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| | issue date = 06/25/2013 | | | issue date = 06/25/2013 |
| | title = IR 05000277-13-008; 05000278-13-008; on 05/06/13 - 05/23/13; Peach Bottom Atomic Power Station, Units 2 and 3 - Nuclear Regulatory Commission Problem Identification and Resolution Inspection Report | | | title = IR 05000277-13-008; 05000278-13-008; on 05/06/13 - 05/23/13; Peach Bottom Atomic Power Station, Units 2 and 3 - Nuclear Regulatory Commission Problem Identification and Resolution Inspection Report |
| | author name = Gray M K | | | author name = Gray M |
| | author affiliation = NRC/RGN-I/DRP/PB4 | | | author affiliation = NRC/RGN-I/DRP/PB4 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000277, 05000278 | | | docket = 05000277, 05000278 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 June 25, 2013 | | {{#Wiki_filter:June 25, 2013 |
|
| |
|
| Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear
| | ==SUBJECT:== |
| | | PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - NUCLEAR REGULATORY COMMISSION PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000277/2013008 AND 05000278/2013008 |
| 4300 Winfield Road
| |
| | |
| Warrenville, IL 60555
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| | |
| SUBJECT: PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - NUCLEAR REGULATORY COMMISSION PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000277/2013008 AND 05000278/2013008 | |
|
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|
| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
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| Docket Nos. 50-277, 50-278 License Nos. DPR-44, DPR-56 | | Docket Nos. 50-277, 50-278 License Nos. DPR-44, DPR-56 |
|
| |
|
| Enclosure: Inspection Report 05000277/2013008 and 05000278/2013008 w/Attachment: Supplementary Information | | ===Enclosure:=== |
| | | Inspection Report 05000277/2013008 and 05000278/2013008 w/Attachment: Supplementary Information |
| cc w/encl: Distribution via ListServ
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|
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|
| ML13176A401 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME TSetzer/TCS RPowell/RP MGray/MG DATE 06/17/13 06/17/13 06/24/13 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION
| | REGION I== |
| | |
| ==REGION I==
| |
|
| |
|
| Docket Nos. 50-277 and 50-278 | | Docket Nos. 50-277 and 50-278 |
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| None | | None |
| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| ==Section 4OA2: Problem Identification and Resolution==
| | |
| : Audits and Self-Assessments
| |
| : Maintenance Rad Worker Practices, (AR 1413766), March 10, 2013
| |
| : Radiation Protection Audit Report,
| |
| : NOSA-PEA-11-06 (AR 1238450), Peach Bottom, August 1 -
| |
| : 16, 2011 Chemistry, Radwaste, Effluent and Environmental Monitoring Increased Frequency Audit Report, Audit
| |
| : NOSA-PEA-11-12 (AR 1202556) Peach Bottom, May 2-6, 2011 2013 NRC Problem Identification and Resolution (PI&R) Inspection;
| |
| : IP 71152, (AR 1440846), 3/27/13
| |
| : Attachment
| |
| : NOSA-PEA-11-08 (AR 1266947), Operations Audit Peach Bottom Atomic Power Station, November 14 - December 1, 2011 Operational Decision-Making Check-In Self-Assessment, June 2012 Peach Bottom Safety Culture Survey Check in Self-Assessment, November 2010
| |
| : 2011 Employee Concerns Program Check-In Self-Assessment, January 18, 2012
| |
| : 2012 Employee Concerns Program Check-In Self-Assessment, December 20, 2012 OPEX Biennial Check-In Self-Assessment, November 20, 2012
| |
| : Quality of Level 3 OPEX Evaluations Check-In Self-Assessment, November 19, 2012 Annual 2011 Review of OPEX Evaluation Quality and Timeliness, December 1, 2011
| |
| : NOS-PEA-11-03, Emergency Preparedness Audit Report
| |
| : NOS-PEA-11-11, Maintenance Increased Frequency Audit Report
| |
| : NOS-PEA-12-01, Maintenance Audit Report
| |
| : NOS-PEA-10-03, Emergency Preparedness Audit Report
| |
| : NOS-PEA-13-12, Maintenance Increased Frequency Audit Report
| |
| : NOSCPA-PB-11-13, Maintenance CPA Report
| |
| : NOSCAP-PB-12-15, Maintenance CPA Report Self-Assessment: Effectiveness of Maintenance and Technical Training (M&TT) Self- Assessment with a Focus on CAP (IR 1436074) Self-Assessment: Maintenance Planning Department Adherence to Risk Assessment Process (IR 1314763)
| |
| ===Condition Reports===
| |
| (* indicates that condition report was generated as a result of this inspection)
| |
| : 260163
| |
| : 278595
| |
| : 1390376
| |
| : 1394841
| |
| : 1491605
| |
| : 284657
| |
| : 1406856
| |
| : 1408782
| |
| : 1483142
| |
| : 1456669
| |
| : 251816
| |
| : 278595
| |
| : 1382220
| |
| : 1420050
| |
| : 22879
| |
| : 249884
| |
| : 250326
| |
| : 250333
| |
| : 1262600
| |
| : 1270436
| |
| : 1302824
| |
| : 2191
| |
| : 895789
| |
| : 898030
| |
| : 901501
| |
| : 986151
| |
| : 207242
| |
| : 249919
| |
| : 1252395
| |
| : 1254179
| |
| : 1266600
| |
| : 1266604
| |
| : 272124
| |
| : 295990
| |
| : 296150
| |
| : 1296400
| |
| : 1296403
| |
| : 296494
| |
| : 1303054
| |
| : 1309636
| |
| : 1310491
| |
| : 1317988
| |
| : 1317995
| |
| : 1319764
| |
| : 28306
| |
| : 1352158
| |
| : 1355773
| |
| : 1359061
| |
| : 1364066
| |
| : 1371735
| |
| : 1377135
| |
| : 1380119
| |
| : 1380121
| |
| : 1380122
| |
| : 1380124
| |
| : 1380125
| |
| : 1380126
| |
| : 1380127
| |
| : 1380128
| |
| : 1380129
| |
| : 1380131
| |
| : 1383337
| |
| : 1393050
| |
| : 1396023
| |
| : 1401183
| |
| : 1409837
| |
| : 1413333
| |
| : 1419073
| |
| : 23042
| |
| : 1428597
| |
| : 1430391
| |
| : 1457767
| |
| : 1466222
| |
| : 1513561
| |
| : 1513692
| |
| : 1518729
| |
| : 1199711
| |
| : 1359373
| |
| : 1414197
| |
| : 1351957
| |
| : 1383301
| |
| : 1423654
| |
| : 21142
| |
| : 246183
| |
| : 1252615
| |
| : 1263661
| |
| : 1344626
| |
| : 1358879
| |
| : 1368694
| |
| : 1394300
| |
| : 1431162
| |
| : 1460745
| |
| : 1487149
| |
| : 1466119
| |
| : 1361089
| |
| : 1474240
| |
| : 1456334
| |
| : 1396262
| |
| : 1496901
| |
| : 1492813
| |
| : 1484821
| |
| : 1495833
| |
| : 1394025
| |
| : 1105303
| |
| : 1440846
| |
| : 1333896
| |
| : 784415
| |
| : 848390
| |
| : 843641
| |
| : 896717
| |
| : 1076488
| |
| : 243219
| |
| : 1243718
| |
| : 1243711
| |
| : 1373124
| |
| : 1381509
| |
| : 1384019
| |
| : 1371526
| |
| : 1371478
| |
| : 1443538
| |
| : 1498912
| |
| : 1499393
| |
| : 24825
| |
| : 1144138
| |
| : 1442380
| |
| : 1442381
| |
| : 1442375
| |
| : 1442377
| |
| : 1166967
| |
| : 807147
| |
| : 871864
| |
| : 938245
| |
| : 965437
| |
| : 973979
| |
| : 1034965
| |
| : 1112339
| |
| : 1120122
| |
| : 1121119
| |
| : 1165407
| |
| : 1184333
| |
| : Attachment
| |
| : 212082
| |
| : 1244984
| |
| : 254395
| |
| : 1262861
| |
| : 1279042
| |
| : 286435
| |
| : 290922
| |
| : 293634
| |
| : 1311040
| |
| : 1314373
| |
| : 1319322
| |
| : 21901
| |
| : 26777
| |
| : 1340452
| |
| : 1342458
| |
| : 1353911
| |
| : 1353913
| |
| : 1356569
| |
| : 1363032
| |
| : 1364394
| |
| : 1364396
| |
| : 1364792
| |
| : 1373999
| |
| : 1377970
| |
| : 1382061
| |
| : 1394863
| |
| : 1408784
| |
| : 1412949
| |
| : 1422294
| |
| : 1425241
| |
| : 27419
| |
| : 1436700
| |
| : 1434493
| |
| : 1442994
| |
| : 1462374
| |
| : 1465277
| |
| : 1468996
| |
| : 1473642
| |
| : 1484821
| |
| : 1489880
| |
| : 1497451
| |
| : 1497456
| |
| : 1497484
| |
| : 1497489
| |
| : 1497495
| |
| : 1497497
| |
| : 1497502
| |
| : 1497508
| |
| : 1497527
| |
| : 1497641
| |
| : 1497695
| |
| : 1497697
| |
| : 1497713
| |
| : 1500538
| |
| : 1516661
| |
| *1512643 *1511693 *1511775
| |
| *1511139 *1512510 *1511617
| |
| *1510670
| |
| *1513303
| |
| *1513407
| |
| *1516193 *1522740
| |
| ===Operating Experience===
| |
| : NRC Information Notice 2012-06, Ineffective Use of Vendor Technical Recommendations
| |
| : 1474240
| |
| : 1466119
| |
| : 1456334
| |
| : 1396262
| |
| : Fairbanks Morse
| |
| : SIL 22, Fuel Oil Control Linkage, Revision 2
| |
| : Non-Cited Violations and Findings
| |
| : 05000277/2012003-01; 05000278/2012003-01, Inadequate Test Control to Demonstrate RCIC System Design Basis Start-up Response Time 05000278/2011005-01, Untimely Corrective Action to Correct MOV Degraded Stem Lubrication
| |
| : 05000277&278/2011403 05000277&278/2012404-02, Failure to Implement a Testing Program to Ensure Security Systems Performed Their Intended Functions 05000277&278/2011502-01, Changes Made to EAL HU6 Which Decreased the Effectiveness of the Plans Without Prior NRC Approval
| |
| ===Drawings===
| |
| : M-1-S-54, Sheet 7, RPS Electrical Schematic Diagram, Revision 81
| |
| : M-1-S-34, Sheet 78, PRNM Elementary Diagram, Revision 1
| |
| ===Procedures===
| |
| : RT-H-099-960-2, Outside Radioactive Material Storage Area Inspection and Survey" Revision 9
| |
| : RP-AA-500-100, Requirements for Radioactive Material Stored Outdoors, Revision 3
| |
| : LS-AA-115, Operating Experience Program, Revision 17
| |
| : LS-AA-115-1001, Processing of Level 1 OPEX Evaluations, Revision 5
| |
| : LS-AA-115-1002, Processing of Level 2 OPEX Evaluations, Revision 3
| |
| : LS-AA-115-1003, Processing of Level 3 OPEX Evaluations, Revision 2
| |
| : LS-AA-115-1004, Processing of NERs, NNOEs, and Root Cause Report Transmittals to INPO, Revision 2
| |
| : Attachment
| |
| : LS-AA-120, Issue Identification and Screening Process, Revision 14
| |
| : LS-AA-125, Corrective Action Program (CAP) Procedure, Revision 17
| |
| : LS-AA-125-1001, Root Cause Manual, Revision 10
| |
| : LS-AA-125-1002, Common Cause Analysis Manual, Revision 7
| |
| : LS-AA-125-1003, Apparent Cause Evaluation Manual, Revision 10
| |
| : LS-AA-125-1004, Effectiveness Review Manual, Revision 5
| |
| : LS-AA-125-1005, Coding and Analysis Manual, Revision 8
| |
| : LS-AA-126, Self-Assessment and Benchmark (SAB) Program, Revision 7
| |
| : LS-AA-126-1001, Focused Area Self-Assessments, Revision 7
| |
| : LS-AA-126-1005, Check-In Self-Assessments, Revision 5
| |
| : NO-AA-10, Quality Assurance Topical Report, Revision 87
| |
| : NO-AA-50, Nuclear Oversight Vendor Audit (NOVA) Process Description, Revision 0
| |
| : NO-AA-210, Nuclear Oversight Regulatory Audit Procedure, Revision 3
| |
| : NO-AA-210-1001, Nuclear Oversight Audit Handbook, Revision 5
| |
| : NO-AA-210-1002, Nuclear Oversight Audit Templates, Revision 3
| |
| : NO-AA-220, Nuclear Oversight Performance Assessment Procedure, Revision 7
| |
| : NO-AA-220-1004, Nuclear Oversight Comprehensive Performance Assessment Rating and Reporting, Revision 11
| |
| : NO-AA-300, Inspection Planning and Execution of Quality Inspection Activities, Revision 4
| |
| : OP-AA-108-115, Operability Determinations (CM-1), Revision 11
| |
| : OP-PB-108-115-1002, Operability Determination Management Guidance, Revision 0
| |
| : OP-AA-108-115-1002, Supplemental Consideration for On-Shift Immediate Operability Determinations, Revision 2
| |
| : WC-AA-101, On-Line Work Control Process, Revision 19
| |
| : WC-AA-101-1002, On-Line Scheduling Process, Revision 11
| |
| : EI-AA-101, Employee Concerns Program, Revision 10
| |
| : EI-AA-101-1001, Employee Concerns Program Process, Revision 11
| |
| : EI-AA-101-1002, Employee Issues Trending, Revision 7
| |
| : ER-AA-302-1004, Motor Operated Valve Performance Trending, Revision 8
| |
| : ER-AA-302-1006, Motor-Operated Valve Maintenance and Testing Guidelines, Revision 12
| |
| : ER-AA-310, Implementation of the Maintenance Rule, Revision 8
| |
| : ER-AA-310-1002, Maintenance Rule Functions - Safety Significance Classification, Revision 3
| |
| : ER-AA-310-1003, Maintenance Rule - Performance Criteria Selection, Revision 3
| |
| : ER-AA-310-1004, Maintenance Rule - Performance Monitoring, Revision 11
| |
| : ER-AA-310-1005, Maintenance Rule - Dispositioning Between (a)(1) and (a)(2), Revision 6
| |
| : ER-AA-310-1006, Maintenance Rule - Expert Panel Roles and Responsibilities, Revision 4
| |
| : ER-AA-310-1007, Maintenance Rule - Periodic (a)(3) Assessment, Revision 4
| |
| : MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000 through 5 Motor Operated Valves, Revision 8
| |
| : RT-O-013-725-2, RCIC Response Time Test, Revision 11
| |
| : ST-O-013-301-2, RCIC Pump, Valve, Flow, and Unit Cooler Functional and In-Service Test, Revision 41 T-200C-3, Containment Venting via the 6-Inch ILRT Line from the Torus, Revision 9
| |
| : T-200F-2, Containment Venting via the 6-Inch ILRT Line from the Drywell, Revision 5
| |
| : WC-AA-106, Work Screening and Processing, Revision 13
| |
| : EP-AA-1007, Exelon Nuclear Radiological Emergency Planning Annex for Peach Bottom Atomic Power Station, Revision 26
| |
| : OP-AA-108-117, Protected Equipment Program, Revision 3
| |
| : RP-AA-460-003, Access to HRAS/LHRAS/VHRAS and Contaminated Areas in Response to a Potential or Actual Emergency, Revision 3
| |
| : Attachment
| |
| : RT-S-045-911-2, Performance Test of E-Field, Microwave, Absolute and Shaker Detection
| |
| : Equipment, Revisions 19 ad 20
| |
| ===Work Orders===
| |
| : A0145774
| |
| : A1684106 A1748919 A1858476 A1895506
| |
| : C0246720 R0760312
| |
| ===Miscellaneous===
| |
| : Level 3 OPEX Evaluation Process Changes Briefing Slides for End-Users
| |
| : List of valves still awaiting conversion to MOV long-life grease (May 10, 2013) (a)(1) Action Plan for Unit 2 and 3 Core Spray Minimum Flow Valve Differential Pressure Switches, dated January 31, 2012 (a)(1) Determination for Unit 2 and 3 Core Spray System Pump Differential Pressure Switches, dated November 9, 2011
| |
| : Peach Bottom Atomic Power Station Updated Final Safety Analysis Report, Revision 24 (Sections 4.7.3 and 14.5.4.4) NRC Information Notice 2012-06, Ineffective Use of Vendor Technical Recommendations Level 3 OPEX Evaluation Process Changes Briefing Slides for End-Users Maintenance Rule Basis Information from Maintenance Rule Database for System 55E
| |
| : Safety Culture OR Survey, January 12, 2012
| |
| : Semi-Annual Safety Culture Reviews, 1Q2012, 2Q2012, 3Q2012, 4Q2012
| |
| : Peach Bottom Safety Culture Monitoring Panel, 4Q2012
| |
| : Employee Feedback Survey, June 2011
| |
| : NRC Inspection Report 05000277&8/2012-005 NSMART Perimeter Intrusion Detection System Performance Routine Test Data, 12/09/2012
| |
| and 01/23/2013
| |
| : Regulatory Guide 5.44, Perimeter Intrusion Alarm Systems, Revision 3
| |
| : Unified Control Room Log keyword searches, 05/20/08 to 05/20/13
| |
| ==LIST OF ACRONYMS==
| |
| : [[ADAMS]] [[Agency-wide Documents Access and Management System]]
| |
| : [[CAPR]] [[Corrective Action to Prevent Recurrence]]
| |
| : [[IMC]] [[Inspection Manual Chapter kV kilovolts]]
| |
| NRC Nuclear Regulatory Commission
| |
| PARS Publicly Available Records System
| |
| Vdc Volts - direct current
| |
| }} | | }} |
|
---|
Category:Inspection Report
MONTHYEARIR 05000277/20234022024-01-11011 January 2024 Security Baseline Inspection Report 05000277/2023402 and 05000278/2023402 and Independent Spent Fuel Storage Installation Security Inspection 07200029/2023401 IR 05000277/20230032023-10-30030 October 2023 Integrated Inspection Report 05000277/2023003 and 05000278/2023003 and Exercise of Enforcement Discretion IR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 IR 05000277/20230102023-09-15015 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000277/2023010 and 05000278/2023010 and Notice of Violation ML23251A2022023-09-11011 September 2023 Cover Letter W/Report IR 05000277/20230052023-08-31031 August 2023 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2023005 and 05000278/2023005) IR 05000277/20230112023-08-15015 August 2023 Comprehensive Engineering Team Inspection Report 05000277/2023011 and 05000278/2023011 IR 05000277/20230022023-08-0808 August 2023 Integrated Inspection Report 05000277/2023002 and 05000278/2023002 IR 05000277/20230402023-07-17017 July 2023 95001 Inspection Supplemental Report 05000277/2023040 and Follow-Up Assessment Letter IR 05000277/20230012023-05-0808 May 2023 Integrated Inspection Report 05000277/2023001 and 05000278/2023001 IR 05000277/20220042023-04-0505 April 2023 Acknowledgement of Dispute of Green Finding - NRC Inspection Report 05000277/2022004 and 05000278/2022004 IR 05000277/20234012023-03-27027 March 2023 Security Baseline Inspection Report 05000277/2023401 and 05000278/2023401 IR 05000277/20230122023-03-10010 March 2023 Title 10 of the Code of Federal Regulations 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components Inspection Report 05000277/2023012 and 05000278/2023012 IR 05000277/20220062023-03-0101 March 2023 Annual Assessment Letter for Peach Bottom Atomic Power Station, Units 2 and 3 (Reports 05000277/2022006 and 05000278/2022006) ML23033A3332023-02-0202 February 2023 Integrated Inspection Report 05000277/2022004 and 05000278/2022004 IR 05000171/20220012023-01-0404 January 2023 Constellation Energy Generation, LLC, Peach Bottom Atomic Power Station, Unit 1 - NRC Inspection Report 05000171/2022001 IR 05000277/20220902022-11-28028 November 2022 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation, Inspection Report 05000277/2022090 IR 05000277/20220032022-10-27027 October 2022 Integrated Inspection Report 05000277/2022003 and 05000278/2022003 and Preliminary White Finding and Apparent Violation IR 05000277/20224012022-09-27027 September 2022 Material Control and Accounting Program Inspection Report 05000277/2022401 and 05000278/2022401 (Cover Letter Only) IR 05000277/20220052022-08-31031 August 2022 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2022005 and 05000278/2022005) IR 05000277/19570012022-08-19019 August 2022 631999-Termination License 50-27757-01 for G. Scott Crowther Dba Crowther Associates IR 07200079/20224042022-08-0404 August 2022 NRC Security Inspection Report 07200079/2022404 (Cover Letter) IR 05000277/20220022022-07-28028 July 2022 Integrated Inspection Report 05000277/2022002 and 05000278/2022002 IR 05000277/20223012022-07-28028 July 2022 Initial Operator Licensing Examination Report 05000277/2022301 and 05000278/2022301 IR 05000277/20224032022-07-13013 July 2022 Cyber Security Inspection Report 05000277/2022403 and 05000278/2022403 (Cover Letter Only) IR 05000277/20224022022-06-15015 June 2022 Security Baseline Inspection Report 05000277/2022402 and 05000278/2022402 and Independent Spent Fuel Storage Installation Security Inspection Report 07200029/2022401 (Cover Letter Only) IR 05000277/20225012022-06-0808 June 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000277/2022501 and 05000278/2022501 IR 05000277/20220112022-05-18018 May 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000277/2022011 and 05000278/2022011 ML22117A0362022-04-27027 April 2022 Integrated Inspection Report 05000277/2022001 and 05000278/2022001 IR 05000482/20220012022-04-25025 April 2022 Integrated Inspection Report 05000482/2022001 and Independent Spent Fuel Storage Installation Inspection Report 07200079/2022001 IR 05000277/20210062022-03-0202 March 2022 Annual Assessment Letter for Peach Bottom Atomic Power Station, Units 2 and 3 (Reports 05000277/2021006 and 05000278/2021006) IR 05000277/20210042022-02-0909 February 2022 Integrated Inspection Report 05000277/2021004 and 05000278/2021004 IR 05000482/20210042022-01-19019 January 2022 Integrated Inspection Report 05000482/2021004 and Independent Spent Fuel Storage Installation Inspection Report 07200079/2021002 IR 05000171/20210012022-01-12012 January 2022 Safstor Inspection Report 05000171/2021001 IR 05000277/20223022022-01-10010 January 2022 Operator Licensing Retake Examination Report 05000277/2022302 and 05000278/2022302 IR 05000277/20210032021-11-0909 November 2021 Integrated Inspection Report 05000277/2021003 and 05000278/2021003 IR 05000482/20210032021-11-0505 November 2021 Integrated Inspection Report 05000482/2021003 and Independent Spent Fuel Storage Installation Inspection Report 07200079/2021001, WC2021003 IR Ch IR 07200079/20214012021-10-21021 October 2021 ISFSI Security Inspection Report 07200079/2021401 IR 05000277/20210122021-09-22022 September 2021 Biennial Problem Identification and Resolution Inspection Report 05000277/2021012 and 05000278/2021012 IR 05000277/20213012021-09-0101 September 2021 Initial Operator Licensing Examination Report 05000277/2021301 and 05000278/2021301 IR 05000277/20210052021-09-0101 September 2021 Updated Inspection Plan for the Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2021005 and 05000278/2021005) IR 05000277/20210022021-08-0404 August 2021 Integrated Inspection Report 05000277/2021002 and 05000278/2021002 IR 05000277/20210102021-07-20020 July 2021 Triennial Fire Protection Inspection Report 05000277/2021010 and 05000278/2021010 IR 05000277/20210012021-04-28028 April 2021 Integrated Inspection Report 05000277/2021001 and 05000278/2021001 IR 05000277/20214012021-04-27027 April 2021 Security Baseline Inspection Report 05000277/2021401 and 05000278/2021401 IR 05000277/20210112021-04-0101 April 2021 Temporary Instruction 2515/194 Inspection Report 05000277/2021011 and 05000278/2021011 IR 05000277/20200062021-03-0303 March 2021 Annual Assessment Letter for Peach Bottom Atomic Power Station, Units 2 and 3 (Reports 05000277/2020006 and 05000278/2020006) IR 05000277/20200042021-02-0505 February 2021 Integrated Inspection Report 05000277/2020004 and 05000278/2020004 and Independent Spent Fuel Storage Installation Inspection Report 07200029/2020401 IR 07200029/20200012021-01-0505 January 2021 Peach Atomic Power Station, Independent Spent Fuel Storage Installation (ISFSI) NRC Inspection Report No. 07200029/2020001 IR 05000277/20205012020-12-17017 December 2020 Emergency Preparedness Biennial Exercise Inspection Report 05000277/2020501 and 05000278/2020501 2024-01-11
[Table view] Category:Letter
MONTHYEARML24022A2262024-01-22022 January 2024 (PBAPS) Unit 3 - Submittal of the Inservice Inspection (ISI) Owner'S Activity Report (OAR) for the 24th Refueling Outage for Unit 3 ML23346A2412024-01-17017 January 2024 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information (EPID L-2019-PMP-0061) - Letter IR 05000277/20234022024-01-11011 January 2024 Security Baseline Inspection Report 05000277/2023402 and 05000278/2023402 and Independent Spent Fuel Storage Installation Security Inspection 07200029/2023401 ML23354A1922024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23355A0622023-12-18018 December 2023 Independent Spent Fuel Storage Installation (Isfsi), Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan 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 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) IR 05000277/20230032023-10-30030 October 2023 Integrated Inspection Report 05000277/2023003 and 05000278/2023003 and Exercise of Enforcement Discretion ML23286A0012023-10-13013 October 2023 Reply to a Notice of Violation (NOV) - NOV 05000277, 05000278/2023010-01 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 ML23271A1342023-10-11011 October 2023 Dtf Analysis Letter IR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 ML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L IR 05000277/20230102023-09-15015 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000277/2023010 and 05000278/2023010 and Notice of Violation ML23251A2022023-09-11011 September 2023 Cover Letter W/Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement IR 05000277/20230052023-08-31031 August 2023 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2023005 and 05000278/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 IR 05000277/20230112023-08-15015 August 2023 Comprehensive Engineering Team Inspection Report 05000277/2023011 and 05000278/2023011 ML23226A1112023-08-14014 August 2023 10 CFR 50.46 Annual Report IR 05000277/20230022023-08-0808 August 2023 Integrated Inspection Report 05000277/2023002 and 05000278/2023002 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 IR 05000277/20230402023-07-17017 July 2023 95001 Inspection Supplemental Report 05000277/2023040 and Follow-Up Assessment Letter ML23188A0532023-07-0707 July 2023 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML23186A1272023-07-0606 July 2023 Response to Disputed Non-Cited Violation Documented in Peach Bottom Atomic Power Station, Units 2 and 3, Inspection Report 05000277/2022004 and 05000278/2022004 ML23178A0352023-06-27027 June 2023 Senior Reactor and Reactor Operator Initial License Examinations 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 ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ML23150A2052023-05-30030 May 2023 Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report 80 January 1, 2022 Through December 31, 2022 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 ML23142A1602023-05-23023 May 2023 Summary of April 11, 2023, Public Observation Meeting with Constellation Energy Generation, LLC Re Proposed Exemption Request from Work Hour Requirements ML23132A1582023-05-18018 May 2023 Correction to Technical Specification 3.4.7 (Page 3.4-16) Issued in Amendment No. 337 ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) IR 05000277/20230012023-05-0808 May 2023 Integrated Inspection Report 05000277/2023001 and 05000278/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI 2024-01-05
[Table view] |
Text
June 25, 2013
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - NUCLEAR REGULATORY COMMISSION PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000277/2013008 AND 05000278/2013008
Dear Mr. Pacilio:
On May 23, 2013, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Peach Bottom Atomic Power Station, Units 2 and 3. The enclosed report documents the inspection results, which were discussed on May 23, 2013, with Mr. Patrick Navin, Plant Manager, and other members of your staff.
This 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 did not identify any findings during this inspection. The inspectors concluded that Exelon was generally effective in identifying, evaluating, and resolving problems. Exelon personnel identified problems and entered them into the corrective action program at a low threshold. Exelon, in general, prioritized and evaluated issues commensurate with the safety significance of the problems and corrective actions were implemented in a timely manner. Lessons learned from industry operating experience were effectively reviewed and applied when appropriate. Additionally, the inspectors concluded that self-assessments and audits reviewed during the inspection were critical, thorough, and effective in identifying issues.
In accordance with Title 10 Code of Federal Regulations 2.390 of the NRC's "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 Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencyw ide Documents Access 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/ Mel Gray, Chief Reactor Projects Branch 4 Division of Reactor Projects
Docket Nos. 50-277, 50-278 License Nos. DPR-44, DPR-56
Enclosure:
Inspection Report 05000277/2013008 and 05000278/2013008 w/Attachment: Supplementary Information
REGION I==
Docket Nos. 50-277 and 50-278
License Nos. DPR-44 and DPR-56
Report Nos. 05000277/2013008 and 05000278/2013008
Licensee: Exelon Generation Company, LLC
Facility: Peach Bottom Atomic Power Station, Units 2 and 3
Location: Delta, PA
Dates: May 6, 2013 through May 23, 2013
Team Leader: Thomas Setzer, Senior Project Engineer
Inspectors: Carey Bickett, Senior Project Engineer George Smith, Physical Security Inspector Adam Ziedonis, Peach Bottom Resident Inspector
Approved by: Mel Gray, Chief Reactor Projects Branch 4 Division of Reactor Projects
2 Enclosure
SUMMARY
IR 05000277/2013008 and 05000278/2013008; 05/06/13 - 05/23/13; Peach Bottom Atomic Power Station, Units 2 and 3; 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, "Reac tor Oversight Process," Revision 4, dated December 2006.
Problem Identification and Resolution The inspectors concluded that Exelon was genera lly effective in identifying, evaluating, and resolving problems. Exelon personnel identified problems, entered them into the corrective action program at a low threshold, and in general, prioritized issues commensurate with their safety significance. Exelon 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 Exelon implemented corrective actions to address the problems identified in the corrective action program in a timely manner.
The inspectors concluded that Exelon adequately identified, reviewed, and applied relevant industry operating experience to Peach Bottom operations. In addition, based on those items selected for review, the inspectors determined that Exelon'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 Exelon's corrective action program at Peach Bottom. 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 Code of Federal Regulations 50, Appendix B, Criterion XVI, "Corrective Action," and Exelon procedure LS-AA-125, "Corrective Action Program Procedure." 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 multiple Plan-of-the-Day, Station Ownership Committee, and Management Review Committee meetings. The inspectors selected items from the following functional areas for review: engineering, operations, maintenance, emergency preparedness, radiation protection, chemistry, physical security, and radiation protection.
- (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 various systems on site, such as the emergency diesel generators, high pressure coolant injection, reactor core isolation cooling, core spray, residual heat removal, 125 Vdc batteries, and 4kV equipment rooms. Additionally, the inspectors reviewed a sample of condition reports written to document issues identified through internal self-assessments, audits, and the operating experience program. The inspectors completed this review to verify that Exelon 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 August 2011. 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 Exelon'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 Exelon'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 Exelon personnel properly evaluated and resolved these issues. In addition, the inspectors expanded the corrective action review to five years to evaluate Exelon actions related to average power range monitors and conditions associated with reactor half-scram signals.
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 Exelon identified problems and entered them into the corrective action program at a low threshold. Exelon staff at Peach Bottom initiated approximately 32,000 condition reports between August 2011 and May 2013. The inspectors observed supervisors at the Plan-of-the-Day, Station Ownership Committee, and Management Review Committee meetings appropriately questioning and challenging condition reports to ensure clarification of the issues.
Based on the samples reviewed, the inspectors determined that Exelon trended equipment and programmatic issues, and appropriately identified problems in condition reports. 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, Exelon personnel promptly initiated condition reports and took immediate action to address the issues.
- (2) Effectiveness of Prioritization and Evaluation of Issues
The inspectors determined that, in general, Exelon appropriately prioritized and evaluated issues commensurate with the safety significance of the identified problem. Exelon 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 Exelon corrective action program implementing procedures appeared sufficient to ensure consistency in categorization of issues. Operability and reportability determinations were 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. However, the inspectors noted the following observation in Exelon's prioritization of condition reports.
Exelon generated condition reports 1396023 and 1272124 to document Maintenance Rule concerns with the 480V and core spray systems, respectively. Included in these condition reports were actions to perform a Maintenance Rule paragraph a(1) determination to evaluate each system's Maintenance rule classification. The station assigned a significance level of 4 to both of these condition reports. Exelon procedure LS-AA-120, Attachment 2, "Issue Report Level and Class Criteria," provides examples to be considered when assigning a condition report significance level. LS-AA-120 defines a potential Maintenance Rule a(1) condition as a significance level 3 condition report. The inspectors determined that assigning a level 4 to condition reports 1396023 and 1272124 did not meet the guidance described in LS-AA-120, and therefore, was a performance deficiency. However, because these issues were isolated cases and did not indicate a programmatic weakness to properly prioritize condition reports, the inspectors determined that the issue was of minor significance and not subject to enforcement action in accordance with the NRC's Enforcement Policy. Exelon documented this issue in condition report 1513303.
- (3) Effectiveness of Corrective Actions The inspectors concluded that corrective actions for identified deficiencies were, in general, timely and adequately implemented. For significant conditions adverse to quality, Exelon, in general, 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 timely and effective. However, the inspectors noted the following observation associated with prompt corrective action.
The inspectors reviewed root cause evaluation 938245 and determined that Exelon did not take prompt corrective action for a condition adverse to quality. Since 2009, Exelon has experienced multiple steam leak detection instrument power supply failures due to grounds that have affected the 125Vdc syst em. Exelon staff developed a corrective action to prevent recurrence (CAPR) to revise design specifications for the steam leak detection system power supplies to include adequate voltage surge suppression capability for equipment connected to the direct current system. The CAPR, however, did not require replacement of the power supplies currently installed in the plant under the previous design specification.
Since power supply failures have continued to occur since the CAPR was completed, the inspectors determined that not promptly correcting the steam leak detection system power supply failures was a performance deficiency.
The inspectors screened the issue in accordance with NRC Inspection Manual Chapter (IMC) 0612, Appendix B, "Issue Screening," and IMC Appendix E, "Examples of Minor 6 Enclosure Issues," and determined the issue was similar to the minor example in example 4d. The inspectors determined the issue was of minor significance and not subject to enforcement action because the failure of Exelon's CAPR to promptly correct power supplies problems did not impact safety. The main steam leak detection system is designed with redundant power supplies, therefore a single power supply failure has no safety impact, and multiple, concurrent failures would be required to generate a single channel containment isolation valve trip signal. Exelon entered this issue into the corrective action program in condition report 1522740.
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 Exelon personnel appropriately evaluated the operating experience information for applicability to Peach Bottom 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 Exelon personnel 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 Exelon 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 operating experience was appropriately applied and lessons learned were communicated and incorporated into plant operations and procedures when applicable. The inspectors also observed that industry operating experience was routinely discussed and considered during the conduct of Station Ownership Committee and Management Review Committee meetings.
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, focused area self-assessments, and check-in self-assessments performed by Exelon. Inspectors performed these reviews to determine if Exelon entered problems identified through these assessments into the corrective action 7 Enclosure program, when appropriate, and whether Exelon 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 focused area self-assessments, check-in self-assessments, and audits were critical, thorough, and effective in identifying issues. The inspectors observed that Exelon personnel knowledgeable in the subject completed these audits and self-assessments in a methodical manner. Exelon staff completed these audits and self-assessments to a sufficient depth to identify issues which were then entered into the corrective action program for evaluation. 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 Peach Bottom. Specifically, the inspectors interviewed personnel to determine whether they were hesitant to raise safety concerns to their management or the NRC. The inspectors also interview ed the station Employee Concerns Program coordinator to determine what actions are implemented to ensure employees were aware of the program and its availability with regards to raising safety concerns. The inspectors reviewed the Employee Concerns Program files to ensure that Exelon entered issues into the corrective action program when appropriate.
b. Assessment During interviews, Peach Bottom 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 these limited interviews, the inspectors concluded that there was not evidence of an unacceptable safety conscious work environment and there were not significant challenges to the free flow of information.
c. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On May 23, 2013, the inspectors presented the inspection results to Mr. Patrick Navin, Plant Manager, and other members of the Peach Bottom 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
- R. Arters, Chemistry Technician
- C. Bauer, RCIC System Manager
- R. Brightup, Air Operated Valve Program Manager
- D. Dullum, Licensing Engineer
- M. Flynn, Senior Maintenance Programs Specialist
- A. Fogarty, Chemistry Staff
- J. Fogarty, Outage Planner
- S. Griffith, Security Operations Manager
- M. Grim, Chemistry Technician
- J. Kelly, Employee Concerns Specialist
- J. Kovalchick, Site Security Manager
- R. Lack, System Engineer
- M. Long, Senior Engineering Manager
- D. McClellan, Senior Regulatory Engineer
- G. Mehrotra, Senior Electrical Engineer
- M. Miller, Employee Concerns Specialist
- J. Moore, Operations Outage Manager Assistant
- R. Moye, System Engineer
- J. Paxson, Chemistry Technician
- C. Reynolds, Motor Operated Valve Program Manager
- R. Shortes, Radiation Engineering Manager
- D. Turek, Shift Operations Superintendent
- D. Wheeler, Maintenance Rule Program Coordinator
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened and Closed
None
LIST OF DOCUMENTS REVIEWED