Similar Documents at Byron |
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Category:Inspection Report Correspondence
MONTHYEARML23192A0362023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report IR 05000454/20214032021-11-22022 November 2021 Security Baseline Inspection Report 05000454/2021403 and 05000455/2021403 ML17269A1082017-09-25025 September 2017 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) (Mjf) ML17137A0562017-05-17017 May 2017 Information Request to Support Upcoming Temporary Instruction 191 Inspection at Byron Station, Units 1 and 2 ML16251A0462016-09-19019 September 2016 NRC Security Inspection Report 05000454; 455/2016201 (Cover Letter Only) IR 05000454/20162012016-09-19019 September 2016 Byron Station - NRC Security Inspection Report 05000454; 455/2016201 (Cover Letter Only) ML16196A1102016-07-14014 July 2016 Notification of NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000454/2016004; 05000455/2016004 IR 05000454/20155012016-02-0303 February 2016 NRC Emergency Preparedness Annual Inspection Report No. 05000454/2015501; 05000455/2015501 ML13065A1122013-03-0505 March 2013 Email - Byron Unit 2 ISI Request for Information DEJ5 IR 05000454/20105012011-01-14014 January 2011 IR 05000454-10-501, 05000455-10-501, on 12/31/10, Byron Station, Units 1 and 2, NRC Emergency Preparedness Annual Inspection IR 05000454/20080072008-10-10010 October 2008 IR 05000454-08-007, (Drs), IR 05000455-08-007, (Drs), on 08/25/2008 - 08/29/2008, Byron Station, Units 1 and 2, Ti 2515/171 Verification of Site Specific Implementation of B.5.b Phase 2 and 3, Mitigating Strategies - Cover Letter ML0731807162007-11-14014 November 2007 Request for Information MOD/50.59 Baseline Inspection and Temporary Instruction 2515/166, Pressurized Water Reactor Containment Sump Blockage. IR 05000454/20074022007-08-0808 August 2007 IR 05000454-07-402, and IR 05000455-07-402, 06/04/2007 - 06/27/2007, Byron Station, Units 1 and 2, Material Control and Accounting Program - Cover Letter IR 05000454/20060092007-01-12012 January 2007 IR 05000454-06-009; 05000455-06-009(DRS) on 10/30/2006 - 12/01/2006 for Byron Station; Component Design Bases Inspection IR 05000454/20060042006-11-0808 November 2006 IR 05000454/2006004; 05000455/2006004; on 07/01/2006 - 09/30/2006; Byron Station, Units 1 and 2; Fire Protection and Radiation Protection IR 05000454/20060032006-08-0303 August 2006 IR 05000454-06-003; 05000455-06-003; 05000454-06-010; 05000455-06-010; on 04/01/2006-06/30/2006; Byron Station, Units 1 and 2; Routine Integrated Inspection Report ML0619504902006-07-0707 July 2006 Orise - Analytical Results for Three Water Samples in Batch Four from the Vicinity of the Byron Generating Station, Byron, Illinois (Inspection Report No. 050-00454/2006-003 (Rfta No. 06-001)) IR 05000454/20060022006-05-12012 May 2006 IR 05000454-06-002; 05000455-06-002; on 01/01/2006-03/31/2006; Byron Station, Units 1 and 2; Maintenance Risk Assessments and Emergent Work Control, Identification and Resolution of Problems IR 05000454/20020032002-04-26026 April 2002 IR 05000454/2002-003(DRP) & IR 05000455/2002-003(DRP), Byron, Units 1 & 2 . Maintenance Risk Assessment, Emergent Work & Refueling & Outage Activities IR 05000455/20020022002-03-0808 March 2002 IR 05000455/2002-002, IR 05000455/2002-002 (Drp), on 12/30/2001-02/11/2002; Exelon Generation Company, LLC; Byron Station, Units 1 & 2. Post-Maintenance Testing. One Green Violation Identified 2023-07-25
[Table view] Category:Letter
MONTHYEARIR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23192A0362023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 IR 05000454/20234022023-07-18018 July 2023 Baseline Security Inspection Document; 05000454/2023402; 05000455/2023402 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) ML23159A1542023-06-0808 June 2023 2022 Regulatory Commitment Change Summary Report RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23003A7882023-05-11011 May 2023 Report for December 12-16, 2022, Regulatory Audit Regarding Reinsertion of a High Burnup Accident Tolerant Fuel Lead Test Assembly 2024-02-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23115A2412023-01-20020 January 2023 NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly ML22237A0272022-08-25025 August 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22116A1272022-04-26026 April 2022 Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21203A3112021-07-21021 July 2021 NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21189A1612021-07-0808 July 2021 NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21036A1102021-02-0404 February 2021 NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20329A4852020-11-24024 November 2020 Notification of NRC Fire Protection Team Inspection Request for Information ML20294A5492020-10-21021 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20077M2212020-03-20020 March 2020 Ti 2515/194 Inspection Documentation Request ML20008D3992020-01-0808 January 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000454/2020001 ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19252C1542019-08-22022 August 2019 NRR E-mail Capture - Issuance of the Remainder of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19232A2242019-08-0707 August 2019 NRR E-mail Capture - Partial Issuance of Final RAIs for Braidwood/Byron TSTF-505 Application ML19207A0672019-07-26026 July 2019 NRR E-mail Capture - Partial Issuance of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19032A1062019-02-0101 February 2019 NRR E-mail Capture - Preliminary RAIs for Byron On--time Extension of Completion Time 3.8.1, A.2 ML19011A3452019-01-11011 January 2019 NRR E-mail Capture - Preliminary RAIs Regarding Byron Request to Use ATF LTAs ML18149A2842018-05-24024 May 2018 NRR E-mail Capture - B/B 50.69 RAI - Potential Typo ML18129A1082018-05-0909 May 2018 NRR E-mail Capture - Preliminary RAIs for Braidwood and Byron Stations 50.69 Amendment ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML18022A0422018-01-19019 January 2018 18 Byron Station, Units 1 and 2 - Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection (DRS-I.Hafeez) ML17179A2852017-06-28028 June 2017 NRR E-mail Capture - Request for Additional Information Regarding Braidwood and Byron Amendments to Remove Obsolete License and Technical Specification Items ML17159A6292017-06-0707 June 2017 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML17137A0562017-05-17017 May 2017 Information Request to Support Upcoming Temporary Instruction 191 Inspection at Byron Station, Units 1 and 2 ML17062A4912017-03-0303 March 2017 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative to RPV Threads in Flange Examination (CAC Nos. MF8712-MF8729) ML17019A2022017-01-19019 January 2017 NRR E-mail Capture - Preliminary RAIs for Byron Station TORMIS License Application Request ML16355A0322016-12-19019 December 2016 Notification of NRC Inspection and Request for Information (Msh) ML16343A2522016-12-0808 December 2016 NRR E-mail Capture - Preliminary Request for Additional Information (RAI) Regarding Relief Request I4R-10 ML16196A1102016-07-14014 July 2016 Notification of NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000454/2016004; 05000455/2016004 2023-07-31
[Table view] |
See also: IR 05000454/2016004
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 July 14, 2016 Mr. Bryan C. Hanson Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: BYRON STATION, UNITS 1 AND 2 NOTIFICATION OF AN NRC TRIENNIAL HEAT SINK PERFORMANCE INSPECTION AND REQUEST FOR INFORMATION; INSPECTION REPORT 05000454/2016004; 05000455/2016004 Dear Mr. Hanson: On October 24, 2016, the U.S. Nuclear Regulatory Commission (NRC) will begin the onsite portion of the Triennial Heat Sink Performance Inspection at your Byron Station, Units 1 and 2. This inspection will be performed in accordance with NRC baseline Inspection Procedure 71111.07. In order to minimize the impact that the inspection has on the site and to ensure a productive inspection, we have enclosed a request for documents needed for the inspection. The documents have been divided into three groups. The first group lists information necessary for our initial inspection scoping activities. This information should be available to the lead inspector no later than August 30, 2016. By September 9, 2016, the inspector will communicate the initial selected set of approximately 1 2 risk-significant heat exchangers. The second group is needed to support our in-office preparation activities. This set of documents, including the calculations associated with the selected heat exchangers, should be available at the Regional Office no later than October 13, 2016. This information should be separated for each selected component, especially if provided electronically (e.g., folder with component name that includes calculations, condition reports, maintenance history, etc). During the in-office preparation activities, the inspector may identify additional information needed to support the inspection. The last group includes the additional information above as well as plant specific reference material. This information should be available onsite to the inspector on October 24, 2016. It is also requested that corrective action documents and/or questions developed during the inspection be provided to the inspector as the documents are generated. All requested documents are to be for the time period from the onsite inspection period back to the documents that were provided in response to the previous Heat Sink Performance Inspection. If no activities were accomplished in that time period, then the request applies to the last applicable document in the previous time period. It is important that these documents be as complete as possible, in order to minimize the number of documents requested during the preparation week or during the onsite inspection.
B. Hanson -2- The lead inspector for this inspection is Mr. Andrew Dunlop. We understand that our licensing contact for this inspection is Ms. L. Zurawski of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at 630-829-9726, or via e-mail at Andrew.Dunlop@nrc.gov. This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number. In accordance with Title 10 of the Code of Federal Regulations of this letter and its enclosure will be available electronically for public inspection in the NRPublic Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely, /RA/ Andrew Dunlop, Senior Reactor Engineer Engineering Branch 2 Division of Reactor Safety Docket Nos. 50454; 50455 License Nos. NPF37; NPF66 Enclosure: Triennial Heat Sink Performance Inspection Document Request cc: Distribution via LISTSERV
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST Enclosure Inspection Report: 05000454/2016004; 05000455/2016004 Inspection Dates: October 24 28, 2016; Inspection Procedure: IP Lead Inspector: Andrew Dunlop, DRS 630-829-9726 Andrew.Dunlop@nrc.gov I. Information Requested By August 30, 2016: 1. List of the Generic Letter (GL) 89-cting Safety-Related heat exchangers in order of risk significance. 2. Copy of heat exchanger performance trending data tracked for each GL 89-13 heat exchanger. 3. List of Corrective Action Program documents (with a short description) associated with GL 89-13 heat exchangers, heat sinks, silting, corrosion, fouling, or heat exchanger testing, for the previous 3 years. 4. Copy of any self-assessment done on any of GL 89-13 heat exchangers. 5. Last two System Health Report(s) and maintenance rule system notebooks for all the GL 89-13 heat exchangers. 6. List of engineering-related operator workarounds (with a short description) associated with GL 89-13 heat exchangers that were in place within the last 3 years. 7. List of permanent and temporary modifications (with a short description) associated with GL 89-13 heat exchangers for the last 3 years. II. Information Requested By October 13, 2016: 1. Copies of the GL 89-13 responses. 2. Copy of the Updated Final Safety Analysis Report (UFSAR) section applicable to the GL 89-13 Heat Exchanger Program. 3. Copies of procedures developed to implement the recommendations of GL 89-13 (e.g. the GL 89-13 Heat Exchanger Program description). 4. Copies of the selected Corrective Action Program documents. 5. For the specific heat exchangers selected: a. Copies of the UFSAR sections applicable for each heat exchanger.
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST 2 b. Copy of system description and design basis document for the heat exchangers (as applicable). c. Provide a list of calculations (with a short description) which currently apply to each heat exchanger. i. establish the limiting design basis heat load required to be removed by each of these heat exchangers; ii. demonstrate the heat exchangers capacity to remove the limiting heat load; iii. correlate surveillance testing and/or inspection results from these heat exchangers with design basis heat removal capability (e.g., basis for surveillance test and/or inspection acceptance criteria); iv. evaluate the potential for water hammer in each heat exchanger or associated piping; and v. evaluate excessive tube vibration in each heat exchanger. d. Copy of any operability determinations or other documentation of degradation associated with the heat exchangers or the systems that support the operation for the selected heat exchangers. e. Copy of the construction code, Design Specification, heat exchanger data sheets, and vendor documents including component drawings applicable for the heat exchangers. f. Copies of normal, abnormal, and emergency operating procedures associated with the selected heat exchangers. 6. For the Ultimate Heat Sink (UHS) and the safety-related service water system (or equivalent): a. Copies of the applicable Updated Final Safety Analysis Report (UFSAR) sections. b. Copy of system description and design basis document (as applicable). c. Copy of any operability determinations or other documentation of degradation associated with the UHS and the safety-related service water system. d. Copy of the document (e.g., UFSAR or Technical Requirements Manual) that states the maximum cooling water system inlet temperature limit that still allows full licensed power operation of the nuclear reactor. e. Copy of system description and design basis document (as applicable). f. Copy of the construction code and Design Specification.
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST 3 g. Copies of normal, abnormal, and emergency operating procedures associated with the UHS and safety-related service water systems including procedures for loss of these systems. h. Copies of corrective action documents associated with waterhammer or hydraulic transients in the service water system since the last Heat Sink Inspection. i. If available, provide an electronic copy of piping and instrumentation diagrams for the service water system, including the intake structure. j. Provide a list of calculations (with a short description), which currently apply to UHS and safety-related service water system. k. Provide a list of instruments (with a short description) associated with automatic or alarm functions for the safety-related service water system and/or UHS. l. Provide a list of any design change (with a short description) performed on the UHS or safety-related service water system since the last heat sink performance inspection. 7. A schedule of all inspections, cleanings, maintenance, or testing of any safety-related plant heat exchanger to be performed during the on-site portion of the inspection. III. Information Requested to be Available on First Day of Inspection, October 24, 2016: 1. For the specific heat exchangers selected. a. Copy of the calculation which correlates surveillance testing results from these heat exchangers with design basis heat removal capability (e.g., basis for surveillance test acceptance criteria b. Copies of the two most recent completed tests and evaluation data confirming thermal performance for those heat exchangers which are performance tested. c. Documentation and procedures that identify the types, accuracy, and location of any special instrumentation used for the two most recently completed thermal performance tests for the heat exchangers (e.g., high accuracy ultrasonic flow instruments or temperature instruments). Include calibration records for the instruments used during these tests. d. Information regarding any alarms which monitor on-line performance. e. Copy of the document describing the inspection results of each heat exchanger. f. The cleaning and inspection maintenance schedule for each heat exchanger for the next 5 years. g. Copy of the design specification and heat exchanger data sheets for each heat exchanger. h. Copy of the vendor manuals including component drawings for each heat exchanger.
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST 4 i. Copy of the calculation which establishes the limiting (maximum) design basis heat load which is required to be removed by each of these heat exchangers. j. Copy of the operating procedure that ensures that the maximum cooling water system inlet temperature limit is not exceeded. k. Copy of the calculations or documents which evaluate the potential for water hammer in each heat exchanger or associated piping. l. Copy of the calculations that evaluate excessive tube vibration in each heat exchanger and the documents that describe the controls that prevent heat exchanger degradation due to excessive flow induced vibration during operation. m. Copy of the periodic flow testing at or near maximum design flow. n. Copy of the document which identifies the current number of tubes in service for each heat exchanger and the supporting calculation which establishes the maximum number of tubes which can be plugged in each heat exchanger. o. Copy of the document establishing the repair criteria (plugging limit) for degraded tubes which are identified in each heat exchanger. p. Copies of the documents that verify the structural integrity of the heat exchanger (e.g. eddy current summary sheets, ultrasonic testing results, and visual inspection results). q. Copies of those documents that describe the methods taken to control water chemistry in the heat exchangers. 2. For the review of the operation of the safety-related service water system (or equivalent) and the UHS: a. Copies of any design change performed on the UHS in last 3 years. b. Copies of any design change performed on the safety-related service water system in last 3 years. c. Copies of procedures for a loss of UHS. d. Copies of procedures for a loss of service water system. e. Inspections and/or maintenance related to preventing macrofouling (e.g., silt, dead mussel shells, or debris) and biotic fouling (e.g., fish, algae, grass, or kelp) in last 3 years. f. Copies of chemistry procedures that monitor for pH, calcium hardness, etc. Also, provide copies of the associated results for the last 3 years. g. Copies of documents associated with the monitoring of pump performance for potential strong-pump vs. weak-pump interaction.
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST 5 3. For the review associated with the system walkdown of the service water intake structure: a. Copies of corrective maintenance for the last 6 years associated with service water strainers, traveling screens and trash racks. b. Copies of the last two inspections and/or surveillances associated with service water strainers, traveling screens and trash racks. c. List of preventive maintenance, including frequency, associated with service water strainers, traveling screens and trash racks. d. Copies of abnormal procedures for the traveling screens and service water strainers. e. Copies of the last two inspections and/or surveillances documenting that component mounts have not excessively degraded (i.e., due to corrosion). For example, inspections for the mounts for the, Service water pumps, service water strainers, traveling screens and trash racks. f. Copies of the documents associated with the monitoring, trending, and remediation of silt accumulation at the service water pump bay. g. Copies of surveillance procedures and testing results for the last performed on the service water pump bay water level instruments. h. Copies of procedures associated with operating during adverse weather conditions (e.g., icing, high-temperatures, or low-level). i. Copy of the evaluation for the potential effects of low-flow/level on underwater weir walls intended to limit silt or sand intake, if applicable. If the information requested above will not be available, please contact Mr. Andrew Dunlop as soon as possible at 630-829-9726, or via e-mail Andrew.Dunlop@nrc.gov.
B. Hanson -2- The lead inspector for this inspection is Mr. Andrew Dunlop. We understand that our licensing contact for this inspection is Ms. L. Zurawski of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at 630-829-9726, or via e-mail at Andrew.Dunlop@nrc.gov. This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number. In accordance with Title 10 of the Code of Federal Regulations of this letter and Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely, /RA/ Andrew Dunlop, Senior Reactor Engineer Engineering Branch 2 Division of Reactor Safety Docket Nos. 50454; 50455 License Nos. NPF37; NPF66 Enclosure: Triennial Heat Sink Performance Inspection Document Request cc: Distribution via LISTSERV DISTRIBUTION: Jeremy Bowen RidsNrrDorlLpl3-2 Resource RidsNrrPMByron Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Richard Skokowski Allan Barker Carole Ariano Linda Linn DRPIII DRSIII ADAMS Accession Number ML16196A110 Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME ADunlop:cl DATE 07/14/16 OFFICIAL RECORD