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Line 3: |
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| | issue date = 06/05/2014 | | | issue date = 06/05/2014 |
| | title = IR 05000333-14-009; 04/14/2014 - 05/01/2014; James A. FitzPatrick Nuclear Power Plant, Biennial Baseline Inspection of Problem Identification and Resolution | | | title = IR 05000333-14-009; 04/14/2014 - 05/01/2014; James A. FitzPatrick Nuclear Power Plant, Biennial Baseline Inspection of Problem Identification and Resolution |
| | author name = Burritt A L | | | author name = Burritt A |
| | author affiliation = NRC/RGN-I/DRP/PB2 | | | author affiliation = NRC/RGN-I/DRP/PB2 |
| | addressee name = Coyle L | | | addressee name = Coyle L |
Line 9: |
Line 9: |
| | docket = 05000333 | | | docket = 05000333 |
| | license number = DPR-059 | | | license number = DPR-059 |
| | contact person = Burritt A L | | | contact person = Burritt A |
| | document report number = IR 14-009 | | | document report number = IR 14-009 |
| | document type = Inspection Report, Letter | | | document type = Inspection Report, Letter |
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Line 18: |
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| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 June 5, 2014 | | {{#Wiki_filter:June 5, 2014 |
|
| |
|
| Mr. Lawrence Coyle Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
| | ==SUBJECT:== |
| | | JAMES A. FITZPATRICK NUCLEAR POWER PLANT - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000333/2014009 |
| SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000333/2014009 | |
|
| |
|
| ==Dear Mr. Coyle:== | | ==Dear Mr. Coyle:== |
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| /RA/ Arthur L. Burritt, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket No. 50-333 License No. DPR-59 | | /RA/ Arthur L. Burritt, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket No. 50-333 License No. DPR-59 |
|
| |
|
| Enclosure: Inspection Report 05000333/2014009 w/Attachment: Supplementary Information | | ===Enclosure:=== |
| | Inspection Report 05000333/2014009 w/Attachment: Supplementary Information |
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| cc w/encl: Distribution via ListServ
| | REGION I== |
| | |
| ML14157A023 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME CBickett/CAB RPowell/RJP per telecon ABurritt/ALB DATE 5/19/14 5/19/14 6/5/14
| |
| | |
| 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION
| |
| | |
| ==REGION I==
| |
| Docket No. 50-333 | | Docket No. 50-333 |
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Line 221: |
Line 215: |
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|
| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| ==Section 4OA2: Problem Identification and Resolution==
| | |
| : Audits and Self-Assessments
| |
| : CEO2014-00048, Nuclear Oversight Fleet Trimester Report, November 2013 - February 2014
| |
| : JAFLO-2011-00169, Post Modification Testing & Return to Service Snapshot Self-Assessment Attachment
| |
| : JAFLO-2012-00117, Focused Self-Assessment - Conduct of Operations
| |
| : JAFLO-2013-00018, Focused Self-Assessment Report - Corrective Action Program Effectiveness
| |
| : LO-HQNLO-2013-00035, FitzPatrick Operating Experience Program
| |
| : QA-3-2013-JAF-1, Quality Assurance Audit - Corrective Action Program
| |
| : QA-7-2013-JAF-1, Quality Assurance Audit - Emergency Preparedness
| |
| : QA-8-2013-JAF-1, Quality Assurance Audit - Engineering Programs
| |
| : QA-10-2012-JAF-1, Maintenance, Planning Scheduling & Outage, Corrective Action & Assessment, June 11, 2012 - August 13, 2012
| |
| : QA-14-15-2013-JAF-1, Combined Radiation Protection and Radwaste (Radiation Protection, Training, Maintenance, Planning Scheduling & Outage, Industrial Safety/Human Performance, and Operations), September 9 - October 31, 2013
| |
| : QS-2014-JAF-002, Quality Assurance Surveillance Report, Oversight Follow-Up Review of Two Quality Assurance Findings and One Mid-Cycle Area for Improvement, January 14, 2014
| |
| ===Condition Reports===
| |
| (* indicates that condition report was generated as a result of this inspection)
| |
| : CR-JAF-2010-00817
| |
| : CR-JAF-2010-03774
| |
| : CR-JAF-2010-07782
| |
| : CR-JAF-2010-07783
| |
| : CR-JAF-2010-07841
| |
| : CR-JAF-2011-00133
| |
| : CR-JAF-2011-01291
| |
| : CR-JAF-2011-04152
| |
| : CR-JAF-2011-06099
| |
| : CR-JAF-2012-00572
| |
| : CR-JAF-2012-00584
| |
| : CR-JAF-2012-01422
| |
| : CR-JAF-2012-01534
| |
| : CR-JAF-2012-01634
| |
| : CR-JAF-2012-01727
| |
| : CR-JAF-2012-01778
| |
| : CR-JAF-2012-01877
| |
| : CR-JAF-2012-02040
| |
| : CR-JAF-2012-02120
| |
| : CR-JAF-2012-02149
| |
| : CR-JAF-2012-02249
| |
| : CR-JAF-2012-02287
| |
| : CR-JAF-2012-02399
| |
| : CR-JAF-2012-02491
| |
| : CR-JAF-2012-02591
| |
| : CR-JAF-2012-02640
| |
| : CR-JAF-2012-02703
| |
| : CR-JAF-2012-02940
| |
| : CR-JAF-2012-02984
| |
| : CR-JAF-2012-03016
| |
| : CR-JAF-2012-03036
| |
| : CR-JAF-2012-03042
| |
| : CR-JAF-2012-03058
| |
| : CR-JAF-2012-03233
| |
| : CR-JAF-2012-03372
| |
| : CR-JAF-2012-03427
| |
| : CR-JAF-2012-03767
| |
| : CR-JAF-2012-03991
| |
| : CR-JAF-2012-04044
| |
| : CR-JAF-2012-04087
| |
| : CR-JAF-2012-04242
| |
| : CR-JAF-2012-04248
| |
| : CR-JAF-2012-04320
| |
| : CR-JAF-2012-04350
| |
| : CR-JAF-2012-04443
| |
| : CR-JAF-2012-04454
| |
| : CR-JAF-2012-04474
| |
| : CR-JAF-2012-04563
| |
| : CR-JAF-2012-04590
| |
| : CR-JAF-2012-04606
| |
| : CR-JAF-2012-04680
| |
| : CR-JAF-2012-04738
| |
| : CR-JAF-2012-05447
| |
| : CR-JAF-2012-05590
| |
| : CR-JAF-2012-06025
| |
| : CR-JAF-2012-06105
| |
| : CR-JAF-2012-06590
| |
| : CR-JAF-2012-06856
| |
| : CR-JAF-2012-06868
| |
| : CR-JAF-2012-06915
| |
| : CR-JAF-2012-06934
| |
| : CR-JAF-2012-07205
| |
| : CR-JAF-2012-07378
| |
| : CR-JAF-2012-07628
| |
| : CR-JAF-2012-07986
| |
| : CR-JAF-2012-08042
| |
| : CR-JAF-2012-08454
| |
| : CR-JAF-2012-08854
| |
| : CR-JAF-2012-08878
| |
| : CR-JAF-2012-08885
| |
| : CR-JAF-2013-00301
| |
| : CR-JAF-2013-00493
| |
| : CR-JAF-2013-00519
| |
| : CR-JAF-2013-00569
| |
| : CR-JAF-2013-00713
| |
| : CR-JAF-2013-00741
| |
| : CR-JAF-2013-01007
| |
| : CR-JAF-2013-01167
| |
| : CR-JAF-2013-01396
| |
| : CR-JAF-2013-01411
| |
| : CR-JAF-2013-01481
| |
| : CR-JAF-2013-01495
| |
| : CR-JAF-2013-01530
| |
| : CR-JAF-2013-01533
| |
| : CR-JAF-2013-01583
| |
| : CR-JAF-2013-01657
| |
| : CR-JAF-2013-01659
| |
| : CR-JAF-2013-01788
| |
| : CR-JAF-2013-02005
| |
| : CR-JAF-2013-02011
| |
| : CR-JAF-2013-02037
| |
| : CR-JAF-2013-02068
| |
| : CR-JAF-2013-02081
| |
| : CR-JAF-2013-02163
| |
| : CR-JAF-2013-02169
| |
| : CR-JAF-2013-02170
| |
| : CR-JAF-2013-02200
| |
| : CR-JAF-2013-02237
| |
| : CR-JAF-2013-02254
| |
| : CR-JAF-2013-02292
| |
| : CR-JAF-2013-02603
| |
| : CR-JAF-2013-02692
| |
| : Attachment
| |
| : CR-JAF-2013-02700
| |
| : CR-JAF-2013-03234
| |
| : CR-JAF-2013-03235
| |
| : CR-JAF-2013-03354
| |
| : CR-JAF-2013-03500
| |
| : CR-JAF-2013-03577
| |
| : CR-JAF-2013-03742
| |
| : CR-JAF-2013-03821
| |
| : CR-JAF-2013-04133
| |
| : CR-JAF-2013-04134
| |
| : CR-JAF-2013-04410
| |
| : CR-JAF-2013-04636
| |
| : CR-JAF-2013-04764
| |
| : CR-JAF-2013-04883
| |
| : CR-JAF-2013-05017
| |
| : CR-JAF-2013-05217
| |
| : CR-JAF-2013-05218
| |
| : CR-JAF-2013-05236
| |
| : CR-JAF-2013-05619
| |
| : CR-JAF-2013-05620
| |
| : CR-JAF-2013-05676
| |
| : CR-JAF-2013-05701
| |
| : CR-JAF-2013-05854
| |
| : CR-JAF-2013-05855
| |
| : CR-JAF-2013-05891
| |
| : CR-JAF-2013-05956
| |
| : CR-JAF-2013-05961
| |
| : CR-JAF-2013-06026
| |
| : CR-JAF-2013-06344
| |
| : CR-JAF-2013-06358
| |
| : CR-JAF-2013-06444
| |
| : CR-JAF-2014-00056
| |
| : CR-JAF-2014-00223
| |
| : CR-JAF-2014-00436
| |
| : CR-JAF-2014-00522
| |
| : CR-JAF-2014-00583
| |
| : CR-JAF-2014-00656
| |
| : CR-JAF-2014-00675
| |
| : CR-JAF-2014-00695
| |
| : CR-JAF-2014-00735
| |
| : CR-JAF-2014-00864
| |
| : CR-JAF-2014-01205
| |
| : CR-JAF-2014-01823
| |
| : CR-JAF-2014-01835
| |
| : CR-JAF-2014-01852
| |
| : CR-JAF-2014-01996
| |
| : CR-JAF-2014-02009*
| |
| : CR-JAF-2014-02016*
| |
| : CR-JAF-2014-02111
| |
| : CR-JAF-2014-02159*
| |
| : CR-JAF-2014-02175
| |
| ===Drawings===
| |
| : Drawing 1.22-108, Revision 0
| |
| : Drawing 1.22-108, Revision 1
| |
| : Drawing 1.22-119, Revision 0
| |
| : Drawing 1.22-119, Revision 1
| |
| ===Operating Experience===
| |
| : NRC Information Notice 2013-06, Corrosion in Fire Protection Piping due to Air and Water Interaction NRC Information Notice 2013-17, Premature Degradation of Spent Fuel Storage Cask Structures and Components from Environmental Moisture NRC
| |
| : EN 47745, HPCI Inoperability due to the Failure of a Turbine Governor Valve NRC
| |
| : IN 2012-11, Age-Related Capacitor Degradation NRC
| |
| : IN 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool
| |
| : Non-Cited Violations and Findings
| |
| : NCV 2012003-01, Failure to Follow Procedure During Removal From Service of Emergency Diesel Generator Ventilation
| |
| : NCV 2012003-02, Inadequate Procedure for Installation of Reactor Water Recirculation Motor-Generator Scoop Tube Positioners
| |
| : NCV 2012004-01, Untimely Corrective Action to Address Crescent Area Unit Cooler Operability
| |
| : NCV 2012005-02, Failure of 'A' Emergency Diesel Generator Output Breaker to Close Following Loss of Offsite Power
| |
| : NCV 2012404-01, Security Finding
| |
| : FIN 2013003-02, Inadequate Corrective Action for Decay Heat Removal System Degradation Results in Loss of Decay Heat Removal during R20 Generator Scoop Tube Positioners
| |
| : NCV 2013004-01, Inadequate Reactor Water Recirculation Digital Flow Control Modification Post Maintenance Test Procedure Results in Unexpected Power Increase
| |
| : NCV 2013007-01, Failure to Correctly Position Emergency Diesel Generator Room Ventilation Temperature Controllers in Automatic
| |
| : Attachment
| |
| ===Procedures===
| |
| : AP-12.06, Equipment Status Control, Revision 24
| |
| : AP-12.08, LCO Tracking and Safety Function Determination Program, Revision 17
| |
| : CHSO-02, Chemistry Notifications, Revision 2
| |
| : EN-DC-149, Acceptance of Vendor Documents, Revision 8
| |
| : EN-DC-153, Preventive Maintenance Component Classification, Revision 9
| |
| : EN-DC-203, Maintenance Rule Program, Revision 2
| |
| : EN-DC-205, Maintenance Rule Monitoring, Revision 5
| |
| : EN-DC-206, Maintenance Rule (a)(1) Process, Revision 3
| |
| : EN-DC-324, Preventive Maintenance Program, Revision 12
| |
| : EN-DC-335, PM Basis Template, Revision 5
| |
| : EN-EC-100, Guidelines for Implementation of the Employee Concerns Program, Revision 7
| |
| : EN-FAP-LI-001, Condition Review Group (CRG), Revision 4
| |
| : EN-FAP-LI-003, Corrective Action Review Board (CARB) Process, Revision 13
| |
| : EN-HU-104, Engineering Task Risk and Rigor, Revision 4
| |
| : EN-LI-102, Corrective Action Process, Revision 23
| |
| : EN-LI-104, Self-Assessment and Benchmark Process, Revision 10
| |
| : EN-LI-118, Cause Evaluation Process, Revision 20
| |
| : EN-LI-119, Apparent Cause Evaluation (ACE) Process, Revision 17
| |
| : EN-LI-121, Trending and Performance Review Process, Revision 15
| |
| : EN-MP-112, Shelf Life Program, Revision 5
| |
| : EN-OE-100, Operating Experience Program, Revision 20
| |
| : EN-OP-104, Operability Determination Process, Revision 7
| |
| : EN-PL-190, Maintaining a Strong Safety Culture, Revision 2
| |
| : EN-QV-105, Nuclear Oversight Performance Reporting, Revision 10
| |
| : EN-RP-108, Radiation Protection Posting, Revision 13
| |
| : IMP-02-184.5A, 'A' Recirculation Motor Generator Scoop Tube Actuator Test and Calibration, Revision 2
| |
| : IMP-02-184.5B, 'B' Recirculation Motor Generator Scoop Tube Actuator Test and Calibration, Revision 0
| |
| : ISP-251A, RCIC Steam Line High Flow Tr ansmitter Calibration (ATTS), Revision 19
| |
| : MP-031.05, Reactor Feed Pump Turbine Coupling, Revision 18
| |
| : MP-046.02 Service Water Pump Maintenance, Revision 21
| |
| : MP-056.01, AC Motor Control Center Maintenance and Subcomponent Replacement, Revision
| |
| : MP-059.87, VIPER Motor Operated Valve Diagnostic Testing, Revision 14
| |
| : OP-2A, Feedwater System, Revision 71
| |
| : OP-2A, Feedwater System, Revision 73
| |
| : RT-01.06, EHC, Stator Cooler Sampling and Analysis, Revision 13
| |
| : SIP-5.1.15, Security Equipment Tests, Revision 42
| |
| : ST-2AM, RHR Loop B Quarterly Operability Test (IST) Revision 34
| |
| : ST-39B, Type B and C LLRT of Containment Penetrations (IST), Revision 35
| |
| ===Action Requests===
| |
| and Work Orders
| |
| : AR 151821
| |
| : AR 154698
| |
| : AR 177345
| |
| : AR 180008
| |
| : JAF-04-37284
| |
| : PMWO
| |
| : 52220993
| |
| : PMWO
| |
| : 52220994 PMWO
| |
| : 52301336
| |
| : WO 00250314
| |
| : WO 00297985
| |
| : WO 00312215
| |
| : WO 00331307
| |
| : WO 00333633
| |
| : WO 00334035
| |
| : WO 00335349
| |
| : WO 00336884
| |
| : WO 00358659
| |
| : WO 00364272
| |
| : WO 00364295
| |
| : WO 00366879
| |
| : WO 51181665
| |
| : Attachment
| |
| : WO 51185485
| |
| : WO 52256768
| |
| : WO 52285745
| |
| : WO 52294094
| |
| : WO 52379121
| |
| : WO 52428559
| |
| : WO 52452865
| |
| : WO 52473958
| |
| : WO 52526378
| |
| : WO
| |
| : JF-011039802
| |
| : Completed Surveillance Tests
| |
| : ST-24J, RCIC Flow Rate and Inservice Test, dated 07/17/2013
| |
| : ST-24J, RCIC Flow Rate and Inservice Test, dated 10/07/2013
| |
| : ST-24J, RCIC Flow Rate and Inservice Test, dated 01/02/2014
| |
| : ST-24J, RCIC Flow Rate and Inservice Test, dated 03/29/2014
| |
| : ST-24L, RCIC Vacuum Pump Discharge Stop Check Valve Functional Test, dated 10/07/2008
| |
| : ST-24L, RCIC Vacuum Pump Discharge Stop Check Valve Functional Test, dated 10/08/2010
| |
| : ST-24L, RCIC Vacuum Pump Discharge Stop Check Valve Functional Test, dated 10/06/2012
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 01/08/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 01/14/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 01/21/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 01/28/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 02/04/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 02/11/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 02/18/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 02/25/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 03/04/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 03/11/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 03/18/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 03/25/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 04/01/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 04/08/2014
| |
| : SIP-5.1.15, Security Equipment Tests, Attachment 7, dated 04/15/2014
| |
| ===Miscellaneous===
| |
| : Condition Review Group Pre-Screening Package for Wednesday April 16, 2014
| |
| : Corrective Action Summary for
| |
| : CR-JAFLO-2012-0032
| |
| : D1-95-108, Pump Component Material and Configuration Changes to Repair/Upgrade
| |
| : DBD-013, Design Basis Document for the Reactor Core Isolation Cooling System, Revision 5
| |
| : DBD-034, Design Basis Document for the Condensate/Feedwater Control Systems, Revision 15
| |
| : EC48365 Emergency Preparedness Plan/Procedure Revision Due Dates, April 3, 2014 Update Employee Concerns Program Brochure Entergy Emergency Planning Functional Area Performance Summary, February 2011 to January 2014 Entergy Ethics Program Brochure FitzPatrick Emergency Plan Procedure Matrix
| |
| : JAF-CALC-RHR-02878, Min Wall Calculation Update for the 10P-1(A-D) Skirt (EC 37363), Revision 1
| |
| : JAFLO-2009-0024
| |
| : JAFLO-2012-00004
| |
| : CA 59
| |
| : JAF-RPT-FWS-03079, Maintenance Rule Basis Document System 34 Feedwater, Revision 4
| |
| : JAF-RPT-MULTI-02294, Maintenance Rule Basis Document for Service Water Systems, Revision 10 James A. FitzPatrick Updated Final Safety Analysis Report
| |
| : JENG-13-0034, (a)(1) Evaluation of the RHRSW System Attachment
| |
| : JENG-14-0001, (a)(1) Evaluation of the 'B' RHR and RHRSW System
| |
| : JENG-APL-13-002, Maintenance Rule (a)(1) Action Plan, Revision 0
| |
| : JLG-OPS-4160, Rack in/out 4160Vac/600Vac Breakers Training, Revision 1
| |
| : JLP-ESPP-R21TESTWRITE,
| |
| : RO-21 Just in time training for test writers Maintenance Rule Functional Failure Determination for
| |
| : CR-JAF-2012-08885
| |
| : Operator Continuing Training Cycle 1301
| |
| ===Operating Experience===
| |
| and Procedure Changes PM Basis Template: EN - I&C - Electronic Circuit Cards, Revision 5
| |
| : System Health Report, Emergency Diesel Generator Ventilation, Fourth Quarter 2013 System Health Report, Emergency Diesel Generator Ventilation, Third Quarter 2013 System Health Report, Emergency Diesel Generator, First Quarter 2013 System Health Report, Emergency Diesel Generator, Fourth Quarter 2013
| |
| : System Health Report, Emergency Diesel Generator, Second Quarter 2013 System Health Report, Emergency Diesel Generator, Third Quarter 2013
| |
| : System Health Report, Feedwater System, First Quarter 2012 System Health Report, Feedwater System, First Quarter 2013 System Health Report, Feedwater System, Fourth Quarter 2010
| |
| : System Health Report, Feedwater System, Fourth Quarter 2011
| |
| : System Health Report, Feedwater System, Fourth Quarter 2013
| |
| : System Health Report, Feedwater System, Second Quarter 2013 System Health Report, Feedwater System, Third Quarter 2012
| |
| : System Health Report, Instrument Air Compressors, First Quarter 2013 System Health Report, Instrument Air Compressors, Fourth Quarter 2013
| |
| : System Health Report, Instrument Air Compressors, Second Quarter 2013
| |
| : System Health Report, Instrument Air Compressors, Third Quarter 2013
| |
| : System Health Report, Primary Containment Atmosphere Control and Dilution System, First Quarter 2014 System Health Report, Primary Containment Atmosphere Control and Dilution System, Fourth Quarter 2013 System Health Report, Primary Containment Atmosphere Control and Dilution System, Third Quarter 2013 System Health Report, Reactor Core Isolation Cooling System, Fourth Quarter 2013
| |
| : System Health Report, Residual Heat Removal Service Water, First Quarter 2013 System Health Report, Residual Heat Removal Service Water, Fourth Quarter 2013
| |
| : System Health Report, Residual Heat Removal Service Water, Second Quarter 2013
| |
| : System Health Report, Residual Heat Removal Service Water, Third Quarter 2013
| |
| : System Health Report: Residual Heat Removal Service Water, Fourth Quarter 2013
| |
| : TEAR-JAF-2012-1075 Temporary Change 12-00465 to
| |
| : OP-46A, 4160 V & 600 V Normal AC Power Distribution Nuclear Safety Culture Assessment, dated February 2012
| |
| : Condition Review Group Meeting Package for Tuesday April 15, 2014
| |
| : Operational Focus Meeting Agenda for Tuesday April 15, 2014 Condition Review Group Meeting Package for Monday April 21, 2014 Operational Focus Meeting Agenda for Monday April 21, 2014
| |
| ==LIST OF ACRONYMS==
| |
| : [[ADAMS]] [[Agencywide Documents Access and Management System]]
| |
| : [[CFR]] [[Code of Federal Regulations NRC Nuclear Regulatory Commission]]
| |
| }} | | }} |
|
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Category:Inspection Report
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 IR 05000333/20220062023-03-0101 March 2023 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2022006) IR 05000333/20220032022-11-10010 November 2022 Integrated Inspection Report 05000333/2022003 IR 05000333/20220052022-08-31031 August 2022 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2022005) IR 05000333/20220022022-08-10010 August 2022 Integrated Inspection Report 05000333/2022002 IR 05000333/20220102022-06-27027 June 2022 Reissued Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 ML22153A2612022-06-0202 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 IR 05000333/20210142022-05-23023 May 2022 Problem Identification and Resolution Inspection Report 05000333/2021014 IR 05000333/20220012022-05-0505 May 2022 Integrated Inspection Report 05000333/2022001 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2022001 IR 05000333/20210062022-03-0202 March 2022 Annual Assessment Letter for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021006) IR 05000333/20210042022-01-27027 January 2022 Integrated Inspection Report 05000333/2021004 IR 05000333/20210402021-11-0808 November 2021 95001 Supplemental Inspection Report 05000333/2021040 and Assessment Follow-Up Letter IR 05000333/20210032021-11-0808 November 2021 Integrated Inspection Report 05000333/2021003 IR 05000333/20213012021-10-0505 October 2021 Initial Operator Licensing Examination Report 05000333/2021301 IR 05000333/20215012021-09-29029 September 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2021501 IR 05000333/20210052021-09-0101 September 2021 Updated Inspection Plan for the James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021005) IR 05000333/20210132021-08-11011 August 2021 Biennial Problem Identification and Resolution Inspection Report 05000333/2021013 IR 05000333/20210022021-08-0303 August 2021 James A. Fitpatrick Nuclear Power Plant - Integrated Inspection Report 05000333/2021002 ML21176A0052021-06-25025 June 2021 Acknowledgement of Dispute of Violations Associated with White Finding - NRC Inspection Report 05000333/2021090 IR 05000333/20210902021-06-25025 June 2021 Acknowledgement of Dispute of Violations Associated with White Finding - NRC Inspection Report 05000333/2021090 IR 05000333/20214022021-06-0909 June 2021 Security Baseline Inspection Report 05000333/2021402 IR 05000333/20210112021-06-0303 June 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000333/2021011 IR 05000333/20210012021-05-0505 May 2021 Integrated Inspection Report 05000333/2021001 IR 05000333/20210122021-05-0404 May 2021 Temporary Instruction 2515/194 Inspection Report 05000333/2021012 IR 05000333/20214012021-04-19019 April 2021 Material Control and Accounting Program Inspection Report 05000333/2021401 (Letter Only) IR 05000333/20210102021-04-0707 April 2021 Triennial Fire Protection Inspection Report 05000333/2021010 IR 05000333/20200062021-03-0303 March 2021 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2020006) IR 05000333/20200042021-02-11011 February 2021 Integrated Inspection Report 05000333/2020004 IR 05000333/20200122021-01-21021 January 2021 Problem Identification and Resolution Report 05000333/2020012 and Preliminary White Finding and Apparent Violation IR 05000333/20204202020-12-10010 December 2020 Security Inspection Report 05000333/2020420 IR 05000333/20200032020-11-10010 November 2020 Integrated Inspection Report 05000333/2020003 IR 05000333/20204022020-09-16016 September 2020 Security Baseline Inspection Report 05000333/2020402 IR 05000333/20200052020-08-31031 August 2020 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2020005) IR 05000333/20200022020-08-10010 August 2020 Integrated Inspection Report 05000333/2020002 IR 05000333/20204012020-07-28028 July 2020 Cyber Security Inspection Report 05000333/2020401 (Letter Only) IR 05000333/20200112020-04-30030 April 2020 Problem Identification and Resolution Annual Sample Inspection Report 05000333/2020011 IR 05000333/20200012020-04-28028 April 2020 Integrated Inspection Report 05000333/2020001 2024-02-07
[Table view] Category:Letter
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report ML23228A1342023-08-16016 August 2023 Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance ML23208A1622023-07-27027 July 2023 Operator Licensing Examination Approval IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML23152A0042023-06-0101 June 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000333/2023401 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 ML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 2024-02-07
[Table view] |
Text
June 5, 2014
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000333/2014009
Dear Mr. Coyle:
On May 1, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your James A. FitzPatrick Nuclear Power Plant (FitzPatrick). The enclosed inspection report documents the inspection results, which were discussed on May 1, 2014, with Mr. Brian Sullivan, General Manager of Plant Operations, and other members of your staff.
The inspection examined activities conducted under your license as they relate to identification and resolution of problems and compliance with the Commission's rules and regulations and conditions of your license. Within these areas, the inspection involved examination of selected procedures and representative records, observations of activities, and interviews with personnel.
Based on the samples selected for review, the inspectors concluded that Entergy was generally effective in identifying, evaluating, and resolving problems. Entergy personnel identified problems and entered them into the corrective action program at a low threshold. Entergy prioritized and evaluated issues commensurate with the safety significance of the problems and corrective actions were generally implemented in a timely manner. Entergy appropriately considered industry operating experience information for applicability, and used the information
for corrective and preventive actions to identify and prevent similar issues when appropriate. The inspectors determined that the self-assessments reviewed were generally thorough, critical, and effective in identifying issues and improvement opportunities. Finally, the team found no evidence of significant challenges to FitzPatrick's safety conscious work environment. Based on the team's observations, FitzPatrick staff are willing to raise nuclear safety concerns through at least one of the several means available.
Based on the results of the inspection, the inspectors did not identify any findings or violations of more than minor significance.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/ Arthur L. Burritt, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket No. 50-333 License No. DPR-59
Enclosure:
Inspection Report 05000333/2014009 w/Attachment: Supplementary Information
REGION I==
Docket No. 50-333
License No. DPR-59
Report No. 05000333/2014009
Licensee: Entergy Nuclear Northeast (Entergy)
Facility: James A. FitzPatrick Nuclear Power Plant
Location: Scriba, NY
Dates: April 14 through May 1, 2014
Team Leader: Carey Bickett, Senior Project Engineer
Inspectors: Mark Draxton, Project Engineer Aaron Dugandzic, Project Engineer Beth Sienel, Resident Inspector, FitzPatrick
Approved by: Arthur L. Burritt, Chief Reactor Projects Branch 2 Division of Reactor Projects
2 Enclosure
SUMMARY
IR 05000333/2014009; 04/14/2014 - 05/01/2014; James A. FitzPatrick Nuclear Power Plant (FitzPatrick); Biennial Baseline Inspection of Problem Identification and Resolution.
This NRC team inspection was performed by three regional inspectors and one resident inspector. The NRC's program for overseeing t he safe operation of commercial nuclear power reactors is described in NUREG-1649, "R eactor Oversight Process," Revision 5.
Problem Identification and Resolution The inspectors concluded that Entergy was generally effective in identifying, evaluating, and resolving problems. Entergy personnel identified problems, entered them into the corrective action program at a low threshold, and prioritized issues commensurate with their safety significance. Entergy staff appropriately screened issues for operability and reportability, and performed causal analyses that appropriately considered extent of condition, generic issues, and previous occurrences. The inspectors also determined that Entergy typically implemented corrective actions to address the problems identified in the corrective action program in a timely manner.
The inspectors concluded that, in general, Entergy staff adequately identified, reviewed, and applied relevant industry operating experience to FitzPatrick operations. In addition, based on those items selected for review, the inspectors determined that Entergy's self-assessments and audits were thorough.
Based on the interviews the inspectors conducted over the course of the inspection, observations of plant activities, and reviews of individual corrective action program and employee concerns program issues, the inspectors did not identify any indications that site personnel were unwilling to raise safety issues nor did they identify any conditions that could have had a negative impact on the site's safety conscious work environment.
No findings were identified.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA2 Problem Identification and Resolution
This inspection constitutes one biennial sample of problem identification and resolution as defined by Inspection Procedure 71152. All documents reviewed during this inspection are listed in the Attachment to this report.
.1 Assessment of Corrective Action Program Effectiveness
a. Inspection Scope
The inspectors reviewed the procedures that described Entergy's corrective action program at FitzPatrick. To assess the effectiveness of the corrective action program, the
inspectors reviewed performance in three primary areas: problem identification, prioritization and evaluation of issues, and corrective action implementation. The inspectors compared performance in thes e areas to the requirements and standards contained in Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix B, Criterion XVI, "Corrective Action," and Entergy procedure EN-LI-102, "Corrective Action Process." For each of these areas, the inspectors considered risk insights from the station's risk analysis and reviewed condition reports selected across the seven
cornerstones of safety in the NRC's Reacto r Oversight Process. Additionally, the inspectors attended Condition Review Group, Condition Review Group Pre-Screening, Plant Health Committee, and Operations Focus meetings. The inspectors selected items from the following functional areas for review: engineering, operations, maintenance, emergency preparedness, radiation protection, chemistry, physical security, and quality assurance programs.
- (1) Effectiveness of Problem Identification In addition to the items described above, the inspectors reviewed system health reports, a sample of completed corrective and preventative maintenance work orders, completed surveillance test procedures, and periodic trend reports. The inspectors also completed field walkdowns of portions of various systems on site, including the residual heat removal service water, instrument air, primary containment atmosphere control and dilution, and emergency diesel generator systems. Additionally, the inspectors reviewed a sample of condition reports written to document issues identified through internal self-assessments, audits, emergency preparedness drills, and the operating experience program. The inspectors completed this review to verify that Entergy entered conditions adverse to quality into their corrective action program as appropriate.
- (2) Effectiveness of Prioritization and Evaluation of Issues
The inspectors reviewed the evaluation and prioritization of a sample of condition reports issued since the last NRC biennial Problem Identification and Resolution inspection completed in March 2012. The inspectors also reviewed condition reports that were assigned lower levels of significance that did not include formal cause evaluations to ensure that they were properly classified. The inspectors' review included the
4 Enclosure appropriateness of the assigned significance, the scope and depth of the causal analysis, and the timeliness of resolution. The inspectors assessed whether the evaluations identified likely causes for the issues and developed appropriate corrective actions to address the identified causes. Further, the inspectors reviewed equipment operability determinations, reportability assessments, and extent-of-condition reviews for selected problems to verify these processes adequately addressed equipment operability, reporting of issues to the NRC, and the extent of the issues.
- (3) Effectiveness of Corrective Actions The inspectors reviewed Entergy's completed corrective actions through documentation review and, in some cases, field walkdowns to determine whether the actions addressed the identified causes of the problems. The inspectors also reviewed condition reports for adverse trends and repetitive problems to determine whether corrective actions were effective in addressing the broader issues. The inspectors reviewed Entergy's timeliness in implementing corrective actions and effectiveness in precluding recurrence for significant conditions adverse to quality. The inspectors also reviewed a sample of condition reports associated with selected non-cited violations and findings to verify that Entergy personnel properly evaluated and resolved these issues. In addition, the inspectors expanded the corrective action review to five years to evaluate Entergy's actions related to feedwater pump issues.
b. Assessment
- (1) Effectiveness of Problem Identification Based on the selected samples, plant walkdowns, and interviews of site personnel in multiple functional areas, the inspectors determined that Entergy staff identified problems and entered them into the corrective action program at a low threshold. The inspectors observed supervisors at the various meetings appropriately questioning and challenging condition reports to ensure clarification of the issues. Based on the samples reviewed, the inspectors determined that Entergy trended equipment and programmatic issues, and appropriately identified problems in condition reports. The inspectors verified that conditions adverse to quality identified through this review were entered into the corrective action program as appropriate. Additionally, inspectors concluded that personnel were identifying trends at low levels. In general, inspectors did not identify any issues or concerns that had not been appropriately entered into the corrective action program for evaluation and resolution. In response to several questions and minor equipment observations identified by the inspectors during plant walkdowns, Entergy personnel promptly initiated condition reports and/or took immediate action to address the issues.
- (2) Effectiveness of Prioritization and Evaluation of Issues
The inspectors determined that, in general, Entergy appropriately prioritized and evaluated issues commensurate with the safety significance of the identified problem. Entergy screened condition reports for operability and reportability, categorized the condition reports by significance, and assigned actions to the appropriate department for evaluation and resolution. The condition report screening process considered human
5 Enclosure performance issues, radiological safety concerns, repetitiveness, adverse trends, and potential impact on the safety conscious work environment.
Based on the sample of condition reports reviewed, the inspectors noted that the guidance provided by Entergy's corrective action program implementing procedures appeared sufficient to ensure consistency in categorization of issues. Operability and reportability determinations were generally performed when conditions warranted and the evaluations supported the conclusion. Causal analyses appropriately considered the extent of condition or problem, generic issues, and previous occurrences of the issue.
- (3) Effectiveness of Corrective Actions
The inspectors concluded that corrective actions for identified deficiencies were generally timely and adequately implemented. For significant conditions adverse to quality, Entergy identified actions to prevent recurrence. The inspectors concluded that corrective actions to address the sample of NRC non-cited violations and findings since the last problem identification and resolution inspection were generally timely and effective. However, the inspectors did observe some weaknesses in Entergy's resolution of the following:
Improper Closure of a Corrective Action for a Procedure Revision Entergy wrote condition report CR-JAF-2013-4410 to evaluate the cause of high vibrations on the 'B' reactor feedwater pump during power ascension on August 23, 2013. Entergy determined that the root cause of the issue was use of an inadequate maintenance procedure to reassemble the turbine to pump coupling following the Fall 2012 refueling outage. This resulted in the coupling disassembling during operation, causing the observed vibrations. Entergy issued a corrective action to preclude repetition to revise applicable sections of procedure MP-031.05, "Reactor Feed Pump Turbine Coupling," to provide a more robust coupling. On March 6, 2014, station staff closed out the corrective action. The inspectors subsequently identified that all applicable steps of the procedure had not been revised.
EN-LI-102, "Corrective Action Process," Section 5.9[4](d) requires that the "corrective action assigner-reviews each completed action and verifies that the required action is complete. This includes: ensuring that the response is adequate, answers all aspects of the assigned action, and the intent of the action is met." Contrary to this, Entergy closed the action in the corrective action program related to revising the procedure without completing the entire intended action. The inspectors determined this issue is of minor significance because although no longer being tracked by the corrective action program, a procedure revision to address applicable portions of the procedure was still in progress. Additionally, no maintenance had been performed on either of the feedwater pumps which would have required the use of this procedure, and related work orders were or have since been placed on hold. Entergy entered this issue into the corrective action process as condition report CR-JAF-2014-02159.
Failure to Implement a Corrective Action for Increased Frequency Low Voltage Testing On January 26, 2012, Entergy determined that a contactor associated with the east crescent area unit cooler fan motor failed the low voltage pick-up testing criteria per MP-056.01, "AC Motor Control Center Maintenance and Subcomponent Replacement."
Entergy cleaned, lubricated, and reused the contactor, and replaced the contactor coil.
6 Enclosure Post-maintenance testing of the contactor and new coil was satisfactory. Entergy documented this failure in condition report CR-JAF-2012-00584 and performed a high-tier apparent cause evaluation to assess the issue. Entergy staff determined that the apparent cause of the issue was higher contactor coil impedance which caused a lower current at a given voltage. This resulted in contactor pick-up at a voltage above the acceptance criteria. To test the effectiveness of the corrective actions already completed, Entergy developed an action to complete an increased frequency low voltage preventative maintenance test on a one year periodicity. Following three successful performances, the staff planned to return this preventative maintenance to its original seven year frequency. Entergy scheduled this work order and closed the associated corrective action.
Following review of condition report CR-JAF-2012-00584, inspectors questioned the status of the increased frequency preventative maintenance work order and discovered that it was inadvertently cancelled without completing the work. This is contrary to Entergy procedure EN-LI-102, "Corrective Action Process," Section 5.8[6](e)(3) which states, "before a work order which had a condition report or corrective action closed to it can be cancelled or closed with no work to be performed, the organization requesting the cancellation will present the condition report and work order to the Condition Review Group for discussion." By performing maintenance on the contactor, and replacing the contactor coil, Entergy completed actions to correct all of the probable causes of the failure, as identified in the apparent cause analysis. Additionally, the contactor and coil are currently within their seven year preventative maintenance frequency. The inspectors reviewed the basis for this seven year frequency and determined that it was reasonable. As such, the inspectors determined that this issue is minor. Entergy entered this issue into the corrective action process as condition report CR-JAF-2014-02016.
Failure to Properly Document Completion of Training The inspectors determined that station personnel were not always consistent in how they used corrective actions to track the completion of training. Entergy procedure EN-LI-102, "Corrective Action Process," Section 5.9[4](b)(1) states, "When training performance or modification to training material is identified as a corrective action in a condition report to address a cause or correct the identified condition, then the completion of the training or modification of training material must be documented in the condition report." Contrary to the above, Entergy closed two corrective actions associated with category 'B' condition report evaluations to training evaluation action requests, and did not document the required corrective actions to track the completion of the training or modification of the training material. Specifically, condition report CR-JAF-2012-06868, corrective action eight, and condition report CR-JAF-2013-06344, corrective action nine, were both closed on December 11, 2012, and February 13, 2014, respectively, solely upon the initiation of a training evaluation action request, and did not have follow-on corrective actions to track the training completion. Closing a corrective action upon the initiation of a training evaluation action request and failing to have follow-on corrective actions to track the completion of the training leaves the station vulnerable by not ensuring that all necessary actions are completed.
In this case, the inspectors determined this issue was minor because Entergy completed the necessary training and modifications to the training material even though the actions
7 Enclosure were not tracked in the corrective action program. The station entered the issue into their corrective action process as condition report CR-JAF-2014-02009.
Inspectors independently evaluated these three observations in accordance with Inspection Manual Chapter 0612, Appendix B, "Issue Screening," and Inspection Manual Chapter 0612, Appendix E, "Examples of Minor Issues." For the reasons discussed above, the inspectors determined that all of these issues were minor and not subject to enforcement action in accordance with the NRC's Enforcement Policy.
c. Findings
No findings were identified.
.2 Assessment of the Use of Operating Experience
a. Inspection Scope
The inspectors reviewed a sample of condition reports associated with review of industry operating experience to determine whether Entergy appropriately evaluated the operating experience information for applicability to FitzPatrick and had taken appropriate actions, when warranted. The inspectors also reviewed evaluations of operating experience documents associated with a sample of NRC generic communications to ensure that Entergy staff adequately considered the underlying problems associated with the issues for resolution via their corrective action program. In addition, the inspectors observed various plant activities to determine if the station considered industry operating experience during the performance of routine and infrequently performed activities.
b. Assessment The inspectors determined that Entergy appropriately considered industry operating experience information for applicability, and used the information for corrective and preventive actions to identify and prevent similar issues when appropriate. The inspectors determined that Entergy appropriately applied operating experience and communicated and incorporated lessons learned into plant operations and procedures when applicable. The inspectors also observed that industry operating experience was routinely discussed and considered during the conduct of various meetings at the station.
c. Findings
No findings were identified.
.3 Assessment of Self-Assessments and Audits
a. Inspection Scope
The inspectors reviewed a sample of audits, including the most recent audit of the corrective action program, departmental self-assessments, and assessments performed by independent organizations. Inspectors performed these reviews to determine if
8 Enclosure Entergy staff entered problems identified through these assessments into the corrective action program, when appropriate, and whether the staff initiated corrective actions to address identified deficiencies. The inspectors evaluated the effectiveness of the audits and assessments by comparing audit and assessment results against self-revealing and NRC-identified observations made during the inspection.
b. Assessment The inspectors concluded that self-assessments, audits, and other internal Entergy assessments were generally critical, thorough, and effective in identifying issues. The inspectors observed that Entergy personnel knowledgeable in the subject completed
these audits and self-assessments in a methodical manner. Entergy completed these audits and self-assessments to a sufficient depth to identify issues which were then entered into the corrective action program for evaluation. In general, the station implemented corrective actions associated with the identified issues commensurate with their safety significance.
c. Findings
No findings were identified.
.4 Assessment of Safety Conscious Work Environment
a. Inspection Scope
During interviews with station personnel, the inspectors assessed the safety conscious work environment at FitzPatrick. Specifically, the inspectors interviewed personnel to determine whether they were hesitant to raise safety concerns to their management and/or the NRC. The inspectors interviewed the station Employee Concerns Program coordinator to determine what actions are implemented to ensure employees are aware of the program and its availability with regards to raising safety concerns. Additionally, the inspectors reviewed Employee Concerns Program files and the results of the most recent site safety culture assessment to ensure that Entergy entered issues into the corrective action program when appropriate.
b. Assessment During interviews, FitzPatrick staff expressed a willingness to use the corrective action program to identify plant issues and deficiencies and stated that they were willing to raise safety issues. The inspectors noted that no one interviewed stated that they personally experienced or were aware of a situation in which an individual had been retaliated against for raising a safety issue. All persons interviewed demonstrated an adequate knowledge of the corrective action program and the Employee Concerns Program. Based on the team's observations, FitzPatrick staff are willing to raise nuclear safety concerns through at least one of the several means available.
c. Findings
No findings were identified.
9 Enclosure
4OA6 Meetings, Including Exit
On May 1, 2014, the inspectors presented the inspection results to Mr. Brian Sullivan, General Manager of Plant Operations, and other members of the FitzPatrick staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- B. Sullivan, General Manager of Plant Operations
- M. Baker, Maintenance Rule Coordinator
- A. Bratek, Containment Atmospheric Dilution System Engineer
- S. Chubon, Senior Emergency Planner
- M. Cook, Emergency Diesel Generator System Engineer
- M. Cronk, Maintenance and Scheduling
- J. Davis, Senior Corrective Action and Assessment Specialist
- B. Dempsey, Residual Heat Removal Service Water System Engineer
- R. Denbleyker, Employee Concerns Program Coordinator
- M. Hawes, Regulatory Assurance Specialist
- E. Hrbac, Project Manager for Projects
- D. Huwe, Quality Assurance Auditor
- S. Juravich, Engineering Fix-it-Now
- A. King, Radiation Protection ALARA Supervisor
- J. Krocke, Maintenance Coordinator/Scheduler
- M. Lamardo, Electrical Maintenance
- J. Lona, Electrical Outage Coordinator
- M. Newshan, Assistant Operations Manager Support
- R. Owen, Maintenance Specialist
- R. Perry, Instrument Air System Engineer
- D. Starczewski, Equipment Reliability Coordinator
- S. Tharrett, Design Engineering Technical Specialist
- P. Thingvoll, Chemistry Supervisor
NRC Personnel
- E. Knutson, Senior Resident Inspector
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
None
LIST OF DOCUMENTS REVIEWED