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| issue date = 05/15/2014
| issue date = 05/15/2014
| title = IR 05000338-14-007, 05000339-14-007; 03/31/2014-04/17/2014; North Anna Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
| title = IR 05000338-14-007, 05000339-14-007; 03/31/2014-04/17/2014; North Anna Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
| author name = Nease R L
| author name = Nease R
| author affiliation = NRC/RGN-II/DRS/EB1
| author affiliation = NRC/RGN-II/DRS/EB1
| addressee name = Heacock D A
| addressee name = Heacock D
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| docket = 05000338, 05000339
| docket = 05000338, 05000339
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 May 15, 2014 Mr. David President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
{{#Wiki_filter:May 15, 2014


SUBJECT: NORTH ANNA POWER STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000338/2014007 AND 05000339/2014007
==SUBJECT:==
NORTH ANNA POWER STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000338/2014007 AND 05000339/2014007


==Dear Mr. Heacock:==
==Dear Mr. Heacock:==
Line 27: Line 28:
The NRC inspectors did not identify any findings or violations of more than minor significance.
The NRC inspectors did not identify any findings or violations of more than minor significance.


In accordance with Title 10 of the Code of Federal Regulations 2.390, "Public Inspections, Exemptions, Requests for Withholding," 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 NRC's Agencywide Documents Access and Managem ent System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, 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 NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


Sincerely,
Sincerely,
/RA/ Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety
/RA/  


Docket Nos.: 05000338, 05000339
Rebecca L. Nease, Chief


License Nos.: NPF-4, NPF-7 Enclosures:
Engineering Branch 1
 
Division of Reactor Safety
 
Docket Nos.: 05000338, 05000339 License Nos.: NPF-4, NPF-7  
 
===Enclosures:===
Inspection Report 05000338/2014007 and 05000339/2014007 w/Attachment: Supplementary Information  
Inspection Report 05000338/2014007 and 05000339/2014007 w/Attachment: Supplementary Information  


cc: Distribution via Listserv
REGION II==
Docket Nos.:
50-338, 50-339
 
License Nos.:
NPF-4, NPF-7
 
Report Nos.:
05000338/2014007, 05000339/2014007
 
Licensee:
 
Virginia Electric and Power Company (VEPCO)


_ML14136A331_ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII: DRS RII: DRS RII: DRS RII: DRS RII: DRP RII: DRS SIGNATURE E. Stamm M. Rile y J. D ymekR. NeaseM. Kin gR. Nease NAME EJS2 MAR1 JLD2RLN1MFK1RLN1 DATE 4/28/2014 4/28/2014 4/29/2014 5/7/2014 5/13/2014 5/15/2014 E-MAIL COPY?
Facility:  
YES NO YES NO YESNO YESNO YESNO YES NO YESNO Letter to David from Rebecca L. Nease dated May 15, 2014.


SUBJECT: NORTH ANNA POWER STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000338/2014007 AND 05000339/2014007
North Anna Power Station, Units 1 and 2


Distribution w/encl:
Location:  
RIDSNRRDIRS PUBLIC RidsNrrPMNorthAnnaResource


Enclosure U. S. NUCLEAR REGULATORY COMMISSION
Mineral, Virginia 23117


==REGION II==
Dates:  
Docket Nos.: 50-338, 50-339


License Nos.: NPF-4, NPF-7
March 31, 2014 - April 17, 2014


Report Nos.: 05000338/2014007, 05000339/2014007
Inspectors:  


Licensee: Virginia Electric and Power Company (VEPCO)  
E. Stamm, Senior Reactor Inspector (Team Leader)  


Facility: North Anna Power Station, Units 1 and 2
M. Riley, Reactor Inspector


Location: Mineral, Virginia 23117
J. Dymek, Reactor Inspector


Dates: March 31, 2014 - April 17, 2014
Approved by:
Rebecca L. Nease, Chief


Inspectors: E. Stamm, Senior Reactor Inspector (Team Leader) M. Riley, Reactor Inspector J. Dymek, Reactor Inspector
Engineering Branch 1


Approved by: Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety  
Division of Reactor Safety  


=SUMMARY=
=SUMMARY=
Inspection Report (IR) 05000338/2014007, 05000339/2014007; 03/31/2014-04/17/2014; North Anna Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
Inspection Report (IR) 05000338/2014007, 05000339/2014007; 03/31/2014-04/17/2014; North  


This report covers a two-week, on-site inspection by one senior reactor inspector and two reactor inspectors. No findings or violations were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
Anna Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
 
This report covers a two-week, on-site inspection by one senior reactor inspector and two reactor inspectors. No findings or violations were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.


=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}}
(71111.17T)


====a. Inspection Scope====
====a. Inspection Scope====
Evaluations of Changes, Tests, and Experiments
Evaluations of Changes, Tests, and Experiments: The team reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 15 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:
: The team reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 15 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team 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;
Line 91: Line 107:
* the design and licensing basis documentation used to support the change was updated to reflect the change.
* the design and licensing basis documentation used to support the change was updated to reflect the change.


The team 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 team 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 seven samples of evaluations and 15 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.
This inspection constituted seven samples of evaluations and 15 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.


Permanent Plant Modifications: The team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below:
Permanent Plant Modifications: The team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below:
* DCP-04-116 - Replacement of RWST Refrigeration Units
* DCP-04-116 - Replacement of RWST Refrigeration Units
* DCP-08-101 - Emergency Condensate Storage Tank Level Indicator Replacements
* DCP-08-101 - Emergency Condensate Storage Tank Level Indicator Replacements
Line 108: Line 124:
* post-modification testing adequately verified system operability and/or functionality.
* post-modification testing adequately verified system operability and/or functionality.


The team also used applicable industry standar ds to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications. Documents reviewed are listed in the Attachment.
The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications.


This inspection constituted six permanent plant modification samples as defined in IP
Documents reviewed are listed in the Attachment.


71111.17-04.
This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.


====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 April 17, 2014, the team presented inspection results to Mr. Mladen and other members of the licensees staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.


On April 17, 2014, the team presented inspection results to Mr. Mladen and other members of the licensee's staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:  
 
ATTACHMENT:


=SUPPLEMENTARY INFORMATION=
=SUPPLEMENTARY INFORMATION=


==KEY POINTS OF CONTACT==
==KEY POINTS OF CONTACT==
===Licensee personnel===
===Licensee personnel===
: [[contact::J. Bischof]], Site Vice President  
: [[contact::J. Bischof]], Site Vice President  
Line 145: Line 160:


==LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED==
==LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED==
===Opened===
===Opened===
None
None  


===Closed===
===Closed===
: None
None  


===Discussed===
===Discussed===
None


None  Updated   None    
Updated  
 
None  


==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS REVIEWED==
CFR 50.59 Evaluations
 
: 0-OP-7.3, Revision 0, Filling U-1 or U-2 SI Accumulators with Air Operated Hydro Pump,  dated 07/02/13
: 2-SE-OT-02, TR 3.9.3, Manipulator Crane Temporary Revision, dated 04/03/12
: DCP-07-016, Fire Protection and Domestic Water System Modifications, dated 03/15/11
: ETE-NAF-2013-0053, Implementation of a Revised Rod Ejection Analysis for North Anna Power Station, dated 07/09/13
: NA-11-01023, JOG MOV Motor and Gear Modification on 1-CH-MOV-1381 and Gear Ratio Mods on 1-CH-MOV-1380 and 1-SW-MOV-105C, dated 09/06/11
: NA-11-01156, Sudden Pressure Relay Protection Bypass, dated 10/07/11
: TM-2013-1213, 2-CC-TV-204B Instrument Air Jumper, dated 12/12/13
: CFR 50.59 Screenings
: CGD-100000021859, Emergency Diesel Generator Battery Charger, dated 04/20/13
: DCP-04-008, Service Water Reservoir Spray Array Piping Replacement, dated 03/24/05
: DCP-07-123, Bearing Cooling Make-up Pump Start Logic, dated 05/16/07
: EE-10000020062, Spent Fuel Pit Cooling Pump Motor Replacement, dated 02/05/13
: NA-1-07-103, MOV Stem Cuts and Spline Adapter Machining to Permit the Installation of Strain Gauges, dated 08/30/07
: NA-08-00125, RCP Thermal Barrier CC Outlet Header Isolation Valve Margin Recovery (
: 1-CC-TV-116A/B/C), dated 11/24/09
: NA-09-00101, PdMA Large Motor Monitoring System Modification for Unit 2 Safety-Related Switchgear Buses, dated 03/08/11
: NA-09-00131, Phase 1 to Install Alternate Power Supply to Spent Fuel Pit Cooling
: Pump 1-FC-P-1A, dated 08/10/11
: NA-10-00126, Replacement of 2-SI-MOV-2867A, 2-SI-MOV-2869A and 2-SI-MOV-2869B with New 3" 1500lb Velan Valves, and
: SMB-0 Actuators with Larger Motors, dated 12/07/10
: NA-11-01031, EDG Day Tank Missile Protection Modification, dated 01/18/12
: NA-11-01098, Steam Flow/Feed Flow Coincident wi th Low Steam Generator Level Reactor Trip Function Elimination, dated 03/28/12
: NA-11-01213, Seismic Monitoring Instrumentation Upgrade, dated 03/01/12
: NA-12-00091, Installation of the JL Jumper in Pressurizer Spray Controller for Unit 2, dated 12/20/12
: NA-14-00022, Spare Conductors of RSST A to Transfer Bus "D" Due to Damaged Insulation, dated 04/04/14 OD000566, OD to Support Comp Measures for Restoration of OSRS Operability, dated 11/21/13
: Permanent Plant Modifications
: DCP-04-116, Replacement of RWST Refrigeration Units, dated 09/30/04
: DCP-08-101, Emergency Condensate Storage Tank Level Indicator Replacements,    dated 01/13/09
: NA-09-00170, EDG Lube Oil S-line Flexible Connections, dated 02/18/10
: NA-11-00006, Phase 2 to Install Alternate Power Supply to Spent Fuel Pit Cooling Pump 1-FC-P-1A, dated 05/22/12
: NA-12-00053, Replacement and Elimination of 1H Undervoltage Relays, dated 06/25/13
: NA-13-00041, Appendix R - Emergency Switchgear Isolation Switch for Service Water,    dated 08/27/13 
===Calculations===
: 11715-10N, Sizing of Refueling Water Storage Tank (RWST) Refrigeration Units, Rev. 0
: 2050-X11-111, Chemical Volume Control and Safety Injection System, Addendums 00A and 00B, Rev. 0 12050-X11-112, Safety Injection System, Addendums 00A and 00B, Rev. 0
: CE-1770, Service Water Reservoir Spray Array Piping Replacement - Heavy Loads Evaluation, Rev. 0
: CEM-0046, Pipe Stress Analysis of Safety Injection Lines for Replacement of Valve 2-SI-MOV-2867A per DC
: NA-10-00126, Rev. 1
: CEM-0103, Evaluation of the 2" Overfill and Vent Lines for the Emergency Diesel Generator (EDG) Fuel Oil Day Tanks with Modification per DC
: NA-11-01031, Emergency Diesel
: Generator Rooms, North Anna Units 1 and 2, Rev. 00
: EE-0027, Emergency Diesel Generator Load Sequencing, Rev. 3
: EE-0100, North Anna Emergency Condensate Storage Tank Level Uncertainty, Rev. 1
: EE-0687, NAPS ETAP Impedance Diagram, Rev. 0
: EE-0869, NAPS Thermal Overload Evaluation for
: GL 89-10 Motor Operated Valves, Rev. 0
: ME-0492, Thrust Band Calculation for North Anna Safety Related Motor Operated Valves, Addendum 00G, Rev. 1
: ME-0659, Evaluation of Category I AOVs to Perform Their Design Basis Function,
: Addendum 00B, Rev. 0
: ME-3207, JOG Calculation of Required Thrust Settings and Margin for 59-02-SI-MOV-2867A, Rev. 1
: ME-3211, JOG Calculation of Required Thrust Settings and Margin for 59-02-SI-MOV-2869A, Rev. 1
: ME-3212, JOG Calculation of Required Thrust Settings and Margin for 59-02-SI-MOV-2869B, Rev. 1
: PM-1363, Maximum Anticipated Spent Fuel Heat Load at North Anna, Rev. 0 
===Condition Reports===
(CRs)
: CR001148, 1-QS-MR-1B did not start with RWST temperature of 46 degrees
: CR014506, All RWST chillers have cracking foundation
: CR428487, 50.59 Screen Part II, Question 3 inadvertently marked NO for DC
: NA-09-00141
: CR429282, Observation from the NRC Modification and 50.59 Inspection
: CR440791, No documentation 50.59 screen was performed on scaffolding in place >90 days
: CR461456, 10
: CFR 50.59 Evaluation for
: DCP 07-016 did not receive FSRC approval
: CR463939,
: DCP 05-014 failed to update UFSAR section 9.5.5.3, will add to
: IPR 10-435
: CR464841, NANN - UFSAR Section 9.2.2.5.2 may need to be updated
: CR492546, 2-EG-REJ-2J4 has cracking at the base of the flanges in 2 places
: CR499981, 50.59 Screen not completed prior to erecting compensatory scaffold
: CR501455, 2-EG-REJ-2H3: face to face readings out of spec
: CR502352, Appendix R-Emergency Switchgear Isolation Switch for Service Water Units 1 and 2
: CR509424, Created
: DCU 13-3074 to revise DC
: NA-11-00006 Implementation Instructions
: CR509481,
: VPAP-2105 requires an unnecessary 50.59/72.48 Evaluation
: CR513829, 2H prelube pump rubber expansion joint has backing plates of different thickness
: CR521972, DC
: NA-12-00050 U2 SS NGV Relays - 50.59 Evaluation Required
: CR528850, Work order required for 1H-EDG expansion joints
: CR533387, Casing Cooling Tank Low Level setpoint does not account for vortexing
: CR539244, 1-QS-MR-1A (RWST Chiller) operation is suspect
: CR539475, 1-QS-MR-1A has local status messages Completed Procedures
: 1-PT-147.1, Valve Inservice Inspection (Class 2 and 3 Safety and Relief Valves), dated 09/28/10 1-PT-210.1, Valve Inservice Inspection (Service Water MOVs to RSHXs), dated 09/11/07  and 10/03/07
: 1-PT-212.34J, Valve Inservice Inspection (1-QS-MOV-102B), dated 04/06/06 and 10/13/07
: 1-PT-214.11, Valve Inservice Inspection (Recirculation Spray Heat Exchangers Service Water Valve Position Indication), dated 10/03/07
: CM-NA-TST-0620, DC
: NA-11-00006 Phase 2 to Install Alternate Power Supply to Spent Fuel Pit Cooling Pump 1-FCP-1A Test Plan, Rev. 0
: CM-NA-TST-0620, DC
: NA-11-01023 JOG MOV Motor & Gear Modification on 1-CH-MOV-1381 and Gear Ratio Mods on 1-CH-MOV-1380 & 1-SW-MOV-105C, Rev. 0
: CM-NA-TST-0620, DC
: NA-12-00051 Replacement and Elimination of 2H Undervoltage Relays Test Plan, Rev. 0
: Design Basis Documents
: NAPS Appendix R Report, Rev. 33
: SDBD-NAPS-CC, System Design Basis Document for Component Cooling Water System,
: Rev. 15
: SDBD-NAPS-EG, System Design Basis Document for Emergency Diesel Generator System, Rev. 18
: SDBD-NAPS-EP, System Design Basis Document for Emergency Power System, Rev. 15
: SDBD-NAPS-FC, System Design Basis Document for Fuel Pool Cooling and Purification System, Rev. 11
: SDBD-NAPS-SI, System Design Basis Document for Safety Injection System, Rev. 20
: SDBD-NAPS-SW, System Design Basis Document for Service Water System, Rev. 17 
===Drawings===
: 08101-2-2CN001, Condensate System Missile Protected Condensate Storage Tank 2-CN
: TK-1 Level Indicators and Alarm, Rev. 0 08101-2-2CN069, Condensate System Missile Protected Condensate Storage Tank 2-CN
: TK-1 Level Indicators and Alarm, Rev. 0 08101-2-2ESK4BA, Equipment List Sheet 41, Rev. 0
: 08101-2-2FE3BD, Wiring Diagram Main Control Vertical Board 2-2 Sh. 9 North Anna Power Station Unit 2 11715-ESK-6FB-1, Elementary Diagram 480V Circuits Bearing Make-up Pumps North Anna Power Station Unit 1, Rev. 4 11715-FB-101C, Valve Operating Numbers, Underground Fire Protection System sheet 3
: Units 3 and 4 Construction Area, North Anna Power Station - Unit 1, Rev. 8
: 11715-FC-42A-B, Support Detail Instruments for Earthquake, North Anna Power Station, Rev. 4
: 11715-FE-3DK-B, Wiring Diagram, Service Water Logic A Panel,
: SW-1A-Sh. 1 North Anna Power Station Unit 1, Rev. 1 11715-FE-3DL-B, Wiring Diagram, Service Water Logic B Panel,
: SW-1B-Sh. 1 North Anna Power Station Unit 1, Rev. 1 11715-FM-096A, Flow Valve Operating Numbers Diagram, Safety Injection System, Sheet 1  of 3, North Anna Power Station Unit 2, Rev. 43
: 11715-FM-096B, Flow Valve Operating Numbers Diagram, Safety Injection System, Sheet 1  of 3, North Anna Power Station Unit 1, Rev. 26 11715-FM-107B, Valve Operating Numbers Diagram Emergency Diesel Lube Oil System,
: Unit 1, Rev. 5
: 1200051-12050-ESK-11R, Elementary Diagram Emergency Bus "2H" Undervoltage Circuit Testing North Anna Power Station Unit 2, Rev. 1 1200051-12050-FE-21T, D.C. Elementary Diag. 4160V Emer. Bus "2H" & Intake Structure
: Bus "2G" Undervoltage North Anna Power Station Unit 2, Rev. 1 12050-ESK-6FB-1, Elementary Diagram 480V Circuits Bearing Cooling Make-up Pumps North Anna Power Station Unit 2, Rev. 6 12050-FM-096A, Flow Valve Operating Numbers Diagram, Safety Injection System, Sheet 1  of 3, North Anna Power Station Unit 2, Rev. 36
: 2050-FM-096B, Flow Valve Operating Numbers Diagram, Safety Injection System, Sheet 1  of 3, North Anna Power Station Unit 1, Rev. 31 12050-FM-107B, Valve Operating Numbers Diagram Emergency Diesel Lube Oil System,
: Unit 2, Rev. 4 Alon/George 12, Unit 1 Spent Fuel Pool Cooling Pump Alternate Power Supply 
: DC's
: NA-09-00131 and 11-00006 N-1101031-0-M-001, Piping Configuration Details, Rev. 0 N-1101031-0-M-002, Vent Pipe and Missile Protection Configuration Details, Rev. 0
: N-1101031-0-S-003, Emergency Diesel Generator Overflow Line Missile Protection Configuration, Rev. 2 
===Miscellaneous Documents===
: Updated Final Safety Analysis, Current Technical Specifications, Current Technical Requirements Manual, Current
: DCP-08-101, Operational Readiness Review, Emergency Condensate Storage Tank Level Indicator, dated 09/22/11
: DCP-08-101, Programs Review Checklist, Emergency Condensate Storage Tank Level Indicator, dated 10/01/11
: DCP-11-1098, Programs Review Checklist, Steam Flow / Feed Flow Coincident with Low
: DCU 10-887, Design Change Update for
: NA-10-00126, dated 03/03/11
: DNES-AA-GN-1007, Digital Asset Modification Considerations, Rev. 0
: DNES-AA-GN-1007, Digital Asset Modification Considerations, Rev. 1
: DNES-AA-GN-1007, Digital Asset Modification Considerations, Rev. 2, Draft B FSRC #13-103, Facility Safety Review Committee Meeting Notes, dated 12/12/13
: IEE 10000020062, Spent Fuel Pump Motor Replacement Equivalency Evaluation, Version 3
: Inspection Results of
: 06514706 Aluminum Capacitor, dated 09/14/01
: Log Entries Report, dated 12/11/13
: NA-11-01098, Operational Acceptance Checklist, LO Feedwater Trip Elimination, Steam Generator Level Reactor Trip Function Elimination, dated 05/16/13
: NA-13-00041, Design Change, Appendix R-Emergency Switchgear Isolation Switch for Service Water, dated 08/27/13
: NA-13-00041, Operational Acceptance Checklist, Appendix R-Emergency Switchgear Isolation Switch for Service Water, dated 09/20/13, 09/26/13, 11/06/13, and 11/14/13
: NAPS-PO-MAT-45907679, Carotek, Inc. Test Report, dated 03/22/12
: NAS-97, Specification for Spent Fuel Pit and Refueling Purification Pumps, Rev. 2
: NCRODP-35-NA, Vital and Emergency Electrical Distribution System, dated 12/10/13
: NCRODP-49-NA, Nuclear Control Room Operator Development Program Spent Fuel Pit System, dated 07/13/13 OD000297, The Vent Lines Associated with the Emergency Diesel Generator Fuel Oil Day Tanks Are Not Missile Protected, dated 05/21/09 OD000566, OD to Support Comp Measures for Restoration of OSRS Operability, dated 11/21/13
: PTE 100000021859, Emergency Diesel Generator Battery Charger La March Model A11-10-
: 130V, Version 00 Purchase Order
: 45225698,
: 42043897 Electrolytic Aluminum Capacitor, dated 09/18/03
: STD-EEN-0026, Electrical Systems Analysis Checklist, Spent Fuel Pit Cooling Pump Motor Replacement/NAPS/Units 1 & 2, Rev. 16
: TRCR-143, TR 3.9.3 License Basis Document Change, dated 03/22/12
: Type CGS Computer Grade Aluminum Electrolytic Capacitor Versatile Measuring Instruments, Inc. Manual No. 2000, Instruction Manual Series 2000 Bargraph Indicators and Indicating Controllers, Rev. 1 Virginia Electric and Power Company (Dominion) North Anna Power Station Units 1 and 2, Summary of Facility Changes, Tests, and Experiments, dated 3/29/11 Virginia Electric and Power Company (Dominion) North Anna Power Station Units 1 and 2, Summary of Facility Changes, Tests, and Experiments, dated 2/27/12 Virginia Electric and Power Company (Dominion) North Anna Power Station Units 1 and 2, Summary of Facility Changes, Tests, and Experiments, dated 3/18/13 Virginia Electric and Power Company (Dominion) North Anna Power Station Units 1 and 2, Summary of Facility Changes, Tests, and Experiments, dated 3/24/14 
===Procedures===
: 0-FCA-1, Control Room Fire, Rev. 41 0-GOP-7.4, Spent Fuel Pit Cooling Pump Alternate Power Supply, Rev. 5
: 0-MPM-1003-09, External Inspection of EDG Lube Oil Line Rubber Expansion Joints, Rev. 0
: 0-OP-4.59, Operation of the Special Fuel Assembly Cruciform Handling Tool (SFACHT), Rev. 2
: 0-OP-7.3, Filling U1 or U2 SI Accumulators with Air Operated Hydro Pump, Rev. 0 0-OP-16.1, Spent Fuel Pool Cooling and Purification System, Rev. 35 1-AR-H-D7, RSS XFMR 1C Trouble, Rev. 2
: 1-FCA-2, Emergency Switchgear Room Fire, Rev. 33
: 1-GOP-4.25, Fuel Assembly Recovery Process, Rev. 1
: 1-OP-7.3, Filling, Draining, Pressurizing, and Venting SI Accumulators, Rev. 52
: 2-FCA-2, Emergency Switchgear Room Fire, Rev. 32
: CM-AA-400, 10
: CFR 50.59 and 10
: CFR 72.48 - Changes, Tests, and Experiments, Rev. 3
: CM-AA-DBD-1001, Control of Design Basis Documents, Rev. 2
: CM-AA-TCC-204, Temporary Configuration Changes, Rev. 2
: IT-AA-SQA-101, Software Quality Assurance, Rev. 5
: PI-AA-100-1007, Operating Experience Program, Rev. 10
: VPAP-0306, Station Software Control, Rev. 7
: VPAP-3001, Safety and Regulatory Reviews, Rev. 12 
===Work Orders===
: 00755722-02, PMT for 1-SW-MOV-105C, dated 09/13/07
: 00755722-03, PMT for 1-SW-MOV-105D, dated 09/13/07
: 00755722-05, PMT for 1-SW-MOV-101A, dated 09/13/07
: 00755722-06, PMT for 1-SW-MOV-101B, dated 09/13/07
: 00755722-10, PMT for 1-QS-MOV-102B, dated 10/10/07
: 59077730101, Perform
: DCP 07-123 FC 1, dated 05/31/11
: 59102027510, PMT for 1-CC-RV-125A, dated 10/03/10
: 59102066408, PMT for 1-CC-RV-125B, dated 10/03/10 59102066427, PMT for 1-CC-RV-125C, dated 10/03/10 59102156699, PMT for 1-CC-RV-125A, dated 10/04/10
: 59102156723, PMT for 1-CC-RV-125B, dated 10/03/10
: 59102156743, PMT for 1-CC-RV-125C, dated 10/04/10
: 59102270670, Perform
: DCP 07-123 FC 2, dated 09/19/11 59102356780, Install Sudden Pressure Relay Bypass on RSST "C" DC
: NA-11-01156,        dated 10/25/11 59102517535, Installation of Tee Spool Piece for Filling U-1 or U2 SI Accumulators with Air Operated Hydro Pump, dated 07/02/13 
===Condition Reports===
generated as a result of the inspection
: CR543785, Admin error in calc
: EE-0027
: CR545212, Missing acceptance criteria in inspection plan
: CR545225, DC did not update system DBD
}}
}}

Latest revision as of 20:43, 10 January 2025

IR 05000338-14-007, 05000339-14-007; 03/31/2014-04/17/2014; North Anna Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
ML14136A331
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 05/15/2014
From: Nease R
NRC/RGN-II/DRS/EB1
To: Heacock D
Virginia Electric & Power Co (VEPCO)
References
IR-14-007
Download: ML14136A331 (14)
v • d • e


Text

May 15, 2014

SUBJECT:

NORTH ANNA POWER STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000338/2014007 AND 05000339/2014007

Dear Mr. Heacock:

On April 17, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your North Anna Power Station Units 1 and 2, and discussed the results of this inspection with Mr. Mladen and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.

The NRC inspectors did not identify any findings or violations of more than minor significance.

In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, 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 NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Rebecca L. Nease, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 05000338, 05000339 License Nos.: NPF-4, NPF-7

Enclosures:

Inspection Report 05000338/2014007 and 05000339/2014007 w/Attachment: Supplementary Information

REGION II==

Docket Nos.:

50-338, 50-339

License Nos.:

NPF-4, NPF-7

Report Nos.:

05000338/2014007, 05000339/2014007

Licensee:

Virginia Electric and Power Company (VEPCO)

Facility:

North Anna Power Station, Units 1 and 2

Location:

Mineral, Virginia 23117

Dates:

March 31, 2014 - April 17, 2014

Inspectors:

E. Stamm, Senior Reactor Inspector (Team Leader)

M. Riley, Reactor Inspector

J. Dymek, Reactor Inspector

Approved by:

Rebecca L. Nease, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

Inspection Report (IR) 05000338/2014007, 05000339/2014007; 03/31/2014-04/17/2014; North

Anna Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.

This report covers a two-week, on-site inspection by one senior reactor inspector and two reactor inspectors. No findings or violations were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.

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 team reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 15 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team 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 team 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 seven samples of evaluations and 15 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.

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

  • DCP-04-116 - Replacement of RWST Refrigeration Units
  • DCP-08-101 - Emergency Condensate Storage Tank Level Indicator Replacements
  • NA-11-00006 - Phase 2 to Install Alternate Power Supply to Spent Fuel Pit Cooling Pump 1-FC-P-1A
  • NA-12-00053 - Replacement and Elimination of 1H Undervoltage Relays
  • NA-13-00041 - Appendix R - Emergency Switchgear Isolation Switch for Service Water The modifications were selected based upon risk significance, safety significance, and complexity. The team 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 team 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.

This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

On April 17, 2014, the team presented inspection results to Mr. Mladen and other members of the licensees staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

J. Bischof, Site Vice President
F. Mladen, Plant Manager
J. Daugherty, Director, Nuclear Station Safety & Licensing
E. Hendrixson, Director, Nuclear Site Engineering
R. Garver, Manager, Nuclear Design Engineering, Site Engineering
R. Klearman, Manager, Nuclear Oversight
P. Kemp, Supervisor, Station Licensing
P. Saksvig, Supervisor, Procurement Engineering
R. Kimble, Nuclear Engineer III, Site Engineering
M. Whalen, Technical Specialist, Licensing

NRC personnel

G. Kolcum, Senior Resident Inspector, North Anna
R. Clagg, Resident Inspector, North Anna

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened

None

Closed

None

Discussed

None

Updated

None

LIST OF DOCUMENTS REVIEWED

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