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| author name = Sandal S
| author name = Sandal S
| author affiliation = NRC/RGN-II/DRP
| author affiliation = NRC/RGN-II/DRP
| addressee name = Lippard G A
| addressee name = Lippard G
| addressee affiliation = South Carolina Electric & Gas Co
| addressee affiliation = South Carolina Electric & Gas Co
| docket = 05000395
| docket = 05000395
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 April 10, 2018  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ril 10, 2018


Mr. George III Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P.O. Box 88, Mail Code 800 Jenkinsville, SC 29065
==SUBJECT:==
 
VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - NRC TEAM INSPECTION REPORT 05000395/2018011
SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - NRC TEAM INSPECTION REPORT 05000395/2018011


==Dear Mr. Lippard:==
==Dear Mr. Lippard:==
On March 8, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at  
On March 8, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Virgil C. Summer Nuclear Station, Unit 1 facility. 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.
 
your Virgil C. Summer Nuclear Station, Unit 1 facility. 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 inspection examined activities conducted under your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commission's rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station


personnel.
The inspection examined activities conducted under your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commissions rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.


The NRC inspectors did not identify any finding or violation of more than minor significance. This letter, its enclosure, and your response (if any) 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. This letter, its enclosure, and your response (if any) 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/
Sincerely,
Shane Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects  
/RA/
 
Shane Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket No.: 50-395 License No.: NPF-12
Docket No.: 50-395 License No.: NPF-12  


===Enclosure:===
===Enclosure:===
IR 05000395/2018011  
IR 05000395/2018011
 
cc Distribution via ListServ
 
ML18100A270 OFFICE RII/DRP RII/DRP RII/DRP RII/DRP RII/DRP RII/DRP NAME GMacdonald BBishop EHilton PMcKenna RMusser SSandal DATE 4/2/2018 3/30/2018 4/2/2018 4/4/2018 4/9/2018 4/10/2018 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report
 
Docket Number: 50-395
 
License Number: NPF-12 Report Numbers: 05000395/2018011
 
Enterprise Identifier: I-2018-011-0034
 
Licensee: South Carolina Electric & Gas (SCE&G) Company
 
Facility: Virgil C. Summer Nuclear Station, Unit 1
 
Location: Jenkinsville, SC
 
Inspection Dates: March 5 - 8, 2018
 
Inspectors: P. McKenna, Senior Resident Inspector (Surry Power Station) (Team Leader) G. MacDonald, Senior Reactor Analyst B. Bishop, Project Engineer E. Hilton, Resident Inspector
 
Approved By: S. Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects


2 Enclosure  
==Inspection Report==
Docket Number: 50-395 License Number: NPF-12 Report Numbers: 05000395/2018011 Enterprise Identifier: I-2018-011-0034 Licensee: South Carolina Electric & Gas (SCE&G) Company Facility: Virgil C. Summer Nuclear Station, Unit 1 Location: Jenkinsville, SC Inspection Dates: March 5 - 8, 2018 Inspectors: P. McKenna, Senior Resident Inspector (Surry Power Station) (Team Leader)
G. MacDonald, Senior Reactor Analyst B. Bishop, Project Engineer E. Hilton, Resident Inspector Approved By: S. Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure


=SUMMARY=
=SUMMARY=
The NRC continued monitoring licensee's performance by conducting a Temporary Instruction 2515/191, "Implementation of Mitigation Strategies and Spent Fuel Pool (SFP) Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment  
The NRC continued monitoring licensees performance by conducting a Temporary Instruction 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool (SFP) Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, inspection (Agencywide Documents Access and Management System (ADAMS)
 
Accession No. ML15257A188) at Virgil C. Summer Nuclear Station, Unit 1, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
Plans," inspection (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15257A188) at Virgil C. Summer Nuclear Station, Unit 1, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.


List of Findings and Violations No findings and more than minor violations were identified.
List of Findings and Violations No findings and more than minor violations were identified.


Additional Tracking Items Type Issue number Title Report Section Status TI TI 2515/191 Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans Other Activities Closed   
Additional Tracking Items Type     Issue number     Title                                       Report     Status Section TI       TI 2515/191     Inspection of the Implementation of         Other      Closed Mitigation Strategies and Spent Fuel Pool   Activities Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans


TABLE OF CONTENTS
TABLE OF CONTENTS


=INSPECTION SCOPE=
=INSPECTION SCOPE=
..............................................................................................................


==OTHER ACTIVITIES==
==OTHER ACTIVITIES==
Line 85: Line 57:


==INSPECTION RESULTS==
==INSPECTION RESULTS==
............................................................................................................
..............................................................................................................


==EXIT MEETINGS AND DEBRIEFS==
==EXIT MEETINGS AND DEBRIEFS==
............................................................................................
............................................................................................ 6


=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=
.......................................................................................................... 7
.......................................................................................................... 7


Enclosure INSPECTION SCOPE
INSPECTION SCOPE
Inspections were conducted using the appropriate portions of Temporary Instruction (TI)
Inspections were conducted using the appropriate portions of Temporary Instruction (TI)
procedure 2515/191, "Implementation of Mitigation Strategies and Spent Fuel Pool (SFP) Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans," (ADAMS Accession No. ML15257A188)
procedure 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool (SFP)
. Documents reviewed by inspectors are listed in the documents reviewed section of this report. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess
Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose
licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Assessment Plans, (ADAMS Accession No. ML15257A188). Documents reviewed by
inspectors are listed in the documents reviewed section of this report. The inspectors reviewed
selected procedures and records, observed activities, and interviewed personnel to assess
licensee performance and compliance with Commission rules and regulations, license
conditions, site procedures, and standards.
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
TI 2515/191 - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans
TI 2515/191 - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool
Inspectors verified plans for complying with NRC Orders EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis
Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose
External Events," (Agencywide Document
Assessment Plans
s Access and Management System (ADAMS) Accession No. ML12056A045) and EA-12-051, "Order Modifying Licenses With Regard to
Inspectors verified plans for complying with NRC Orders EA-12-049, Order Modifying
Reliable Spent Fuel Pool Instrumentation," (ML12054A679) were in place and were being implemented by the licensee. Additionally, the inspection verified implementation of staffing and communications information provided in response to the March 12, 2012, request for
Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis
information letter (ML12053A340) and dose assessment information provided per COMSECY-13-0010, "Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons
External Events, (Agencywide Documents Access and Management System (ADAMS)
Learned," dated March 27, 2013 (ML12339A262).  
Accession No. ML12056A045) and EA-12-051, Order Modifying Licenses With Regard to
(1) Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate el
Reliable Spent Fuel Pool Instrumentation, (ML12054A679) were in place and were being
ements of the Diverse and Flexible Coping Strategies (FLEX) as described in the plant-specific submittals and the associated safety
implemented by the licensee. Additionally, the inspection verified implementation of staffing and
communications information provided in response to the March 12, 2012, request for
information letter (ML12053A340) and dose assessment information provided per COMSECY-
13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons
Learned, dated March 27, 2013 (ML12339A262).
    (1) Based on samples selected for review, the inspectors verified that the licensee
satisfactorily implemented appropriate elements of the Diverse and Flexible Coping
Strategies (FLEX) as described in the plant-specific submittals and the associated safety
evaluation (ML17089A617) and determined that the licensee is in compliance with NRC
evaluation (ML17089A617) and determined that the licensee is in compliance with NRC
Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis Ex
Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation
ternal Events" (ADAMS Accession No. ML12056A045). The inspectors verified the licensee satisfactorily:
Strategies for Beyond-Design-Basis External Events (ADAMS Accession No.
a) developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX strategies for postulated external events; b) integrated their FSGs into their existing plant procedures such that entry into and departure from the FSGs were clear when using existing plant procedures; c) protected FLEX equipment from site-specific hazards; d) developed and implemented adequate testing and maintenance of FLEX equipment to ensure their availability and capability e) trained their staff to ensure personnel proficiency in the mitigation of beyond-design basis events; and
ML12056A045). The inspectors verified the licensee satisfactorily:
Enclosure f) developed the means to ensure the necessary off-site FLEX equipment would be available from off-site locations. (2) Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals and the associated safety evaluation (ML17089A617) and determined that the licensee was in compliance with NRC Order NRC Order EA-12-
a) developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX
051, "Order Modifying Licenses With
strategies for postulated external events;
Regard to Reliable Spent Fuel Pool Instrumentation" (ADAMS Accession No. ML12054A679). The inspectors verified that the licensee satisfactorily: a) installed the SFP instrumentation sensors, cabling and power supplies to provide physical and electrical separation as described in the plant specific submittals and safety evaluation; b) installed the SFP instrumentation display in the location, environmental conditions and accessibility as described in the plant specific submittals; c) trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation; and d) developed and issued procedures for maintenance, testing and use of the reliable SFP instrumentation. (3) The inspectors reviewed information provided in the licensee's dose submittal and in response to the NRC's March 12, 2012, request for information letter (ML12053A340), and verified that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task Force (NTTF) Recommendation 9.3 response to a large-scale natural
b) integrated their FSGs into their existing plant procedures such that entry into and
emergency event that results in an extended loss of all alternating current (ac) power  
departure from the FSGs were clear when using existing plant procedures;
(ELAP) to all site units and impedes access to the site The inspectors verified the
c) protected FLEX equipment from site-specific hazards;
d) developed and implemented adequate testing and maintenance of FLEX equipment
to ensure their availability and capability
e) trained their staff to ensure personnel proficiency in the mitigation of
beyond-design basis events; and
 
f)   developed the means to ensure the necessary off-site FLEX equipment would be
available from off-site locations.
    (2) Based on samples selected for review, the inspectors verified that the licensee
satisfactorily implemented appropriate elements of the FLEX strategy as described in the
plant specific submittals and the associated safety evaluation (ML17089A617) and
determined that the licensee was in compliance with NRC Order NRC Order EA-12-
051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool
Instrumentation (ADAMS Accession No. ML12054A679). The inspectors verified that
the licensee satisfactorily:
a) installed the SFP instrumentation sensors, cabling and power supplies to provide
physical and electrical separation as described in the plant specific submittals and
safety evaluation;
b) installed the SFP instrumentation display in the location, environmental conditions
and accessibility as described in the plant specific submittals;
c) trained their staff to assure personnel proficiency with the maintenance, testing, and
use of the SFP instrumentation; and
d) developed and issued procedures for maintenance, testing and use of the reliable
SFP instrumentation.
    (3) The inspectors reviewed information provided in the licensees dose submittal and in
response to the NRCs March 12, 2012, request for information letter (ML12053A340),
and verified that the licensee satisfactorily implemented enhancements pertaining to
Near-Term Task Force (NTTF) Recommendation 9.3 response to a large-scale natural
emergency event that results in an extended loss of all alternating current (ac) power
        (ELAP) to all site units and impedes access to the site The inspectors verified the
following:
following:
a) the licensee satisfactorily implemented required staffing changes to support a
a) the licensee satisfactorily implemented required staffing changes to support a
ELAP scenario; b) EP communications equipment and facilities are sufficient for dealing with a ELAP scenario; and c) the licensee implemented dose assessment capabilities (including releases from SFPs) using the licensee's site-specific dose assessment software and approach. The inspectors verified that noncompliances with requirements, and standards identified during the inspection were entered into the licensee's corrective action program as appropriate.
ELAP scenario;
Enclosure INSPECTION RESULTS
b) EP communications equipment and facilities are sufficient for dealing with a
ELAP scenario; and
c) the licensee implemented dose assessment capabilities (including releases from
SFPs) using the licensees site-specific dose assessment software and approach.
The inspectors verified that noncompliances with requirements, and standards identified during
the inspection were entered into the licensee's corrective action program as appropriate.
 
INSPECTION RESULTS
No findings were identified.
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
EXIT MEETINGS AND DEBRIEFS
No proprietary information was retained by the inspectors or documented in this report.
No proprietary information was retained by the inspectors or documented in this report.
On March 8, 2018, the inspectors presented the inspection results to Mr. G. Lippard and other members of the licensee's staff.
On March 8, 2018, the inspectors presented the inspection results to Mr. G. Lippard and
other members of the licensees staff.
On April 10, 2018, the lead inspector presented the final inspection results to
On April 10, 2018, the lead inspector presented the final inspection results to
Mr.  
Mr.  
: [[contact::M. Moore]], Nuclear Licensing Manager.
: [[contact::M. Moore]], Nuclear Licensing Manager.
Enclosure
 
DOCUMENTS REVIEWED
DOCUMENTS REVIEWED
Condition Reports Initiated as a Result of the Inspection CR-18-00988, FX 4160/7.2 KV Transformer Listed in VCS-ERP-0012 as credited for FLEX CR-18-01018, FLEX SFPLI Primary Remote Transmitter Calibration Frequency Changed
Condition Reports Initiated as a Result of the Inspection
CR-18-00988, FX 4160/7.2 KV Transformer Listed in VCS-ERP-0012 as credited for FLEX
CR-18-01018, FLEX SFPLI Primary Remote Transmitter Calibration Frequency Changed
CR-18-01021, SW Pump House Not Evaluated for Heat-up when running FLEX Alternate EFW
CR-18-01021, SW Pump House Not Evaluated for Heat-up when running FLEX Alternate EFW
Suction Pumps
Suction Pumps
Procedures AOP-123.1, Decreasing Level in the Spent Fuel Pool or Refueling Cavity during Refueling,
Procedures
AOP-123.1, Decreasing Level in the Spent Fuel Pool or Refueling Cavity during Refueling,
Rev. 6
Rev. 6
AOP-123.2, Decreasing Boron Concentration in the Spent Fuel Pool or Refueling Cavity, Rev. 1
AOP-123.2, Decreasing Boron Concentration in the Spent Fuel Pool or Refueling Cavity, Rev. 1
AOP-123.3, Potential Fuel Assembly Damage While Handling Fuel, Rev. 3 AOP-123.4, Loss of Spent Fuel Pool Cooling, Rev. 5 AOP-123.5, Decreasing Level in the Spent Fuel Pool with Fuel Transfer Tube Valve Closed,
AOP-123.3, Potential Fuel Assembly Damage While Handling Fuel, Rev. 3
AOP-123.4, Loss of Spent Fuel Pool Cooling, Rev. 5
AOP-123.5, Decreasing Level in the Spent Fuel Pool with Fuel Transfer Tube Valve Closed,
Rev. 4
Rev. 4
AOP-304.4 ARG-4 Loss of ESF AC Power While on RHR Cooling, Rev. 5
AOP-304.4 ARG-4 Loss of ESF AC Power While on RHR Cooling, Rev. 5
EOP-6.0 ECA-0.0 Loss of all ESF AC Power, Rev. 35 ERMP-100.032, FLEX 5500 Watt Diesel Generator Preventative Maintenance, Rev. 0 ERMP-100.021, FLEX Transformer Preventative Maintenance, Rev.0
EOP-6.0 ECA-0.0 Loss of all ESF AC Power, Rev. 35
ERMP-100.032, FLEX 5500 Watt Diesel Generator Preventative Maintenance, Rev. 0
ERMP-100.021, FLEX Transformer Preventative Maintenance, Rev.0
ERMP-100.016, FLEX RCS Makeup Pump Preventative Maintenance, Rev. 1 Change A
ERMP-100.016, FLEX RCS Makeup Pump Preventative Maintenance, Rev. 1 Change A
ERMP-100.015, FLEX SG Feed Pump Preventative Maintenance, Rev. 0
ERMP-100.015, FLEX SG Feed Pump Preventative Maintenance, Rev. 0
ERMP-100.014, FLEX Booster/Transfer Pump Preventative Maintenance, Rev. 0
ERMP-100.014, FLEX Booster/Transfer Pump Preventative Maintenance, Rev. 0
ERMP-100.012, FLEX Heat Sink Lift and Main Pumps Preventative Maintenance, Rev. 0 ERMP-100.011, FLEX 1MW Combustion Turbine Generator Preventative Maintenance, Rev. 1
ERMP-100.012, FLEX Heat Sink Lift and Main Pumps Preventative Maintenance, Rev. 0
ERMP-100.011, FLEX 1MW Combustion Turbine Generator Preventative Maintenance, Rev. 1
Change A
Change A
ERTP-100.005, FLEX Hose Test Procedure, Rev. 1
ERTP-100.005, FLEX Hose Test Procedure, Rev. 1
Line 154: Line 182:
FSP-6.0, Alternate CST Makeup, Rev. 1
FSP-6.0, Alternate CST Makeup, Rev. 1
FSP-9.0, Low Decay Heat Temperature Control, Rev. 1
FSP-9.0, Low Decay Heat Temperature Control, Rev. 1
FSP-11.0, Alternate Spent Fuel Pool Makeup and Cooling, Rev. 1 FSP14.0 Shutdown RCS Makeup, Rev. 1
FSP-11.0, Alternate Spent Fuel Pool Makeup and Cooling, Rev. 1
FSP14.0 Shutdown RCS Makeup, Rev. 1
FSP-20.1, Vital Area Emergency Ventilation, Rev.1
FSP-20.1, Vital Area Emergency Ventilation, Rev.1
FSP-20.3.2, Staging the FX SG Feed Pump Using the West Strategy, Rev. 1
FSP-20.3.2, Staging the FX SG Feed Pump Using the West Strategy, Rev. 1
FSP-20.3.1, Staging the FX SG Feed Pump Using the East Strategy, Rev. 1 FSP-20.4.1, Staging the FX UHS Pumps, Rev. 1 FSP-20.5.1, Staging the FX RCS MU Pump, Rev.1
FSP-20.3.1, Staging the FX SG Feed Pump Using the East Strategy, Rev. 1
FSP-20.4.1, Staging the FX UHS Pumps, Rev. 1
FSP-20.5.1, Staging the FX RCS MU Pump, Rev.1
FSP-20.6.1, Staging the FX BSTR XFER Pump, Rev. 1
FSP-20.6.1, Staging the FX BSTR XFER Pump, Rev. 1
FSP-20.7, FLEX Combustion Turbine Generator Operation, Rev. 0
FSP-20.7, FLEX Combustion Turbine Generator Operation, Rev. 0
ICP-390.012, Spent Fuel Level ILT09780 and ILT09781 Calibration, Rev. 1, Change A
ICP-390.012, Spent Fuel Level ILT09780 and ILT09781 Calibration, Rev. 1, Change A
NL-121, Regulatory Commitment Management, Rev. 9 OAP 100.6, Control Room Conduct and Control of Shift Activities, Rev. 4 OAP-106.1, AB Upper Tech SPEC Rounds Attachment IV, Rev. 17f
NL-121, Regulatory Commitment Management, Rev. 9
OAP 100.6, Control Room Conduct and Control of Shift Activities, Rev. 4
OAP-106.1, AB Upper Tech SPEC Rounds Attachment IV, Rev. 17f
OAP-109.1 Guidelines for Severe Weather, Rev. 4
OAP-109.1 Guidelines for Severe Weather, Rev. 4
SAP-107, Applicability Determination (AD), Attachment 1, Rev. 7
SAP-107, Applicability Determination (AD), Attachment 1, Rev. 7
Enclosure SOP-211, Emergency Feedwater, Rev. 14 VCS-EPP-0032, Alternate Emergency Response Facility, Rev. 0
 
VCS-ERP-0012, BDB Equipment Availability Monitoring, Rev. 1 VCS-ERP-0050, Emergency Response Procedure, ERU Equipment Inventory, Rev. 3 VCS-ERP-0111, ERU BDB Debris Clearing, Rev. 0
SOP-211, Emergency Feedwater, Rev. 14
VCS-EPP-0032, Alternate Emergency Response Facility, Rev. 0
VCS-ERP-0012, BDB Equipment Availability Monitoring, Rev. 1
VCS-ERP-0050, Emergency Response Procedure, ERU Equipment Inventory, Rev. 3
VCS-ERP-0111, ERU BDB Debris Clearing, Rev. 0
VCS-ERP-0112, BDB Equipment Availability Monitoring, Rev. 1
VCS-ERP-0112, BDB Equipment Availability Monitoring, Rev. 1
VCS-ERP-0113, ERU BDB Refueling Operations, Rev. 0
VCS-ERP-0113, ERU BDB Refueling Operations, Rev. 0
VCS-ERP-0114, ERU BDB Lighting and Communications Support, Rev. 0
VCS-ERP-0114, ERU BDB Lighting and Communications Support, Rev. 0
VCS-ERP-0115, ERU Communications Tower Deployment, Rev. 0 VCS-SAP-0130, BDB Flex Program, Rev. 0
VCS-ERP-0115, ERU Communications Tower Deployment, Rev. 0
Drawings C-317-322, Sh. 15, Vega Waveguide Isometric Southwest, Rev. 0
VCS-SAP-0130, BDB Flex Program, Rev. 0
C-317-322, Sh. 14, Vega Waveguide Isometric Northwest, Rev. 0 E-215-080, Conduit Layout Aux Building North above Elev. 463', Rev. 48
Drawings
E-215-161, Conduit Layout Fuel Handling Building above Elev. 435', Rev. 27
C-317-322, Sh. 15, Vega Waveguide Isometric Southwest, Rev. 0
E-215-162, Conduit Layout Fuel Handling Building above Elev. 453', Rev. 29
C-317-322, Sh. 14, Vega Waveguide Isometric Northwest, Rev. 0
E-811-014, Instrument Location Layout Aux Building Open Floor above Elev. 463', Rev. 21
E-215-080, Conduit Layout Aux Building North above Elev. 463, Rev. 48
E-811-033, Instrument Location Layout Fuel Handling Area Mezzanine Floor, Rev. 10 E-811-034, Instrument Location Layout Fuel Handling Area Operating Floor, Rev. 13 Simplified Drawings Depicting FLEX Strategies and Connection Capabilities:
E-215-161, Conduit Layout Fuel Handling Building above Elev. 435, Rev. 27
E-215-162, Conduit Layout Fuel Handling Building above Elev. 453, Rev. 29
E-811-014, Instrument Location Layout Aux Building Open Floor above Elev. 463, Rev. 21
E-811-033, Instrument Location Layout Fuel Handling Area Mezzanine Floor, Rev. 10
E-811-034, Instrument Location Layout Fuel Handling Area Operating Floor, Rev. 13
Simplified Drawings Depicting FLEX Strategies and Connection Capabilities:
Restoration of DC power
Restoration of DC power
Steam Generator Feed FLEX Lineup
Steam Generator Feed FLEX Lineup
Line 185: Line 227:
VC Summer Unit 1 FLEX Strategy Simplified Mechanical Diagram
VC Summer Unit 1 FLEX Strategy Simplified Mechanical Diagram
VC Summer Unit 1 FLEX Strategy Simplified Electrical Diagram
VC Summer Unit 1 FLEX Strategy Simplified Electrical Diagram
Work Orders 1613554-001, Spent Fuel Pool Level ILT09780 Check/Calibration, 1/31/17 1605636-001, Spent Fuel Pool Level ILT09780 Check/Calibration, 8/10/16 1613555-001, Spent Fuel Pool Level ILT09781 Check/Calibration, 1/31/17 1605637-001, Spent Fuel Pool Level ILT09781 Check/Calibration, 8/11/16
Work Orders
1613554-001, Spent Fuel Pool Level ILT09780 Check/Calibration, 1/31/17
1605636-001, Spent Fuel Pool Level ILT09780 Check/Calibration, 8/10/16
1613555-001, Spent Fuel Pool Level ILT09781 Check/Calibration, 1/31/17
1605637-001, Spent Fuel Pool Level ILT09781 Check/Calibration, 8/11/16
1615160-001, FLEX RCS Makeup Pump Annual Preventative Maintenance, 05/04/17
1615160-001, FLEX RCS Makeup Pump Annual Preventative Maintenance, 05/04/17
1703946-001, Combustion Turbine Generator Annual Preventative Maintenance, 10/02/17
1703946-001, Combustion Turbine Generator Annual Preventative Maintenance, 10/02/17
1705485-001, FLEX Heat Sink Lift and Main Pump Annual Preventative Maintenance, 01/15/18 1706212-001, FLEX Booster/Transfer Pump Annual Preventative Maintenance, 11/25/17 1706461-001, FLEX SG Feed Pump Annual Preventative Maintenance, 01/30/18  
1705485-001, FLEX Heat Sink Lift and Main Pump Annual Preventative Maintenance, 01/15/18
 
1706212-001, FLEX Booster/Transfer Pump Annual Preventative Maintenance, 11/25/17
Design Changes DC 00080-002 Site Hazard Design Parameters for Flex, Rev. 1
1706461-001, FLEX SG Feed Pump Annual Preventative Maintenance, 01/30/18
ECR 50890 External Flooding Door Modifications, Excerpts from 60% Design Package ECR 51001, Flex Spent Fuel Pool Level Indication, Rev. 0 ECR 51001 Supporting Documentation Part 1, Rev. 0
Design Changes
DC 00080-002 Site Hazard Design Parameters for Flex, Rev. 1
ECR 50890 External Flooding Door Modifications, Excerpts from 60% Design Package
ECR 51001, Flex Spent Fuel Pool Level Indication, Rev. 0
ECR 51001 Supporting Documentation Part 1, Rev. 0
ECR 51001 Supporting Documentation Part 2, Rev. 0
ECR 51001 Supporting Documentation Part 2, Rev. 0
ECR 51003B, FLEX EFW Alternate Suction Source, Rev. 2
ECR 51003B, FLEX EFW Alternate Suction Source, Rev. 2
ECR 51003K, FLEX EFW Alternate Suction Source, Rev. 0
ECR 51003K, FLEX EFW Alternate Suction Source, Rev. 0
Enclosure Minor Change Form ECR51001B EC02 Minor Change Form ECR51001B EC03
 
Condition Reports CR-12-01098 CR-12-01102 CR-13-05162 CR-14-01307 CR-14-03196 CR-15-03191 CR-15-03206 CR-15-05662 CR-15-05934 CR-15-06611 CR-15-06858 CR-16-00149
Minor Change Form ECR51001B EC02
CR-16-02624 CR-16-04082 CR-16-04089 CR-16-04206 CR-16-05260 CR-16-05568
Minor Change Form ECR51001B EC03
CR-16-05797 CR-16-05957 CR-17-00452 CR-17-00453 CR-17-01273 CR-17-01479
Condition Reports
CR-17-01584 CR-17-02287 CR-17-02632 CR-17-04011 CR-17-04379 CR-17-05620 CR-18-00056 CR-18-00546 CR-18-00551 CR-18-00642
CR-12-01098 CR-12-01102 CR-13-05162         CR-14-01307   CR-14-03196 CR-15-03191
Training Documents and Records QA Periodic Reading Flex Response Strategies, ERU Personnel, 9/21/15
CR-15-03206 CR-15-05662 CR-15-05934         CR-15-06611   CR-15-06858 CR-16-00149
ERU FLEX Training Attendance Records, Test Unit FLEX 2 Year Requalification, Q-ERU-BDB-   02, 03, 04, 13 conducted 9/13/17, 9/19/17, 9/20/17, and 9/12/17 Course FLEX-1.0, Introduction to FLEX Fundamentals, training attendance/completion records
CR-16-02624 CR-16-04082 CR-16-04089         CR-16-04206   CR-16-05260 CR-16-05568
CR-16-05797 CR-16-05957 CR-17-00452         CR-17-00453   CR-17-01273 CR-17-01479
CR-17-01584 CR-17-02287 CR-17-02632         CR-17-04011   CR-17-04379 CR-17-05620
CR-18-00056 CR-18-00546 CR-18-00551         CR-18-00642
Training Documents and Records
QA Periodic Reading Flex Response Strategies, ERU Personnel, 9/21/15
ERU FLEX Training Attendance Records, Test Unit FLEX 2 Year Requalification, Q-ERU-BDB-
2, 03, 04, 13 conducted 9/13/17, 9/19/17, 9/20/17, and 9/12/17
Course FLEX-1.0, Introduction to FLEX Fundamentals, training attendance/completion records
for ERU personnel supervisors and ERO leaders
for ERU personnel supervisors and ERO leaders
Training attendance records for Operations/Emergency Response Unit personnel for IC-FLEX-
Training attendance records for Operations/Emergency Response Unit personnel for IC-FLEX-
SFPLI Operations Training, FLEX 1.0, Introduction to FLEX Fundamentals Lesson Plan, Rev. 0 Operations Training, FLEX 2.0, FLEX Implementing Procedures Lesson Plan, Rev. 0
SFPLI
Operations Training, FLEX 1.0, Introduction to FLEX Fundamentals Lesson Plan, Rev. 0
Operations Training, FLEX 2.0, FLEX Implementing Procedures Lesson Plan, Rev. 0
Operations Training, FLEX 3.0, FLEX Equipment Procedures Lesson Plan, Rev. 0
Operations Training, FLEX 3.0, FLEX Equipment Procedures Lesson Plan, Rev. 0
Operations FLEX Training Records, Flex Fundamentals, 9/14/15
Operations FLEX Training Records, Flex Fundamentals, 9/14/15
Operations FLEX Training Records, FLEX for Operators, 6/29/16
Operations FLEX Training Records, FLEX for Operators, 6/29/16
Mechanical Maintenance Training Records, Introduction to FLEX Fundamentals, 8/5/15 and
Mechanical Maintenance Training Records, Introduction to FLEX Fundamentals, 8/5/15 and
8/11/15 Electrical Maintenance Training Records, Electrical Maintenance-FLEX, 6/12/17
8/11/15
Electrical Maintenance Training Records, Electrical Maintenance-FLEX, 6/12/17
Q-AP-EM-337-Flex, Maintain Disconnect /FLEX Links Disconnect Switch Maintenance, 5/17/17
Q-AP-EM-337-Flex, Maintain Disconnect /FLEX Links Disconnect Switch Maintenance, 5/17/17
FLEX-SFPLI-V, Spent Fuel Pool Level Indicator FLEX, Training attendance, 5/27/15
FLEX-SFPLI-V, Spent Fuel Pool Level Indicator FLEX, Training attendance, 5/27/15
Other AREVA Customer Service Bulletin 15-04, Spent Fuel Pool Level Instrument (SFPLI) Sensor
Other
AREVA Customer Service Bulletin 15-04, Spent Fuel Pool Level Instrument (SFPLI) Sensor
Mounting Outdoors
Mounting Outdoors
AREVA Document No. 38-9238014-001, SAFER Response Plan for Virgil C. Summer Nuclear
AREVA Document No. 38-9238014-001, SAFER Response Plan for Virgil C. Summer Nuclear
Station, Rev.1
Station, Rev.1
Beyond Design Basis Program Manual Virgil  
Beyond Design Basis Program Manual Virgil  
: [[contact::C. Summer Nuclear Station]], Rev. 0 Calculation DC00080-002, Site Hazards Design Parameters For FLEX, Rev. 1 IMS-94B-1752, Through Air Radar Spent Fuel Pool Lev
: [[contact::C. Summer Nuclear Station]], Rev. 0
el Instrument (SFPLI) Instruction Manual   for VC Summer, Doc. No. 01-9225772-002
Calculation DC00080-002, Site Hazards Design Parameters For FLEX, Rev. 1
IMS-94B-1752, Through Air Radar Spent Fuel Pool Level Instrument (SFPLI) Instruction Manual
for VC Summer, Doc. No. 01-9225772-002
JG40733, FLEX Tornado Study - CR-14-00911 Action 6, 04/29/15
JG40733, FLEX Tornado Study - CR-14-00911 Action 6, 04/29/15
NEI 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Rev. 2 NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and   Communications Capabilities
NEI 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Rev. 2
NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and
Communications Capabilities
NEI 10-05, Assessment of On-Shift Emergency Response Organization Staffing and
NEI 10-05, Assessment of On-Shift Emergency Response Organization Staffing and
Capabilities
Capabilities
PM Revision, RPM Revision 1801928, ICP0390.012 Frequency Change from 6 Months to 18
PM Revision, RPM Revision 1801928, ICP0390.012 Frequency Change from 6 Months to 18
Months ILT09780 and ILT09781 Calibration per ICP-390.012 Power Point Presentation slides for FLEX Re
Months ILT09780 and ILT09781 Calibration per ICP-390.012
sponse and Strategies NRC TI-191 Inspection RC-13-0119, South Carolina Electric and Gas Company's Response to Requests for Additional
Power Point Presentation slides for FLEX Response and Strategies NRC TI-191 Inspection
RC-13-0119, South Carolina Electric and Gas Companys Response to Requests for Additional
Information - Overall Integrated Plan in Response to Commission Order Modifying License
 
Requirements for Reliable Spent Fuel Pool Level Instrumentation (Order Ea-12-051)
RC-14-0173, South Carolina Electric and Gas Companys Response to Requests for Additional
Information - Overall Integrated Plan in Response to Commission Order Modifying License
Information - Overall Integrated Plan in Response to Commission Order Modifying License
Enclosure  Requirements for Reliable Spent Fuel Pool Level Instrumentation (Order Ea-12-051) RC-14-0173, South Carolina Electric and Gas Company's Response to Requests for Additional
Requirements For Reliable Spent Fuel Pool Level Instrumentation (Order Ea-12-051)
Information - Overall Integrated Plan in Response to Commission Order Modifying License    Requirements For Reliable Spent Fuel Pool Level Instrumentation (Order Ea-12-051) RC-15-0093, Response to Request for Additional
RC-15-0093, Response to Request for Additional Information Regarding Phase 2 Staffing
Information Regarding Phase 2 Staffing   submittals Associated with Near-Term Task Force Recommendation 9.3 Related to the
submittals Associated with Near-Term Task Force Recommendation 9.3 Related to the
Fukushima Dai-ichi Nuclear Power Plant Accident
Fukushima Dai-ichi Nuclear Power Plant Accident
RC-16-0001, Report of Full Compliance with March 12, 2012 Commission Order Modifying
RC-16-0001, Report of Full Compliance with March 12, 2012 Commission Order Modifying
Licenses with Regard to Reliable Spent Fuel Pool Level Instrumentation (Order EA-12-051)   and Responses to Requests for Additional Information RC-16-0143, Report of Full Compliance and Final Integrated Plan in Response to March 12,
Licenses with Regard to Reliable Spent Fuel Pool Level Instrumentation (Order EA-12-051)
and Responses to Requests for Additional Information
RC-16-0143, Report of Full Compliance and Final Integrated Plan in Response to March 12,
2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation
2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation
Strategies for Beyond-Design-Bases External Events (Order EA-12-049) for Virgil C. Summer
Strategies for Beyond-Design-Bases External Events (Order EA-12-049) for Virgil C. Summer
Nuclear Station Unit 1 Regulatory Commitment Evaluation Worksheet for SFP Level Indication and Battery   Replacement, 03/28/18
Nuclear Station Unit 1
Regulatory Commitment Evaluation Worksheet for SFP Level Indication and Battery
Replacement, 03/28/18
Regulatory Commitment Change Request for SFP Level Indication and Battery Replacement,
Regulatory Commitment Change Request for SFP Level Indication and Battery Replacement,
03/28/18
03/28/18
SA16-EP-03, FLEX Program - NRC Inspection Manual Self-Assessment, Rev. 1 TR02060-001, Verification Walkdown Report for VCSNS Plant Flood Protective Features,
SA16-EP-03, FLEX Program - NRC Inspection Manual Self-Assessment, Rev. 1
TR02060-001, Verification Walkdown Report for VCSNS Plant Flood Protective Features,
Rev. 0
Rev. 0
TR02060-003, Flood Hazard Reevaluation Report for VCSNS, Rev. 1
TR02060-003, Flood Hazard Reevaluation Report for VCSNS, Rev. 1
TR02060-005, External Flooding Focused Evaluation Summary for VCSNS, Rev. 0
TR02060-005, External Flooding Focused Evaluation Summary for VCSNS, Rev. 0
TR00080-001, Engineering Services Technical Report, Guidance for Development of
TR00080-001, Engineering Services Technical Report, Guidance for Development of
Specifications for Flex Equipment, Rev. 3 TR00080-003, FLEX Equipment Ventilation and Habitability Assessment, Rev. 2 TR00080-006, FLEX Timeline Constraint Basis, Rev. 1
Specifications for Flex Equipment, Rev. 3
TR00080-003, FLEX Equipment Ventilation and Habitability Assessment, Rev. 2
TR00080-006, FLEX Timeline Constraint Basis, Rev. 1
TR00080-007 VCS Unit 1 Flex Validation Document, Rev. 1
TR00080-007 VCS Unit 1 Flex Validation Document, Rev. 1
V-100, Vantran Industries Operation and Maintenance Manual for Padmount and Substation
V-100, Vantran Industries Operation and Maintenance Manual for Padmount and Substation
Transformers (Single and Three Phase), 02/12 VC Summer Unit 1 NEI-12-01 Report, Rev. 1, NEI 12-01 Phase 2 Extended Loss of AC Power   
Transformers (Single and Three Phase), 02/12
  (ELAP) ERO Staffing Analysis Report
VC Summer Unit 1 NEI-12-01 Report, Rev. 1, NEI 12-01 Phase 2 Extended Loss of AC Power
  (ELAP) ERO Staffing Analysis Report
VCSNS Warehouse Storage Database Information for FLEX SFPLI batteries
VCSNS Warehouse Storage Database Information for FLEX SFPLI batteries
Enclosure
}}
}}

Latest revision as of 16:57, 2 November 2019

NRC Team Inspection Report 05000395/2018011
ML18100A270
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 04/10/2018
From: Shane Sandal
Division Reactor Projects II
To: Lippard G
South Carolina Electric & Gas Co
References
IR 2018011
Download: ML18100A270 (13)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ril 10, 2018

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - NRC TEAM INSPECTION REPORT 05000395/2018011

Dear Mr. Lippard:

On March 8, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Virgil C. Summer Nuclear Station, Unit 1 facility. 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 inspection examined activities conducted under your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commissions rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.

The NRC inspectors did not identify any finding or violation of more than minor significance. This letter, its enclosure, and your response (if any) 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/

Shane Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket No.: 50-395 License No.: NPF-12

Enclosure:

IR 05000395/2018011

Inspection Report

Docket Number: 50-395 License Number: NPF-12 Report Numbers: 05000395/2018011 Enterprise Identifier: I-2018-011-0034 Licensee: South Carolina Electric & Gas (SCE&G) Company Facility: Virgil C. Summer Nuclear Station, Unit 1 Location: Jenkinsville, SC Inspection Dates: March 5 - 8, 2018 Inspectors: P. McKenna, Senior Resident Inspector (Surry Power Station) (Team Leader)

G. MacDonald, Senior Reactor Analyst B. Bishop, Project Engineer E. Hilton, Resident Inspector Approved By: S. Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure

SUMMARY

The NRC continued monitoring licensees performance by conducting a Temporary Instruction 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool (SFP) Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, inspection (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML15257A188) at Virgil C. Summer Nuclear Station, Unit 1, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations No findings and more than minor violations were identified.

Additional Tracking Items Type Issue number Title Report Status Section TI TI 2515/191 Inspection of the Implementation of Other Closed Mitigation Strategies and Spent Fuel Pool Activities Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans

TABLE OF CONTENTS

INSPECTION SCOPE

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

INSPECTION RESULTS

..............................................................................................................

EXIT MEETINGS AND DEBRIEFS

............................................................................................ 6

DOCUMENTS REVIEWED

.......................................................................................................... 7

INSPECTION SCOPE

Inspections were conducted using the appropriate portions of Temporary Instruction (TI)

procedure 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool (SFP)

Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose

Assessment Plans, (ADAMS Accession No. ML15257A188). Documents reviewed by

inspectors are listed in the documents reviewed section of this report. The inspectors reviewed

selected procedures and records, observed activities, and interviewed personnel to assess

licensee performance and compliance with Commission rules and regulations, license

conditions, site procedures, and standards.

OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

TI 2515/191 - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool

Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose

Assessment Plans

Inspectors verified plans for complying with NRC Orders EA-12-049, Order Modifying

Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis

External Events, (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML12056A045) and EA-12-051, Order Modifying Licenses With Regard to

Reliable Spent Fuel Pool Instrumentation, (ML12054A679) were in place and were being

implemented by the licensee. Additionally, the inspection verified implementation of staffing and

communications information provided in response to the March 12, 2012, request for

information letter (ML12053A340) and dose assessment information provided per COMSECY-

13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons

Learned, dated March 27, 2013 (ML12339A262).

(1) Based on samples selected for review, the inspectors verified that the licensee

satisfactorily implemented appropriate elements of the Diverse and Flexible Coping

Strategies (FLEX) as described in the plant-specific submittals and the associated safety

evaluation (ML17089A617) and determined that the licensee is in compliance with NRC

Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation

Strategies for Beyond-Design-Basis External Events (ADAMS Accession No.

ML12056A045). The inspectors verified the licensee satisfactorily:

a) developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX

strategies for postulated external events;

b) integrated their FSGs into their existing plant procedures such that entry into and

departure from the FSGs were clear when using existing plant procedures;

c) protected FLEX equipment from site-specific hazards;

d) developed and implemented adequate testing and maintenance of FLEX equipment

to ensure their availability and capability

e) trained their staff to ensure personnel proficiency in the mitigation of

beyond-design basis events; and

f) developed the means to ensure the necessary off-site FLEX equipment would be

available from off-site locations.

(2) Based on samples selected for review, the inspectors verified that the licensee

satisfactorily implemented appropriate elements of the FLEX strategy as described in the

plant specific submittals and the associated safety evaluation (ML17089A617) and

determined that the licensee was in compliance with NRC Order NRC Order EA-12-

051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool

Instrumentation (ADAMS Accession No. ML12054A679). The inspectors verified that

the licensee satisfactorily:

a) installed the SFP instrumentation sensors, cabling and power supplies to provide

physical and electrical separation as described in the plant specific submittals and

safety evaluation;

b) installed the SFP instrumentation display in the location, environmental conditions

and accessibility as described in the plant specific submittals;

c) trained their staff to assure personnel proficiency with the maintenance, testing, and

use of the SFP instrumentation; and

d) developed and issued procedures for maintenance, testing and use of the reliable

SFP instrumentation.

(3) The inspectors reviewed information provided in the licensees dose submittal and in

response to the NRCs March 12, 2012, request for information letter (ML12053A340),

and verified that the licensee satisfactorily implemented enhancements pertaining to

Near-Term Task Force (NTTF) Recommendation 9.3 response to a large-scale natural

emergency event that results in an extended loss of all alternating current (ac) power

(ELAP) to all site units and impedes access to the site The inspectors verified the

following:

a) the licensee satisfactorily implemented required staffing changes to support a

ELAP scenario;

b) EP communications equipment and facilities are sufficient for dealing with a

ELAP scenario; and

c) the licensee implemented dose assessment capabilities (including releases from

SFPs) using the licensees site-specific dose assessment software and approach.

The inspectors verified that noncompliances with requirements, and standards identified during

the inspection were entered into the licensee's corrective action program as appropriate.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

No proprietary information was retained by the inspectors or documented in this report.

On March 8, 2018, the inspectors presented the inspection results to Mr. G. Lippard and

other members of the licensees staff.

On April 10, 2018, the lead inspector presented the final inspection results to

Mr.

M. Moore, Nuclear Licensing Manager.

DOCUMENTS REVIEWED

Condition Reports Initiated as a Result of the Inspection

CR-18-00988, FX 4160/7.2 KV Transformer Listed in VCS-ERP-0012 as credited for FLEX

CR-18-01018, FLEX SFPLI Primary Remote Transmitter Calibration Frequency Changed

CR-18-01021, SW Pump House Not Evaluated for Heat-up when running FLEX Alternate EFW

Suction Pumps

Procedures

AOP-123.1, Decreasing Level in the Spent Fuel Pool or Refueling Cavity during Refueling,

Rev. 6

AOP-123.2, Decreasing Boron Concentration in the Spent Fuel Pool or Refueling Cavity, Rev. 1

AOP-123.3, Potential Fuel Assembly Damage While Handling Fuel, Rev. 3

AOP-123.4, Loss of Spent Fuel Pool Cooling, Rev. 5

AOP-123.5, Decreasing Level in the Spent Fuel Pool with Fuel Transfer Tube Valve Closed,

Rev. 4

AOP-304.4 ARG-4 Loss of ESF AC Power While on RHR Cooling, Rev. 5

EOP-6.0 ECA-0.0 Loss of all ESF AC Power, Rev. 35

ERMP-100.032, FLEX 5500 Watt Diesel Generator Preventative Maintenance, Rev. 0

ERMP-100.021, FLEX Transformer Preventative Maintenance, Rev.0

ERMP-100.016, FLEX RCS Makeup Pump Preventative Maintenance, Rev. 1 Change A

ERMP-100.015, FLEX SG Feed Pump Preventative Maintenance, Rev. 0

ERMP-100.014, FLEX Booster/Transfer Pump Preventative Maintenance, Rev. 0

ERMP-100.012, FLEX Heat Sink Lift and Main Pumps Preventative Maintenance, Rev. 0

ERMP-100.011, FLEX 1MW Combustion Turbine Generator Preventative Maintenance, Rev. 1

Change A

ERTP-100.005, FLEX Hose Test Procedure, Rev. 1

ERTP-100.002, FLEX Combustion Turbine Generator Test Procedure, Rev. 0

ERTP-100.001, FLEX Pump Test Procedure, Rev. 0

EPP-005, Offsite Calculation, Rev. 21

FSP-2.0, Alternate EFW Suction Source, Rev. 0

FSP-4.0 ELAP DC Bus Load Shed Management, Rev. 0

FSP-5.0, Initial Assessment and Flex Equipment Staging, Rev. 2

FSP-6.0, Alternate CST Makeup, Rev. 1

FSP-9.0, Low Decay Heat Temperature Control, Rev. 1

FSP-11.0, Alternate Spent Fuel Pool Makeup and Cooling, Rev. 1

FSP14.0 Shutdown RCS Makeup, Rev. 1

FSP-20.1, Vital Area Emergency Ventilation, Rev.1

FSP-20.3.2, Staging the FX SG Feed Pump Using the West Strategy, Rev. 1

FSP-20.3.1, Staging the FX SG Feed Pump Using the East Strategy, Rev. 1

FSP-20.4.1, Staging the FX UHS Pumps, Rev. 1

FSP-20.5.1, Staging the FX RCS MU Pump, Rev.1

FSP-20.6.1, Staging the FX BSTR XFER Pump, Rev. 1

FSP-20.7, FLEX Combustion Turbine Generator Operation, Rev. 0

ICP-390.012, Spent Fuel Level ILT09780 and ILT09781 Calibration, Rev. 1, Change A

NL-121, Regulatory Commitment Management, Rev. 9

OAP 100.6, Control Room Conduct and Control of Shift Activities, Rev. 4

OAP-106.1, AB Upper Tech SPEC Rounds Attachment IV, Rev. 17f

OAP-109.1 Guidelines for Severe Weather, Rev. 4

SAP-107, Applicability Determination (AD), Attachment 1, Rev. 7

SOP-211, Emergency Feedwater, Rev. 14

VCS-EPP-0032, Alternate Emergency Response Facility, Rev. 0

VCS-ERP-0012, BDB Equipment Availability Monitoring, Rev. 1

VCS-ERP-0050, Emergency Response Procedure, ERU Equipment Inventory, Rev. 3

VCS-ERP-0111, ERU BDB Debris Clearing, Rev. 0

VCS-ERP-0112, BDB Equipment Availability Monitoring, Rev. 1

VCS-ERP-0113, ERU BDB Refueling Operations, Rev. 0

VCS-ERP-0114, ERU BDB Lighting and Communications Support, Rev. 0

VCS-ERP-0115, ERU Communications Tower Deployment, Rev. 0

VCS-SAP-0130, BDB Flex Program, Rev. 0

Drawings

C-317-322, Sh. 15, Vega Waveguide Isometric Southwest, Rev. 0

C-317-322, Sh. 14, Vega Waveguide Isometric Northwest, Rev. 0

E-215-080, Conduit Layout Aux Building North above Elev. 463, Rev. 48

E-215-161, Conduit Layout Fuel Handling Building above Elev. 435, Rev. 27

E-215-162, Conduit Layout Fuel Handling Building above Elev. 453, Rev. 29

E-811-014, Instrument Location Layout Aux Building Open Floor above Elev. 463, Rev. 21

E-811-033, Instrument Location Layout Fuel Handling Area Mezzanine Floor, Rev. 10

E-811-034, Instrument Location Layout Fuel Handling Area Operating Floor, Rev. 13

Simplified Drawings Depicting FLEX Strategies and Connection Capabilities:

Restoration of DC power

Steam Generator Feed FLEX Lineup

Condensate Storage Tank Makeup FLEX Lineup

RCS Boration and Inventory Control

Containment Integrity

Spent Fuel Pool Makeup/Cooling

Alternate EFW Suction FLEX Lineup

VC Summer Unit 1 FLEX Strategy Simplified Mechanical Diagram

VC Summer Unit 1 FLEX Strategy Simplified Electrical Diagram

Work Orders

1613554-001, Spent Fuel Pool Level ILT09780 Check/Calibration, 1/31/17

1605636-001, Spent Fuel Pool Level ILT09780 Check/Calibration, 8/10/16

1613555-001, Spent Fuel Pool Level ILT09781 Check/Calibration, 1/31/17

1605637-001, Spent Fuel Pool Level ILT09781 Check/Calibration, 8/11/16

1615160-001, FLEX RCS Makeup Pump Annual Preventative Maintenance, 05/04/17

1703946-001, Combustion Turbine Generator Annual Preventative Maintenance, 10/02/17

1705485-001, FLEX Heat Sink Lift and Main Pump Annual Preventative Maintenance, 01/15/18

1706212-001, FLEX Booster/Transfer Pump Annual Preventative Maintenance, 11/25/17

1706461-001, FLEX SG Feed Pump Annual Preventative Maintenance, 01/30/18

Design Changes

DC 00080-002 Site Hazard Design Parameters for Flex, Rev. 1

ECR 50890 External Flooding Door Modifications, Excerpts from 60% Design Package

ECR 51001, Flex Spent Fuel Pool Level Indication, Rev. 0

ECR 51001 Supporting Documentation Part 1, Rev. 0

ECR 51001 Supporting Documentation Part 2, Rev. 0

ECR 51003B, FLEX EFW Alternate Suction Source, Rev. 2

ECR 51003K, FLEX EFW Alternate Suction Source, Rev. 0

Minor Change Form ECR51001B EC02

Minor Change Form ECR51001B EC03

Condition Reports

CR-12-01098 CR-12-01102 CR-13-05162 CR-14-01307 CR-14-03196 CR-15-03191

CR-15-03206 CR-15-05662 CR-15-05934 CR-15-06611 CR-15-06858 CR-16-00149

CR-16-02624 CR-16-04082 CR-16-04089 CR-16-04206 CR-16-05260 CR-16-05568

CR-16-05797 CR-16-05957 CR-17-00452 CR-17-00453 CR-17-01273 CR-17-01479

CR-17-01584 CR-17-02287 CR-17-02632 CR-17-04011 CR-17-04379 CR-17-05620

CR-18-00056 CR-18-00546 CR-18-00551 CR-18-00642

Training Documents and Records

QA Periodic Reading Flex Response Strategies, ERU Personnel, 9/21/15

ERU FLEX Training Attendance Records, Test Unit FLEX 2 Year Requalification, Q-ERU-BDB-

2, 03, 04, 13 conducted 9/13/17, 9/19/17, 9/20/17, and 9/12/17

Course FLEX-1.0, Introduction to FLEX Fundamentals, training attendance/completion records

for ERU personnel supervisors and ERO leaders

Training attendance records for Operations/Emergency Response Unit personnel for IC-FLEX-

SFPLI

Operations Training, FLEX 1.0, Introduction to FLEX Fundamentals Lesson Plan, Rev. 0

Operations Training, FLEX 2.0, FLEX Implementing Procedures Lesson Plan, Rev. 0

Operations Training, FLEX 3.0, FLEX Equipment Procedures Lesson Plan, Rev. 0

Operations FLEX Training Records, Flex Fundamentals, 9/14/15

Operations FLEX Training Records, FLEX for Operators, 6/29/16

Mechanical Maintenance Training Records, Introduction to FLEX Fundamentals, 8/5/15 and

8/11/15

Electrical Maintenance Training Records, Electrical Maintenance-FLEX, 6/12/17

Q-AP-EM-337-Flex, Maintain Disconnect /FLEX Links Disconnect Switch Maintenance, 5/17/17

FLEX-SFPLI-V, Spent Fuel Pool Level Indicator FLEX, Training attendance, 5/27/15

Other

AREVA Customer Service Bulletin 15-04, Spent Fuel Pool Level Instrument (SFPLI) Sensor

Mounting Outdoors

AREVA Document No. 38-9238014-001, SAFER Response Plan for Virgil C. Summer Nuclear

Station, Rev.1

Beyond Design Basis Program Manual Virgil

C. Summer Nuclear Station, Rev. 0

Calculation DC00080-002, Site Hazards Design Parameters For FLEX, Rev. 1

IMS-94B-1752, Through Air Radar Spent Fuel Pool Level Instrument (SFPLI) Instruction Manual

for VC Summer, Doc. No. 01-9225772-002

JG40733, FLEX Tornado Study - CR-14-00911 Action 6, 04/29/15

NEI 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Rev. 2

NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and

Communications Capabilities

NEI 10-05, Assessment of On-Shift Emergency Response Organization Staffing and

Capabilities

PM Revision, RPM Revision 1801928, ICP0390.012 Frequency Change from 6 Months to 18

Months ILT09780 and ILT09781 Calibration per ICP-390.012

Power Point Presentation slides for FLEX Response and Strategies NRC TI-191 Inspection

RC-13-0119, South Carolina Electric and Gas Companys Response to Requests for Additional

Information - Overall Integrated Plan in Response to Commission Order Modifying License

Requirements for Reliable Spent Fuel Pool Level Instrumentation (Order Ea-12-051)

RC-14-0173, South Carolina Electric and Gas Companys Response to Requests for Additional

Information - Overall Integrated Plan in Response to Commission Order Modifying License

Requirements For Reliable Spent Fuel Pool Level Instrumentation (Order Ea-12-051)

RC-15-0093, Response to Request for Additional Information Regarding Phase 2 Staffing

submittals Associated with Near-Term Task Force Recommendation 9.3 Related to the

Fukushima Dai-ichi Nuclear Power Plant Accident

RC-16-0001, Report of Full Compliance with March 12, 2012 Commission Order Modifying

Licenses with Regard to Reliable Spent Fuel Pool Level Instrumentation (Order EA-12-051)

and Responses to Requests for Additional Information

RC-16-0143, Report of Full Compliance and Final Integrated Plan in Response to March 12,

2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation

Strategies for Beyond-Design-Bases External Events (Order EA-12-049) for Virgil C. Summer

Nuclear Station Unit 1

Regulatory Commitment Evaluation Worksheet for SFP Level Indication and Battery

Replacement, 03/28/18

Regulatory Commitment Change Request for SFP Level Indication and Battery Replacement,

03/28/18

SA16-EP-03, FLEX Program - NRC Inspection Manual Self-Assessment, Rev. 1

TR02060-001, Verification Walkdown Report for VCSNS Plant Flood Protective Features,

Rev. 0

TR02060-003, Flood Hazard Reevaluation Report for VCSNS, Rev. 1

TR02060-005, External Flooding Focused Evaluation Summary for VCSNS, Rev. 0

TR00080-001, Engineering Services Technical Report, Guidance for Development of

Specifications for Flex Equipment, Rev. 3

TR00080-003, FLEX Equipment Ventilation and Habitability Assessment, Rev. 2

TR00080-006, FLEX Timeline Constraint Basis, Rev. 1

TR00080-007 VCS Unit 1 Flex Validation Document, Rev. 1

V-100, Vantran Industries Operation and Maintenance Manual for Padmount and Substation

Transformers (Single and Three Phase), 02/12

VC Summer Unit 1 NEI-12-01 Report, Rev. 1, NEI 12-01 Phase 2 Extended Loss of AC Power

(ELAP) ERO Staffing Analysis Report

VCSNS Warehouse Storage Database Information for FLEX SFPLI batteries

Enclosure