Letter Sequence Response to RAI |
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EPID:L-2019-LLA-0216, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (Approved, Closed) |
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MONTHYEARML19182A1042019-07-0101 July 2019 Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E Project stage: Request SBK-L-19104, License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements2019-10-0303 October 2019 License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements Project stage: Request ML19282B8322019-10-22022 October 2019 Cover Letter with Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opp. for a Hearing Project stage: Acceptance Review ML19282C6142019-10-22022 October 2019 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing Project stage: Acceptance Review SBK-L-19120, Response to Request for Additional Information Related to Seabrook Inverter Amendment2019-10-30030 October 2019 Response to Request for Additional Information Related to Seabrook Inverter Amendment Project stage: Response to RAI ML19326C4802019-12-0505 December 2019 Issuance of Amendment No. 163 One-Time Change to the Onsite Power Distribution Requirements Project stage: Approval ML19344C1152019-12-10010 December 2019 Response to Request for Additional Information (RAI) Regarding Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E Project stage: Response to RAI 2019-10-30
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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24242A3032024-09-0909 September 2024 Letter - Three Mile Island Station, Unit 2, Issuance of Amendment No. 68, Historic and Cultural Resources IR 05000320/20240012024-08-28028 August 2024 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report Nos. 05000320/2024001 and 05000320/2024002 ML24240A2222024-08-27027 August 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 6 ML24220A2742024-08-15015 August 2024 Request for Additional Information Clarification Call Regarding Three Mile Island Station, Unit 2, Amended Post-Shutdown Decommissioning Activities Report, Rev. 6 ML24135A3292024-08-0909 August 2024 Amendment No 68, Historic and Cultural Resources Cover Letter IR 07200077/20240012024-06-18018 June 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 07200077/2024001 ML24135A1972024-06-13013 June 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0091 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24157A3672024-06-13013 June 2024 Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24120A3242024-05-24024 May 2024 TMI-2 Email to Fws RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24121A2472024-04-29029 April 2024 and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24120A2552024-04-29029 April 2024 Annual Radiological Environmental Operating Report ML24113A0212024-04-18018 April 2024 (TMI-2), Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 ML24065A0042024-03-28028 March 2024 Submittal of 2023 Aircraft Movement Data Annual Report ML24088A0122024-03-28028 March 2024 Notification of Amended Post-Shutdown Decommissioning Activities Report (PSDAR) in Accordance with 10 CFR 50.82(a)(7), Revision 6 ML24092A0012024-03-28028 March 2024 (TMI-2), Decommissioning Trust Fund Annual Report ML24085A2152024-03-25025 March 2024 (TMI-2) - Annual Notification of Property Insurance Coverage RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24052A0602024-03-20020 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0061 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24074A3922024-03-14014 March 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML24075A0062024-03-14014 March 2024 List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML24073A2312024-03-13013 March 2024 and Three Mile Island Nuclear Station, Unit 2 - Management Change ML24044A0092024-02-12012 February 2024 License Amendment Request – Three Mile Island, Unit 2, Historic and Cultural Resources Review, Response to Request for Additional Information IR 05000320/20230042024-02-0707 February 2024 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023004 ML24038A0222024-02-0505 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 ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 IR 05000289/20230052023-08-14014 August 2023 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005 ML23216A1772023-08-14014 August 2023 Consultation Letter to Rebecca Countess for TMI-2 ML23216A1782023-08-14014 August 2023 Consultation Letter to Steve Letavic for TMI-2 ML23216A1732023-08-14014 August 2023 Consultation Letter to Christine Turner for TMI-2 ML23216A1752023-08-14014 August 2023 Consultation Letter to Joanna Cain for TMI-2 ML23216A1742023-08-14014 August 2023 Consultation Letter to David Morrison 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 ML23138A0662023-05-17017 May 2023 TMI-2 NHPA Section 106 Shpo Letter to NRC 5-17-23 2024-09-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24240A2222024-08-27027 August 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 6 ML24228A1922024-07-29029 July 2024 Request for Additional Information Response Due Date Extension E-Mail String ML24074A3922024-03-14014 March 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML24044A0092024-02-12012 February 2024 License Amendment Request – Three Mile Island, Unit 2, Historic and Cultural Resources Review, Response to Request for Additional Information ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23221A1402023-08-0808 August 2023 (TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 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 ML23121A2492023-05-0101 May 2023 License Amendment Request, Historic and Cultural Resources Review, Response to Request for Additional Information ML23025A0392023-01-20020 January 2023 License Amendment Request - Three Mile Island, Unit 2, Decommissioning Technical Specifications, Response to Request for Additional Information Regarding Historical and Cultural Resources ML22307A0822022-10-31031 October 2022 (TMl-2), License Amendment Request, Decommissioning Technical Specifications, Supplement to Response to Request for Additional Information ML22276A0242022-09-29029 September 2022 (TMl-2), License Amendment Request - Decommissioning Technical Specifications, Response to Request for Additional Information ML22126A1402022-05-0606 May 2022 Response to Request for Additional Information - License Amendment Request - Revise Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan ML22102A3072022-03-31031 March 2022 Attachment - Response to 18 March Clarification Request - 31 March 2022 ML22010A0662022-01-0505 January 2022 Supplemental Information to License Amendment Request, Decommissioning Technical Specifications 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 ML21036A0242021-01-28028 January 2021 EP-TM-1001, Revision 0, Three Mile Island Permanently Defueled Emergency Plan (PDEP) & EP-TM-1001, Addendum 1, Rev 0, Three Mile Island Station Permanently Defueled Emergency Action Levels and Technical Bases TMI-20-026, Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation2020-09-15015 September 2020 Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation TMI-20-021, Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative2020-07-0808 July 2020 Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative ML19344C1152019-12-10010 December 2019 Response to Request for Additional Information (RAI) Regarding Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E 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 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 ML19093A9502019-04-0101 April 2019 Submittal of Reponses to NRC Request for Clarification of Response to Request for Additional Information for the Technical Review of the Three Mile Island Unit 2 Independent Spent Fuel Storage Installation License Renewal Application 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 TMI-18-088, Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report2018-08-21021 August 2018 Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report ML18225A1802018-08-13013 August 2018 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request - Proposed Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML18108A2872018-04-18018 April 2018 Submittal of Response to Request for Additional Information Regarding Inspection Plan for Reactor Internals Action Item 7 ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 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 RS-16-179, High Frequency Supplement to Seismic Hazard Screening Report, Response to Nrg Request for Information Pursuant to 1 O CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights.2016-10-28028 October 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to Nrg Request for Information Pursuant to 1 O CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights. TMI-16-091, Response to Draft Request for Additional Information Regarding the Submittal of Relief Request RR-16-01 Concerning the Use of ASME Code Case N-722-22016-09-0808 September 2016 Response to Draft Request for Additional Information Regarding the Submittal of Relief Request RR-16-01 Concerning the Use of ASME Code Case N-722-2 RS-16-126, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 1O CFR 50.54(f) Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 1O CFR 50.54(f) Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML15237A4172015-08-25025 August 2015 Response to Request for Additional Information - License Amendment Request Involving Temporary Restoration of Borated Water Storage Tank Cleanup and Recirculation Operation RS-15-147, Response to March 12, 2012, Request for Information, Per 10CFR50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3..2015-06-29029 June 2015 Response to March 12, 2012, Request for Information, Per 10CFR50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3.. 2024-08-27
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Michael P. Gallagher Exelon Nuclear Exelon Generation . Vice President License Renewal and Decomm1ss1on1ng 200 Exelon Way Kennett Square, PA 19348 610 765 5958 Office 610 765 5658 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50.12 10 CFR 50.47 10 CFR 50, Appendix E TMl-19-166 December 10, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289 Three Mile Island Nuclear Station, Unit 2 Possession Only License No. DPR-73 NRC Docket No. 50-320
Subject:
Response to Request for Additional Information (RAI) Regarding Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E
References:
- 1) Letter from Michael P. Gallagher, (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission - "Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E," dated July 1, 2019(ML19182A104)
- 2) Letter from J. Bradley Fewell (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, "Certification of Permanent Cessation of Power Operations for Three Mile Island Nuclear Station, Unit 1," dated June 20, 2017 (Accession No. ML17171A151)
- 3) Letter from Michael P. Gallagher (Exelon Generation Company, LLC),
"Certification of Permanent Removal of Fuel from the Reactor Vessel for Three Mile Island Nuclear Station, Unit 1," dated September 26, 2019 (Accession No. ML19269E480)
- 4) U.S. Nuclear Regulatory Commission Electronic Mail Request to Leslie E. Holden and Robert R. Brady - "DRAFT RAJ for EP and EAL Amendment/Exemption," dated November 5, 2019
U.S. Nuclear Regulatory Commission TMI Request for EP Exemption RAI Response Docket Nos. 50-289 and 50-320 December 10, 2019 Page 2
- 5) U.S. Nuclear Regulatory Commission Electronic Mail Request to Leslie E. Holden and Robert R. Brady - "Request for Additional Information Related to TMl-1 Request for Exemption from Portions of 10 CFR 50.47 and Part 50 Appendix E (L-2019-LLA-0216)," dated November 15, 2019 (ML19319B208)
By letter dated July 1, 2019 (Reference 1), Exelon Generation Company, LLC (Exelon) requested an exemption pursuant to the requirements of 10 CFR 50.12 from specific emergency planning requirements in 10 CFR 50.47and10 CFR Part 50, Appendix E forthe Three Mile Island Nuclear Station (TMI) based on the permanent cessation of power operations and removal of fuel from the reactor vessel on TMI, Unit 1 (TMl-1 ). Exelon has docketed the certifications for permanent cessation of operations and permanent removal of fuel from the reactor vessel (References 2 and 3), therefore in accordance with 10 CFR 50.82(a) the 10 CFR Part 50 license for TMl-1 no longer authorizes operation of the reactor or emplacement or retention of fuel into the reactor vessel.
Subsequently, in an electronic mail request dated November 5, 2019 (Reference 4) the U.S.
Nuclear Regulatory Commission (NRC) issued draft Requests for Additional Information (RAls) indicating that it had reviewed the information submitted in the Reference 1 letter and that additional clarifying information was needed to support its continued review. The draft RAI in Reference 4 was further discussed during teleconferences between Exelon and NRC representatives held on November 14, 2019. As a result of the discussions, it was determined that no modifications to the draft RAI was needed and the NRC subsequently issued formal RAI on November 15, 2019 (Reference 5) and requested a response 30 days from the clarification call on November 14, 2019.
Exelon's responses to the NRC's RAls are provided in Attachment to this letter.
Exelon has reviewed the information supporting a finding of No Significant Hazards Consideration and the Environmental Consideration provided to the NRC in Reference 1. The additional information provided in this submittal does not affect the previously stated bases in Reference 1 for concluding that the proposed exemption does not involve a significant hazards consideration.
In addition, the information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed exemption.
There are no regulatory commitments contained in this submittal.
U.S. Nuclear Regulatory Commission TMI Request for EP Exemption RAI Response Docket Nos. 50-289 and 50-320 December 10, 2019 Page 3 If you have any questions concerning this submittal, please contact Leslie Holden at (630) 657-2524.
Respectfully,
~{? I Michael P. Gallagher Vice President, License Renewal & Decommissioning Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information Regarding Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E cc: Regional Administrator - NRC Region I NRC Project Manager, NRR - TMl-1 Director, Bureau of Radiation Protection - PA Department of Environmental Resources
ATTACHMENT Response to Request for Additional Information Regarding Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E
Attachment TMI Request for EP Exemption RAI Response Docket Nos. 50-289 and 50-320 Page A-1 of A-2 NRC REQUEST FOR ADDITIONAL INFORMATION (RAil 10 CFR 50 provides regulatory requirements for emergency planning for operating reactors to ensure protection of the health and safety of the public. By letter dated July 1, 2019, pursuant to 10 CFR 50.12 "Specific Exemptions," Exelon requested exemptions from certain emergency planning regulations in 10 CFR 50.47 and 10 CFR Part 50, Appendix E, for the permanently shut down Three Mile Island Nuclear Station, Unit 1 (TMl-1).
NUREG-1738, "Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants," (ADAMS Accession No. ML010430066) describes a modeling approach of a typical decommissioning plant with design assumptions and industry commitments. The NRC staff's analyses and conclusions apply to decommissioning facilities with spent fuel pools (SFPs) that meet the design and operational characteristics assumed in the risk analysis. These characteristics are identified in the study as industry decommissioning commitments (IDCs) and staff decommissioning assumptions (SDAs). In the exemption request, Exelon evaluated the IDCs and SDAs contained in NUREG-1738 and submitted Tables 4 and 5 to identify how the TMl-1 SFP meets or compares with each of these IDCs and SDAs.
A characteristic of concern documented in IDCs and SDAs is the potential for loss of SFP inventory and uncovering of fuel. The following is related to mitigation of draining or inventory loss:
SDA #4 states, "Licensee determines that there are no drain paths in the SFP that could lower the pool level (by draining, suction, or pumping) more than 15 feet below the normal pool operating level and that licensee must initiate recovery using offsite sources."
The TMl-1 exemption request provides comparison (Section 5.5 and Tables 4 and 5 of ) to the NUREG-1738 IDCs and the SDAs. The configuration of SFPs in the TMI Fuel Handling Building consists of two connected pools, Pool A (1494 SFP storage locations) and Pool B (496 SFP storage locations). A cask loading pit is located within Pool B.
The TMl-1 SFP is contained in the Fuel Handling Building and is connected to the Fuel Transfer Canal via two fuel transfer tubes. As indicated in Section 9.4.6, "Leakage Considerations" of Updated Final Safety Analysis Report (FSAR), a locked closed gate valve (on the Fuel Handling Building side) and blind flange (on the Reactor Building side) are used to isolate the fuel transfer tubes when not actively performing refueling. The transfer tube passes through the primary containment wall and through an exterior wall of the fuel handling building.
The licensee discussion in the exemption request related to leakage prevention devices are limited to locked closed gate valves and blank flanges on the reactor building side. As discussed in the associated license amendment request, also submitted on July 1, 2019, the top of active fuel is approximated at 320 ft. Licensee documentation (Drawing IE-154-02-009, Revision 9, General Arrangement Fuel Handling Building) shows the transfer tubes penetrating the pool wall below the top of stored fuel (Transfer Tube CL at EL 314'-6" and pool floor at 305'-0").
Since the fuel transfer tube penetration has the capability of inadvertent draining below top of fuel, provide additional details regarding administrative control of the pool-side gate valves and
Attachment TMI Request for EP Exemption RAI Response Docket Nos. 50-289 and 50-320 Page A-2 of A-2 describe any design features that could prevent or mitigate the consequences of opening of the gate valve when the reactor refueling cavity is not flooded.
EXELON'S RESPONSE TO RAI TMl-1 has two transfer tubes that connect the Spent Fuel Pool (SFP) to the Fuel Transfer Canal in the Reactor Building. The design provides double isolation of each transfer tube to prevent inadvertent draining of the Spent Fuel Pool. On the SFP side, each transfer tube is isolated with a locked closed manual gate valve (FH-V-1A/B). On the Reactor Building side the transfer tube is isolated with a blank flange. Since 50.82(a)(2) no longer permits operation of TMl-1 or emplacement of fuel in the reactor vessel, there is no longer a need to transfer fuel between the reactor and the SFP, therefore there is no need to manipulate FH-V-1A/B or remove the blank flange.
FH-V-1A/B will remain locked closed under administrative control per OP-M-108-103, "Locked Equipment Program." The blank flange on the Reactor Building side of the fuel transfer tube, is bolted in place and not readily removable.