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| number = ML16305A378
| number = ML16305A378
| issue date = 10/25/2016
| issue date = 10/25/2016
| title = McGuire Nuclear Station - NRC Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications Inspection Report 05000369/2016008 and 05000370/2016008
| title = NRC Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications Inspection Report 05000369/2016008 and 05000370/2016008
| author name = Bartley J H
| author name = Bartley J
| author affiliation = NRC/RGN-II/DRS/EB1
| author affiliation = NRC/RGN-II/DRS/EB1
| addressee name = Capps S D
| addressee name = Capps S
| addressee affiliation = Duke Energy Carolinas, LLC
| addressee affiliation = Duke Energy Carolinas, LLC
| docket = 05000369, 05000370
| docket = 05000369, 05000370
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ber 25, 2016
[[Issue date::October 25, 2016]]


Mr. Steven Site Vice President Duke Energy Carolinas, LLC McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078
==SUBJECT:==
 
MCGUIRE NUCLEAR STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000369/2016008 AND 05000370/2016008
SUBJECT: MCGUIRE NUCLEAR STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000369/2016008 AND 05000370/2016008


==Dear Mr. Capps:==
==Dear Mr. Capps:==
On September 29, 2016, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your McGuire Nuclear Station, Units 1 and 2, and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
On September 29, 2016, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your McGuire Nuclear Station, Units 1 and 2, and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.


The NRC inspectors did not identify any finding or violation of more than minor significance. This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding.
The NRC inspectors did not identify any finding or violation of more than minor significance.


Sincerely,/RA/ Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000369, 05000370 License Nos.: NPF-9, NPF-17  
This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
 
Sincerely,
/RA/
Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000369, 05000370 License Nos.: NPF-9, NPF-17


===Enclosure:===
===Enclosure:===
Inspection Report 05000369/2016008 and 05000370/2016008  
Inspection Report 05000369/2016008 and 05000370/2016008 w/Attachment:
Supplemental Information


===w/Attachment:===
REGION II==
Supplemental Information
Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17 Report Nos.: 05000369/2016008, 05000370/2016008 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station Location: Huntersville, NC 28078 Dates: September 12, 2016, through September 29, 2016 Inspectors: M. Riley, Reactor Inspector (Team Leader)
R. Patterson, Reactor Inspector M. Greenleaf, Reactor Inspector C. Franklin (Trainee)
Approved by: Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Enclosure


cc: Distribution via Listserv October 25, 2016 Mr. Steven
=SUMMARY=
Inspection Report (IR) 05000369/2016008 and 05000370/2016008; September 12 - 29, 2016;


=SUMMARY=
McGuire Nuclear Station, Units 1 & 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
Inspection Report (IR) 05000369/2016008 and 05000370/2016008; September 12 - 29, 2016; McGuire Nuclear Station, Units 1 & 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.


This report covers a two-week onsite inspection by four regional reactor inspectors. No findings were identified. The Nuclear Regulatory Commission's (NRC's) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5.
This report covers a two-week onsite inspection by four regional reactor inspectors. No findings were identified. The Nuclear Regulatory Commissions (NRCs) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5.


=REPORT DETAILS=
=REPORT DETAILS=


==REACTOR SAFETY==
==REACTOR SAFETY==
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity {{a|1R17}}
{{a|1R17}}
==1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications==
==1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications==
{{IP sample|IP=IP 71111.17T}}
{{IP sample|IP=IP 71111.17T}}


====a. Inspection Scope====
====a. Inspection Scope====
Evaluations of Changes, Tests, and Experiments: The inspectors reviewed eight safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, "Changes, tests, and experiments," to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 18 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
Evaluations of Changes, Tests, and Experiments: The inspectors reviewed eight safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 18 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
* the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
* the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
* the safety issues requiring the changes, tests or experiments were resolved;
* the safety issues requiring the changes, tests or experiments were resolved;
* the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
* the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
* the design and licensing basis documentation used to support the change was updated to reflect the change. The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000.
* the design and licensing basis documentation used to support the change was updated to reflect the change.
 
The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000.


This inspection constituted eight evaluation samples and 18 screening and/or applicability determination samples as defined in Inspection Procedure (IP) 71111.17-04.
This inspection constituted eight evaluation samples and 18 screening and/or applicability determination samples as defined in Inspection Procedure (IP) 71111.17-04.


Permanent Plant Modifications: The inspectors reviewed 11 permanent plant modifications that had been installed during the last three years. The modifications reviewed are listed below:
Permanent Plant Modifications: The inspectors reviewed 11 permanent plant modifications that had been installed during the last three years. The modifications reviewed are listed below:
* EC 098815, 2ETB8, 2ETB12 & 2ETB13 Relay Setting Changes
* EC 098815, 2ETB8, 2ETB12 & 2ETB13 Relay Setting Changes
* EC 101497, Thermal Barrier Hi Flow Set point Increase
* EC 101497, Thermal Barrier Hi Flow Set point Increase
* EC 101499, Revise Rotork Actuator Limit Switch MOV 1ND0058A
* EC 101499, Revise Rotork Actuator Limit Switch MOV 1ND0058A
* EC 101520, Steam Generator Primary Manway Nut Replacement with Hydra-Nut U1
* EC 101520, Steam Generator Primary Manway Nut Replacement with Hydra-Nut U1
* EC 103396, Design Change Request for FD, Fuel Oil Transfer Pump Motor, 1.0 H.P. AC Motor MNT Replacement 20/40 Exception
* EC 103396, Design Change Request for FD, Fuel Oil Transfer Pump Motor, 1.0 H.P. AC Motor MNT Replacement 20/40 Exception
* EC 106365, Replace Panelboard 1EKVA
* EC 106365, Replace Panelboard 1EKVA
* EC 106409, Replace DC Converters for EDG 1B Speed Switches
* EC 106409, Replace DC Converters for EDG 1B Speed Switches
Line 78: Line 84:
* the procedures and training plans affected by the modification had been adequately updated;
* the procedures and training plans affected by the modification had been adequately updated;
* the test documentation as required by the applicable test programs had been updated; and
* the test documentation as required by the applicable test programs had been updated; and
* post-modification testing adequately verified system operability and/or functionality The inspectors also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications. Documents reviewed are listed in the Attachment.
* post-modification testing adequately verified system operability and/or functionality The inspectors also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications.
 
Documents reviewed are listed in the Attachment.


====b. Findings====
====b. Findings====
No findings were identified.  
No findings were identified.
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Meetings, Including Exit==
==4OA6 Meetings, Including Exit==


On September 29, 2016, the inspectors presented inspection results to Mr. Steven Capps and other members of the licensee's staff. The inspectors verified no proprietary information was retained or documented in this report.
On September 29, 2016, the inspectors presented inspection results to Mr. Steven Capps and other members of the licensees staff. The inspectors verified no proprietary information was retained or documented in this report.


ATTACHMENT:
ATTACHMENT:  


=SUPPLEMENTARY INFORMATION=
=SUPPLEMENTARY INFORMATION=
Line 94: Line 102:


===Licensee personnel===
===Licensee personnel===
: [[contact::S. Capps]], Site Vice President  
: [[contact::S. Capps]], Site Vice President
: [[contact::S. Snider]], Plant Manager  
: [[contact::S. Snider]], Plant Manager
: [[contact::N. Kunkel]], Engineering Manager  
: [[contact::N. Kunkel]], Engineering Manager
: [[contact::J. Robertson]], Regulatory Affairs Manager  
: [[contact::J. Robertson]], Regulatory Affairs Manager
: [[contact::P. Vu]], Regulatory Affairs  
: [[contact::P. Vu]], Regulatory Affairs
: [[contact::B. Richards]], Regulatory Affairs  
: [[contact::B. Richards]], Regulatory Affairs
: [[contact::B. Hutchinson]], Mechanical Design Principal Engineer  
: [[contact::B. Hutchinson]], Mechanical Design Principal Engineer
: [[contact::B. Underwood]], Mechanical Design Senior Engineer  
: [[contact::B. Underwood]], Mechanical Design Senior Engineer
: [[contact::P. Fuhs]], Electrical Design
: [[contact::P. Fuhs]], Electrical Design
===NRC personnel===
===NRC personnel===
: [[contact::F. Ehrhardt]], Chief, Projects Branch 5, Division of Reactor Projects  
: [[contact::F. Ehrhardt]], Chief, Projects Branch 5, Division of Reactor Projects
: [[contact::A. Hutto]], Senior Resident Inspector, Division of Reactor Projects  
: [[contact::A. Hutto]], Senior Resident Inspector, Division of Reactor Projects
: [[contact::R. Cureton]], Resident Inspector, Division of Reactor Projects
: [[contact::R. Cureton]], Resident Inspector, Division of Reactor Projects
 
==LIST OF REPORT ITEMS==
==LIST OF REPORT ITEMS==


===Opened, Closed, and Discussed===
===Opened, Closed, and Discussed===
None
 
None


==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS REVIEWED==
Permanent Plant Modifications
 
: EC 098815, MD201893  -
: 2ETB8, 2ETB12 & 2ETB13 Relay Setting Changes
: EC 101497, Thermal Barrier Hi Flow Setpoint Increase
: EC 101499, Revise Rotork Actuator Limit Switch MOV 1ND0058A
: EC 101520, Steam Generator Primary Manway Nut Replacement with Hydra-Nut U1
: EC 103396, Design Change Request for FD, Fuel Oil Transfer Pump Motor, 1.0
: H.P. AC Motor 
: MNT Replacement 20/40 Exception
: EC 106112, Replace SSPS Slave Relays with Cutler-Hammer D26MR802A
: EC 106365, Replace Panelboard 1EKVA
: EC 106409, Replace DC Converters For EDG 1B Speed Switches
: EC 108642, Replace 1NCLT5170 with a Rosemount 1153HD5RB
: EC 112046, Replace Agastat Time Delay Relay 7022AB with Agastat time delay relay
: E7022AB004 Spec-Ngd-Cgd-2006.10-00-0004-002, Mastergear Model
: MBF 44/11A Gearbox Piece Parts
: CFR 50.59 Evaluations
: EC 097370, SR/IR Replacement
: EC 101080, "B" Train RN to CA Suction Relocation - Unit 1
: EC 101081, "B" Train RN to CA Suction Relocation - Unit 2 Phase 2
: EC 103951, Replace Main Power Relays to Maintain GCB Functionality
: EC 107118, Replace Unit 2 MSU Transformer 2A
: EC 109071, Assured CA Suction for Extended SBO Per NRC Order Ea-12-049 Unit 1
: EC 113050, RN A Train Manway Wet Tap
: EC 113220, DRPI I/O Controller Replacement
: CFR 50.59 Screenings
: EC 098517, Remove Internals and Add New Valve. - MNT
: EC 098748, MD101882 - 1ETA10 Relay Setting Changes - Mod
: EC 100612, Install High Pt Vents On ND for
: GL 08-01 U1 Mod
: EC 102477, RN Strainer Backwash Pump - 1A Mod
: EC 103921, Actuator Change (And Wiring Reversal)
: EC 103927, Actuator Replacement
: EC 104506, EDG 2B Voltage Regulator Design Change
: EC 105885, U1 Measurement Uncertainty Recapture (Mur) Power Uprate Supports 10
: CFR 50
: Appendix K
: EC 107213, Junction Box Cover Replacement
: EC 107768, Change Breaker Size for U1 VE Heater Circuits From 50A To 60A
: EC 108639, Revise RN, NM, NV, VE and VI System Tac Sheet Valve Stroke Times
: EC 108772, OBDN Resolution Support For RN A Train Suction Pipe from SNSWP (RN
: Manway)
: EC 111274, Install Ca System Tees (Ec103963 Pre-Implementation) Supports CA Pumps Assured Minimum Flow Paths EC - Unit 2
: EC 112364, Fuel Oil Booster Pump Motor Setpoints for Starting Resistor
: EC 112805, Change the Running Overload Heater for 2emxb-1 Compt 6C - Valve 2NI-183b
: EC 113861, Rosemount Transmitter Replacement
: EC 403610, Revise Mctc-1561-Nd.V009-01 to Provide Compensatory Action for Valve Failed
: Open 
===Procedure===
: Change AP/1/A/5500/20, OBDN
: Licensing Bases Documents SER and Supplements TRM, Current
: TS, Current
: UFSAR, Current 
===Calculations===
: MCC-1223.42-00-0026, CA Valve Design Basis and
: GL 89-10 Response, Rev. 19
: MCC-1205.19-00-0003, 1CA-42, 46, 58, 62 Design Calculation, dated 8/5/97
: DPC-1381.05-00-0009, Qualified Life of Agastat E7000 Series Timing Relays, Rev. 3
: MCC-1381.05-00-0194-ICC-0002, Allow Replacing SSPS Slave Relays with Cutler-Hammer
: D26MR802A, Rev. 0
: DPC-1381.05-00-0006, Duke Power Company - Shelf Life and Storage, Rev. 2
: MCS-1240.03-00-0001, McGuire Nuclear Station Plant Environmental Qualification and
: Parameters, Rev. 9
: MCC-1381.05-00-0094-ICC-0001, NV and
: KF 50/51 Relay Setting Changes, dated 11/19/13
: MCC-1381.05-00-0007, Cable Ampacities and Impedances to be Used in Cable Sizing, Rev. 13
: MCC-1381.05-00-0335-ICC-0001, Change Breaker Size for U1 VE Heater Circuits, Rev. 0
: MCC-1381.06-00-0094, FMEA for
: MSU-2A
: EC 107118, Rev. 1
: MCC-1381.16-00-0433, Design Input Calculation for
: EC 107118 Replace 2A MSU Transformer,
: Rev. 3
: DPC-1381.05-00-0053, 120V AC Panel Fuse Sizing Calculation (EPF and EPG) for McGuire and Catawba, Rev. 0
: MCC-1381.06-00-0007, Symmetrical Short Circuit MVA on Generator Breaker During Bolted 3-
: Phase Fault on Low Side (24kV) Terminals on Main Step-Up Transformer, Rev. 16
: MCC-1223.42-00-0053, Suction Transfer Analysis, Rev. 4
: MCC-1223.42-00-0037, Inadvertent Autoswap Evaluation, Rev. 12
: MCC-1205.19-00-0003, 89-10 Valve Calculation for CA Valves, Rev. 44
: MCC-1206.02-74-0012, Seismic Analysis Calculation, Rev. 0
: MCC-1121.00-00-0007, Accumulator Seismic Analysis Calculation, Rev. 10
: MCC-1201.05-00-0006, Rerate Qualification for AuxFeed Pump, Rev. 1
: MCM-1218.02-0023.001, Seismic Calculation for RN Strainer Valves, Rev. 4 
===Procedures===
: AP-1-A-5500-020, Loss of RN, Rev 33
: AP-1-A-5500-019, Loss of ND or ND System Leakage, Rev. 28
: PT-1-A-4200-002 C, Containment Closure, Rev 87
: AD-EG-ALL-1133, Preparation and Control of Equivalent Change Engineering Changes, Rev. 0 IP/0/A/3090/002, Instrument and Electrical Configuration Control, Troubleshooting and
: Corrective Maintenance, Rev. 64
: 173-9230092-005, Commercial Grade Dedication Plan Duke Specific Dedication Plan for D26 
: Relays, Rev. 5 OP/1/A/6100/010L, Annunciator Response for Panel 1AD-11
: AD-EG-ALL-1202, Preventative Maintenance and Surveillance Testing Administration, Rev. 3
: IP/1/A/4971/001, Brown Boveri
: ITE 50 and
: ITE 51 Relay Test, Rev. 17
: IP/2/A/4971/001, Brown Boveri
: ITE 50 and
: ITE 51 Relay Test, Rev. 16
: TE-MN-ALL-0202, Transformer and Apparatus Testing, Rev. 0 IP/0/B/2007/005, Oil Filled Transformer Inspection and Maintenance, Rev. 7 PT/2/A/4252/003B, CA Train B Valve Stroke Timing - Quarterly TDAFW Flowpath, Rev. 27
: PT/2/A/4252/002B, CA Valve Stroke Timing - Quarterly 1B MDAFW Flowpath, Rev. 47 
: PT/2/A/4252/002A, CA Valve Stroke Timing - Quarterly 1A MDAFW Flowpath, Rev. 43 EP/1A/5000/E-1, Emergency Operating Procedure, Rev. 17
: EP/1A/5000/ES-1.2, Emergency Operating Procedure, Rev. 18 AP/1A/5500/034, Abnormal Operating Procedure, Rev. 23 EP/1A/5000/034, Emergency Operating Procedure, Rev. 39
: PT/2/A/4403/007, RN Train 2A Flow Balance, Rev. 96
: PT/2/A/4200/038, Venting of CA System Suction Piping, Rev. 45
: IP/1/A3090/021KC, KC Loop Claibration And Operational Test, Rev. 28
: IP/0/A3066/013B, Testing Kerotest Valves Using VIPER, Rev. 14
: Completed Procedures PT/1/A/4350/002B, Diesel Generator 1B Operability Test, dated 2/18/16
: TT/1/A/EC106365/001, Post Modification Testing of 120 VAC Vital Power Panelboard 1EKVA, dated 4/11/16
===Drawings===
: MCFD-1561-01.00, Flow diagram Residual Heat Removal System (ND), Rev. 23
: MCFD-1574-01.00, Flow diagram of Nuclear Service Water System (RN), Rev. 31
: MCFD-1574-01.01, Flow diagram of Nuclear Service Water System (RN), Rev. 36
: MCFD-1574-02.00, Flow diagram of Nuclear Service Water System (RN), Rev. 35
: MCFD-1574-02.01, Flow diagram of Nuclear Service Water System (RN), Rev. 12
: MCFD-1574-03.00, Flow diagram of Nuclear Service Water System (RN), Rev. 37
: MCFD-1574-03.01, Flow diagram of Nuclear Service Water System (RN), Rev. 11
: MCFD-1574-04.00, Flow diagram of Nuclear Service Water System (RN), Rev. 20
: MCFD-1574-05.00, Flow diagram of Nuclear Service Water System (RN), Rev. 7
: MCFD-2562-03.01, Flow Diagram of Safety Injection System (NI), Rev. 15
: MCEE-0147-33.00, Elementary Diagram Aux. Feedwater System (CA) Valve 1CA0162B, Rev. 4
: MC-1705-01.00, One Line Diagram 125 VDC / 120 VAC Vital Instrument and Control PWR.
: SYS, Rev. 110
: MCSRD-CAA-001, Composite DWG SYS CA, Rev. 6 
===Miscellaneous Documents===
: 00813-0100-4388, Rosemount 1153 Series D Alphaline Nuclear Pressure Transmitters,
: Rev. BA
: AB2, Operator Rounds for
: CA-162B, Rev. 21
: Addendum 1, Rev. 1 to Qualification Report No. 828, Class 1E Qualification of
: 201592 Cables For McGuire Nuclear Station Unit 1 and 2, Rev. 2
: CGD-2006.10-00-004, Mastergear Model
: MBF 44/11A Gearbox and Piece Parts, Rev. 2
: DPM-1391.01-0003, Environmental Qualification Package for Amerace Corporation (Agastat)     
: E7000 Series Pneumatic Timing Relays Model Nos. E7012, E7022, and E7024 and 7000
: Series Pneumatic Timing Relay 7032ACC, Rev. D11
: EC 097370, Replacement of Source Range and Intermediate Range Excore Detectors and
: Electronics, Rev. 8
: EC 101520, S/G Primary Manway Nut Replacement with Hydra-Nut U1 Mod, Rev. 0
: EC 101545, 1B RN Strainer Backwash Inlet Valve Assured Air Supply, Rev. 13
: EC 103921, Change Actuator on 2NI0185A from 90NA2-86 to 90NA1E-86, Rev. 2
: EC 103927, Change Actuator on 2RN-299A from NA2 to NA1E, Rev. 2
: EC 106112, Allow Replacing SSPS Slave Relays with Cutler-Hammer D26MR802A, Rev, 1
: EC 107213, Evaluate Use of New Gammametrics Junction Box Covers, Rev. 0
: EC 108642, Replace 1NCLT5170 with a Rosemount 1153HD5RB, Rev. 0
: EC 112046, Agastat Time Delay Relay 7022AB is Obsolete. Allow Agastat Time, Rev. 0
: EC 113861, Replace 1NCLT5160 with a Rosemount Model 3154, Rev. 0
: EQMM-1393.01-F04-00, Environmental Qualification Maintenance Manual, Rev. 7
: McGuire Nuclear Station, Unit 1 and 2, Issuance of Amendments Regarding Measurement
: Uncertainty Recapture Power Uprate (TAC NOS. ME8213 and ME8214), dated 5/16/13
: MCM 1201.05-0479, Westinghouse Motor Company Induction Motor Starting Characteristics, Rev. 3
: MCM 1205.19-0066.001, Electrical Data for Rotork Actuators, Rev, D4
: MCM-1346.23-0009.002, Qualification Test Report for the Neutron Flux Monitoring System,
: Rev. 2
: MCS-1240.03-00-0001, McGuire Nuclear Station Plant Environmental Qualifications and
: Parameters, Rev. 9
: MCTC-1562-NI-V025-01, ND Valve Design Criteria/Operability Requirements and
: Compensatory Measures, Rev. 10
: MCTC-1573-KC.V050-01, Testing and Acceptance Criteria for KC Valves, Rev. 0
: MCTC-1592-CA.I001-01, SR Pressure Switch Setpoints TAC, Rev. 5
: MCTC-1592-CA.I003-01, ELAP Pressure Switch Setpoints TAC, Rev. 5
: NP-5024, Seismic Ruggedness of Aged Electrical Components, January 1987
: QTR-040, Gamma-metrics RCS Series Neutron Flux Monitoring System Qualification Test
: Report No. 040, Rev. 3 Seismic Qualification Review of SuperPipe for Valve 1CA-116B
: WCAP-15977-P, Reliability Assessment of Cutler-Hammer D26MR802A Relays Used as SSPS
: Slave Relays, Rev. 1 
: Corrective Action Documents
: 01665889
: 01961266
: 01901577
: 02018668
: 01690806
: 02018758
: 01906316 M-14-02167
: 01943497
: 01943678
===Work Orders===
: 02129016-28
: 20006261-01
: 20011688-03
: 20013005-01
: 20016801-01
: 20068249-01
===Condition Reports===
generated as a result of the inspection
: 2061357, Commercial Grade Dedication
: 2061662, Fuel Leak at 1FDPT5010
: 2061860, Oil Leak noted during Walk-down of 2A MSU Transformer
: 2061892, Housekeeping Issues During Walk-down
: 2062089,
: EC 98815 Mod Test Plan
: 2062265, 1NCLT5170 Harsh Environment Qualification
: 2062307,
: EC 112406 Agastat Shelf Life/PM Generating
: 2062972, Create PMs for Timing Relays
: 2063246, 2RN-299A Actuator Nameplate Discrepancy
: 2063262, EC97370 O-ring replacement PM
: 2063615, SR/IR Detector Junction Box O-ring Total Life
: 2064684, Agastat Relay Change from Equipment Reliability Class
: ER-1 to
: ER-3
: 2065517, 2CATE7630 Wiring Degradation
: 2065528, Housekeeping Issues in U2 CA Pump Room
: 2065807, Revision of Agastat E7000 Relay Qualified Life Calculation
}}
}}

Latest revision as of 19:32, 19 December 2019

NRC Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications Inspection Report 05000369/2016008 and 05000370/2016008
ML16305A378
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 10/25/2016
From: Bartley J
NRC/RGN-II/DRS/EB1
To: Capps S
Duke Energy Carolinas
References
IR 2016008
Download: ML16305A378 (12)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ber 25, 2016

SUBJECT:

MCGUIRE NUCLEAR STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000369/2016008 AND 05000370/2016008

Dear Mr. Capps:

On September 29, 2016, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your McGuire Nuclear Station, Units 1 and 2, and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000369, 05000370 License Nos.: NPF-9, NPF-17

Enclosure:

Inspection Report 05000369/2016008 and 05000370/2016008 w/Attachment:

Supplemental Information

REGION II==

Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17 Report Nos.: 05000369/2016008, 05000370/2016008 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station Location: Huntersville, NC 28078 Dates: September 12, 2016, through September 29, 2016 Inspectors: M. Riley, Reactor Inspector (Team Leader)

R. Patterson, Reactor Inspector M. Greenleaf, Reactor Inspector C. Franklin (Trainee)

Approved by: Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

Inspection Report (IR) 05000369/2016008 and 05000370/2016008; September 12 - 29, 2016;

McGuire Nuclear Station, Units 1 & 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.

This report covers a two-week onsite inspection by four regional reactor inspectors. No findings were identified. The Nuclear Regulatory Commissions (NRCs) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications

Main article: IP 71111.17T

a. Inspection Scope

Evaluations of Changes, Tests, and Experiments: The inspectors reviewed eight safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 18 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:

  • the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
  • the safety issues requiring the changes, tests or experiments were resolved;
  • the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
  • the design and licensing basis documentation used to support the change was updated to reflect the change.

The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000.

This inspection constituted eight evaluation samples and 18 screening and/or applicability determination samples as defined in Inspection Procedure (IP) 71111.17-04.

Permanent Plant Modifications: The inspectors reviewed 11 permanent plant modifications that had been installed during the last three years. The modifications reviewed are listed below:

  • EC 098815, 2ETB8, 2ETB12 & 2ETB13 Relay Setting Changes
  • EC 101497, Thermal Barrier Hi Flow Set point Increase
  • EC 103396, Design Change Request for FD, Fuel Oil Transfer Pump Motor, 1.0 H.P. AC Motor MNT Replacement 20/40 Exception
  • EC 108642, Replace 1NCLT5170 with a Rosemount 1153HD5RB
  • EC 112046, Replace Agastat Time Delay Relay 7022AB with Agastat time delay relay E7022AB004
  • EC 106112, Replace SSPS Slave Relays with Cutler-Hammer D26MR802A
  • Spec-Ngd-Cgd-2006.10-00-0004-002, Mastergear Model MBF 44/11A Gearbox Piece Parts The modifications were selected based upon risk significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:
  • the supporting design and licensing basis documentation was updated;
  • the changes were in accordance with the specified design requirements;
  • the procedures and training plans affected by the modification had been adequately updated;
  • the test documentation as required by the applicable test programs had been updated; and
  • post-modification testing adequately verified system operability and/or functionality The inspectors also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications.

Documents reviewed are listed in the Attachment.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

On September 29, 2016, the inspectors presented inspection results to Mr. Steven Capps and other members of the licensees staff. The inspectors verified no proprietary information was retained or documented in this report.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

S. Capps, Site Vice President
S. Snider, Plant Manager
N. Kunkel, Engineering Manager
J. Robertson, Regulatory Affairs Manager
P. Vu, Regulatory Affairs
B. Richards, Regulatory Affairs
B. Hutchinson, Mechanical Design Principal Engineer
B. Underwood, Mechanical Design Senior Engineer
P. Fuhs, Electrical Design

NRC personnel

F. Ehrhardt, Chief, Projects Branch 5, Division of Reactor Projects
A. Hutto, Senior Resident Inspector, Division of Reactor Projects
R. Cureton, Resident Inspector, Division of Reactor Projects

LIST OF REPORT ITEMS

Opened, Closed, and Discussed

None

LIST OF DOCUMENTS REVIEWED

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