Letter Sequence RAI |
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MONTHYEARML0817104702008-05-19019 May 2008 License Renewal Application, May 19, 2008 Draft Request for Additional Information, for Sections 4.2 and 4.4 Project stage: Draft RAI ML0817800062008-07-23023 July 2008 License Renewal Application, June 5, 2008 Conference Call Between USNRC and Amergen to Discuss Draft Requests for Additional Information for Sections 4.2 and 4.4 Project stage: Draft RAI ML0821700462008-08-20020 August 2008 Unit - 1, Request for Additional Information, License Renewal Application, Sections 4.2 and 4.4, TAC MD7701 Project stage: RAI ML0821804992008-08-20020 August 2008 Request for Additional Information, License Renewal Application, Sections 2.3.3 & 2.3.4 Project stage: RAI ML0821800062008-08-22022 August 2008 License Renewal Application, Summary of June 25, 2008 Conference Call with Amergen Energy Company LLC, to Discuss Draft Request for Additional Information for Sections 2.2, 2.3, 2.4, and 2.5 Project stage: Draft RAI ML0821907812008-08-22022 August 2008 Request for Additional Information, License Renewal Application, Section 2.1.5.2 Project stage: RAI ML0822000322008-08-22022 August 2008 Request for Additional Information, on License Renewal Application Sections 2.2, 2.3, 2.4 & 2.5 Project stage: RAI ML0823301922008-08-26026 August 2008 License Renewal Application, Enclosure 2 to Summary of June 25, 2008 Conference Call with Amergen Energy Company to Discuss Draft Request for Additional Information, Sections 2.2, 2.3, 2.4 & 2.5 Project stage: Draft RAI ML0825601782008-09-10010 September 2008 Response to NRC Request for Additional Information Related to Three Mile Island Nuclear Station, Unit 1, License Renewal Application Project stage: Response to RAI ML0826300302008-09-16016 September 2008 Response to NRC Request for Additional Information Related to Three Mile Island Nuclear Station, Unit 1, License Renewal Application Project stage: Response to RAI ML0826703592008-09-19019 September 2008 Response to Request for Additional Information Related to License Renewal Application Project stage: Response to RAI ML0824900892008-09-29029 September 2008 Unit - 1, Request for Additional Information, License Renewal Application, Appendix B, Aging Management Programs, Part 1 Project stage: RAI ML0825205732008-09-30030 September 2008 Unit - 1, Request for Additional Information, License Renewal Application, Time Limited Aging Analysis Project stage: RAI ML0825200202008-10-0707 October 2008 Request for Additional Information, License Renewal Application, Appendix B, Aging Management Programs, Part 2 Project stage: RAI ML0825206142008-10-16016 October 2008 Unit - 1, Request for Additional Information, License Renewal Application, Aging Management Review Results Project stage: RAI ML0825201222008-10-20020 October 2008 Request for Additional Information, License Renewal Application, Boral Neutron Absorbing Material in Spent Fuel Pool Racks Project stage: RAI ML0830204062008-10-23023 October 2008 Response to NRC Request for Additional Information on License Renewal Application Project stage: Response to RAI ML0830803762008-10-30030 October 2008 Response to NRC Request for Additional Information Related to Three Mile Island, Unit 1, License Renewal Application Project stage: Response to RAI ML0831900392008-11-12012 November 2008 Response to NRC Request for Additional Information Related to Three Mile Island Nuclear Station, Unit 1, License Renewal Application Project stage: Response to RAI ML0831900382008-11-12012 November 2008 Response to NRC Request for Additional Information on License Renewal Application Project stage: Response to RAI ML0830900532008-11-17017 November 2008 License Renewal Application, Summary of Conference Call with Amergen Energy Company Regarding Responses to Request for Additional Information for Sections 2.3.3 and 2.3.4 Project stage: RAI ML0831700382008-11-24024 November 2008 License Renewal Application, Request for Additional Information, Sections 2.3 & 2.4 Project stage: RAI ML0828800032008-11-24024 November 2008 Unit - 1, License Renewal Application, Aging Management Programs, Audit Summary Report Project stage: Acceptance Review ML0832402452008-12-0303 December 2008 License Renewal Application Regarding Scoping and Screening Audit Summary Project stage: Other ML0834400582008-12-0505 December 2008 Response to NRC Request for Additional Information Related to License Renewal Application, Sections 2.3 & 2.4 Project stage: Response to RAI ML0835100402009-01-0505 January 2009 Unit - 1, License Renewal Application, Request for Additional Information Project stage: RAI ML0907106042009-03-31031 March 2009 Safety Evaluation Report with Open Items Related to the License Renewal of Three Mile Island Nuclear Station, Unit 1 Project stage: Approval ML0913200422009-06-30030 June 2009 Safety Evaluation Report Related to the License Renewal of Three Mile Island, Unit 1 Project stage: Approval ML0916604702009-06-30030 June 2009 Safety Evaluation Report Related to the License Renewal of Three Mile Island, Unit 1 Project stage: Approval 2008-07-23
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Category:Letter
MONTHYEARML24038A0222024-02-0505 February 2024 Achp Letter on Section 106 Programmatic Agreement Participation IR 05000289/20230062024-01-29029 January 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 05000289/2023006 ML23342A1242024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23325A1092024-01-0505 January 2024 Review of the Management Plan for Three Mile Island Station, Unit No. 2, Debris Material ML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 IR 05000320/20230032023-11-28028 November 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2, NRC Inspection Report No. 05000320/2023003 ML23243A9082023-08-29029 August 2023 Shpo Letter to TMI-2 Regarding Section 106 Activities IR 05000320/20230022023-08-17017 August 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023002 ML23216A1742023-08-14014 August 2023 Consultation Letter to David Morrison for TMI-2 ML23216A1772023-08-14014 August 2023 Consultation Letter to Rebecca Countess for TMI-2 ML23216A1752023-08-14014 August 2023 Consultation Letter to Joanna Cain for TMI-2 ML23216A1732023-08-14014 August 2023 Consultation Letter to Christine Turner for TMI-2 IR 05000289/20230052023-08-14014 August 2023 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005 ML23216A1782023-08-14014 August 2023 Consultation Letter to Steve Letavic for TMI-2 ML23221A1402023-08-0808 August 2023 (TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23200A1882023-07-31031 July 2023 TMI-2 Correction Letter Amendment 67 ML23209A7632023-07-28028 July 2023 Letter from PA Shpo to TMI-2 Solutions on Cultural and Historic Impacts of Decommissioning ML23192A8272023-07-10010 July 2023 TMI-2 Solutions, LLC - Response to Shpo Request for Additional Information for Er Project 2021PR03278.006, TMI-2 Decommissioning Project ML23167A4642023-07-0505 July 2023 Letter - TMI-2- Exemption 10 CFR Part 20 Append G Issuance ML23167A0312023-06-28028 June 2023 Acceptance Review and Schedule for the Request for Exemption from a Requirement from 10 CFR 20, Appendix G, Section Iii.E, EPID L-2023-LLE-0016 ML23171B0222023-06-19019 June 2023 (TMI-2) - Notification Pursuant to 10 CFR 72.140(d) Regarding Application of Previously Approved TMI-2 Quality Assurance Program to Independent Spent Fuel Storage Installation Activities ML23137A2822023-05-17017 May 2023 (TMI-2), Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23138A0662023-05-17017 May 2023 TMI-2 NHPA Section 106 Shpo Letter to NRC 5-17-23 ML23026A3132023-05-0202 May 2023 Issuance of Exemption from 10 CFR 70.24 (EPID-L-2023-LLE-0003) ML23122A1842023-05-0101 May 2023 Shpo_Er_Summary_Letter ML23121A2492023-05-0101 May 2023 License Amendment Request, Historic and Cultural Resources Review, Response to Request for Additional Information ML23117A0012023-04-26026 April 2023 Commitment Revision Summary Report ML23027A0832023-04-24024 April 2023 Environmental Assessment/Finding of No Significant Impact - Request for Exemption from 10 CFR 70.24 ML23108A0802023-04-18018 April 2023 Annual Radiological Effluent Release Report ML23108A0822023-04-18018 April 2023 Annual Radiological Environmental Operating Report IR 05000320/20230012023-04-12012 April 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report No. 05000320/2023001 ML23102A0382023-04-10010 April 2023 Occupational Radiation Exposure Annual Report ML23108A2002023-04-10010 April 2023 CFR 20.2206(b) Personnel Radiation Exposure Report for 2022 ML23094A2582023-04-0606 April 2023 Letter to Sidney Hill, Chief, Onondaga Nation, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23093A0572023-04-0606 April 2023 Letter to Joanna Cain, President, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2362023-04-0606 April 2023 Letter to Carissa Speck, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2542023-04-0606 April 2023 Ltr J Bendremer Thpo Stockbridge-Munsee Community Band of Mohican Indians Re Initiation of Consultation Under Section 106 of the NHPA for Proposed License Amendment Request for TMI 2 ML23086C0652023-04-0606 April 2023 Ltr Larry Heady, Thpo, De. Tribe of Indian; Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI Nuclear Station, Unit 2 ML23093A0562023-04-0606 April 2023 Letter to Steve Minnick, Site Decommissioning Director, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2602023-04-0606 April 2023 Letter to William Tarrant, Seneca-Cayuga Nation, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23094A2392023-04-0606 April 2023 Letter to Courtney Gerzetich, Thpo, Onedia Nation of Wisconsin, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23093A0592023-04-0606 April 2023 Letter to Rebecca Countess, Chair, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 2024-02-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24011A2352024-01-11011 January 2024 Eco Request for Additional Information for 2023 License Amendment Request 1-11-24 ML23187A0202023-06-29029 June 2023 TMI Unit 2 RAI Related to the Amended Post-Shutdown Decommissioning Activities Report ML23187A0332023-06-29029 June 2023 TMI Unit 2, PSDAR Rev. 5 RAIs ML23082A3432023-03-31031 March 2023 Enclosure - RAI - Three Mile Island, Unit 2 - Acceptance Review and Request for Additional Information for the Historic and Cultural Resources License Amendment Request - EPID: 2023-LLA-0026 ML22357A0142022-12-22022 December 2022 NRC Request for Additional Information Related to the TMI-2 Pdms Transition License Amendment Request ML22210A0882022-07-29029 July 2022 Enclosure - Three Mile Island, Unit No. 2 - Request for Additional Information for Requested Licensing Action Regarding Decommissioning Technical Specifications ML22143A8902022-05-23023 May 2022 Request for Additional information- TMI-1 ISFSI Only Physical Security License Amendment Request ML22125A0122022-04-28028 April 2022 Clarification RAI Partial Response Email from C Smith to a Snyder ML22110A0202022-04-19019 April 2022 Unit 1 Request for Additional Information ML22038A9362022-02-0707 February 2022 TMI2 Accident Analyses Questions ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML20164A0902020-06-10010 June 2020 Request for Additional Information Related to TMI-1 License Amendment Request to Delete Permanently Defueled Technical Specification 3/4.1.4 (L-2019-LLA-0250) ML19319B2082019-11-15015 November 2019 NRR E-mail Capture - Request for Additional Information Related to TMI-1 Request for Exemption from Portions of 10 CFR 50.47 and Part 50 Appendix E (L-2019-LLA-0216) ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML18220A7832018-08-0707 August 2018 NRR E-mail Capture - Request for Additional Information Related to TMI Fall 2017 Steam Generator Tube Inspection Report ML18212A2712018-07-31031 July 2018 NRR E-mail Capture - Request for Additional Information Related to Amendment Regarding Decommissioning ERO Staffing Changes ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. 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) ML16356A4802016-12-21021 December 2016 NRR E-mail Capture - RAIs on TMI License Amendment Request for Approval of Changes to the Three Mile Island Nuclear Station Emergency Plan Related to Staffing ML16337A0072016-12-0101 December 2016 NRR E-mail Capture - Draft RAIs Three Mile Island Nuclear Station, Units 1 and 2, License Amendment Request for Approval of Changes to the Three Mile Island Nuclear Station Emergency Plan Related to Staffing ML16287A4042016-10-11011 October 2016 Notification of Conduct of a Triennial Fire Protection Baseline Inspection ML15230A5332015-08-18018 August 2015 Draft Request for Additional Information ML15020A7372015-03-0808 March 2015 Request for Additional Information Regarding Related to December 22, 2014, Report Submitted Pursuant to 10 CFR 50.46 ML14307A1172014-11-14014 November 2014 Request for Additional Information Regarding Relief Request RR-14-01 Concerning Alternative Root Mean Square Depth Sizing Requirements ML14240A4122014-09-0404 September 2014 Request for Additional Information Regarding License Amendment Request to Eliminate Certain Technical Specification Reporting Requirements (Tac MF0628) ML14134A3222014-05-22022 May 2014 Request for Additional Information Regarding Review of Three Mile Island Nuclear Station Unit 1 Cycle 20 Core Operating Limits Report ML14134A1722014-05-14014 May 2014 Draft RAIs in Support of NRC Staff Review of TMI Cycle 20 COLR ML14052A2592014-02-27027 February 2014 Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specification Reporting Requirements ML14030A5832014-01-29029 January 2014 Draft Request for Additional Information Proposed Revision to Technical Specifications Reporting Requirements Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1 ML13266A2852013-10-21021 October 2013 Request for Additional Information on Three Mile Island Nuclear Station Unit 2 - post-shutdown Decommissioning Activities Report ML13276A6492013-10-0303 October 2013 Notification of Conduct of a Triennial Fire Protection Baseline Inspection ML13269A1792013-09-25025 September 2013 Draft Request for Additional Information ML13253A2252013-09-10010 September 2013 Draft Request for Additional Information ML13249A2072013-09-0505 September 2013 Draft Request for Additional Information ML13193A1752013-07-22022 July 2013 Request for Additional Information Regarding Revision to Pressure and Temperature Limit Curves and Exemption Request for Initial Reference Temperature Values ML13196A3382013-07-15015 July 2013 2013 Decommissioning Fund Report RAI ML13193A1452013-07-12012 July 2013 Electronic Transmission, Draft Request for Additional Information Regarding Proposed Revision to Pressure and Temperature Limit Curves and Exemption Request for Initial Reference Temperature Values (TAC Nos. MF0425 & MF0426) ML13176A4702013-06-26026 June 2013 Request for Additional Information Regarding Overall Integrated Plan in Response to Order Number EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13177A3902013-06-26026 June 2013 Electronic Transmission, Draft Request for Additional Information Regarding Overall Integrated Plan in Response to Order Number EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13066A2442013-03-19019 March 2013 Request for Additional Information Regarding Fifth Inservice Test Interval Relief Request PR-01 Nuclear Services Closed Cooling Water Flow Measurement ML13066A1262013-03-0707 March 2013 Electronic Transmission, Draft Request for Additional Information Regarding Fifth Inservice Test Interval Relief Request PR-01 Nuclear Services Closed Cooling Water Flow Measurement ML13044A3212013-03-0505 March 2013 Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML13045A6432013-02-25025 February 2013 Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval ML13051A3852013-02-25025 February 2013 Request for Additional Information Regarding End-of-Interval Relief Request RR-12-01, Pressure Nozzle-to-Head Weld Exams ML13050A6362013-02-20020 February 2013 Draft RAI Memo ML13044A3122013-02-13013 February 2013 Electronic Transmission, Draft Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML13044A6652013-02-13013 February 2013 Electronic Transmission, Draft Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval ML12306A4812012-11-19019 November 2012 Request for Additional Information Regarding 2011 Steam Generator Tube Inspection Report ML12310A1752012-11-13013 November 2012 Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 2024-01-11
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Text
January 5, 2009 Mr. Michael P. Gallagher Vice President License Renewal Projects AmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THREE MILE ISLAND NUCLEAR STATION, UNIT 1, LICENSE RENEWAL APPLICATION, (TAC NO.
MD7701)
Dear Mr. Gallagher:
By letter dated January 8, 2008, AmerGen Energy Company, LLC (AmerGen) submitted an application pursuant to 10 Code of Federal Regulation Part 54 (10 CFR Part 54) to renew the operating license for Three Mile Island Nuclear Station, Unit 1 for review by the U.S. Nuclear Regulatory Commission (NRC or the staff).
By letter dated October 16, 2008 (ADAMS Accession No. ML082520614) the staff requested additional information. By letter dated November 12, 2008 (ADAMS Accession No.
ML083190038) you replied to the request.
Based on the review of your response, the staff has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Chris Wilson, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-2878 or e-mail Jay.Robinson@nrc.gov.
Sincerely,
\RA\
Jay Robinson, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
As stated cc w/encl: See next page
ML082520614) the staff requested additional information. By letter dated November 12, 2008 (ADAMS Accession No.
ML083190038) you replied to the request.
Based on the review of your response, the staff has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Chris Wilson, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-2878 or e-mail Jay.Robinson@nrc.gov.
Sincerely,
\RA\
Jay Robinson, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION: See next page ADAMS Accession No.: ML083510040 OFFICE LA:DLR DLR:RER1 PM:DLR:RPB1 BC:DLR:RPB1 NAME SFigueroa JDozier JRobinson DPelton DATE 12/31/08 1/5/09 1/5/09 1/5/09
Letter to M. Gallagher from J. Robinson dated January 5, 2009 DISTRIBUTION:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THREE MILE ISLAND NUCLEAR STATION, UNIT 1, LICENSE RENEWAL APPLICATION (TAC NO.
MD7701)
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr RidsNrrDlrRpb1 RidsNrrDlrRpb2 RdsNrrDlrRer1 RidsNrrDlrRer2 RidsNrrDlrRerb RidsOgcMailCenter
MModes, RI DKern JBrand RConte RBellamy PBamford
Three Mile Island Nuclear Station, Unit 1 cc:
Site Vice President - Three Mile Island Director Nuclear Station, Unit 1 Bureau of Radiation Protection AmerGen Energy Company, LLC Pennsylvania Department of P.O. Box 480 Environmental Protection Middletown, PA 17057 Rachel Carson State Office Building P.O. Box 8469 Senior Vice President - Operations, Mid- Harrisburg, PA 17105-8469 Atlantic AmerGen Energy Company, LLC Plant Manager - Three Mile Island Nuclear 200 Exelon Way, KSA 3-N Station, Unit 1 Kennett Square, PA 19348 AmerGen Energy Company, LLC P. O. Box 480 Vice President - Licensing and Regulatory Middletown, PA 17057 Affairs AmerGen Energy Company, LLC Regulatory Assurance Manager - Three 4300 Winfield Road Mile Island Nuclear Station, Unit 1 Warrenville, IL 60555 AmerGen Energy Company, LLC P.O. Box 480 Regional Administrator Middletown, PA 17057 Region I U.S. Nuclear Regulatory Commission Ronald Bellamy, Region I 475 Allendale Road U.S. Nuclear Regulatory Commission King of Prussia, PA 19406 475 Allendale Road King of Prussia, PA 19406 Chairman Board of County Commissioners Michael A. Schoppman of Dauphin County Framatome ANP Dauphin County Courthouse Suite 705 Harrisburg, PA 17120 1911 North Ft. Myer Drive Rosslyn, VA 22209 Chairman Board of Supervisors Dr. Judith Johnsrud of Londonderry Township National Energy Committee R.D. #1, Geyers Church Road Sierra Club Middletown, PA 17057 433 Orlando Avenue State College, PA 16803 Senior Resident Inspector (TMI-1)
U.S. Nuclear Regulatory Commission Eric Epstein P.O. Box 219 TMI Alert Middletown, PA 17057 4100 Hillsdale Road Harrisburg, PA 17112 Director - Licensing and Regulatory Affairs AmerGen Energy Company, LLC Correspondence Control Desk Correspondence Control AmerGen Energy Company, LLC P.O. Box 160 200 Exelon Way, KSA 1-N-1 Kennett Square, PA 19348 Kennett Square, PA 19348
Three Mile Island Nuclear Station, Unit 1 cc:
Manager Licensing - Three Mile Island Nuclear Station, Unit 1 Exelon Generation Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Charles G. Pardee Chief Nuclear Officer AmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA 19348 Associate General Counsel AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Chief Operating Officer (COO)
AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Frederick W. Polaski Manager License Renewal Exelon Nuclear 200 Exelon Way Kennett Square, PA 19348 Albert A. Fulvio License Renewal Senior Project Manager Exelon Nuclear 200 Exelon Way Kennett Square, PA 19348
REQUEST FOR ADDITIONAL INFORMATION (RAI)
THREE MILE ISLAND NUCLEAR STATION, UNIT - 1 LICENSE RENEWAL APPLICATION RAI#: AMR-GENERIC-2 LRA Section: 3.X.1 Tables, Associated Evaluation Paragraphs
Background:
In the Three Mile Island, Unit - 1, (TMI-1), License Renewal Application, section 3.X.1 tables, Not Applicable is listed in the discussion column for many line items (ie; lines 3.1.1-23 and 3.2.1-17). For many of the line items, a subsection of the LRA is referenced (ie; See Subsection 3.1.2.2.7, and See Subsection 3.2.2.2.9). In many cases, the referenced subsection does not provide a specific reason why the item is not applicable. (ie: Item Number 3.2.1-17 is not applicable to TMI-1. This component, material, environment, and aging effect/mechanism does not apply to Engineered Safety Features).
In AmerGen Energy Company, LLCs (the applicant) response to RAI-AMR-GENERIC-1 (ADAMS Accession No. ML083190038), the applicant indicated that Not Applicable has been used when the component, material and environment combination does not exist in the identified GALL system grouping and also when the component, material and environment combination does exist but the LRA Table 3.x.1 item was not used because a different Table 3.x.1 item was selected to manage the identified aging effect/mechanism.
Issue:
Based on the response to RAI-AMR-GENERIC-1, the staff cannot determine the specific reason why certain items are not applicable and therefore, cannot complete its evaluation. The two reasons cited in the response to RAI-AMR-GENERIC-1 are general reasons and not specific to each item.
Request:
For each of the LRA Table 3.x.1 items where Not Applicable is listed in the Discussion column, indicate the specific reason why the item is considered not applicable to TMI-1. For example, one reason may be that the component, material, environment combination does not exist at TMI-1. Items that are listed as Not Applicable due to reactor type (BWR vs. PWR) do not have to be listed.
If the component, material and environment does exist but the LRA Table 3.x.1 item was not used, indicate what other 3.x.1 item was selected to manage the identified aging effect/
mechanism.
RAI#: AMR-GENERIC-3
Background:
In AmerGens responses to RAIs 3.3.1.21-1, 3.3.1.32-1, 3.3.1-48-1, 3.3.2.2-1, and 3.3.2.2-3 (ADAMS Accession No. ML083190038), Electric Power Research Institute (EPRI) Report 1010639, "Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools", Revision 4, is used to justify elimination of aging mechanisms from evaluation.
Issue:
Only citing EPRI Report 1010639 as the basis to justify elimination of aging mechanisms from evaluation does not provide sufficient information to enable the staff to complete its evaluation.
Request:
Provide the following:
For RAIs 3.3.1.21-1 and 3.3.2.2-3, state the reasons why the loss of material due to fouling is not predicted in steel components in a lubricating oil environment.
For RAIs 3.3.1.32-1 and 3.3.2.2-1, state the reasons why pitting and crevice corrosion is not predicted for copper alloy with less than 15% zinc in a fuel oil environment.
For RAI 3.3.1-48-1, state the reasons why galvanic corrosion is not predicted for component, material, and environment combinations when the material subject to aging management review (AMR) is not in contact with a material of different electrochemical potential.
RAI# 3.1.1-2
Background:
In AmerGens response to RAI# 3.1.1-1 (ADAMS Accession No. ML083190038) it is stated that the ISI program includes examination of small bore piping welds and that under the RISI program, socket welds have been selected for VT-2 examination. The response further states that the RISI program includes small bore piping welds.
Issue:
Welds selected for inspection are based on RISI, however, it is not clear if welds specific to the reactor coolant system (RCS) and Core Flooding System will be subject to inspection.
Request:
Provide information indicating which small bore piping welds of the RCS and Core Flooding System receive volumetric or VT-2 inspection. Identify inspections and the schedule for welds in small bore piping where cracking has been discovered.
RAI#: 3.1.2.2.7-2 LRA Section: 3.1.2.2.7, Cracking due to Stress Corrosion Cracking, and AmerGen Response to RAI# 3.1.2.2.7-1
Background:
In AmerGens response to RAI 3.1.2.2.7-1 (ADAMS Accession No. ML083190038) it was stated that the stainless steel reactor vessel closure head flange leak detection line and the stainless steel bottom-mounted instrument guide tubes exist and are in scope for license renewal. The response also stated that the components are stainless steel with an external environment of Air in Borated Water Leakage and an internal environment of Reactor Coolant. The response also stated that the aging management review (AMR) results for these components are included in LRA Table 3.1.2-2 and are shown on pages 3.1-74 and 3.1-75 of the LRA.
Issue:
The Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, NUREG-1800, Rev. 1, (SRP-LR), Section 3.1.2.2.7, paragraph 1, states that cracking due to stress corrosion cracking (SCC) could occur in the stainless steel reactor vessel flange leak detection line and the bottom-mounted instrument guide tubes exposed to reactor coolant.
The GALL Report recommends further evaluation of a plant specific aging management program (AMP) to ensure that the aging effects are adequately managed.
The AMPs credited in the LRA to manage the aging effect of cracking due to SCC in the stainless steel reactor vessel flange leak detection line and the bottom-mounted instrument guide tubes are Water Chemistry and the ASME Section XI Inservice Inspection, Subsections IWB, IWC and IWD.
Request:
Explain how the aging effect of cracking due to SCC in the stainless steel reactor vessel closure head flange leak detection line and the stainless steel bottom-mounted instrument guide tubes will be detected by the ASME Section XI Inservice Inspection, Subsections IWB, IWC and IWD and what corrective actions would be taken if indications of cracking or leakage are found in these components.
RAI# B.2.1.20-2
Background:
The staff reviewed API Standard 1631 and noted that Section 10.6.2 provides a requirement to install cathodic protection if UT examination determines the wall thickness to be between 75%
and 85% of the original wall thickness.
Issue:
The staff noted that wall thicknesses between 75% and 85% of the original wall thickness indicates active loss of material and measures should be implemented to mitigate corrosion.
Request:
Confirm that cathodic protection will be implemented if wall thicknesses between 75% and 85%
of the original wall thickness are detected, or indicate what measures will be taken to mitigate corrosion if cathodic protection will not be implemented.