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| | issue date = 03/16/2017 | | | issue date = 03/16/2017 |
| | title = March 7, 2017, Summary of Public Pre-Submittal Teleconference Meeting with Exelon Generation Company, LLC to Discuss Proposed License Amendment Request Regarding Residual Heat Removal System Operability in Mode 3 at Clinton Power Station, U | | | title = March 7, 2017, Summary of Public Pre-Submittal Teleconference Meeting with Exelon Generation Company, LLC to Discuss Proposed License Amendment Request Regarding Residual Heat Removal System Operability in Mode 3 at Clinton Power Station, U |
| | author name = Rankin J K | | | author name = Rankin J |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000461 | | | docket = 05000461 |
| | license number = NPF-062 | | | license number = NPF-062 |
| | contact person = Rankin J K | | | contact person = Rankin J |
| | case reference number = CAC MF9152 | | | case reference number = CAC MF9152 |
| | document type = Meeting Briefing Package/Handouts, Meeting Summary, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Meeting Summary, Slides and Viewgraphs |
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| {{#Wiki_filter:LICENSEE: FACILITY: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 16, 2017 LICENSEE : Exelon Generation Company, LLC FACILITY: Clinton Power Station , Unit No. 1 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 16, 2017 Exelon Generation Company, LLC Clinton Power Station, Unit No. 1 SUMMARY OF MARCH 7, 2017, PUBLIC PRE-SUBMITTAL TELECONFERENCE MEETING WITH EXELON GENERAION COMPANY, LLC TO DISCUSS PROPOSED LICENSE AMENDMENT REQUEST REGARDING RESIDUAL HEAT REMOVAL SYSTEM OPERBILITY IN MODE 3 AT CLINTON POWER STATION, UNIT 1 (CAC NO. MF9152) On March 7, 2017, a Category 1 public teleconference meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Exelon Generation Company, LLC (Exelon or the licensee). The purpose of the meeting was for Exelon to discuss with the NRC a proposed license amendment request (LAR) regarding residual heat removal (RHR) system operability in Mode 3 at Clinton Power Station, Unit No. 1 (Clinton). The meeting notice and agenda, dated February 21, 2017, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 17052A 154. A list of attendees is enclosed. The licensee's presentation is available at ADAMS Accession No. ML 17067 A372. The licensee provided background information which includes a green finding and associated non-cited violation issued by the NRC related to the RHR system. Specifically, RHR cannot be realigned from shutdown cooling mode of operations to provide the technical specification (TS) required functions of the emergency core cooling system (ECCS) when the reactor coolant temperature is greater than 150 degrees Farenheit. In addition, the licensee provided information on the Clinton ECCS design and TS history. The licensee proposes to submit a LAR to align the TS requirements with the design capabilities. The licensee expects their LAR to be similar to a LAR submitted for LaSalle County Station, Units 1 and 2 (LaSalle), which resolved a similar issue. The NRC approval of the LaSalle LAR is available at ADAMS Accession No. ML 15244B410. The licensee expects to submit the LAR for Clinton on or before May 5, 2017. There were no public comments made at this meeting and no public meeting feedback forms were received.
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| -2 -Please direct any inquiries to me at 301-415-1530, or by email at Jennivine.Rankin@nrc.gov. Docket No.: 50-461
| | ==SUMMARY== |
| | OF MARCH 7, 2017, PUBLIC PRE-SUBMITTAL TELECONFERENCE MEETING WITH EXELON GENERAION COMPANY, LLC TO DISCUSS PROPOSED LICENSE AMENDMENT REQUEST REGARDING RESIDUAL HEAT REMOVAL SYSTEM OPERBILITY IN MODE 3 AT CLINTON POWER STATION, UNIT 1 (CAC NO. MF9152) |
| | On March 7, 2017, a Category 1 public teleconference meeting was held between the U.S. |
| | Nuclear Regulatory Commission (NRC) and representatives of Exelon Generation Company, LLC (Exelon or the licensee) . The purpose of the meeting was for Exelon to discuss with the NRC a proposed license amendment request (LAR) regarding residual heat removal (RHR) system operability in Mode 3 at Clinton Power Station, Unit No. 1 (Clinton) . The meeting notice and agenda , dated February 21 , 2017, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML17052A154. A list of attendees is enclosed . |
| | The licensee's presentation is available at ADAMS Accession No. ML17067A372 . |
| | The licensee provided background information which includes a green finding and associated non-cited violation issued by the NRC related to the RHR system. Specifically, RHR cannot be realigned from shutdown cooling mode of operations to provide the technical specification (TS) required functions of the emergency core cooling system (ECCS) when the reactor coolant temperature is greater than 150 degrees Farenheit. In addition, the licensee provided information on the Clinton ECCS design and TS history. |
| | The licensee proposes to submit a LAR to align the TS requirements with the design capabilities . The licensee expects their LAR to be similar to a LAR submitted for LaSalle County Station, Units 1 and 2 (LaSalle) , which resolved a similar issue. The NRC approval of the LaSalle LAR is available at ADAMS Accession No. ML15244B410. The licensee expects to submit the LAR for Clinton on or before May 5, 2017. |
| | There were no public comments made at this meeting and no public meeting feedback forms were received . |
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| | Please direct any inquiries to me at 301-415-1530, or by email at Jennivine.Rankin@nrc.gov. |
| | Sincerely, J nivine K. Rankin , Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-461 |
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| ==Enclosure:== | | ==Enclosure:== |
| List of Attendees cc w/encl: Distribution via Listserv Sincerely, J nivine K. Rankin, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
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| ==SUBJECT:==
| | List of Attendees cc w/encl : Distribution via Listserv |
| SUMMARY OF MARCH 7, 2017, PUBLIC PRE-SUBMITTAL TELECONFERENCE MEETING WITH EXELON GENERAION COMPANY, LLC TO DISCUSS PROPOSED LICENSE AMENDMENT REQUEST REGARDING RESIDUAL HEAT REMOVAL SYSTEM OPERBILITY IN MODE 3 AT CLINTON POWER STATION, UNIT 1 (CAC NO. MF9152) DATED MARCH 16, 2017 DISTRIBUTION: PUBLIC LPL3 r/f RidsACRS_MailCTR Resource RidsNrrDorlLpl3 Resource RidsOpaMail Resource RidsNrrPMClinton Resource RidsNrrLASRohrer Resource ADAMS Accession Nos.: Meeting Notice: ML 17052A 154 Meeting Summary: ML 17067 A372 Handouts: ML 17067 A362 OFFICE NRR/DORL/LPL3/PM NAME JRankin DATE 03/09/17 NRR/DORL/LPL3/LA SRohrer 03/09/17 RidsRgn3MailCenter Resource RidsNrrDssStsb Resouce RidsNrrDssSrxb Resource MRazzaque, NRR CTilton, NRR KStoedter, RI II NRR/DORL/LPL3/BC (A) NRR/DORL/LPL3/PM KGreen JRankin 03/16/17 03/16/17 OFFICIAL RECORD COPY LIST OF ATTENDEES MARCH 7, 2017, MEETING WITH EXELON GENERATION COMPANY, LLC RESIDUAL HEAT REMOVAL SYSTEM OPERABILITY IN MODE 3 CLINTON POWER STATION, UNIT NO. 1 Name Afffiliation Eric Oesterle U.S. Nuclear Regulatory Commission (NRC)/Office of Nuclear Reactor Regulation (NRR) Muhammad NRC/NRR Razzaque Caroline Tilton NRC/NRR Jennie Rankin NRC/NRR John Schrage Exelon Generation Company, LLC (Exelon) Patrick Simpson Exelon Dale Shelton Exelon Jonathon Grim Exelon John Pfabe Exelon Enclosure Clinton Power Station License Amendment Request Mode 3 Applicability -LPCl/SDC NRC Pre-Submittal Teleconference March 7, 2017 Exelon Agenda *Objective of Meeting *Background and Need for Amendment *Schedule 1 :"Exelon.
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| | Meeting Notice: ML17052A154 Meeting Summary: ML17067A372 Handouts: ML17067A362 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC (A) NRR/DORL/LPL3/PM NAME JRankin SRohrer KGreen JRankin DATE 03/09/17 03/09/17 03/16/17 03/16/17 LIST OF ATTENDEES MARCH 7, 2017, MEETING WITH EXELON GENERATION COMPANY, LLC RESIDUAL HEAT REMOVAL SYSTEM OPERABILITY IN MODE 3 CLINTON POWER STATION, UNIT NO. 1 Name Afffiliation U.S. Nuclear Regulatory Commission (NRC)/Office of Nuclear Eric Oesterle Reactor Regulation (NRR) |
| | Muhammad NRC/NRR Razzaque Caroline Tilton NRC/NRR Jennie Rankin NRC/NRR John Schrage Exelon Generation Company, LLC (Exelon) |
| | Patrick Simpson Exelon Dale Shelton Exelon Jonathon Grim Exelon John Pfabe Exelon Enclosure |
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| | Clinton Power Station License Amendment Request Mode 3 Applicability - LPCl/SDC NRC Pre-Submittal Teleconference March 7, 2017 Exelon |
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| | Agenda |
| | *Objective of Meeting |
| | *Background and Need for Amendment |
| | *Schedule 1 : " Exelon. |
| | |
| Objective | | Objective |
| * Present information to the NRC staff describing a proposed License Amendment Request (LAR) for Clinton Power Station (CPS) to resolve a CDBI violation concerning incapability of the residual heat removal (RHR) design to support Technical Specification (TS) operability requirements. | | * Present information to the NRC staff describing a proposed License Amendment Request (LAR) for Clinton Power Station (CPS) to resolve a CDBI violation concerning incapability of the residual heat removal (RHR) design to support Technical Specification (TS) operability requirements. |
| * Obtain feedback from the NRC staff on the proposed LAR and gain an understanding of the NRC staff's expectations for the content of a high quality submittal. | | * Obtain feedback from the NRC staff on the proposed LAR and gain an understanding of the NRC staff's expectations for the content of a high quality submittal. |
| * Answer any questions from the NRC staff regarding the proposed LAR. 2 Background 3 December 2016 NRC CDBI Inspection | | * Answer any questions from the NRC staff regarding the proposed LAR. |
| | 2 ~ Exelon. |
| | |
| | === |
| | Background=== |
| | December 2016 NRC CDBI Inspection |
| * Green finding and associated Non-cited Violation (NCV) for failure to promptly identify that the incapability of the RHR design to support TS operability requirements was a condition adverse to quality. | | * Green finding and associated Non-cited Violation (NCV) for failure to promptly identify that the incapability of the RHR design to support TS operability requirements was a condition adverse to quality. |
| * Specifically, when reactor coolant temperature is greater than 150° F, RHR cannot be realigned from SOC mode of operations to provide the TS required functions of the emergency core cooling system. | | * Specifically, when reactor coolant temperature is greater than 150° F, RHR cannot be realigned from SOC mode of operations to provide the TS required functions of the emergency core cooling system. |
| * CPS captured this issue in the Corrective Action Program (CAP) both prior to, and subsequent to the inspection. The planned corrective action, as documented in NRC Inspection Report 05000461/12016009, was to submit an LAR to align TS requirements with the design capabilities. | | * CPS captured this issue in the Corrective Action Program (CAP) both prior to, and subsequent to the inspection. The planned corrective action, as documented in NRC Inspection Report 05000461/12016009, was to submit an LAR to align TS requirements with the design capabilities. |
| Background {cont.) 4 CPS Design | | 3 ~ Exelon. |
| * TS 3.5.1(1) requires all low pressure ECCS injection/spray systems to be OPERABLE in Modes 1, 2, and 3. | | |
| | Background {cont.) |
| | CPS Design |
| | * TS 3.5.1( 1 ) requires all low pressure ECCS injection/spray systems to be OPERABLE in Modes 1, 2, and 3. |
| * By design, the suppression pool suction valve on the ECCS Loop that is supporting SOC operations must be shut, otherwise the reactor coolant would drain to the suppression pool. The suppression pool suction valve does not automatically realign on a LPCI signal. | | * By design, the suppression pool suction valve on the ECCS Loop that is supporting SOC operations must be shut, otherwise the reactor coolant would drain to the suppression pool. The suppression pool suction valve does not automatically realign on a LPCI signal. |
| * In addition, the suppression pool suction valve is not capable of opening for manual realignment, due to both water hammer and pressure locking/thermal binding concerns which have not been analyzed above 150 ° F. (1) TS 3.5.1, ECCS -Operating ;iF Exelon. | | * In addition, the suppression pool suction valve is not capable of opening for manual realignment, due to both water hammer and pressure locking/thermal binding concerns which have not been analyzed above 150 ° F. |
| Background (cont.) TS History | | (1) TS 3.5.1, ECCS - Operating 4 ;iF Exelon. |
| * Prior to implementing NUREG-1434 Improved Tech Specs (ITS) in 1994, the CPS TS 3.5.1 recognized the required LPCI inoperability, and annotated Mode 3 applicability with a Note that stated: One LPCI subsystem of the RHR system may be aligned in the shutdown cooling mode when reactor vessel pressure is less than the LPCI cut-in permissive set point. | | |
| * ITS did not include this site-specific Mode 3 note, and therefore it was removed in the CPS ITS conversion. Instead, ITS provided a new note in the Surveillance Requirements for TS 3.5.1, and a similar note in TS 3.5.2, TS 3.6.1. 7, TS 3.6.1.9, and TS 3.6.2.3(2): 5 Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor vessel pressure less than the residual heat removal cut-in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable. (2) TS 3.5.2, ECCS -Shutdown; TS 3.6.1.7, Residual Heat Removal (RHR) Containment Spray System; TS 3.6.1.9, Feedwater Leakage Control System (FWLCS); and TS 3.6.2.3, Residual Heat Removal (RHR) Suppression Pool Cooling 411F Exelon. | | Background (cont.) |
| Background (cont.) TS History {cont.) | | TS History |
| | * Prior to implementing NUREG-1434 Improved Tech Specs (ITS) in 1994, the CPS TS 3.5.1 recognized the required LPCI inoperability, and annotated Mode 3 applicability with a Note that stated: |
| | One LPCI subsystem of the RHR system may be aligned in the shutdown cooling mode when reactor vessel pressure is less than the LPCI cut-in permissive set point. |
| | * ITS did not include this site-specific Mode 3 note, and therefore it was removed in the CPS ITS conversion. Instead, ITS provided a new note in the Surveillance Requirements for TS 3.5.1, and a similar note in TS 3.5.2, TS 3.6.1. 7, TS 3.6.1.9, and TS 3.6.2.3( 2 ): |
| | Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor vessel pressure less than the residual heat removal cut-in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable. |
| | (2) TS 3.5.2, ECCS - Shutdown; TS 3.6.1.7, Residual Heat Removal (RHR) Containment Spray System; TS 3.6.1.9, Feedwater Leakage Control System (FWLCS); and TS 3.6.2.3, Residual Heat Removal (RHR) |
| | Suppression Pool Cooling 5 411F Exelon. |
| | |
| | Background (cont.) |
| | TS History {cont.) |
| * CPS implemented the new TS 3.5.1, TS 3.5.2, TS 3.6.1.7, TS 3.6.1.9, and TS 3.6.2.3 with the same interpretation as the pre-ITS TSs. That is, the station considered the new note to be an allowance to consider LPCI operable, if capable of being realigned. | | * CPS implemented the new TS 3.5.1, TS 3.5.2, TS 3.6.1.7, TS 3.6.1.9, and TS 3.6.2.3 with the same interpretation as the pre-ITS TSs. That is, the station considered the new note to be an allowance to consider LPCI operable, if capable of being realigned. |
| * However, since the suppression pool suction valve is not capable of opening for manual realignment (i.e., as previously discussed), CPS is not able to implement the ITS Note, and therefore, declares LPCI inoperable during decay heat removal in Mode 3 with reactor pressure than the cut-in permissive. | | * However, since the suppression pool suction valve is not capable of opening for manual realignment (i.e., as previously discussed), CPS is not able to implement the ITS Note, and therefore, declares LPCI inoperable during decay heat removal in Mode 3 with reactor pressure l~ss than the cut-in permissive. |
| * The current NRC interpretation of the ITS LCO and associated Note is that the systems are required to be OPERABLE, and failure to implement the Note 6 (i.e., declaring LPCI inoperable) constitutes entry into the ACTIONS for operational convenience. 4!F Exelon. | | * The current NRC interpretation of the ITS LCO and associated Note is that the systems are required to be OPERABLE, and failure to implement the Note (i.e., declaring LPCI inoperable) constitutes entry into the ACTIONS for operational convenience. |
| | 6 4!F Exelon. |
| | |
| Proposed Resolution | | Proposed Resolution |
| * The NRC issued a similar Green Finding and associated NCV to LaSalle County Station (LSCS) in 2012. In response to that Finding/NCV, LSCS submitted, and the NRC approved an LAR in October 2015 that deleted this Note [ML15244B410]. | | * The NRC issued a similar Green Finding and associated NCV to LaSalle County Station (LSCS) in 2012. In response to that Finding/NCV, LSCS submitted, and the NRC approved an LAR in October 2015 that deleted this Note [ML15244B410]. |
| * The proposed change will delete the ITS Note from CPS TS 3.5.1, TS 3.5.2, TS 3.6.1.7, TS 3.6.1.9, and TS 3.6.2.3. | | * The proposed change will delete the ITS Note from CPS TS 3.5.1, TS 3.5.2, TS 3.6.1.7, TS 3.6.1.9, and TS 3.6.2.3. |
| * The proposed CPS TS change will also reinstate the pre-ITS Note to the Applicability for TS 3.5.1, TS 3.6.1.7, TS 3.6.1.9, and TS 3.6.2.3. 7 One Low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut-in permissive pressure in MODE 3. | | * The proposed CPS TS change will also reinstate the pre-ITS Note to the Applicability for TS 3.5.1, TS 3.6.1.7, TS 3.6.1.9, and TS 3.6.2.3. |
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| | One Low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut-in permissive pressure in MODE 3. |
| * 00
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Letter Sequence Meeting |
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MONTHYEARML17067A3622017-03-0707 March 2017 License Amendment Request; Mode 3 Applicability - Lpci/Sdc; NRC Pre-Submittal Teleconference - March 7, 2017 Project stage: Meeting ML17067A3722017-03-16016 March 2017 March 7, 2017, Summary of Public Pre-Submittal Teleconference Meeting with Exelon Generation Company, LLC to Discuss Proposed License Amendment Request Regarding Residual Heat Removal System Operability in Mode 3 at Clinton Power Station, U Project stage: Meeting 2017-03-16
[Table View] |
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24127A0952024-05-0606 May 2024 License Renewal Public Scoping Meeting May 2024 ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23172A2092023-06-28028 June 2023 LRA - NRC Pre-Submittal Meeting Slides ML23172A2102023-06-28028 June 2023 CPS Lr Pre-Submittal Meeting Presentation ML23145A1342023-06-14014 June 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting - Constellation Slides ML23165A0162023-06-14014 June 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting - NRC Slides ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1582021-07-13013 July 2021 and Lasalle Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML21021A0652021-01-21021 January 2021 NRC Pre-Application Meeting - Clinton One-Time Extension of the Containment Type a Leak Rate Test Frequency (Meeting Handout) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8662020-08-25025 August 2020 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas U-604453, Regulatory Conference Information2018-11-19019 November 2018 Regulatory Conference Information ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17067A3722017-03-16016 March 2017 March 7, 2017, Summary of Public Pre-Submittal Teleconference Meeting with Exelon Generation Company, LLC to Discuss Proposed License Amendment Request Regarding Residual Heat Removal System Operability in Mode 3 at Clinton Power Station, U ML17067A3622017-03-0707 March 2017 License Amendment Request; Mode 3 Applicability - Lpci/Sdc; NRC Pre-Submittal Teleconference - March 7, 2017 ML16314E4812016-11-14014 November 2016 Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016 ML16189A4332016-07-12012 July 2016 July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15342A3542015-12-0808 December 2015 License Amendment Request Extension of Secondary Containment - NRC Pre- Application Meeting December 9, 2015 ML15173A3812015-06-19019 June 2015 Regulatory Conference Supplemental Information ML14223A5742014-08-11011 August 2014 8/7/14 Clinton Power Station Annual Assessment Meeting Licensee Slides ML14220A2492014-08-0707 August 2014 8/7/2014 NRC Slides of Clinton Power Station Annual Assessment Meeting Cy 2013 ML14114A7402014-04-0909 April 2014 Application of GE Hitachi Simplified Stability Solution GS3 Pre-Submittal Presentation ML13184A3152013-07-0202 July 2013 EOC Public Meeting Presentation July 2, 2013 ML12111A1282012-04-19019 April 2012 End-of-Cycle Performance Assessment Meeting Presentation Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1111905212011-04-28028 April 2011 Clinton Power Station Cy 2010 End-Of-Cycle Open House Presentation ML1111905312011-04-28028 April 2011 Clinton Power Station Cy 2010 End-of-Cycle Open House Presentation (Short) ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes ML0914003322009-05-11011 May 2009 Slides Presented at the Clinton 2008 EOC Performance/Reactor Issue Open House ML0908904942009-03-30030 March 2009 Presentation Slides for 03/31/2009 Meeting with the NRC Staff Concerning Proposed CO-60 Production at Clinton Station 2024-05-06
[Table view] Category:Meeting Summary
MONTHYEARML24214A1402024-08-0505 August 2024 July 24, 2024, Summary of the Public Meeting Regarding Clinton Power Station, Unit 1, Partial Site Release ML24183A1642024-07-0202 July 2024 June 27, 2024, Summary of the Public Outreach to Discuss the NRC 2023 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 ML24135A3722024-05-22022 May 2024 Enclosure 1 - Meeting Summary for May 7 and May 9 2024 Public Scoping Meetings ML24128A2512024-05-14014 May 2024 Summary of April 11, 2024, Public Meeting with Constellation Energy Generation, LLC Regarding Proposed Alternative to Implement American Society of Mechanical Engineers Operation and Maintenance Code Case OMN-32 ML24113A2872024-04-25025 April 2024 Summary of Public Meeting with Constellation Energy Generation, LLC Regarding Hooded Masks ML24032A0862024-02-0202 February 2024 Summary of Meeting with Constellation Energy Generation, LLC, on Planned Requests to Use Code Case N-932 ML23320A2472023-11-17017 November 2023 Constellation - Summary of November 14, 2023, Public Pre-Application Meeting with Constellation Energy Generation, LLC on Adoption of TSTF-591 ML23263B1062023-09-22022 September 2023 R. E. Ginna Nuclear Power Plant - Constellation - Pre-Application Amse 9/18/2023 Meeting Summary ML23198A0152023-07-27027 July 2023 License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23200A2592023-07-24024 July 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary ML23173A0142023-06-22022 June 2023 Summary of the June 14, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 ML23055A0352023-03-24024 March 2023 Summary of February 23, 2023, with Constellation Energy Generation, LLC on Proposed Changes to Emergency Plans to Revise Emergency Action Levels ML22140A2912022-05-23023 May 2022 Summary of Public Outreach to Discuss the NRC 2021 End-Of-Cycle Plant Performance Assessment of Clinton, Unit 1, and Lasalle, Units 1 and 2 ML22032A3112022-02-18018 February 2022 January 31, 2022, Summary of Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Extending the Clinton Power Station, Unit 1, Secondary Containment to Include the Fuel Building Railroad Ai ML21333A1532021-11-30030 November 2021 Summary of November 16, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Extend the Inservice Inspection Interval ML21237A0412021-08-30030 August 2021 Summary of the July 27, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use Case OMN-28, ML21195A3932021-07-14014 July 2021 June 30, 2021, Summary of Public Outreach to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1, and Lasalle County Station, Units 1 & 2 ML21176A0822021-07-0606 July 2021 June 15, 2021, Summary of Meeting with Exelon Generation Company, LLC Vessel Nozzle Repair Related to a Planned Request for an Alternative Related to Reactor Pressure ML21139A1852021-06-22022 June 2021 Summary of Meeting with Exelon Generation Company, LLC Regarding Its Requested Alternative to Eliminate Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting ML21028A1472021-01-28028 January 2021 Summary of January 21, 2021, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding One-Time Extension of the Clinton Power Station, Unit 1, Containment Type a ILRT Frequency EPID L- ML21011A2822021-01-21021 January 2021 Summary of January 6, 2021, Presubmittal Meeting Between the NRC and Exelon Generation Company, LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Unit Nos. 1 and 2 and Dresden, Units 2 and 3 ML20351A2832020-12-18018 December 2020 Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Exemption to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs ML20342A3522020-12-10010 December 2020 Summary of November 13, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alterantive to Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting (EPID-L-2020-LRM-0102) ML20323A0332020-12-0101 December 2020 Summary of November 4, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs ML20239A8252020-08-25025 August 2020 Summary of the August 4, 2020 Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 ML20181A0002020-06-29029 June 2020 Summary of 6/24/20 Meeting with Exelon Generation Company, LLC Regarding Planned Request for Alternative to Supplemental Valve Position Indication Testing Requirements for Braidwood, Calvert Cliffs, Clinton, Limerick, Nine Mile, Peach Botto ML19326A3152019-12-0303 December 2019 Summary of November 18, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Supplemental Valve Position Indication Testing Requirements ML19326C3582019-12-0303 December 2019 Summary of November 20, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Revise the Quality Assurance Program ML19162A0272019-06-21021 June 2019 Summary of June 4, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Extend the Test Interval for Safety Relief Valves ML19036A8832019-02-0707 February 2019 Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use ASME Code Case N-879 ML18354B1712019-01-0202 January 2019 Summary of December 19, 2018, Meeting with Exelon Generation Company, LLC Regarding the Use of Boiling Water Reactor Vessel and Internals Project Guidelines IR 05000461/20180512018-12-19019 December 2018 Summary of November 30, 2018, Meeting with Exelon Generation Company, LLC Regarding the Preliminary Safety Significance Determination in NRC Inspection Report 05000461/2018051 Dated November 6, 2018 ML18325A1712018-11-28028 November 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Planned Fleet License Amendment Request to Revise Technical Specifications for High Radiation Areas ML18297A1722018-10-26026 October 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Planned License Amendment Request to Adopt TSTF-427 ML18120A1772018-05-0101 May 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing ML18099A2562018-04-0909 April 2018 March 28, 2018, Summary of the Public Outreach/Open House to Discuss the NRC 2017 End-of-Cycle Plant Performance Assessment of Clinton Power Station ML18065A8362018-03-0707 March 2018 Summary of February 27, 2018, Meeting with Exelon Generation Company, LLC Planned Fleet License Amendment Request to Relocate Staff Qualification Requirements from TSs to the Quality Assurance Topical Report ML18058A5232018-03-0101 March 2018 Summary of February 26, 2018, Meeting with Exelon Generation Company, LLC Regarding Proposed Alternative to the Main Steam Isolation Valve Testing Requirements ML17347B1022017-12-14014 December 2017 Summary of Meeting with Exelon Generation Company, LLC on Its Planned Fleet License Amendment Request to Revise the Minimum Staffing Requirements for Emergency Response ML17184A0092017-07-10010 July 2017 Summary of June 29, 2017, Meeting with Exelon Generation Company, LLC, on Proposed Changes to Emergency Plans to Revise Emergency Action Levels (CAC Nos. MF9779-MF9801) ML17096A6512017-04-0606 April 2017 Summary of Public Outreach/Open House to Discuss the NRC 2016 End-Of-Cycle Plant Performance Assessment of Clinton Power Station ML17067A3722017-03-16016 March 2017 March 7, 2017, Summary of Public Pre-Submittal Teleconference Meeting with Exelon Generation Company, LLC to Discuss Proposed License Amendment Request Regarding Residual Heat Removal System Operability in Mode 3 at Clinton Power Station, U ML16307A3162016-11-28028 November 2016 Summary of Public Meeting with Exelon to Discuss Pre-Submittal License Amendment Requests And/Or Exemptions to Part 37 for Decommissioning Plans for Clinton, Quad Cities, and Oyster Creek ML16195A4482016-07-22022 July 2016 Summary of July 12, 2016, Public Meeting with Exelon to Discuss Decommissioning Transition Plans for Clinton, Quad Cities, and Oyster Creek ML16085A3292016-04-0606 April 2016 Summary of March 22, 2016, Meeting with Exelon Generation Company, LLC, on Proposed License Amendment Request to Adopt ANSI 3.1-2014 Operating Training Standards ML16095A3072016-04-0101 April 2016 Summary of the March 30, 2016, Public Outreach/Open House to Discuss the NRC 2015 End-Of-cycle Plant Performance Assessment of Clinton Power Station ML16040A2182016-02-11011 February 2016 January 21, 2016, Summary of Meeting with Exelon Generation Company, LLC Licensing Managers ML16035A1762016-02-11011 February 2016 Summary of January 7, 2016, Meeting with Exelon Generation Company, LLC on It'S Planned Fleet License Amendment Request to Revise the Minimum Staffing Requirements for Emergency Response (CAC Nos. MF7162 - MF7183) ML16032A4112016-02-0404 February 2016 Summary of December 9, 2015 Meeting with Exelon Generation Company, LLC to Discuss Proposed Submittal Related to Secondary Containment Airlock Extension ML15072A4242015-04-16016 April 2015 February 23, 2015, Summary of Meeting with Exelon Generation Company, LLC Regarding Relief Request for Clinton Power Station, Unit 1 (TAC Nos. MF5334, MF5344, and MF5345 2024-08-05
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24310A0672024-11-0505 November 2024 Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization ML24127A0952024-05-0606 May 2024 License Renewal Public Scoping Meeting May 2024 ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23172A2092023-06-28028 June 2023 LRA - NRC Pre-Submittal Meeting Slides ML23172A2102023-06-28028 June 2023 CPS Lr Pre-Submittal Meeting Presentation ML23165A0162023-06-14014 June 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting - NRC Slides ML23145A1342023-06-14014 June 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting - Constellation Slides NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML22028A0112022-01-31031 January 2022 Slides for Fbra Pre-submittal Meeting of 2022-01-31 ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1582021-07-13013 July 2021 and Lasalle Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21021A0652021-01-21021 January 2021 NRC Pre-Application Meeting - Clinton One-Time Extension of the Containment Type a Leak Rate Test Frequency (Meeting Handout) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8662020-08-25025 August 2020 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18333A3332018-11-30030 November 2018 Regulatory Enforcement Conference Slides for Clinton Power Station on November 30, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas U-604453, Regulatory Conference Information2018-11-19019 November 2018 Regulatory Conference Information ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17067A3722017-03-16016 March 2017 March 7, 2017, Summary of Public Pre-Submittal Teleconference Meeting with Exelon Generation Company, LLC to Discuss Proposed License Amendment Request Regarding Residual Heat Removal System Operability in Mode 3 at Clinton Power Station, U ML16314E4812016-11-14014 November 2016 Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016 ML16189A4332016-07-12012 July 2016 July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML15342A3542015-12-0808 December 2015 License Amendment Request Extension of Secondary Containment - NRC Pre- Application Meeting December 9, 2015 ML15173A3812015-06-19019 June 2015 Regulatory Conference Supplemental Information ML14223A5742014-08-11011 August 2014 8/7/14 Clinton Power Station Annual Assessment Meeting Licensee Slides ML14220A2492014-08-0707 August 2014 8/7/2014 NRC Slides of Clinton Power Station Annual Assessment Meeting Cy 2013 RS-14-148, Transmittal of Proprietary Meeting Slides2014-04-28028 April 2014 Transmittal of Proprietary Meeting Slides ML14114A7402014-04-0909 April 2014 Application of GE Hitachi Simplified Stability Solution GS3 Pre-Submittal Presentation ML13184A3152013-07-0202 July 2013 EOC Public Meeting Presentation July 2, 2013 ML12185A0122012-07-12012 July 2012 Summary of June 14, 2012, Public Meeting to Discuss the Application Partial Site Release Request for Clinton Power Station ML12188A5122012-07-0606 July 2012 IEMA HAB Lessons Learned_rev1 ML12111A1282012-04-19019 April 2012 End-of-Cycle Performance Assessment Meeting Presentation Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML11201A2132011-07-20020 July 2011 Summary of Public Meeting to Discuss Exelon'S Plans for Implementing an Electronic Document Control System (Edocs) for Use by NRC Inspectors with U.S. Nuclear Regulatory Commission (NRC) Region III Staff ML1111905212011-04-28028 April 2011 Clinton Power Station Cy 2010 End-Of-Cycle Open House Presentation ML1015502442010-06-0202 June 2010 Presentation Slides from Clinton Power Station June 2, 2010 Annual Assessment Meeting ML0929400522009-10-22022 October 2009 Meeting Power Uprate Meeting Slides ML0914003322009-05-11011 May 2009 Slides Presented at the Clinton 2008 EOC Performance/Reactor Issue Open House 2024-05-06
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 16, 2017 LICENSEE : Exelon Generation Company, LLC FACILITY: Clinton Power Station , Unit No. 1
SUBJECT:
SUMMARY
OF MARCH 7, 2017, PUBLIC PRE-SUBMITTAL TELECONFERENCE MEETING WITH EXELON GENERAION COMPANY, LLC TO DISCUSS PROPOSED LICENSE AMENDMENT REQUEST REGARDING RESIDUAL HEAT REMOVAL SYSTEM OPERBILITY IN MODE 3 AT CLINTON POWER STATION, UNIT 1 (CAC NO. MF9152)
On March 7, 2017, a Category 1 public teleconference meeting was held between the U.S.
Nuclear Regulatory Commission (NRC) and representatives of Exelon Generation Company, LLC (Exelon or the licensee) . The purpose of the meeting was for Exelon to discuss with the NRC a proposed license amendment request (LAR) regarding residual heat removal (RHR) system operability in Mode 3 at Clinton Power Station, Unit No. 1 (Clinton) . The meeting notice and agenda , dated February 21 , 2017, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML17052A154. A list of attendees is enclosed .
The licensee's presentation is available at ADAMS Accession No. ML17067A372 .
The licensee provided background information which includes a green finding and associated non-cited violation issued by the NRC related to the RHR system. Specifically, RHR cannot be realigned from shutdown cooling mode of operations to provide the technical specification (TS) required functions of the emergency core cooling system (ECCS) when the reactor coolant temperature is greater than 150 degrees Farenheit. In addition, the licensee provided information on the Clinton ECCS design and TS history.
The licensee proposes to submit a LAR to align the TS requirements with the design capabilities . The licensee expects their LAR to be similar to a LAR submitted for LaSalle County Station, Units 1 and 2 (LaSalle) , which resolved a similar issue. The NRC approval of the LaSalle LAR is available at ADAMS Accession No. ML15244B410. The licensee expects to submit the LAR for Clinton on or before May 5, 2017.
There were no public comments made at this meeting and no public meeting feedback forms were received .
Please direct any inquiries to me at 301-415-1530, or by email at Jennivine.Rankin@nrc.gov.
Sincerely, J nivine K. Rankin , Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-461
Enclosure:
List of Attendees cc w/encl : Distribution via Listserv
Meeting Notice: ML17052A154 Meeting Summary: ML17067A372 Handouts: ML17067A362 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC (A) NRR/DORL/LPL3/PM NAME JRankin SRohrer KGreen JRankin DATE 03/09/17 03/09/17 03/16/17 03/16/17 LIST OF ATTENDEES MARCH 7, 2017, MEETING WITH EXELON GENERATION COMPANY, LLC RESIDUAL HEAT REMOVAL SYSTEM OPERABILITY IN MODE 3 CLINTON POWER STATION, UNIT NO. 1 Name Afffiliation U.S. Nuclear Regulatory Commission (NRC)/Office of Nuclear Eric Oesterle Reactor Regulation (NRR)
Muhammad NRC/NRR Razzaque Caroline Tilton NRC/NRR Jennie Rankin NRC/NRR John Schrage Exelon Generation Company, LLC (Exelon)
Patrick Simpson Exelon Dale Shelton Exelon Jonathon Grim Exelon John Pfabe Exelon Enclosure
Clinton Power Station License Amendment Request Mode 3 Applicability - LPCl/SDC NRC Pre-Submittal Teleconference March 7, 2017 Exelon
Agenda
- Background and Need for Amendment
Objective
- Present information to the NRC staff describing a proposed License Amendment Request (LAR) for Clinton Power Station (CPS) to resolve a CDBI violation concerning incapability of the residual heat removal (RHR) design to support Technical Specification (TS) operability requirements.
- Obtain feedback from the NRC staff on the proposed LAR and gain an understanding of the NRC staff's expectations for the content of a high quality submittal.
- Answer any questions from the NRC staff regarding the proposed LAR.
2 ~ Exelon.
=
Background===
December 2016 NRC CDBI Inspection
- Green finding and associated Non-cited Violation (NCV) for failure to promptly identify that the incapability of the RHR design to support TS operability requirements was a condition adverse to quality.
- CPS captured this issue in the Corrective Action Program (CAP) both prior to, and subsequent to the inspection. The planned corrective action, as documented in NRC Inspection Report 05000461/12016009, was to submit an LAR to align TS requirements with the design capabilities.
3 ~ Exelon.
Background {cont.)
CPS Design
- TS 3.5.1( 1 ) requires all low pressure ECCS injection/spray systems to be OPERABLE in Modes 1, 2, and 3.
- By design, the suppression pool suction valve on the ECCS Loop that is supporting SOC operations must be shut, otherwise the reactor coolant would drain to the suppression pool. The suppression pool suction valve does not automatically realign on a LPCI signal.
- In addition, the suppression pool suction valve is not capable of opening for manual realignment, due to both water hammer and pressure locking/thermal binding concerns which have not been analyzed above 150 ° F.
(1) TS 3.5.1, ECCS - Operating 4 ;iF Exelon.
Background (cont.)
TS History
- Prior to implementing NUREG-1434 Improved Tech Specs (ITS) in 1994, the CPS TS 3.5.1 recognized the required LPCI inoperability, and annotated Mode 3 applicability with a Note that stated:
One LPCI subsystem of the RHR system may be aligned in the shutdown cooling mode when reactor vessel pressure is less than the LPCI cut-in permissive set point.
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor vessel pressure less than the residual heat removal cut-in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
(2) TS 3.5.2, ECCS - Shutdown; TS 3.6.1.7, Residual Heat Removal (RHR) Containment Spray System; TS 3.6.1.9, Feedwater Leakage Control System (FWLCS); and TS 3.6.2.3, Residual Heat Removal (RHR)
Suppression Pool Cooling 5 411F Exelon.
Background (cont.)
TS History {cont.)
- However, since the suppression pool suction valve is not capable of opening for manual realignment (i.e., as previously discussed), CPS is not able to implement the ITS Note, and therefore, declares LPCI inoperable during decay heat removal in Mode 3 with reactor pressure l~ss than the cut-in permissive.
- The current NRC interpretation of the ITS LCO and associated Note is that the systems are required to be OPERABLE, and failure to implement the Note (i.e., declaring LPCI inoperable) constitutes entry into the ACTIONS for operational convenience.
6 4!F Exelon.
Proposed Resolution
- The NRC issued a similar Green Finding and associated NCV to LaSalle County Station (LSCS) in 2012. In response to that Finding/NCV, LSCS submitted, and the NRC approved an LAR in October 2015 that deleted this Note [ML15244B410].
One Low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut-in permissive pressure in MODE 3.
7 ~ Exelon.
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