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Category:Conference/Symposium/Workshop Paper
MONTHYEARML24192A1272024-07-10010 July 2024 Scale and Melcor non-LWR Fuel Cycle Demonstration Project - MSR ML24163A0412024-06-11011 June 2024 Arcop Ws 3 Exercise NRC Facilitator Handout ML24163A0422024-06-11011 June 2024 Arcop Ws 3 Exercise Participant Handout ML24088A0012024-03-29029 March 2024 Thank You Letter for Presenting at RIC 2024 - Tina Taylor ML24085A7822024-03-20020 March 2024 RIC-2024 W14 - Thank You Letter to Sarah Jane Eaton for Presenting at the NRCs 36th Regulatory Information Conference ML24085A7832024-03-20020 March 2024 RIC-2024 W14 - Thank You Letter to Robert Cox for Presenting at the NRCs 36th Regulatory Information Conference ML24085A7842024-03-20020 March 2024 RIC-2024 W14 - Thank You Mr Holtzman ML24052A2232024-03-14014 March 2024 Regulatory Information Conference (RIC) 2024 - Digital Exhibit - the NRC Is Advanced Reactor Ready! ML24068A2542024-03-14014 March 2024 RIC 2024 TH21 Wkennedy Optimizing Regulatory Landscape for Licensing and Deployment of Factory Fabricated Micro-Reactors ML24030A6732024-03-13013 March 2024 RIC 2024 Krepel Presentation Adapting to a Changing Landscape ML24040A1832024-03-12012 March 2024 RIC 2024 T4 Slides - Vhuckabay Spent Fuel Reprocessing: Past, Present, and Future ML24067A2572024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Rtaylor Chair Opening Remarks ML24067A2582024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Ncoovert and Jgreives Future of Construction Oversight ML24088A2552024-03-12012 March 2024 RIC 2024 T4 NRC Form 1105 - Victoria Huckabay ML24149A1492024-03-12012 March 2024 Enclosure 1 - 36th Annual RIC Presentation - Opening Remarks & Fulfilling the Mission Today and Tomorrow - Miranda Ross ML24088A1092024-01-30030 January 2024 RIC-2024 TH21 - Micro-Reactors Invitation Gogan.Pdf ML24088A1082024-01-16016 January 2024 RIC-2024 TH21 - Micro-Reactors Invitation Corletti ML24088A1502023-12-28028 December 2023 RIC-2024 W14 - Innovations in Advanced Reactor Construction Oversight Invitation Eaton ML24088A1512023-12-28028 December 2023 RIC-2024 W14 - Innovations in Advanced Reactor Construction Oversight Invitation Cox ML24088A1672023-12-28028 December 2023 RIC-2024 W14 - Innovations in Advanced Reactor Construction Oversight Invitation Nichol ML24088A1062023-12-27027 December 2023 RIC-2024 TH21 - Micro-Reactors Invitation Schilthelm ML24088A1072023-12-27027 December 2023 RIC-2024 TH21 - Micro-Reactors Invitation Jackson ML24080A2522023-12-18018 December 2023 Speaker Invitation Letter to Flavien Simon in France ML24080A2542023-12-18018 December 2023 Speaker Invitation Letter to Jinho Lee in South Korea ML23079A0482023-03-16016 March 2023 RIC 2023 Slides - Intro TH19 ML23017A1872023-03-14014 March 2023 RIC 2023: T2 New Fuels Licensing Readiness NRC RIC Presentations Donoghue ML23017A1882023-03-14014 March 2023 RIC 2023: T2 New Fuels Licensing Readiness NRC RIC Presentation Vanwert ML23045A2932023-03-14014 March 2023 RIC 2023 -3/14/2023 to 3/16/2023 Regulatory Information Conference (RIC) ML23045A2912023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2862023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (Ric). Advances in RIDM: Past, Present, Future Technical Session T5 ML23045A2902023-03-14014 March 2023 RIC 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2922023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23061A0832023-03-14014 March 2023 W11 RIC 2023 Presentation by Rob Taylor Re Perspectives on Risk-Informed Licensing of Advanced Reactors ML22341A1782022-12-13013 December 2022 RIC 2023 Fernando Ferrante Speaker Invitation Letter ML22339A2132022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Justin Hudson and Ching Ng Presentation on Risk Informed Decisionmaking ML22339A1862022-10-12012 October 2022 National Organization for Test, Research and Training Reactors Trtr 2022 Annual Conference Joshua Borromeo Presentation on Npuf Licensing ML22339A1912022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Travis Tate Presentation on Npuf Oversight ML22339A2162022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Adrian Muniz Presentation on Advanced Reactor Licensing ML22339A2192022-10-12012 October 2022 Trtr 2022 Annual Conference Duane Hardesty Presentation on Irsrr Red.Pdf ML22339A2212022-10-12012 October 2022 Trtr 2022 Annual Conference Duane Hardesty Presentation on Performance Based Approach to Licensing ML22339A2282022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Beth Reed Presentation on SNM Options ML22339A2302022-10-12012 October 2022 National Organization of Test, Research, and Training Reactors Trtr 2022 Annual Conference Beth Reed Breakout Session Presentation on Draft Security Measures ML22262A2522022-09-20020 September 2022 Presentation - 09/20/2022 Scale Melcor Sodium Fast Reactor (Sfr) Workshop ML22145A2362022-06-22022 June 2022 baranj-w15-bio ML22153A3052022-06-21021 June 2022 sessionabstract-t5 ML22153A3082022-06-21021 June 2022 sessionabstract-t8 ML22153A3382022-06-0808 June 2022 smithb-hv-th28 ML22048C2422022-03-31031 March 2022 Regulatory Information Conference (RIC) 2022 - Technical Session W16 Be Risksmart Presentation ML22118A9812022-03-25025 March 2022 2022 RIC Presentation of Mark Franke for W20 Lessons Learned Performing Oversight of NRC Facilities During the Pandemic ML22153A3502022-03-10010 March 2022 veila-hv-t5-r1 2024-07-10
[Table view]Some use of "" in your query was not closed by a matching "". Category:Meeting Briefing Package/Handouts
MONTHYEARML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24205A0202024-07-23023 July 2024 5 - RG 1.59 - Appendix K - Consideration for Applying Guidance to Advanced Reactor and Small Modular Reactors - Stakeholders Meeting 07/24/2024 ML24205A0192024-07-23023 July 2024 6-Licensing and Deployment Considerations for Noak Micro-Reactors - AR Stakeholders Meeting July 24 2024 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24192A1272024-07-10010 July 2024 Scale and Melcor non-LWR Fuel Cycle Demonstration Project - MSR ML24190A1462024-07-0808 July 2024 Arcop Ws 4 Ppt - Public ML24172A3062024-06-27027 June 2024 Risk-Informing Materials Issues Risk Insights for Materials Issues NRC Perspective ML24172A3052024-06-27027 June 2024 NRC- Perspective on ASME Code Efforts ML24163A0422024-06-11011 June 2024 Arcop Ws 3 Exercise Participant Handout ML24163A0412024-06-11011 June 2024 Arcop Ws 3 Exercise NRC Facilitator Handout ML24144A1832024-05-23023 May 2024 Advanced Reactor Stakeholder Meeting 2024-05-23 ML24143A0802024-05-22022 May 2024 Arcap ISG Documents and Ticap Guidance Final Documents ML24123A2172024-05-15015 May 2024 Research Test Rx Construction Workshop Date 5.15.25 - Public ML24131A0142024-05-14014 May 2024 NRC Slides Micro-Reactor Licensing 5_14_24 Public Meeting ML24129A0752024-05-0808 May 2024 Arcop Work Shop 3 May 7 Version ML24122C6322024-05-0101 May 2024 ROP Bi-Monthly Meeting Slides on IP93100 Revision Update ML24030A6732024-03-13013 March 2024 RIC 2024 Krepel Presentation Adapting to a Changing Landscape ML24067A2582024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Ncoovert and Jgreives Future of Construction Oversight ML24067A2572024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Rtaylor Chair Opening Remarks ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24043A1812024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2-14-24 Rev1 ML24030A0092024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2/14/2024 ML24044A1402024-02-0808 February 2024 TSTF Handout for 02/08/2024 Quarterly Meeting ML24038A3492024-02-0707 February 2024 NRC Comments for Pre-submittal Meeting TSTF-600, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency ML23338A2792023-11-30030 November 2023 Technology-Inclusive, Risk-Informed, and Performance-Based Licensing Approaches ML23306A1262023-11-0707 November 2023 Terrapower Public Outreach Meeting Wyoming Final (1) ML23298A1342023-10-27027 October 2023 DG-4034 (RG 4-7 Rev 4) Presentation on Population-Related Siting Oct 27 2023 ML23270B9282023-09-28028 September 2023 50.72 Aug 9 2023 Public Meeting Slides ML23256A0012023-09-20020 September 2023 Generic Issues Program Presentation - ROP Public Meeting ML23250A1292023-09-11011 September 2023 NRC Staff Presentation on the NRC Draft White Paper on Licensing and Deployment Considerations for Factory-Fabricated Micro-Reactors ML23243B0092023-08-30030 August 2023 Public Meeting Presentation - University of California Davis - Mcclellan Nuclear Research Center Reactor Meeting August 30, 2023 ML23219A1382023-08-0707 August 2023 50.72 Rulemaking Update ML23200A3392023-06-21021 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Travis Tate on Non-power Production and Utilization Facilities Oversight ML23122A1372023-05-0202 May 2023 NDE of AMT NRC Presentation ML23101A1232023-04-18018 April 2023 Staff Presentation on PRA Used to Implement Lmp in Support of Non-LWR Construction Permit Applications Under 10 CFR Part 50 ML23192A0392023-04-13013 April 2023 Abilene Christian University, NRC Slides from April 13, 2023, Closed Meeting to Discuss Security Topics ML23094A0562023-04-0404 April 2023 Presentation - April 4, 2023 Licensing Review Framework for Advanced Reactors I&C Workshop 2 ML23079A0482023-03-16016 March 2023 RIC 2023 Slides - Intro TH19 ML23045A2922023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2932023-03-14014 March 2023 RIC 2023 -3/14/2023 to 3/16/2023 Regulatory Information Conference (RIC) ML23017A1872023-03-14014 March 2023 RIC 2023: T2 New Fuels Licensing Readiness NRC RIC Presentations Donoghue ML23045A2912023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2902023-03-14014 March 2023 RIC 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2862023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (Ric). Advances in RIDM: Past, Present, Future Technical Session T5 ML23017A1112023-01-11011 January 2023 ACRS Presentation CNSC - U.S. NRC Cooperation on Advanced Reactor Technologies and Small Modular Reactors ML22342B1632022-12-13013 December 2022 NRC Staff Presentation on the Regulatory Basis for Changes to Reporting Requirements for Nonemergency Events at Nuclear Power Plants ML22340A4732022-12-0505 December 2022 NRC Presentation, Expansion of Policy for Addressing Potential Common Cause Failures in U.S. Nuclear Power Plant Digital Instrumentation and Control Systems, IAEA Technical Meeting, December 6-8 2022 ML22333A7402022-12-0505 December 2022 NRC Presentation - ASME OM Code and Snubber Issues at Inservice Service Testing Owner Group (Istog) Final - Meeting December 5-6, 2022, in Clearwater, Fl ML22311A5532022-11-16016 November 2022 Kairos Hermes NRC Staff Presentation at Nov 16 Public Meeting on the Draft Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor ML22298A2162022-10-25025 October 2022 TSTF Meeting Handout TSTF-585 and the Maintenance Rule 2024-07-08
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24218A1922024-07-30030 July 2024 NRC Presentation for 7-30-24 Public Meeting RG 1.247 Finalization Plan ML24205A0202024-07-23023 July 2024 5 - RG 1.59 - Appendix K - Consideration for Applying Guidance to Advanced Reactor and Small Modular Reactors - Stakeholders Meeting 07/24/2024 ML24205A0192024-07-23023 July 2024 6-Licensing and Deployment Considerations for Noak Micro-Reactors - AR Stakeholders Meeting July 24 2024 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24192A1272024-07-10010 July 2024 Scale and Melcor non-LWR Fuel Cycle Demonstration Project - MSR ML24190A1462024-07-0808 July 2024 Arcop Ws 4 Ppt - Public ML24172A3062024-06-27027 June 2024 Risk-Informing Materials Issues Risk Insights for Materials Issues NRC Perspective ML24172A3052024-06-27027 June 2024 NRC- Perspective on ASME Code Efforts ML24163A0422024-06-11011 June 2024 Arcop Ws 3 Exercise Participant Handout ML24163A0412024-06-11011 June 2024 Arcop Ws 3 Exercise NRC Facilitator Handout ML24144A1832024-05-23023 May 2024 Advanced Reactor Stakeholder Meeting 2024-05-23 ML24143A0802024-05-22022 May 2024 Arcap ISG Documents and Ticap Guidance Final Documents ML24142A5492024-05-21021 May 2024 Adv Rx Stakeholders - Risk Metrics Workshop - Rev 2 ML24142A5512024-05-21021 May 2024 Path Forward - Arsm Slides for 5-23-24 ML24141A1552024-05-20020 May 2024 NRC Slides Micro-Reactor Licensing May 23 2024 Advanced Reactor Stakeholder Meeting ML24123A2172024-05-15015 May 2024 Research Test Rx Construction Workshop Date 5.15.25 - Public ML24131A0142024-05-14014 May 2024 NRC Slides Micro-Reactor Licensing 5_14_24 Public Meeting ML24129A0752024-05-0808 May 2024 Arcop Work Shop 3 May 7 Version ML24122C6322024-05-0101 May 2024 ROP Bi-Monthly Meeting Slides on IP93100 Revision Update ML24052A2232024-03-14014 March 2024 Regulatory Information Conference (RIC) 2024 - Digital Exhibit - the NRC Is Advanced Reactor Ready! ML24030A6732024-03-13013 March 2024 RIC 2024 Krepel Presentation Adapting to a Changing Landscape ML24067A2572024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Rtaylor Chair Opening Remarks ML24040A1832024-03-12012 March 2024 RIC 2024 T4 Slides - Vhuckabay Spent Fuel Reprocessing: Past, Present, and Future ML24067A2582024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Ncoovert and Jgreives Future of Construction Oversight ML24149A1492024-03-12012 March 2024 Enclosure 1 - 36th Annual RIC Presentation - Opening Remarks & Fulfilling the Mission Today and Tomorrow - Miranda Ross ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24043A1812024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2-14-24 Rev1 ML24030A0092024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2/14/2024 ML23338A2792023-11-30030 November 2023 Technology-Inclusive, Risk-Informed, and Performance-Based Licensing Approaches ML23306A1262023-11-0707 November 2023 Terrapower Public Outreach Meeting Wyoming Final (1) ML23298A1342023-10-27027 October 2023 DG-4034 (RG 4-7 Rev 4) Presentation on Population-Related Siting Oct 27 2023 ML23270B9282023-09-28028 September 2023 50.72 Aug 9 2023 Public Meeting Slides ML23256A0012023-09-20020 September 2023 Generic Issues Program Presentation - ROP Public Meeting ML23250A1292023-09-11011 September 2023 NRC Staff Presentation on the NRC Draft White Paper on Licensing and Deployment Considerations for Factory-Fabricated Micro-Reactors ML23219A1382023-08-0707 August 2023 50.72 Rulemaking Update ML23200A3392023-06-21021 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Travis Tate on Non-power Production and Utilization Facilities Oversight ML23200A3372023-06-21021 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Josh Borromeo on Non-power Production and Utilization Facilities and Advanced Reactors Licensing ML23200A3422023-06-19019 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Beth Reed on Secy Option Paper for Enhanced Security of Special Nuclear Material ML23200A3432023-06-19019 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Beth Reed on Physical Security Event Notification and Suspicious Activity Reporting Rule ML23184A1282023-06-0707 June 2023 Advanced Reactors ML23122A1372023-05-0202 May 2023 NDE of AMT NRC Presentation ML23101A1232023-04-18018 April 2023 Staff Presentation on PRA Used to Implement Lmp in Support of Non-LWR Construction Permit Applications Under 10 CFR Part 50 ML23192A0392023-04-13013 April 2023 Abilene Christian University, NRC Slides from April 13, 2023, Closed Meeting to Discuss Security Topics ML23094A0562023-04-0404 April 2023 Presentation - April 4, 2023 Licensing Review Framework for Advanced Reactors I&C Workshop 2 ML23079A0482023-03-16016 March 2023 RIC 2023 Slides - Intro TH19 ML23045A2902023-03-14014 March 2023 RIC 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2862023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (Ric). Advances in RIDM: Past, Present, Future Technical Session T5 ML23045A2912023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) ML23045A2932023-03-14014 March 2023 RIC 2023 -3/14/2023 to 3/16/2023 Regulatory Information Conference (RIC) 2024-07-08
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Text
Advanced Reactor Construction Oversight Process (ARCOP)
Workshop #3 Draft Material for External Participants
1 Group activity - Example Scenario 1 (For demonstration purpose only)
While walking down the salt processing system in the reactor building of a MSR project, an NRC inspector observes damage to a system pipe. That portion of the reactor building has not been completed (no roof ) and the inspector is aware of a severe weather event that occurred 2 days ago at the site. The licensee informs the NRC inspector that they intend to walkdown all the SSCs that were potentially affected by the weather event, but they hadnt walked down that portion of the reactor building yet. The NRC inspector reviews work requests generated after the weather event and observes that there is an open work request to walkdown the reactor building for potential damage to SSCs.
Screening Result:
Notes:
2 Group activity - Example Scenario 2 (For demonstration purpose only)
While reviewing condition reports (CAP entries) as part of an auxiliary heat removal system inspection, an NRC inspector reviews a condition report that documents an error in a work procedure that led to 4 nonconforming welds in system piping. The NRC inspector also noted that corrective actions were complete for 2 of the 4 welds (grind out weld and reweld) but not the other 2 welds. Those corrective actions are marked as pending further evaluation in the CAP database.
Screening Result:
Notes:
3 Group activity - Example Scenario 3 (For demonstration purpose only)
While comparing seismic design requirements for the safety related portion of the reactor building , an NRC inspector notes that part of the north wall rebar configuration does not match the design drawing. In response to the NRC inspector s observation, the licensee repaired the nonconformance which required substantive rework.
Screening Result:
Notes:
4 Group activity - Example Scenario 4 (For demonstration purpose only)
During an NRC inspection, the inspector noted that an orifice in a reactor cavity cooling system pipe was smaller than others in the system (1 of 2 trains affected). The NRC inspector also noted that the orifice size was in accordance with the design drawing. However, the PSAR states that the design flow of ___ is needed for the line, and the design calculations for pipe flow assume a larger orifice (the same size as installed in the other line).
Screening Result:
Notes:
5 Group activity - Example Scenario 5 (For demonstration purpose only)
During a review of measurement and test equipment (M&TE) records, an NRC inspector noted that a differential pressure instrument was not calibrated within its required periodicity as defined by the site M&TE program QA procedures. The inspector also noted that the instrument was used during pre -
operational tests of the Boron Injection System and the system was turned over to operations.
Screening Result:
Notes:
6 Group activity - Example Scenario 6 (For demonstration purpose only)
NRC inspectors identified a generic setpoint control program problem that resulted in non -conservative setpoints in the reactor protection system. All scram and runback setpoints, and all RPS trains were adversely/non-conservatively affected. Systems had already been turned over to operations (e. g., there was no reasonable opportunity for the licensee to have identified and corrected the issue prior to operations).
Screening Result:
Notes:
7 Group activity - Example Scenario 7 (For demonstration purpose only)
While reviewing radiographs at the manufacturing facility of a non -licensed manufacturer for the CVCS piping system associated with an SMR, the NRC inspector observed a previously unidentified unacceptable weld indication on the radiograph. The radiograph had already been reviewed/accepted by the manufacturer s NDE personnel.
Screening Result:
Notes:
8 Issue Screening Flowchart (DRAFT)
Issue of Potentially Y W illfulness is not covered Concern Involves in this workshop.
W illfulness?
N
Y Traditional enforcement in Non- Follow both Traditional Enforcement Path not covered in this Compliance? paths workshop
N
N
No finding
The noncompliance Go to Y More Y licensee or Performance than is an NRC- identified Non-Deficiency? Minor? or self-revealing licensee flow finding chart
N N
No finding No finding
9 Minor/More-than-Minor Screening Flowchart (DRAFT)
Noncompliance with Self-identified Y Performance Construction The noncompliance is minor Deficiency Noncompliance?
N
Y The noncompliance is More than minor more than minor impact on SSC?
Continue screening
N
More than minor Y impact on Operational Readiness?
N
More than minor Y impact on Security or Safeguards?
N
The noncompliance is minor
10 Dispositioning Licensee Findings - Flowchart (DRAFT)
NRC- Identified or self-revealing licensee finding.
Legally Y A violation is Enforcement Y Document in binding associated with Discretion accordance with the requirement? the finding Apply? Enforcem ent Policy
N N
A violation is Screen finding not associated significance with the finding
Y Y Noncited Green Noncited Violation Go to Finding? violation? (NCV)
next flowchart N N
Enter the Notice of SERP Process Violation (NOV) 11 Dispositioning Non-Licensee Findings Flowchart (DRAFT)
From the NRC- identified or Document as a Notice initial of Nonconformance Note: all screening self-revealing non- licensee (NON) to the manufacturer NONs flow chart finding manufacturer are assessed for potential follow-up inspection.
Enforcement Process
12 Flowchart Instructions (DRAFT)
Issue of Concern Noncompliance Performance Legally Binding Deficiency Requirements A w e l l-defined A failure to adhere to a observation or collection requirement or - Regulations of observations that may commitment. The noncompliance was - License conditions have a bearing on safety reasonably within the - NRC Orders or security and warrants Legally binding licensees ability to foresee further inspection, requirements include and correct and should Non- legally binding screening, evaluation, or regulations, license have been prevented. requirements regulatory action. conditions, and NRC Orders. Self- imposed requirements to establish Non- legally binding and maintain quality commitments include self-imposed requirements to establish and maintain quality or requirements specified in procurement contracts..
13 Flowchart Instructions (Minor/More-than-Minor Screening)
(DRAFT)
Self-identified Construction Noncompliance (SCN) Criteria SSC Issues - Minor Criteria Questions
- 1. The noncompliance is self-identified (not NRC- a. Does the performance deficiency represent an adverse identified or self-revealing), and condition that rendered the quality of a risk-significant or s afet y-related SSC unacceptable or indeterminate, and
- 2. The noncompliance must be in a facility-approved QAP requires substantive corrective action?
process for correction when evaluated by NRC b. Does the noncompliance represent an irretrievable loss inspectors, as defined by facility-approved QAP or inadequate documentation of a quality assurance procedures. This may include: record; or a record-keeping issue that could preclude the
- Entry into an QAP work -flow process or corrective licensee from demonstrating adequacy of quality or from action program. properly evaluating risk-significant or safety-related
- Proper timing and tracking of planned corrective activities?
actions so that the noncompliance will not adversely c. Does the noncompliance prevent the licensee from impact reactor operations. meeting an ITAAC Design Commitment or approved
- If corrective actions are complete, the corrective Technical Specification?
actions are adequate. d. Does the noncompliance invalidate the performance of Note: NRC-identified weaknesses with corrective actions an Inspection, Test, or Analysis described in an ITAAC?
are processed as separate noncompliances.
14 Significance Determination (DRAFT)
Significance of Finding Findings Impact on SSCs Red Not applicable to ARCOP findings.
- a. The finding, if left uncorrected, would reasonably be expected to result in the loss of a fundamental safety function (FSF)1 because no systems, trains, or design features are credited for fulfilling the FSF; or Yellow
- b. The finding is not adequately addressed by the significance criteria in this table 2, and screens as yellow using Appendix F of this IMC.
- a. The finding, if left uncorrected, would reasonably be expected to result in t he loss of two or more systems, trains, or design features ability to fulfill one or more FSFs, and other systems, trains, or design features are credited in fulfillin g White the FSFs; or
- b. The finding is not adequately addressed by the significance criteria in this table 2, and screens as white using Appendix F of this IMC.
- a. The finding, if left uncorrected, would reasonably be expected to result in the loss of one system, train, or design features ability to fulfill an FSF, and another system, train, or design feature is credited for fulfilling that FSF; or
- b. The finding is associated with an issue where no manufacture, fabrication, placement, erection, installation, or modification of hardware associated with the SSC has begun; or Green c. There is a quality assurance program (QAP) backstop 3 for the deficiency associated with the finding; or
- d. The finding is associated with a hazard protection feature 4 and does not potentially represent a significant quality assurance program breakdown 5; or
- e. It is demonstrated with reasonable assurance that the design function of the SSC would not be impaired by the deficiency. 15 SSC SDP Table Notes (DRAFT)
Note 1: Fundamental safety functions (FSFs), as used in ARCOP, are:
Control of Heat Generation (Reactivity and Power Control),
Control of Heat Removal (including reactor and spent fuel decay heat and heat generated from waste stores), and Radionuclide Retention.
Note 2: Findings not adequately addressed by the significance criteria of the SDP table. When the ARCOP construction significance determination process guidance is not adequate to provide a reasonable estimate of the significance of an inspection finding, the safety significance should ultimately be determined by using engineering judgement and regulatory oversight experience, which is acceptable in a risk-informed process. Appendix F provides guidance to the NRC to apply a consistent process for risk-informed decision making.
Note 3: Quality assurance program (QAP) backstop. A QAP backstop is a scheduled QAP activity designed to detect SSC deficiencies or noncompliances that are associated with the finding. To give credit for a QAP backstop, the QAP activity must be reasonably defined or contained in a procedure, scheduled prior to the receipt of an operating license (Part 50) or before the 103(g) finding (Part 52), and would reasonably be able to detect the deficiency or noncompliance associated with the finding.
Note 4: Hazard protection features are those SSCs and design features that mitigate the effects of internal (e.g., fire, internal flooding, internal chemical release) or external (e.g., seismic event, external flooding, severe weather events) hazards.
Note 5: Use Appendix F of this IMC to determine if an issue should be considered a potentially significant quality assurance program breakdown.
16