, the staff inspect the applicant's programs for managing water intrusion into underground cable vaults and cable insulation testing.2. Status of Resolution of Generic Safety Issue -191 The Committee met with representatives of the NRC staff to discuss the status of resolution of Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on PWR Sump Performance." The Committee noted that significant progress has been made towards resolving GSI-191. All PWR licensees have installed significantly larger sump screens and some have undertaken further actions, such as changing fibrous insulation and chemical buffer. The staff described progress made toward resolving GSI 191, including the response of licensees to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized Water Reactors." The presentation focused on sump strainer head loss testing, chemical effects, and in-vessel sump strainer downstream effects. The staff indicated that testing of the new strainer design has been performed by nearly all licensees and that the initial review of the industry submittals by the staff is nearing completion.
The staff provided an overview of the testing that has been performed and the results obtained.Committee Action The Committee issued a report to the NRC Chairman on this matter, dated October 22, 2008, stating that significant progress has been made towards resolving GSI-1 91. The Committee recommended, to ensure the prototypicality of tests for extrapolation to plant conditions, further guidance be developed for the test cases in which a significant portion of the debris is allowed to settle out upstream of the screens. Also, the staff should develop guidance with regard to the conditions and protocols for the PWR Owners Group tests to facilitate closure of issues related to in-vessel downstream effects.3. Selected Chapters of the SER Associated with the ESBWR Desiqn Certification Application The Committee met with representatives of the NRC staff and General Electric -Hitachi Nuclear Energy (GEH) todiscuss Chapters 19 and 22 of the NRC Staff's SER with Open Items associated with the Economic Simplified Boiling Water Reactor (ESBWR) Design Certification Application. GEH discussed the objectives of the Design Certification Probabilistic Risk Assessment (PRA), and stated that 386 of 450 requests for additional information on this topic have been resolved.GEH intends to issue Revision 4 of the PRA in December 2008. GEH described the nature and approach of the risk analysis calculations, discussed the results and their implications for the ESBWR risk profile, and noted that the PRA was a major influence on the ESBWR design.They also discussed the criteria used to classify structures, systems, and components (SSCs)as part of the "regulatory treatment of non-safety systems" (RTNSS) program. A high relative risk importance is one of several criteria which can add SSCs to this list.NRC staff stated that its review of these Chapters covered overall PRA quality as well as the seismic margins analysis, high winds analysis, non-power operational modes, severe accident management, and severe accident mitigation.
The staff discussed a number of open items which need to be resolved and also summarized its review of RTNSS. The objectives of this review were to confirm that all non-safety SSCs requiring treatment are identified, to confirm that the reliability and availability missions for active systems are consistent with the risk assessment, and to confirm that the level of treatment is based on the ability to meetreliability/availability missions.Committee Action The Committee issued a letter to the Executive Director for Operations on this matter, dated October 29, 2008. The Committee recommended that a more detailed explanation of the applicant's analysis of the low failure probabilities of the passive systems and a more systematic evaluation of the relevant uncertainties be provided.
In addition, the technical basis for the failure probability of the digital instrumentation and control systems should be provided and specific issues need to be clarified to ensure the functionality of the Basemat-Internal Melt Arrest and Coolability (BiMAC) device. The Committee also stated that it is awaiting the completion of the staffs review of Revision 3 of the ESBWR PRA, and that it would review the resolution of open items in SER Chapters 19 and 22 in future meetings.4. Quality Assessment of Selected Research Proiects The Committee completed its report on the quality assessment of the research projects on: "Assessment of Predictive Bias and the Influence of Manufacturing, Model, and Power Uncertainties in NRC Fuel Performance Code Predictions," and NUREG/CR -6943, "A Study of Remote Visual Methods to Detect Cracking in Reactor Components." Committee Action The Committee issued a letter to the Director of the Office of Nuclear Regulatory Research, dated October 22, 2008, transmitting its report on the quality assessment of the research projects noted above.5. Historical Perspectives and Insiqhts on Reactor Consequence Analyses The Committee discussed the draft White Paper prepared by Dr. Nourbakhsh, ACRS Senior Technical Advisor, regarding historical perspectives and insights on reactor consequence analyses. Committee Action The Committee plans to issue a letter transmitting the White Paper to the Executive Director for Operations during its November 2008 meeting.6. Materials, Metallurgy, and Reactor Fuels Subcommittee Report The Chairman of the Materials, Metallurgy, and Reactor Fuels Subcommittee provided a report to the Committee summarizing the results of the October 1, 2008, meeting with the NRC staff to review the proposed amendment to 10 CFR 50.61: "Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events." He stated that the NRC staff provided a detailed discussion on the technical basis for the proposed supplemental rule, including treatment of uncertainties, PRA event sequence analysis, thermal hydraulic analysis, and probabilistic fracture mechanics analysis.
The Subcommittee requested additional information regarding the independent review of the FAVOR code, the studies conducted to show the general applicability of the rule to the entire fleet of PWRs, and the justification for not treating thermal hydraulic parameter uncertainties.
The staff is expected to provide additional information to the Subcommittee on these topics. The Subcommittee will review the draft final revision to 10 CFR 50.61 after reconciliation of public comments.7. Reliability and PRA Subcommittee Report The Chairman of the Reliability and Probabilistic Risk Assessment Subcommittee provided a report to the Committee summarizing the results of the September 28, 2008, meeting with the NRC staff and EPRI to discuss draft NUREG-1855, "Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decisionmaking," and the latest version of the companion EPRI report, "Treatment of Parameter and Model Uncertainty for Probabilistic Risk Assessments." The draft NUREG-1 855 is intended to provide the needed guidance recommended by the ACRS. EPRI, in parallel with the NRC, has been developing guidance documents on the treatment of uncertainties.
This work is meant to complement the guidance included in NUREG-1855. Where possible the NUREG-1 855 refers to the EPRI work for acceptable treatment of uncertainties.
The staff plans to complete the NUREG report by the end of the calendar year and then hold a public workshop.OTHER RELATED ACTIVITIES OF THE COMMITTEE During the period from September 8, 2008, through October 1, 2008, the following Subcommittee meetings were held:* Thermal Hydraulic Phenomena
-September 23, 2008 The Subcommittee discussed the status of resolution of GSI-191 and heard presentations from the staff, the PWR Owners Group, and the Union of Concerned Scientists, in this regard.
-September 30, 2008 The Subcommittee-discussed NUREG-1 855 and EPRI-1016737 documents, and heard presentations from the staff and the EPRI, in this regard.* Materials, Metallurqy, and Reactor Fuels -October 1, 2008 The Subcommittee reviewed the technical basis for the amendment to 10 CFR 50.61: "Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events."* Planning and Procedures
-October 1, 2008 The Subcommittee discussed prop5osed ACRS activities, practices, and procedures for conducting Committee business and organizational and personnel matters relating to ACRS and its staff.LIST OF MATTERS FOR THE ATTENTION OF THE EDO* The Committee will review the draft final revision to 10 CFR 50.61, after reconciliation of public comments.
Additional information was requested on the independent review of the FAVOR code, the studies conducted to show the general applicability of the rule to the entire fleet of PWRs, and the justification for not treating thermal hydraulic parameter uncertainties.
The Committee would like to have an opportunity to review the final versions of Interim Staff Guidances COL/ESP-ISG-004 and DC/COL-ISG-07, after reconciliation of public comments.The Committee plans to review draft NUREG-1 855, "Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decisionmaking," during a future meeting.The Committee plans to review the resolution of open items in SER Chapters 19 and 22 associated with the ESBWR design certification application.
PROPOSED SCHEDULE FOR THE 5 5 7 th ACRS MEETING The Committee agreed to consider the following topics during the 5 5 7 th ACRS meeting, to be held during November 6-8, 2008: " Chapter 14 of the SER Associated with the ESBWR Design Certification Application
- Position Paper on Incorporating the International Commission on Radiological Protection (ICRP) Recommendations into 10 CFR Parts 20 and 50 0 Status of License Renewal Activities
- Current Issues Associated with Fire Protection and Related Matters* Proposed Changes to. the Review Process for Subsequent Combined License Applications (SCOLAs)In addition, the Committee will meet with the Commission on November 7, 2008, to discuss several items of mutual interest, including BWR Power Uprate Issues, PWR Sump Performance Issues, and TRACE Code Development.
Sincerely, IRA/William J. Shack Chairman