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Category:Letter
MONTHYEARML24313A1012024-11-13013 November 2024 SLRA Supplemental Environmental Audit Plan ML24310A2832024-11-0404 November 2024 Issuance of the Core Operating Limits Report for Reload 25, Cycle 26 IR 05000277/20240032024-11-0404 November 2024 Integrated Inspection Report 05000277/2024003 and 05000278/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24281A1012024-10-0707 October 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24221A2582024-09-0606 September 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Peach Bottom Atomic Power Station, Units 2 and 3 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification 05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum2024-09-0505 September 2024 Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum IR 05000277/20240022024-09-0404 September 2024 Reissued Integrated Inspection Report 05000277/2024002 and 05000278/2024002 IR 05000277/20240052024-08-29029 August 2024 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2024005 and 05000278/2024005) IR 05000277/20240102024-08-23023 August 2024 Fire Protection Team Inspection Report 05000277/2024010 and 05000278/2024010 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24235A0342024-08-23023 August 2024 U.S. Nuclear Regulatory Commission’S Analysis of Constellation Energy Generation’S Decommissioning Funding Status Report ML24227A5492024-08-14014 August 2024 Integrated Inspection Report 05000277/2024002 and 05000278/2024002 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24225A1692024-08-12012 August 2024 10 CFR 50.46 Annual Report ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24214A3232024-08-0101 August 2024 Response to Request for Additional Information - Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) ML24191A0612024-07-0606 July 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24177A1512024-06-24024 June 2024 Post Accident Monitoring Instrumentation Report ML24166A1172024-06-20020 June 2024 Regulatory Audit Summary Regarding Proposed Alternative Schedule to Complete Decommissioning Beyond 60 Years RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000277/20243012024-06-13013 June 2024 Initial Operator Licensing Examination Report 05000277/2024301 and 05000278/2024301 RS-24-058, Regarding Subsequent License Renewal Environmental Review2024-06-0505 June 2024 Regarding Subsequent License Renewal Environmental Review ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24150A2722024-05-29029 May 2024 Annual Radiological Environmental Operating Report 81, January 1, 2023 Through December 31, 2023 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000277/20240012024-05-13013 May 2024 Integrated Inspection Report 05000277/2024001 and 05000278/2024001 ML24134A1792024-05-13013 May 2024 Supplemental Information in Support of Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations IR 05000277/20245012024-05-0808 May 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000277/2024501 and 05000278/2024501 ML24121A1832024-04-30030 April 2024 Pre-Submittal Meeting Presentation Material Peach Bottom ECCS Compensated Level System Replacement Project RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24120A2762024-04-23023 April 2024 Independent Spent Fuel Storage Installation (ISFSI) Facility - Annual Radioactive Effluent Release Report 66 January 1, 2023 Through December 31, 2023 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24107A2462024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24102A0472024-04-11011 April 2024 Operator Licensing Examination Approval 05000277/LER-2024-002, Uncoordinated DC Circuits Cause Unanalyzed Condition2024-04-0808 April 2024 Uncoordinated DC Circuits Cause Unanalyzed Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report 2024-09-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24214A3232024-08-0101 August 2024 Response to Request for Additional Information - Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24134A1792024-05-13013 May 2024 Supplemental Information in Support of Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations CCN:23-09, 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 ML22312A3642022-11-0808 November 2022 Response to NRC Inspection Report and Preliminary White Finding ML22145A0852022-05-25025 May 2022 Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel N-16A Nozzle Repair RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting ML21035A0332021-02-0404 February 2021 Response to Request for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative ML21029A1662021-01-29029 January 2021 Response to Request for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 ML20224A5302020-08-11011 August 2020 Response to the Order for Implementation of Additional Security Measures and Fingerprinting for Unescorted Access for Wolf Creek Operating Corporation Independent Spent Fuel Storage Installation ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML19276F2812019-10-0303 October 2019 Supplemental Response to Request for Additional Information (RAl-1) License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources-Operating ML19241A4652019-08-29029 August 2019 Response to Request for Additional Information (RAl-1) License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources-Operating ML19225B9762019-08-13013 August 2019 Response to NRC Request for Clarification of Information, Dated August 1, 2019 Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML19206A0562019-07-24024 July 2019 Stations, Units 2 and 3 - Response to Request for Additional Information - License Amendment Request to Revise Technical Specifications 3.8.1, Required Action A.3, for Temporary One-Time Extension of Completion Time ML19163A2232019-06-12012 June 2019 Revised Response to NRC Request for Additional Information, Core Shroud Support Fatigue Analysis Reevaluation, Related to the Subsequent License Renewal Application ML19157A0092019-06-0606 June 2019 Response to NRC Request for Additional Information, Dated May 15, 2019 Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 ML19150A2972019-05-30030 May 2019 Revised Responses to NRC Requests for Additional Information, Fire Water System, Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML19122A2892019-05-0202 May 2019 Response to NRC Requests for Additional Information, Set 1, Dated April 10, 2019 Related to Plant Subsequent License Renewal Application NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants ML19085A3852019-03-26026 March 2019 Response to Second Request for Additional Information - License Amendment Request to Reduce High Pressure Service Water System Design Pressure and Revise Technical Specifications ... ML19065A0082019-03-0505 March 2019 Response to Nrg Audit Review Information Request - Application for Subsequent Renewed Operating Licenses Section 4.6 Primary Containment Fatigue Analyses ML19046A1292019-02-15015 February 2019 Response to RAI - License Amendment Request to Reduce High Pressure Service Water System Design Pressure and Revise Technical Specifications 3.6.2.3, 3.6.2.4, 3.6.2.5, and 3.7.1 for Temporary Extension of Completion Times ML19028A2802019-01-28028 January 2019 Response to NRC Request for Additional Information, Dated December 13, 2018, Regarding Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Severe Accident Mitigation Alternatives Requests for Additional Information JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 ML19007A3262019-01-0707 January 2019 Response to Request Dated December 7, 2018 for Docketing of Additional Documents to Support Nrc'S Environmental Review of the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML18354B0612018-12-20020 December 2018 Response to NRC Request for Additional Information, Dated November 23, 2018, Regarding the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application, Environmental Requests for Additional Information ML18340A1852018-12-0606 December 2018 Response to Request for Additional Information License Amendment Request - Revise Technical Specifications to Allow Two Safety Relief Valves/Safety Valves to Be Out-of-Service with Increased Reactor Pressure Safety Limit RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements ML18337A2402018-11-28028 November 2018 Response to Request for Additional Information - Relief Requests Associated with the Fifth Inservice Inspection Interval ML18305B2702018-11-0101 November 2018 Response to Request for Additional Information - License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements ML18257A0172018-09-14014 September 2018 Response to Request for Additional Information Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite Update to ... ML18222A3872018-08-10010 August 2018 Response to Request for Additional Information and Supplemental Information - Application to Adopt 1 O CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components ... ML18128A0092018-05-0707 May 2018 Response to Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML17354A3812017-12-20020 December 2017 Supplemental Response Concerning License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 RS-17-149, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2017-12-15015 December 2017 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. ML17241A1942017-08-29029 August 2017 License Amendment Request - Revise Technical Specifications Section 3.4.3 (Srvs/Svs) for the Remainder of the Current Operating Cycle for Unit 2 - Supplement 1 Response to Request for Additional Information ML17223A6262017-08-11011 August 2017 Response to Request for Additional Information Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML17220A2142017-08-0808 August 2017 Measurement Uncertainty Recapture License Amendment Request - Supplement 3 Response to Request for Additional Information ML17195A2852017-07-13013 July 2017 Measurement Uncertainty Recapture License Amendment Request - Supplement 2 Response to Request for Additional Information RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML16224A3422016-08-11011 August 2016 Response to Request for Additional Information Regarding Proposed License Amendment Concerning Diesel Generator Lube Oil Inventory (TSTF-501-A) for Peach Bottom Atomic Power Station, Units 2 and 3 2024-08-09
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Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp com 10 CFR 50.55a November 28, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Response to Request for Additional Information - Relief Requests Associated with the Fifth lnservice Inspection Interval
References:
- 1) Letter from J. Barstow (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, "Relief Requests Associated with the Fifth lnservice Inspection Interval," dated April 19, 2018
- 2) Email from J. Tobin (U.S. Nuclear Regulatory Commission) to D. Helker (Exelon Generation Company, LLC), "Peach Bottom Units 2 and 3 -
Request for Additional Information - Relief Request 15R-05 (EPID L-2018-LLR-0058)," dated August 14, 2018 (ML18226A201)
- 3) Email from J. Tobin (U.S. Nuclear Regulatory Commission) to D. Helker (Exelon Generation Company, LLC), "Peach Bottom Units 2 and 3 -
Request for Additional Information - Relief Request l5R-06 (EPID L-2017-LLR-0059)," dated August 15, 2018 (ML18227A107)
- 4) Email from J. Tobin (U.S. Nuclear Regulatory Commission) to D. Helker (Exelon Generation Company, LLC), "Peach Bottom Units 2 and 3 -
Request for Additional Information FINAL - Relief Request 15R-04 (EPID L-2018-LLR-0057)," dated August 27, 2018 (ML18239A132)
- 5) Letter from J. Barstow (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, "Response to Request for Additional Information - Relief Requests Associated with the Fifth lnservice Inspection Interval," dated September 6, 2018 In the Reference 1 letter, Exelon Generation Company, LLC submitted for your review relief requests associated with the fifth lnservice Inspection (ISi) interval for the Peach Bottom Atomic Power Station, Units 2 and 3. The fifth interval program complies with the 2013 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code.
In the Reference 2, 3, and 4 emails, the U.S. Nuclear Regulatory Commission Staff requested additional information. Reference 5 was our response.
Response to Request for Additional Information Relief Requests Associated with the Fifth lnservice Inspection Interval November 28, 2018 Page 2 Based on additional discussions with the U.S. Nuclear Regulatory Commission Staff, the response to Question 15R-06 is being supplemented. Attached is the original response with the supplemental information identified with a revision bar.
There are no regulatory commitments in this response.
If you have any questions concerning this response, please contact Tom Loomis at (610) 765-5510.
/J '71-----
d Respectfully,
(,Vl'Wo t~ .
James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1) Supplemental Response to Request for Additional Information - 15R-06 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R.R. Janati, Pennsylvania Bureau of Radiation Protection D. A. Tancabel, State of Maryland
Attachment 1 Supplemental Response to Request for Additional Information -
15R-06
Response to Request for Additional Information Page 1 Question (ISR-06):
"Address the following plant-specific items for the fifth ISi interval. The plant-specific responses are to consider the impact of stuck studs, missing studs, flange holes with bushings, and other unique flange-stud configurations, as applicable.
- 1. Provide a detailed description of the "care and visual inspections" performed on the RPV threads in flange and studs each time the RPV head is removed. Alternatively, provide the procedures that control the care and visual inspection activities.
- 2. Justify that the existing care and visual inspection activities will provide assurance that degradation of the RPV threads in flange is detected and mitigated prior to returning the reactor to service each time the RPV closure head is removed during the fifth ISi interval if volumetric inspections are not performed."
Response
As stated in Relief Request ISR-06, to protect against non-service related degradation, detailed procedural guidance is used during each refueling outage for the removal, care and visual inspection of the RPV studs and the threads in flange each time the RPV closure head is removed. Care is taken to not only remove the studs, but once the studs are removed, to inspect the RPV threads for damage and to install RPV stud plugs to protect threads from damage. Prior to reinstallation, the studs and stud holes are cleaned and lubricated. The studs are then reinstalled and tensioned into the RPV flange. This activity is performed each refueling outage and the procedure documents each step. These controlled maintenance activities provide further assurance that degradation is detected and mitigated prior to returning the reactor to service.
The care and visual inspections performed on the RPV threads in flange and studs are described in the following excerpts of the PBAPS, Units 2 and 3 site specific procedures:
REACTOR PRESSURE VESSEL DISASSEMBLY (M-004-200)
- 5. 7 RPV Head Stud Detensioning Preparation 5.7.16 CLEAN RPV head flange, studs, and area around each nut/washer.
5.7.17 LUBRICATE studs with lubricant (DAG 156}.
WV 5.7.18 INITIAL AND DATE indicating subsection complete.
WV
Response to Request for Additional Information Page2 REACTOR PRESSURE VESSEL REASSEMBLY (M-004-400) 5.1 O RPV Head Installation Preparation 5.10.9 NOTIFY Radiation Protection prior to cleaning RPV stud holes and RPV flange.
Person Contacted WV 5.10.10 CLEAN six vacated RPV flange stud holes, THEN APPLY lubricant (DAG 156) to stud hole threads.
5.12 RPV Head Stud Installation 5.12.6 INSTALL studs as follows:
- 1. ENSURE stud hole is clean and free of debris, THEN LUBRICATE stud hole threads with lubricant (DAG 156).
- 6. LUBRICATE stud threads with lubricant (DAG 156).
5.13 RPV Head Stud Tensioning Preparation 5.13.6 INSPECT accessible surfaces of studs for dirt, grit, or other foreign material in thread roots and outside stud surfaces. CLEAN as necessary.
5.13.7 CLEAN stud rod holes using wet vacuum or other suitable tool.
PEER CHECK 5.13.8 VERIFY studs and stud rod holes are clean and free of debris.
WV PC In the event that damage is identified to the RPV studs and the threads, a corrective action issue report is initiated to document the condition in accordance with plant administrative procedures. The 10 CFR Part 50, Appendix B corrective action program ensures that conditions adverse to quality are promptly corrected.