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{{#Wiki_filter:Omaha Public Power District | {{#Wiki_filter:Omaha Public Power District May 23, 2014 LICENSEE: | ||
FACILITY: | Omaha Public Power District (OPPD) | ||
FACILITY: | |||
Fort Calhoun Station | |||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF MAY 13, 2014 MEETING WITH OMAHA PUBLIC POWER DISTRICT On May 13, 2014, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD), at the Omaha Marriott located at 10220 Regency Circle, Omaha, Nebraska. | OF MAY 13, 2014 MEETING WITH OMAHA PUBLIC POWER DISTRICT On May 13, 2014, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD), at the Omaha Marriott located at 10220 Regency Circle, Omaha, Nebraska. | ||
| Line 25: | Line 26: | ||
http://www.nrc.gov/info-finder/reactor/fcs/special-oversight.html. | http://www.nrc.gov/info-finder/reactor/fcs/special-oversight.html. | ||
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Public Electronic Reading Room page of the NRCs public web site at: http://www.nrc.gov/reading-rm/adams.html. | In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Public Electronic Reading Room page of the NRCs public web site at: http://www.nrc.gov/reading-rm/adams.html. | ||
CONTACT: Michael Hay, RIV/DRP (817) 200-1147 Docket No.: 50-285 | CONTACT: Michael Hay, RIV/DRP (817) 200-1147 Docket No.: 50-285 NRC Presentation Slides : | ||
NRC Presentation Slides : | OPPD Presentation Slides | ||
OPPD Presentation Slides | |||
SUNSI Review By: MCH ADAMS Yes No Publicly Available Non-Publicly Available Non-Sensitive Sensitive Keyword: | |||
By: MCH | SUNSI REV Compl. | ||
OFFICE | OFFICE RIV/C:DRP/F NAME MCHay:DLL/PBH SIGNATURE | ||
DATE | /RA/ | ||
DATE 05/23/14 | |||
Omaha Public Power District Electronic distribution by RIV: | |||
RIV Regional Administrator (Marc.Dapas@nrc.gov) | RIV Regional Administrator (Marc.Dapas@nrc.gov) | ||
RIV Deputy Regional Administrator (Steve.Reynolds@nrc.gov) | RIV Deputy Regional Administrator (Steve.Reynolds@nrc.gov) | ||
| Line 60: | Line 63: | ||
NRR Project Manager (Lynnea.Wilkins@nrc.gov) | NRR Project Manager (Lynnea.Wilkins@nrc.gov) | ||
ACES (R4ACES@nrc.gov) | ACES (R4ACES@nrc.gov) | ||
FortCalhounStation PublicMeeting NuclearRegulatoryCommission May13,2014 Omaha,Nebraska 1 | |||
===Introductions=== | ===Introductions=== | ||
* Welcome | |||
* Welcome | * IntroductionofNRCpersonnel 2 | ||
* | PurposeofMeeting | ||
* | * NRCwillpresentstatusofregulatoryactivities associatedwiththeFortCalhounStation | ||
* | * OPPD willpresentdetailsofFortCalhoun Stationperformanceimprovementinitiatives | ||
* Publiccommentsandquestions OpeningRemarks | |||
* | * TonyVegel,Director,DivisionofReactorSafety | ||
* | - Chair,FortCalhounStationOversightPanel | ||
* LouiseLund,DeputyDirector,DivisionofOperating ReactorLicensing | |||
* | - ViceChair,FortCalhounStationOversightPanel 4 | ||
PostRestartCAL OPPDcommittedtotheNRCtocontinue implementingimprovementinitiativesinkey areasandaddressspecifictechnicalitems 5 | |||
NRCActionsCompleted | |||
* NRCissuedPostRestartConfirmatoryAction LetterDecember17,2013 | |||
- Keyareasforsustainedperformanceimprovement | |||
* HumanPerformance | |||
* SafetyCulture | |||
* CorrectiveActionProcess | |||
* DesignBasisReconstitution 6 | |||
NRCAssessmentActivities | |||
* Routineinspections | |||
- ResidentInspectors | |||
- Regionalinspections | |||
* Teaminspection(Summer2014) | |||
- AssessCorrectiveActionProcesseffectiveness | |||
- AssessPostRestartConfirmatoryActionLetter items 7 | |||
InSummary | |||
* IncreasedNRCoversightactivitiesremain | |||
* NRCcontinuestoimplementindependentand thoroughinspectionactivitiestoassessstation performanceimprovementprogress 8 | |||
OPPDPresentation 9 | |||
ContactingtheNRC | |||
* Reportanemergency | |||
- (301)8165100(callcollect) | |||
* Reportasafetyconcern | |||
- (800)6957403 | |||
- Allegation@nrc.gov | |||
* Generalinformationorquestions | |||
- www.nrc.gov 10 11 | |||
1 OPPDs Fort Calhoun Station Driving To Excellence Public meeting with the U.S. Nuclear Regulatory Commission May 13, 2014 2 | |||
* Plant Status | |||
* Problem Identification and Resolution | |||
* Engineering Products | * Engineering Products | ||
* Design and Licensing Basis Control and Use | * Design and Licensing Basis Control and Use | ||
| Line 107: | Line 113: | ||
* Integration | * Integration | ||
* Nuclear Oversight | * Nuclear Oversight | ||
* Closing Remarks | * Closing Remarks Topics for Discussion 3 | ||
Untreated Injuries: | Plant Status Sitewide Industrial Safety Injury Comparison Summary 2013 2014 Untreated Injuries: | ||
11 3 | |||
First Aid Injuries: | |||
15 0 | |||
Occupational Safety and Health Administration (OSHA) Recordable: | |||
4 0 | |||
Lost-Time / Restricted: | |||
4 0 | |||
4 Plant Status Industry best is in the range of 0 to 2 sitewide clock resets per year Sitewide Human Performance 2014 Sitewide Clock Reset: | |||
March 17: Stator water cooling leak caused an automatic trip of the unit | |||
Plant Status | 5 134 58 41 8 | ||
8 0 | |||
20 40 60 80 100 120 140 2011 2012 2013 | |||
* 2014 Year-to-Date | *2014 | ||
* Corrective Action Program (CAP) changes implemented to | **2015 | ||
**2016 6* | |||
Plant Status Industry best is in range of 6 to 12 dept. clock resets per year Department-Level Human Performance | |||
** Department-Level Performance Goals | |||
* 2014 Year-to-Date 61 6 | |||
Plant Status Capacity Factor 20 30 40 50 60 70 80 90 100 Dec-13 Jan-14 Feb-14 Mar-14 Apr-14 May-14 Jun-14 Jul-14 Aug-14 Sep-14 Oct-14 Nov-14 Dec-14 Percent Historical Data Site Performance Goal Industry Top Quartile Year End Projection 93.2% | |||
since restart 7 | |||
Operational Challenges | |||
* Shut down due to maintenance evolution on stator water system | |||
* Down power due to VA-46 Control Room Air Conditioning Units Plant Status 8 | |||
* Corrective Action Program (CAP) changes implemented to improve OPPDs detection and correction of plant issues | |||
- Provide an updated status of actions and effectiveness reviews | |||
* Results | * Results | ||
- Focused area self-assessment insights | |||
- Performance indicators insights | |||
- Trending insights | |||
- Areas providing challenges and actions to address Problem Identification and Resolution | |||
9 | |||
* Observations and trends for: | |||
* Observations and trends for: | - Corrective Action Products | ||
- Quality of Engineering Products | |||
- Operability Evaluations | |||
- Reportability Determinations Engineering Products Engineering M arch 2013 Engineering M arch 2014 1 | |||
0 Overall 392 124 65% | |||
66% | |||
42% | |||
DCARB | 74% | ||
4 0 | |||
RCA Rejection Rate (3 month avg.) | 1 0 | ||
0 0 | |||
DCARB | 0% | ||
0% | |||
29% | |||
20% | |||
58% | |||
13% | |||
57% | |||
0% | |||
0% | |||
0% | |||
30% | |||
15% | |||
50% | |||
25% | |||
Engineering CAP Health: March 2013 - March 2014 Comparison MRC CR Closure Rejection Rate (3 month avg.) | |||
DCARB CR Closure Rejection Rate (3 month avg.) | |||
DCARB ACA (Tier 1) Rejection Rate (3 month avg.) | |||
RCA Rejection Rate (3 month avg.) | |||
Number of Ineffective Effective Review s for Root Causes Only (1 month) | |||
Number of CAP Meeting Observations (1 month) | |||
Analysis Number of Repeat Events (1 year) | |||
DCARB RCA Rejection Rate (3 month avg.) | |||
DCARB ACA (Tier 2) Rejection Rate (3 month avg.) | |||
ACA (Tier 1) Rejection Rate (3 month avg.) | |||
Number of Significant Events (1 year) | |||
Identification and Screening Meetings Number of CRs Identified (1 month) | |||
Self-Identification Ratio - Level 1,2,3 CRs (1 month) 3 Month Engagement Ratio Coding and Analysis (trending) | |||
Event Code Backlog (1 month) | |||
Cause Code Backlog (1 month) | |||
Number of CRs Coded w ith Adverse Trend (1 month) 10 Engineering M arch 2013 Engineering M arch 2014 47 7 | |||
9 0 | |||
9 7 | |||
8 0 | |||
151 83 252 380 241 68 15 15 965 1,148 212 733 1,930 2,294 261 124 26 15 1,785 1,270 465 144 774 956 320 321 917 497 Timeliness Overdue Priorities (1 month) | |||
Number of Overdue Non-ACA and Non-RCA REs (1 month) | |||
Number of Overdue Corrective Actions (3 month total) | |||
Average Time to Perform RCAs (12 month avg.) | |||
Number of Overdue Simple Causes (1 month) | |||
Average Time to Perform Tier 2 ACAs (1 month) | |||
Average Time to Perform Tier 1 ACAs (1 month avg.) | |||
Median Age of Open Non-Outage AIs (days) (1 month) | |||
Average Time to Perform Simple Causes (1 month) | |||
Oldest Open Non-Outage AI (days) (1 month) | |||
Number of Open Non-Outage AIs > 365 days (1 month) | |||
Number of Open CA's (1 month) | |||
Number of Open CAPR's (1 month) | |||
Number of Open Outage-Related AIs (1 month) | |||
Engineering CAP Health: March 2013 - March 2014 Comparison CRs in Ready to Close (1 month) | |||
Number of Open RA's > 365 days (1 month) | |||
Median Age of Open RA's (days) (1 month) | |||
Number of Open RE's (1 month) 11 12 0 | |||
500 1000 1500 2000 2500 3000 3500 4000 Number of Action items Dec13 Jan14 Feb14 Mar14 Apr14 Number of AC Actions 3,683 3,459 3,230 2,652 2,374 Closure Rate for Engineering of Active Action items A, B, C | |||
13 | |||
* Observations and trends for: | * Observations and trends for: | ||
- Corrective Action Products | |||
- Quality of Engineering Products | |||
- Operability Evaluations | |||
- Reportability Determinations Engineering Products 14 50.59 Screens Applicability Determinations Applicability Determinations 72.48 Screens Engineering Products Immediate Operability Determinations Operability Evaluations Reportability Evaluations 50.59 Evaluations Total Percent Accepted 2013 82.80% | |||
94.29% | |||
98.53% | |||
90.75% | |||
98.00% | |||
70.30% | |||
80.43% | |||
78.38% | |||
94.87% | |||
Percent Accepted 2014 100.00% | |||
96.55% | |||
96.43% | |||
92.31% | |||
98.49% | |||
66.67% | |||
81.25% | |||
0 97.56% | |||
0.00% | |||
20.00% | |||
40.00% | |||
60.00% | |||
80.00% | |||
100.00% | 100.00% | ||
120.00% | |||
Percent of Accepted EAG Products Engineering Assurance Group Products 2013-2014 Comparison 15 Design and Licensing Basis Control and Use | |||
2013 | |||
2014 | |||
* OPPDs post-restart commitment states: | * OPPDs post-restart commitment states: | ||
- After restart, OPPD will complete a significant effort to perform a risk-focused reconstitution of the: | |||
Design basis, Licensing basis, and Updated Safety Analysis Report | |||
- As part of this project, OPPD will: | |||
Ensure proper classification of equipment, Convert to a safety-related Q List approach for equipment classification, and Complete a key calculation review | |||
- A pilot program will be completed during 2014 on a selected system to check & adjust the process, scheduling and resource allocation | |||
- Complete the reconstitution project before the end of the 4th quarter, 2018 15 16 Design and Licensing Basis Control and Use | |||
* Project Activities Completed or In Progress | * Project Activities Completed or In Progress | ||
- January 2014 - Commenced drafting project request for proposal (COMPLETE) | |||
- February 7, 2014 - Issue project request for proposal to vendors (COMPLETE) | |||
- March 28, 2014 - Vendor proposals due (COMPLETE) | |||
- April 30, 2014 - Award project contract (COMPLETE) | |||
- May 5, 2014 - Commence project (COMPLETE) | |||
- January 2014: Commenced review of key calculations Pre-restart 93 calculations were reviewed, with 45 revisions recommended 330 of 382 key calculations have been reviewed with 147 revisions recommended Calculation issues identified to date have been determined to be not consequential, but calculations must be brought up to todays standards 16 | |||
Design and Licensing Basis | 17 Design and Licensing Basis Control and Use | ||
* Project Activities to be Completed | * Project Activities to be Completed | ||
- June 30, 2014 - Complete Phase 1 (Develop project processes/procedures) | |||
- December 31, 2014 - Complete Phase 2 (Pilot program - NRC commitment) | |||
- February 1, 2015 - Complete project status assessment Approximately every six months between Feb. 1, 2015, and Dec. 31, 2018 - | |||
Perform project status assessments | |||
- February 28, 2015 - Complete Phase 3 (Incorporate lessons learned from pilot program) | |||
- December 31, 2018 - Complete Phase 4 (Complete reconstitution project - NRC commitment) | |||
- February 1, 2019 - Complete project final effectiveness review 17 18 Design and Licensing Basis Control and Use | |||
* Project Oversight | * Project Oversight | ||
- Oversight to be provided as follows: | |||
* OPPD project manager who is independent of the production work | |||
* OPPD project manager who is independent of the production work | |||
* OPPD/Exelon senior management | * OPPD/Exelon senior management | ||
* Periodic project status assessments | |||
* Periodic | |||
* Independent project oversight board | * Independent project oversight board | ||
* FCS Nuclear Oversight Department | * FCS Nuclear Oversight Department | ||
* Nuclear Safety Review Board 18 19 | |||
* Nuclear Safety Review Board | |||
* OPPD committed to: | * OPPD committed to: | ||
Evaluate the structural design margin for the containment internal structure, and reactor cavity and compartments, and resolve any deficiencies in accordance with FCSs CAP Regarding Beams 22A and Beam 22B under Safety Injection Tanks 6B/D, resolve any deficiencies in accordance with the CAP Resolve and correct any deficiencies surrounding the reactor vessel head stand (RVHS) prior to its next use Containment Internal Structures 20 | |||
* Resolution strategy for 2015 refueling outage | * Resolution strategy for 2015 refueling outage | ||
- Install columns in the basement of the containment building under floor Beams 22A and Beam 22B to reduce the loading on the two floor beams | |||
- Replace the existing RVHS pedestal supports with a structural steel box frame that spans the floor and transfers the loads to adjacent walls and columns | |||
- Preliminary design will be complete by third quarter 2014 Containment Internal Structures | |||
Site Operational Focus | 21 Site Operational Focus Procedures | ||
* Procedure focus | * Procedure focus | ||
- Quality | |||
- Use and Adherence | |||
- Level of Detail | |||
* Cornerstone for performance | |||
- Emergency and Abnormal Operations Demonstrated using simulator Upgrades continue | |||
- Normal Operations Support plant operations Require verbatim compliance | |||
- Administrative Station-wide effort 22 Integration status | |||
* More than 4,000 tasks completed | * More than 4,000 tasks completed | ||
- Design Review Board | |||
- Human Performance Fundamentals | |||
- Nuclear Oversight Processes | |||
- Learning Programs | |||
- Operations Standards and Expectations | |||
* Approximately 8,000 tasks remain, with 6,000 of these | * Approximately 8,000 tasks remain, with 6,000 of these scheduled for completion in 2014 | ||
- Weekly integration status meetings to review schedule adherence | |||
* Lessons Learned | * Lessons Learned | ||
- Data Sharing | |||
- Gap Analysis The Exelon Nuclear Management Model 23 Nuclear Oversight Independent Assessment Plant Observations and Performance 24 Five Flooding Recovery Post-Restart Action commitments outlined in Section 2 of the Confirmatory Action Letter (CAL) | |||
Three of the Section 2 Flooding Recovery Post-Restart Action commitments have been submitted to the NRC resident inspectors Item 4.4.3.1 - Gather flood response lessons learned through condition report reviews to determine if procedure or strategy changes should be implemented (completed December 12, 2012) | |||
Item 4.4.3.3 - Implement procedure and strategy changes as indicated by the lessons learned review conducted (completed February 20, 2013) | |||
Item 1.2.3.21 - Inspect tank and equipment on demineralized water tank for damage (completed February 10, 2014) | |||
Two of the Section 2 Flooding Recovery Post-Restart Action commitments are scheduled Item 4.4.3.2 - Review flood design basis and determine if the 2011 flood event provides additional information that should drive design basis changes Item 1.2.3.82 - Perform independent spent fuel storage installation route load test Flooding Recovery Action Plans | |||
25 | |||
* Project scope Flooding reevaluation and seismic evaluation Flooding and seismic walkdowns | |||
Results submitted to the NRC | |||
Actions ongoing Mitigating strategies for beyond design basis external events Strategy developed and submitted to NRC | |||
Portable equipment pre-staged at FCS | |||
Procedures (Admin/Operations/PM/Testing) | |||
Staffing | |||
Fukushima Response Project | Communications (internal and external) | ||
Spent Fuel Pool Instrumentation (SFPI) | |||
SFPI modifications submitted to the NRC Fukushima Response Project Portable Submersible Pumps 26 | |||
* Plant Status | * Plant Status | ||
* Problem Identification and Resolution | * Problem Identification and Resolution | ||
* Engineering Products | |||
* Engineering Products | * Design and Licensing Basis Control and Use | ||
* Design and Licensing Basis Control | |||
* Containment Internal Structures | * Containment Internal Structures | ||
* Site Operational Focus | |||
* Site Operational Focus | * Integration | ||
* Integration | |||
* Nuclear Oversight | * Nuclear Oversight | ||
* Closing Remarks Closing Remarks }} | |||
* Closing Remarks | |||
Latest revision as of 20:35, 10 January 2025
| ML14143A289 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 05/23/2014 |
| From: | Hay M NRC/RGN-IV/DRP |
| To: | |
| Hay M | |
| References | |
| Download: ML14143A289 (13) | |
Text
Omaha Public Power District May 23, 2014 LICENSEE:
Omaha Public Power District (OPPD)
FACILITY:
Fort Calhoun Station
SUBJECT:
SUMMARY
OF MAY 13, 2014 MEETING WITH OMAHA PUBLIC POWER DISTRICT On May 13, 2014, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD), at the Omaha Marriott located at 10220 Regency Circle, Omaha, Nebraska.
The NRC presented the status of Inspection Manual Chapter 0350 oversight activities at Fort Calhoun Station, and the Omaha Public Power District presented details of their actions for continued performance improvement following the plant restart in December, 2013. The slide presentations are available electronically from the NRCs Agency wide Documents Access and Management System (ADAMS) and are enclosed in this notice. A video of the public meeting will be posted on the web site devoted to the special oversight at Fort Calhoun Station, available at:
http://www.nrc.gov/info-finder/reactor/fcs/special-oversight.html.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Public Electronic Reading Room page of the NRCs public web site at: http://www.nrc.gov/reading-rm/adams.html.
CONTACT: Michael Hay, RIV/DRP (817) 200-1147 Docket No.: 50-285 NRC Presentation Slides :
OPPD Presentation Slides
SUNSI Review By: MCH ADAMS Yes No Publicly Available Non-Publicly Available Non-Sensitive Sensitive Keyword:
SUNSI REV Compl.
OFFICE RIV/C:DRP/F NAME MCHay:DLL/PBH SIGNATURE
/RA/
DATE 05/23/14
Omaha Public Power District Electronic distribution by RIV:
RIV Regional Administrator (Marc.Dapas@nrc.gov)
RIV Deputy Regional Administrator (Steve.Reynolds@nrc.gov)
RIV DRP Director (Kriss.Kennedy@nrc.gov)
RIV DRP Deputy Director (Troy.Pruett@nrc.gov)
RIV DRS Director (Anton.Vegel@nrc.gov)
RIV DRS Deputy Director (Jeff.Clark@nrc.gov)
RIV Senior Resident Inspector (John.Kirkland@nrc.gov)
RIV Resident Inspector (Jacob.Wingebachl@nrc.gov)
RIV Branch Chief, DRP/F (Michael.Hay@nrc.gov)
Project Engineer, DRP/F (Chris.Smith@nrc.gov)
FCS Administrative Assistant (Janise.Schwee@nrc.gov)
RIV Public Affairs Officer (Victor.Dricks@nrc.gov)
RIV Public Affairs Officer (Lara.Uselding@nrc.gov)
RIV Project Manager (Joseph.Sebrosky@nrc.gov)
RIV Branch Chief, DRS/TSB (Geoffrey.Miller@nrc.gov)
RIV RITS Coordinator (Marisa.Herrera@nrc.gov)
RIV Regional Counsel (Karla.Fuller@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
Technical Support Assistant (Loretta.Williams@nrc.gov)
OEMail Resource OEWEB Resource (Sue.Bogle@nrc.gov)
RIV/ETA: OEDO (Joseph.Nick@nrc.gov)
RIV RSLO (Bill.Maier@nrc.gov)
MC 0350 Panel Vice Chairman (Louise.Lund@nrc.gov)
MC 0350 Panel Member (Michael.Balazik@nrc.gov)
MC 0350 Panel Member (Michael.Markley@nrc.gov)
NRR Project Manager (Lynnea.Wilkins@nrc.gov)
ACES (R4ACES@nrc.gov)
FortCalhounStation PublicMeeting NuclearRegulatoryCommission May13,2014 Omaha,Nebraska 1
Introductions
- Welcome
- IntroductionofNRCpersonnel 2
PurposeofMeeting
- NRCwillpresentstatusofregulatoryactivities associatedwiththeFortCalhounStation
- OPPD willpresentdetailsofFortCalhoun Stationperformanceimprovementinitiatives
- Publiccommentsandquestions OpeningRemarks
- TonyVegel,Director,DivisionofReactorSafety
- Chair,FortCalhounStationOversightPanel
- LouiseLund,DeputyDirector,DivisionofOperating ReactorLicensing
- ViceChair,FortCalhounStationOversightPanel 4
PostRestartCAL OPPDcommittedtotheNRCtocontinue implementingimprovementinitiativesinkey areasandaddressspecifictechnicalitems 5
NRCActionsCompleted
- NRCissuedPostRestartConfirmatoryAction LetterDecember17,2013
- Keyareasforsustainedperformanceimprovement
- HumanPerformance
- SafetyCulture
- CorrectiveActionProcess
- DesignBasisReconstitution 6
NRCAssessmentActivities
- Routineinspections
- ResidentInspectors
- Regionalinspections
- Teaminspection(Summer2014)
- AssessCorrectiveActionProcesseffectiveness
- AssessPostRestartConfirmatoryActionLetter items 7
InSummary
- IncreasedNRCoversightactivitiesremain
- NRCcontinuestoimplementindependentand thoroughinspectionactivitiestoassessstation performanceimprovementprogress 8
OPPDPresentation 9
ContactingtheNRC
- Reportanemergency
- (301)8165100(callcollect)
- Reportasafetyconcern
- (800)6957403
- Allegation@nrc.gov
- Generalinformationorquestions
- www.nrc.gov 10 11
1 OPPDs Fort Calhoun Station Driving To Excellence Public meeting with the U.S. Nuclear Regulatory Commission May 13, 2014 2
- Plant Status
- Problem Identification and Resolution
- Engineering Products
- Design and Licensing Basis Control and Use
- Containment Internal Structures
- Site Operational Focus
- Integration
- Nuclear Oversight
- Closing Remarks Topics for Discussion 3
Plant Status Sitewide Industrial Safety Injury Comparison Summary 2013 2014 Untreated Injuries:
11 3
First Aid Injuries:
15 0
Occupational Safety and Health Administration (OSHA) Recordable:
4 0
Lost-Time / Restricted:
4 0
4 Plant Status Industry best is in the range of 0 to 2 sitewide clock resets per year Sitewide Human Performance 2014 Sitewide Clock Reset:
March 17: Stator water cooling leak caused an automatic trip of the unit
5 134 58 41 8
8 0
20 40 60 80 100 120 140 2011 2012 2013
- 2014
- 2015
- 2016 6*
Plant Status Industry best is in range of 6 to 12 dept. clock resets per year Department-Level Human Performance
- Department-Level Performance Goals
- 2014 Year-to-Date 61 6
Plant Status Capacity Factor 20 30 40 50 60 70 80 90 100 Dec-13 Jan-14 Feb-14 Mar-14 Apr-14 May-14 Jun-14 Jul-14 Aug-14 Sep-14 Oct-14 Nov-14 Dec-14 Percent Historical Data Site Performance Goal Industry Top Quartile Year End Projection 93.2%
since restart 7
Operational Challenges
- Shut down due to maintenance evolution on stator water system
- Down power due to VA-46 Control Room Air Conditioning Units Plant Status 8
- Corrective Action Program (CAP) changes implemented to improve OPPDs detection and correction of plant issues
- Provide an updated status of actions and effectiveness reviews
- Results
- Focused area self-assessment insights
- Performance indicators insights
- Trending insights
- Areas providing challenges and actions to address Problem Identification and Resolution
9
- Observations and trends for:
- Corrective Action Products
- Quality of Engineering Products
- Operability Evaluations
- Reportability Determinations Engineering Products Engineering M arch 2013 Engineering M arch 2014 1
0 Overall 392 124 65%
66%
42%
74%
4 0
1 0
0 0
0%
0%
29%
20%
58%
13%
57%
0%
0%
0%
30%
15%
50%
25%
Engineering CAP Health: March 2013 - March 2014 Comparison MRC CR Closure Rejection Rate (3 month avg.)
DCARB CR Closure Rejection Rate (3 month avg.)
DCARB ACA (Tier 1) Rejection Rate (3 month avg.)
RCA Rejection Rate (3 month avg.)
Number of Ineffective Effective Review s for Root Causes Only (1 month)
Number of CAP Meeting Observations (1 month)
Analysis Number of Repeat Events (1 year)
DCARB RCA Rejection Rate (3 month avg.)
DCARB ACA (Tier 2) Rejection Rate (3 month avg.)
ACA (Tier 1) Rejection Rate (3 month avg.)
Number of Significant Events (1 year)
Identification and Screening Meetings Number of CRs Identified (1 month)
Self-Identification Ratio - Level 1,2,3 CRs (1 month) 3 Month Engagement Ratio Coding and Analysis (trending)
Event Code Backlog (1 month)
Cause Code Backlog (1 month)
Number of CRs Coded w ith Adverse Trend (1 month) 10 Engineering M arch 2013 Engineering M arch 2014 47 7
9 0
9 7
8 0
151 83 252 380 241 68 15 15 965 1,148 212 733 1,930 2,294 261 124 26 15 1,785 1,270 465 144 774 956 320 321 917 497 Timeliness Overdue Priorities (1 month)
Number of Overdue Non-ACA and Non-RCA REs (1 month)
Number of Overdue Corrective Actions (3 month total)
Average Time to Perform RCAs (12 month avg.)
Number of Overdue Simple Causes (1 month)
Average Time to Perform Tier 2 ACAs (1 month)
Average Time to Perform Tier 1 ACAs (1 month avg.)
Median Age of Open Non-Outage AIs (days) (1 month)
Average Time to Perform Simple Causes (1 month)
Oldest Open Non-Outage AI (days) (1 month)
Number of Open Non-Outage AIs > 365 days (1 month)
Number of Open CA's (1 month)
Number of Open CAPR's (1 month)
Number of Open Outage-Related AIs (1 month)
Engineering CAP Health: March 2013 - March 2014 Comparison CRs in Ready to Close (1 month)
Number of Open RA's > 365 days (1 month)
Median Age of Open RA's (days) (1 month)
Number of Open RE's (1 month) 11 12 0
500 1000 1500 2000 2500 3000 3500 4000 Number of Action items Dec13 Jan14 Feb14 Mar14 Apr14 Number of AC Actions 3,683 3,459 3,230 2,652 2,374 Closure Rate for Engineering of Active Action items A, B, C
13
- Observations and trends for:
- Corrective Action Products
- Quality of Engineering Products
- Operability Evaluations
- Reportability Determinations Engineering Products 14 50.59 Screens Applicability Determinations Applicability Determinations 72.48 Screens Engineering Products Immediate Operability Determinations Operability Evaluations Reportability Evaluations 50.59 Evaluations Total Percent Accepted 2013 82.80%
94.29%
98.53%
90.75%
98.00%
70.30%
80.43%
78.38%
94.87%
Percent Accepted 2014 100.00%
96.55%
96.43%
92.31%
98.49%
66.67%
81.25%
0 97.56%
0.00%
20.00%
40.00%
60.00%
80.00%
100.00%
120.00%
Percent of Accepted EAG Products Engineering Assurance Group Products 2013-2014 Comparison 15 Design and Licensing Basis Control and Use
- OPPDs post-restart commitment states:
- After restart, OPPD will complete a significant effort to perform a risk-focused reconstitution of the:
Design basis, Licensing basis, and Updated Safety Analysis Report
- As part of this project, OPPD will:
Ensure proper classification of equipment, Convert to a safety-related Q List approach for equipment classification, and Complete a key calculation review
- A pilot program will be completed during 2014 on a selected system to check & adjust the process, scheduling and resource allocation
- Complete the reconstitution project before the end of the 4th quarter, 2018 15 16 Design and Licensing Basis Control and Use
- Project Activities Completed or In Progress
- January 2014 - Commenced drafting project request for proposal (COMPLETE)
- February 7, 2014 - Issue project request for proposal to vendors (COMPLETE)
- March 28, 2014 - Vendor proposals due (COMPLETE)
- April 30, 2014 - Award project contract (COMPLETE)
- May 5, 2014 - Commence project (COMPLETE)
- January 2014: Commenced review of key calculations Pre-restart 93 calculations were reviewed, with 45 revisions recommended 330 of 382 key calculations have been reviewed with 147 revisions recommended Calculation issues identified to date have been determined to be not consequential, but calculations must be brought up to todays standards 16
17 Design and Licensing Basis Control and Use
- Project Activities to be Completed
- June 30, 2014 - Complete Phase 1 (Develop project processes/procedures)
- December 31, 2014 - Complete Phase 2 (Pilot program - NRC commitment)
- February 1, 2015 - Complete project status assessment Approximately every six months between Feb. 1, 2015, and Dec. 31, 2018 -
Perform project status assessments
- February 28, 2015 - Complete Phase 3 (Incorporate lessons learned from pilot program)
- December 31, 2018 - Complete Phase 4 (Complete reconstitution project - NRC commitment)
- February 1, 2019 - Complete project final effectiveness review 17 18 Design and Licensing Basis Control and Use
- Project Oversight
- Oversight to be provided as follows:
- OPPD project manager who is independent of the production work
- OPPD/Exelon senior management
- Periodic project status assessments
- Independent project oversight board
- FCS Nuclear Oversight Department
- Nuclear Safety Review Board 18 19
- OPPD committed to:
Evaluate the structural design margin for the containment internal structure, and reactor cavity and compartments, and resolve any deficiencies in accordance with FCSs CAP Regarding Beams 22A and Beam 22B under Safety Injection Tanks 6B/D, resolve any deficiencies in accordance with the CAP Resolve and correct any deficiencies surrounding the reactor vessel head stand (RVHS) prior to its next use Containment Internal Structures 20
- Resolution strategy for 2015 refueling outage
- Install columns in the basement of the containment building under floor Beams 22A and Beam 22B to reduce the loading on the two floor beams
- Replace the existing RVHS pedestal supports with a structural steel box frame that spans the floor and transfers the loads to adjacent walls and columns
- Preliminary design will be complete by third quarter 2014 Containment Internal Structures
21 Site Operational Focus Procedures
- Procedure focus
- Quality
- Use and Adherence
- Level of Detail
- Cornerstone for performance
- Emergency and Abnormal Operations Demonstrated using simulator Upgrades continue
- Normal Operations Support plant operations Require verbatim compliance
- Administrative Station-wide effort 22 Integration status
- More than 4,000 tasks completed
- Design Review Board
- Human Performance Fundamentals
- Nuclear Oversight Processes
- Learning Programs
- Operations Standards and Expectations
- Approximately 8,000 tasks remain, with 6,000 of these scheduled for completion in 2014
- Weekly integration status meetings to review schedule adherence
- Lessons Learned
- Data Sharing
- Gap Analysis The Exelon Nuclear Management Model 23 Nuclear Oversight Independent Assessment Plant Observations and Performance 24 Five Flooding Recovery Post-Restart Action commitments outlined in Section 2 of the Confirmatory Action Letter (CAL)
Three of the Section 2 Flooding Recovery Post-Restart Action commitments have been submitted to the NRC resident inspectors Item 4.4.3.1 - Gather flood response lessons learned through condition report reviews to determine if procedure or strategy changes should be implemented (completed December 12, 2012)
Item 4.4.3.3 - Implement procedure and strategy changes as indicated by the lessons learned review conducted (completed February 20, 2013)
Item 1.2.3.21 - Inspect tank and equipment on demineralized water tank for damage (completed February 10, 2014)
Two of the Section 2 Flooding Recovery Post-Restart Action commitments are scheduled Item 4.4.3.2 - Review flood design basis and determine if the 2011 flood event provides additional information that should drive design basis changes Item 1.2.3.82 - Perform independent spent fuel storage installation route load test Flooding Recovery Action Plans
25
- Project scope Flooding reevaluation and seismic evaluation Flooding and seismic walkdowns
Results submitted to the NRC
Actions ongoing Mitigating strategies for beyond design basis external events Strategy developed and submitted to NRC
Portable equipment pre-staged at FCS
Procedures (Admin/Operations/PM/Testing)
Staffing
Communications (internal and external)
Spent Fuel Pool Instrumentation (SFPI)
SFPI modifications submitted to the NRC Fukushima Response Project Portable Submersible Pumps 26
- Plant Status
- Problem Identification and Resolution
- Engineering Products
- Design and Licensing Basis Control and Use
- Containment Internal Structures
- Site Operational Focus
- Integration
- Nuclear Oversight
- Closing Remarks Closing Remarks