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Category:Inspection Report
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 IR 05000335/20234202023-03-21021 March 2023 Security Baseline Inspection Report 05000335/2023420 and 05000389/2023420 IR 05000335/20220062023-03-0101 March 2023 Annual Assessment Letter for St. Lucie Units 1 & 2 (Report 05000335/2022006 and 05000389/2022006) IR 05000335/20220042023-02-10010 February 2023 Integrated Inspection Report 05000335/2022004 and 05000389/2022004 IR 05000335/20220112022-12-27027 December 2022 Triennial Fire Protection Inspection Report 05000335/2022011 and 05000389/2022011 IR 05000335/20220032022-11-0404 November 2022 Integrated Inspection Report 05000335/2022003 and 05000389/2022003 ML22208A1762022-08-0404 August 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report IR 05000335/20220022022-08-0101 August 2022 Integrated Inspection Report 05000335/2022002 and 05000389/2022002 ML22210A0782022-07-22022 July 2022 Stl 2022003 Document Request IR 05000335/20220122022-06-29029 June 2022 Biennial Problem Identification and Resolution Inspection Report 05000335 2022012 and 05000389 2022012 IR 05000335/20224012022-05-20020 May 2022 Security Baseline Inspection Report 05000335/2022401 and 05000389/2022401 IR 05000335/20220012022-05-12012 May 2022 Integrated Inspection Report 05000335/2022001 and 05000389/2022001 IR 05000335/20220102022-04-27027 April 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000335/2022010 and 05000389/2022010 IR 05000335/20214022022-04-0404 April 2022 Material Control and Accounting Program Inspection Report 05000335/2021402 and 05000389/2021402 - Public IR 05000335/20210062022-03-0202 March 2022 Annual Assessment Letter for St. Lucie, Units 1 & 2 (Report No. 05000335/2021006 and 05000389/2021006) IR 05000335/20210042022-02-14014 February 2022 Integrated Inspection Report 05000335/2021004 and 05000389/2021004 IR 05000335/20214032021-12-14014 December 2021 Security Baseline Inspection Report 05000335/2021403 and 05000389/2021403 IR 05000335/20210102021-12-0707 December 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000335/2021010 and 05000389/2021010 IR 05000335/20210032021-11-0303 November 2021 Integrated Inspection Report 05000335/2021003 and 05000389/2021003 IR 05000335/20210052021-08-25025 August 2021 Updated Inspection Plan for St. Lucie Plant Units 1 & 2 (Report 05000335/2021005 and 05000389/2021005) IR 05000335/20210022021-08-10010 August 2021 Integrated Inspection Report 05000335/2021002 and 05000389/2021002 IR 05000335/20214012021-06-23023 June 2021 Security Baseline Inspection Report 05000335/2021401 and 05000389/2021401 IR 05000335/20213012021-06-21021 June 2021 NRC Examination Report 05000335/2021301 and 05000389/2021301 IR 05000335/20210012021-05-12012 May 2021 Integrated Inspection Report 05000335/2021001 and 05000389/2021001 IR 05000335/20200062021-03-0303 March 2021 Annual Assessment Letter for St. Lucie Nuclear Plant, Unit 1 and Unit 2 Report 05000335/2020006 and 05000389/2020006 IR 05000335/20203012021-02-16016 February 2021 NRC Operator License Examination Report 05000335/2020301 and 05000389/2020301 IR 05000335/20200042021-02-0808 February 2021 Integrated Inspection Report 05000335/2020004 and 05000389/2020004 and Independent Spent Fuel Storage Installation (ISFSI) Inspection 07200061/2020002 IR 05000335/20204012021-01-0505 January 2021 Security Baseline Inspection Report 05000335/2020401 and 05000389/2020401 IR 05000335/20200112020-12-16016 December 2020 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000335/2020011 and 05000389/2020011 IR 05000335/20200032020-10-30030 October 2020 Integrated Inspection Report 05000335/2020003 and 05000389/2020003 ML20296A3732020-10-22022 October 2020 Security Inspection Report IR 05000335/20200052020-08-24024 August 2020 Updated Inspection Plan for St. Lucie Plant, Unit 1 and 2 (Report 05000335/2020005 and 05000389/2020005) IR 05000335/20200022020-07-29029 July 2020 St.Lucie Units 1 & 2 Integrated Inspection Report 05000335/2020002, 05000389/2020002, and Independent Spent Fuel Storage Installation Inspection (Lsfsi) 07200061/2020001 IR 05000335/20200102020-07-16016 July 2020 Biennial Problem Identification and Resolution Inspection Report 05000335/2020010 and 05000389/2020010 IR 05000335/20200012020-05-0505 May 2020 Integrated Inspection Report 05000335/2020001 and 05000389/2020001 and Exercise of Enforcement Discretion IR 05000335/20190062020-03-0303 March 2020 Annual Assessment Letter for St. Lucie Nuclear Plant, Units 1 and 2 NRC Report 05000335/2019006 and 05000389/2019006 IR 05000335/20190032019-11-14014 November 2019 Integrated Inspection Report 05000335/2019003 and 05000389/2019003 IR 05000335/20193022019-10-18018 October 2019 NRC Examination Report 05000335/2019302 and 05000389/2019302 IR 05000335/20194112019-10-0707 October 2019 NRC Security Inspection Report 05000335/2019411 and 05000389/2019411 IR 05000335/20194012019-09-0909 September 2019 Cyber Security Inspection Report 05000335/2019401 and 05000389/2019401 (Public) IR 05000335/20190052019-08-27027 August 2019 Updated Inspection Plan for St. Lucie Plant, Unit 1 and Unit 2 - (Report 05000335/2019005 and 05000389/2019005) IR 05000335/20190112019-08-20020 August 2019 Triennial Fire Protection Inspection Report 05000335/2019011 and 05000389/2019011 2024-01-26
[Table view] Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 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 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ril 12, 2017
SUBJECT:
ST. LUCIE PLANT UNIT 2 - U.S. NUCLEAR REGULATORY COMMISSION POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000389/2017008
Dear Mr. Nazar:
On March 3, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval Site Inspection for License Renewal at your St. Lucie Plant, Unit 2, in accordance with NRC Inspection Procedure 71003. On March 3, 2017, the NRC inspector discussed the results of this inspection with Mr. Dan Deboer, Plant Saint Lucie Site Director, and other members of your staff. Inspector documented the results of this inspection in the enclosed inspection report (IR).
The NRC inspector did not identify any findings or violations of more than minor significance.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public inspections, exemptions, requests for withholding of the NRC's "Agency Rules of Practice and Procedure," a copy of this letter, its Enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room, or from the Publically Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS); accessible from the NRC Web site at http://www.nrc.gov/
reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Binoy B. Desai, Acting Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-389 License No. NPF-16
Enclosures:
NRC Post-Approval Site Inspection For License Renewal, IR 05000389/2017008 w/Attachment: Supplementary Information
REGION II==
Docket No: 05000389 License No: NPF-16 Report No: 05000389/2017008 Licensee: Florida Power & Light Company Facility: St. Lucie Plant, Unit 2 Location: 6501 S. Ocean Drive Jensen Beach, FL 34957 Dates: February 27 - March 3, 2017 Inspector: Robert Carrion, Senior Reactor Inspector Approved by: Binoy B. Desai, Acting Chief Engineering Branch 3 Division of Reactor Safety Enclosure
SUMMARY
Inspection Report (IR) 05000389/2017008; February 27 - March 3, 2017; St. Lucie Plant, Unit 2;
Post-Approval Site Inspection for License Renewal, Phase 1 This report covers an inspection conducted by one regional inspector in accordance with NRC Inspection Manual Chapter 2515 and NRC Inspection Procedure 71003.
Based on the sample selected for review, the inspector determined that commitments, license conditions, and regulatory requirements associated with the renewed facility operating license were met. The inspector also determined that the licensee had administrative controls in place to ensure completion of pending actions scheduled both prior to and during the period of extended operation.
The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.
No findings were identified.
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Other Activities
.1 Post-Approval Site Inspection for License Renewal - Inspection Procedure 71003
(Phase 1)
a. Inspection Scope
- (1) Implementation of License Conditions and Commitments, including Aging Management Programs The inspector reviewed a sample of license renewal activities scheduled for the Unit 2 spring 2017 refueling outage. The inspector selected this refueling outage because it would present the best opportunity to observe the implementation of Aging Management Programs (AMPs) associated with license renewal commitments specific to Unit 2. The inspection objective was to maximize observations of the actual implementation of license renewal activities before the beginning of the period of extended operation (PEO)
(April 6, 2023), and to verify that the licensee completed the necessary actions to: (a)comply with the conditions stipulated in the renewed facility operating license;
- (b) meet the license renewal commitments described in NUREG-1779, Safety Evaluation Report (SER) Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2, dated September 2003 (ADAMS Accession Number ML032940205); and
- (c) meet the future inspection activities described in the Updated Final Safety Analysis Report (UFSAR)supplement submitted pursuant to 10 CFR 54.21(d). The license renewal application (LRA) for St. Lucie, Units 1 and 2, and the corresponding NRC SER, documented in NUREG-1779, is publicly available on ADAMS under Accession Numbers ML013400155 and ML032940205, respectively.
The inspector reviewed the licensing basis and program basis documents of these programs; and for select programs, implementing procedures, applicable condition reports, and work orders to verify that the selected AMPs were implemented as described in the LRA. In addition, the inspector conducted interviews with licensee staff, observed in-process outage activities, and performed visual inspection of structures, systems, and components (SSCs), including those not accessible during power operation. The commitment items and AMPs selected for the inspection sample are summarized below, based on their description in Appendix A of the LRA, and their respective UFSAR description. The specific additional inspection activities conducted for each AMP are also described below. Specific documents reviewed are listed in this reports Attachment.
Updated Final Safety Analysis Report, Section 18.1.1 - Galvanic Corrosion Susceptibility Inspection Program [NUREG-1779, Commitment No. 1]:
This commitment specified that prior to the end of the initial operating license terms for Units 1 and 2, selected one-time inspections on the surfaces of piping and components with the greatest susceptibility for galvanic corrosion, would be conducted to manage the aging effect of loss of material due to galvanic corrosion on the surfaces of susceptible piping and components. Baseline examinations (visual inspection or volumetric examinations) in select systems were performed and evaluated to establish if this corrosion mechanism was active. Evaluation of the inspection results considered the minimum required wall thickness for the component, consistent with the applicable design codes. Based on the results of these inspections, the need for followup examinations or programmatic corrective actions were established.
The inspector verified that the licensee developed procedures and conducted inspections, as described in the Program Basis Document and the UFSAR. The inspector also verified that the inspections were appropriately scheduled and tracked. In addition, the inspector directly observed the visual examination inspection of the Instrument Air System, between flanges of stainless steel flex hose and carbon steel piping (compressor 2A discharge), to verify that inspection procedures were followed, and any adverse conditions found were entered in the licensee Corrective Action Program (CAP) and evaluated properly, in accordance with the license renewal commitment.
Updated Final Safety Analysis Report, Section 18.1.4 - Small Bore Class 1 Piping Inspection Program [NUREG-1779, Commitment Nos. 5 and 6]:
These commitments specified that prior to the end of the initial operating license terms for Units 1 and 2, selected one-time volumetric inspections and destructive examinations of a sample of small bore Class 1 piping, would be performed to determine if cracking is an aging effect requiring management during the PEO. This one-time inspection addressed Class 1 piping less than 4 inches in diameter. Based on the results of these inspections, the need for additional inspections or programmatic corrective actions were established.
The inspector verified that the licensee developed procedures and conducted inspections, as described in the Program Basis Document and the UFSAR. The inspector also verified that the inspections were appropriately scheduled and tracked. In addition, the inspector performed a review of the samples that the licensee selected, and a walkdown of the areas where the five socket weld samples were taken to verify that they were performed in accordance with the license renewal commitments. The inspector also observed the ultrasonic examination (UT) of a small bore piping line (I-3-SI-191) which is part of this program.
Updated Final Safety Analysis Report, Section 18.1.5 - Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Program [NUREG-1779, Commitment No. 7]:
This commitment specified that continuing through the PEO, the licensee would perform a determination of the susceptibility of Class 1 Cast Austenitic Stainless Steel (CASS)piping components to thermal aging embrittlement and would provide for the subsequent aging management of those components that were identified as being potentially susceptible. Aging management, if required, would be accomplished through either enhanced volumetric examination or plant-specific or component-specific flaw tolerance evaluation.
The inspector verified that the licensee developed procedures and conducted inspections, as described in the Program Basis Document and the UFSAR. The inspector also verified that the inspections were appropriately scheduled and tracked. In addition, the inspector directly observed the phased array ultrasonic examination and data acquisition of a CASS (steam generator 2B1 cold leg), and interviewed the qualified examiner/analyst who performed the analysis of the element to verify that it was done in accordance with the license renewal commitment. The examination results were evaluated and dispositioned in accordance with the acceptance criteria specified in licensee procedures.
Updated Final Safety Analysis Report, Section 18.2.13 - Systems and Structures Monitoring Program [NUREG-1779, Commitment No. 16]:
This commitment specified that continuing through the PEO, the Systems and Structures Monitoring Program managed the aging effects of loss of material, cracking, fouling (for mechanical components only), loss of seal, and change in material properties. The program provided for periodic visual inspection and examination for degradation of accessible surfaces of specific SSCs and corrective actions, as required, based upon these inspections. The program was enhanced to provide guidance for managing the aging effects of inaccessible concrete, inspection of insulated equipment and piping, and evaluating masonry wall degradation and uniform corrosion.
The inspector verified that the licensee developed procedures and conducted inspections, as described in the Program Basis Document and the UFSAR. The inspector also verified that the inspections were appropriately scheduled and tracked. In addition, the inspector performed direct observations of the following systems to verify that they were inspected in accordance with the license renewal commitments:
- A walkdown of accessible components of the Unit 2 Chemical and Volume Control System (CVCS) at Elevations 18 and 23 of the Reactor Containment Building (RCB).
- (2) Review of Newly-Identified Structures, Systems, and Components This inspection requirement will be completed during the Phase 2 implementation of IP 71003.
- (3) Review of License Renewal Commitment Changes As part of the review of license renewal commitments described in Section 4OA5.1.a(1)of this report, the inspector reviewed license renewal commitment change documents to verify the licensee followed the guidance in Nuclear Energy Institute (NEI) 99-04, Guidelines for Managing NRC Commitment Changes, for any change to the commitments, including their elimination. The inspector verified that the licensee properly evaluated, reported, and approved, where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59.
The inspector also reviewed the licensees procedures for commitment revision to obtain reasonable assurance that future changes to (or elimination of) license commitments would follow the guidance in NEI 99-04, and would properly evaluate, report, and approve changes to license renewal commitments listed in the UFSAR, in accordance with 10 CFR 50.59.
During the course of the Unit 2 spring 2017 refueling outage, the licensee identified potential commitment changes to the Small Bore Class 1 Piping AMP; the details of which are documented as an observation in the Findings and Observations section below.
b. Findings and Observations
No findings were identified. Based on the review of licensee actions completed at the time of this inspection, and the timeliness of those actions, the inspector determined that the implementation of AMP activities reviewed during the Unit 2 spring 2017 refueling outage were consistent with license renewal commitments, license conditions, and applicable regulatory requirements. The inspector also determined that the licensee had administrative controls in place to ensure completion of pending actions scheduled both prior to and during the PEO.
The following observation for the Small Bore Class 1 Piping AMP was made:
- By letter dated September 3, 2014, (ADAMS accession number ML14261A107),the licensee submitted their Inspection Plan for Small Bore Class 1 Piping, in accordance with the commitments set forth in the SER. In this commitment letter, the licensee stated in Section 4, Description of Aging Effects, The one-time inspection to detect cracking in socket welds will be either a volumetric or destructive examination. The inspection to detect cracking resulting from thermal and mechanical loading, vibration, or intergranular stress corrosion of full penetration welds will be a volumetric examination. Volumetric examination will be performed using demonstrated techniques from the ASME Code that are capable of detecting the aging effects in the examination volume of interest. In addition, the licensees plan stated, The inspection sample size will be at least 3 percent, up to a maximum of 10 welds, of each weld type, for each operating unit using a methodology to select the most susceptible and risk-significant welds, from the risk-informed approach as described above. For socket welds, destructive examination may be performed in lieu of volumetric examinations.
Because more information can be obtained from a destructive examination than from nondestructive examination, credit will be taken for each weld destructively examined equivalent to having volumetrically examined two welds.
Accordingly, the licensee selected a total number of five destructive examinations on socket welds, and three volumetric examinations on full penetration welds, to represent their Small Bore Class 1 inspection program. During the spring 2017 refueling outage, the licensee was pursuing this strategy and was in the process of completing the work during this inspection.
4OA6 Management Meetings
.1 Exit Meeting Summary
On March 3, 2017, the inspector presented the inspection results to Mr. Dan DeBoer, Site Director, and other members of the licensee staff. The inspector confirmed that none of the potential report input discussed was considered proprietary.
ATTACHMENT: Supplementary Information
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- P. Atkinson, License Renewal Implementation Project Manager
- L. Berry, Principal Nuclear Engineer, Licensing
- B. DiVentura, License Renewal Engineer
- D. Patel, License Renewal Engineer
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
None
LIST OF DOCUMENTS REVIEWED