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Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 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 ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides 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) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (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 ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation 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) ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 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 ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 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 ML18018B4432018-01-25025 January 2018 Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047 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 ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations 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 ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations ML14342A8122014-12-10010 December 2014 Presentation Slides for December 10, 2014 Meeting on Alloy 600 PWSCC Mitigation for Rvh Nozzles ML14261A1112014-09-22022 September 2014 2014 NEI Fire Protection Information Forum NRC Public Slides ML14251A4852014-09-10010 September 2014 Byron/Braidwood Auxiliary Feedwater Cross-Tie ML14177A6412014-06-23023 June 2014 UHS Pre-submittal Meeting Presentation ML13249A1892013-09-0404 September 2013 ILRT Extension LAR Pre-submittal Meeting Slides ML13224A2922013-08-0808 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting NRC Presentation ML13107A0532013-04-23023 April 2013 Pre-Submittal Meeting MSIV Actuators Slides ML12227A5332012-08-14014 August 2012 NRC End-of-Cycle Slide Presentation 2024-01-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 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 ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides 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) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation 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 ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (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 ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation 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 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) 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 ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 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 ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 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 ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15204A4932015-07-23023 July 2015 Bb Station Requests for Relief for Alternate Examination Frequency ML15204A5052015-07-23023 July 2015 EPRI Tech Basis for Brd-Byr Head RR ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations ML15135A4262015-05-19019 May 2015 EOC Public Meeting Slides ML15104A4932015-04-14014 April 2015 Preliminary Site-Specific Results of the Environmental Review for Braidwood Station License Renewal ML14342A8122014-12-10010 December 2014 Presentation Slides for December 10, 2014 Meeting on Alloy 600 PWSCC Mitigation for Rvh Nozzles ML14261A1112014-09-22022 September 2014 2014 NEI Fire Protection Information Forum NRC Public Slides ML14251A4852014-09-10010 September 2014 Byron/Braidwood Auxiliary Feedwater Cross-Tie ML14177A6412014-06-23023 June 2014 UHS Pre-submittal Meeting Presentation ML13249A1892013-09-0404 September 2013 ILRT Extension LAR Pre-submittal Meeting Slides ML13224A2882013-08-12012 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting Licensee Presentation ML13224A2922013-08-0808 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting NRC Presentation ML13107A0532013-04-23023 April 2013 Pre-Submittal Meeting MSIV Actuators Slides ML12227A5172012-08-14014 August 2012 Licensee End-of-Cycle Public Meeting Slides ML12227A5332012-08-14014 August 2012 NRC End-of-Cycle Slide Presentation 2024-01-08
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Annual Assessment Meeting Nuclear Regulatory Commission
NRC Performance Goals P Maintain safety and protect the environment P Enhance public confidence P Improve effectiveness, efficiency, and realism of processes and decision making P Reduce unnecessary regulatory burden
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response
Key Aspects of the Assessment Program P Objective review of licensee performance P Action Matrix identifies agency response commensurate with safety significance P Increasing safety significance results in:
- Increased levels of inspection
- Involvement of higher levels of NRC and Licensee management
- Increased regulatory action P Plant specific assessment information on NRC public web site
Regional Organization Jim Dyer, Regional Administrator James Caldwell, Deputy Regional Administrator Jan Strasma, Regional Public Affairs Officer Division of Reactor Projects Division of Reactor Safety Geoffrey E. Grant, Director Cynthia Pederson, Director Steven Reynolds, Deputy Director Roy Caniano, Deputy Director Reactor Projects Branch 3 Regional Specialists Ann Marie Stone, Chief Thomas Tongue, Project Engineer Jack Rutkowski, Reactor Engineer Jamie Bond, Intern Braidwood Resident Inspector Office Steven Ray, Senior Resident Inspector Nirodh (Nick) Shah, Resident Inspector
Annual Licensee Assessment Meeting P A public forum for discussion of the licensees performance P NRC will address the licensee performance issues identified in the Annual Assessment Letter P Licensee will respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance
ROP Action Matrix Summary for 2002 P Column 1 - Licensee Response P Column 2 - Regulatory Response P Column 3 - Degraded Cornerstone P Column 4 - Multiple/ Repetitive Degraded Cornerstone P Column 5 - Unacceptable Performance (Nationwide number does not contain Davis Besse)
Column 1 Column 2 Column 3 Column 4 Column 5 Nationwide 59 33 7 3 0 Region I 9 14 2 1 0 Region II 26 4 1 1 0 Region III 11 10 2 0 0 Region IV 13 5 2 1 0
Security & Safeguards Update P Creation of Office of Nuclear Security and Incident Response P Top-to-Bottom Review of Security Program Initiated P Issuance of Orders/ Interim Compensatory Measures (ICM)
P Verification of Licensee Actions on ICM
Security & Safeguards Update P Proposed Revisions to Design Basis Threat P Pending Orders on Fatigue/Guard Training P Initiation of Pilot Force-on-Force Excercise Program
Plant Information P Name of Plant: Braidwood Station, Units 1 and 2 P Plant Operator: Exelon P Number of Units: 2 P Reactor Type and Vendor: PWR/W P Location: Braidwood, IL P Power Output (thermal): 3586.6 megawatts P Source of Circulating Water: Kankakee River
Major Plant Activities in 2002 Braidwood Station, Unit 1 P Unit operated at or near full power throughout the assessment period
Major Plant Activities in 2002 Braidwood Station, Unit 2 P Reactor shutdown for refueling outage (4/20/02)
P 75% power reduction for repairs to feedwater isolation valve (5/28/02)
P Reactor shutdown for rod control troubleshooting and repairs (8/27/02)
P 12% power reduction to address problem with feedwater heaters (11/01/02)
Major Plant Activities in 2002 Braidwood Station, Unit 2 (continued)
P 72% power reduction for testing of feedwater isolation valves (11/02/02)
P 76% power reduction and electric generator taken off electrical grid for balancing (12/26/02)
Plant Performance Summary Braidwood Station, Unit 2 P 11 GREEN Findings
< Maintenance errors
< Failure to maintain proper operational configuration
< Failure to follow procedures
< Inadequate procedures
< Failure to adequately evaluate conditions P All Performance Indicators Within GREEN Band
Plant Performance Summary Braidwood Station, Unit 2 P Operated Safely P Fully met all Cornerstone Objectives P Licensee Response Band of NRC Action Matrix
Plant Performance Summary Braidwood Station, Unit 1 P 6 GREEN Findings
< Failure to follow procedures
< Failure to maintain proper operational configuration
< Inadequate procedures P All Performance Indicators Presently Within GREEN Band
Greater than GREEN Findings and PIs Braidwood Station, Unit 1 P 1 WHITE Finding (2/22/2002)
< Inoperable Pressurizer Power Operated Relief Air Accumulator Check Valves
< Failure to identify cause and prevent recurrence
< Migitation System Cornerstone P 1 Performance Indicator within WHITE band
< Auxiliary Feedwater System Unavailability
< 1st and 2nd Quarters 2002
< Migitation System Cornerstone
Greater Than Green Results and Requirements Braidwood Station, Unit 1 P Degraded Cornerstone Band (1st and 2nd quarters, 2002)
P Required Actions
< Licensee self-assessment with NRC oversight
< NRC perform supplemental inspection
< NRC discuss Licensee performance with Licensee P Regulatory Response Band (3rd and 4th quarters, 2002)
Supplemental Inspection Braidwood Station, Unit 1 P Purpose
< Assure Root Cause for individual and collective concerns are understood
< Independently assess extent of condition
< Assure Licensee corrective actions are appropriate to prevent recurrence P Conducted November 4 - December 4, 2002
Supplemental Inspection Results Braidwood Station, Unit 1 P Report Conclusions
< Unit Operated Safety
< No additional findings or violations
< Liscensee investigation was in-depth
< Extent of condition addressed Generic Concerns
< Planned corrective actions appear adequate to prevent recurrence P NRC Problem Identification and Resolution Inspection Scheduled for 2003
Plant Performance Summary Braidwood Station, Unit 1 P Operated Safely P Met Cornerstone Objectives P Regulatory Response Band of NRC Action Matrix
Contacts for additional information for:
Braidwood Station, Units 1 and 2 P Regional Public Affairs Officer:
< Name: Jan Strasma
< Phone: 630-829-9663 P State Liaison Officer:
< Name: Roland Lickus
< Phone: 630-829-9660 P Branch Chief:
< Name: Ann Marie Stone
< Phone: 630-829-9729 P Senior Resident Inspector:
< Name: Steve Ray
< Phone: 815-458-2852
Contacting the NRC P Report an emergency
< (301) 816-5100 (call collect)
P Report a safety concern:
< (800) 695-7403
< Allegation@nrc.gov P General information or questions
< www.nrc.gov
< Select What We Do for Public Affairs
An Action Matrix is used to assess overall plant safety performance and specify thresholds for NRC Enforcement Actions L ic e n s e e R e s p o n s e R e g u la to ry R e s p o n s e D e g ra d e d C o rn e rs to n e M u lt ip l e / R e p e titi ve U n a c c e p ta b le C o lu m n C o lu m n C olum n D e g ra d e d C o rn e rs to n e P e rfo rm a n c e C o lu m n C o lu m n R A ll A s s e ss m e n t In p u ts O n e o r T w o W h i te O n e D e g ra d e d R e p e tit iv e D e g ra d e d O ve ra ll U n a c c e p ta b l e E (P e rf o rm a n c e In p u ts (i n d iff e re n t C o rn e rs to n e (2 W h i te C o rn e rs to n e , M u l tip le P e rfo rm a n c e ; P l a n ts S In d ic a t o rs (P Is ) a n d c o rn e rs to n e s ) in a In p u ts o r 1 Y e ll o w D e g ra d e d N o t P e rm itte d to In s p e c tio n F i n d in g s ) S tra te g ic P e rfo rm a n c e In p u t) o r a n y 3 W h it e C o rn e rs to n e s , M u lti p l e O p e ra t e W ith i n t h is U
G re e n ; C o rn e rs to n e A re a ; C o rn e rs to n e In p u ts i n a S tra t e g ic Y e l lo w In p u ts , o r 1 R e d B a n d , U n a c c e p ta b le L O b je c t iv e s F u l ly M e t O b je c t iv e s F u l ly M e t P e rfo rm a n c e A re a ; In p u t; C o rn e rs to n e M a rg in to S a fe ty T C o rn e rs to n e O b je c t iv e s O b je c ti ve s M e t w ith S M e t w it h M in im a l L o n g s ta n d i n g Is s u e s o r R e d u c t io n in S a f e ty S ig n if ic a n t R e d u c t io n in M a rg i n S a fe ty M a rg i n R R e g u l a to ry N on e B ra n c h C h i e f (B C ) o r D D o r R e g io n a l R A (o r E D O ) M e e t w ith C o m m is s io n m e e t in g E P e rfo rm a n c e D iv is io n D ire c t o r (D D ) A d m in is tra to r (R A ) S e n io r L ic e n s e e w ith S e n i o r L ic e n s e e S M e e tin g M e e t w ith L ic e n s e e M e e t w ith L ic e n s e e M a na gem en t M a nag em en t P L ic e n s e e A c tio n L ic e n s e e C o rre c ti ve L ic e n s e e ro o t c a u s e L ic e n s e e S e lf L ic e n s e e P e rfo rm a n c e O A c tio n e v a l u a tio n a n d As s e s s m e n t w i th N R C Im p ro v e m e n t P l a n w ith N c o rre c ti ve a c tio n w i th O ve rs ig h t N R C O v e rs ig h t S N R C O ve rs ig h t E
N R C In s p e c t io n R is k- In fo rm e d B a s e lin e B a s e l in e a n d B a s e l in e a n d B a s e l in e a n d In s p e c tio n s u p p le m e n ta l s u p p le m e n ta l s u p p le m e n ta l P ro g ra m in s p e c tio n p ro c e d u re in s p e c tio n p ro c e d u re in s p e c tio n p ro c e d u re 95 00 1 95 002 95 003 R e g u l a to ry A c ti o n s N on e S up plem ent al S u p p le m e n ta l -1 0 C F R 2 .2 0 4 D F I O rd e r to M o d i fy ,
in s p e c tio n o n l y in s p e c tio n o n ly -1 0 C F R 5 0 .5 4 (f) L e tte r S us pen d, or R ev ok e
- C A L /O rd e r L ic e n s e d A c ti vi tie s C A s s e ss m e n t L e tte rs B C o r D D re vi e w /s ig n D D re v ie w /s i g n R A re v ie w /s i g n R A re v ie w /s i g n O a s s e s sm e n t re p o rt (w / a s s e s sm e n t re p o rt a s s e ss m e n t re p o rt a s s e ss m e n t re p o rt M in s p e c tio n p la n ) (w / i n s p e c ti o n p la n ) (w / in s p e c tio n p la n ) (w / in s p e c tio n p la n )
M C o m m iss io n In fo rm e d U
N I A n n u a l P u b l ic S R I o r B C M e e t w ith B C o r D D M e e t w it h R A (or d e s ig n e e ) E D O (o r C o m m iss io n ) C o m m is s io n M e e t in g C M e e tin g L ic e n s e e L ic e n s e e D is c u ss P e rf o rm a n c e D is c u ss P e rf o rm a n c e w ith S e n i o r L ic e n s e e A w ith L ic e n s e e w ith S e n io r L ic e n s e e M a nag em en t T M a na gem en t I
O N
IN C REASING SAFETY SIGN IFICA NC E ---------->
Significance Threshold Inspection Findings Green: Very low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue