IR 05000395/2020010: Difference between revisions

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{{Adams
{{Adams
| number = ML20356A295
| number = ML20196L778
| issue date = 12/21/2020
| issue date = 07/13/2020
| title = NRC Design Bases Assurance Inspection (Team) Report 05000395/2020010
| title = Notification of Virgil C. Summer Nuclear Station Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000395/2020010
| author name = Baptist J
| author name = Baptiste J
| author affiliation = NRC/RGN-II/DRS/EB1
| author affiliation = NRC/RGN-II
| addressee name = Lippard G
| addressee name = Lippard G
| addressee affiliation = Dominion Energy, Inc
| addressee affiliation = South Carolina Electric & Gas Co
| docket = 05000395
| docket = 05000395
| license number = NPF-021
| license number = NPF-012
| contact person =  
| contact person =  
| document report number = IR 2020010
| document report number = IR 2020010
| document type = Inspection Report, Letter
| document type = Inspection Report, Letter, Request for Additional Information (RAI)
| page count = 14
| page count = 5
}}
}}


Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:December 21, 2020
{{#Wiki_filter:July 13, 2020


==SUBJECT:==
==SUBJECT:==
VIRGIL C. SUMMER - DESIGN BASIS ASSURANCE INSPECTION (TEAMS)
NOTIFICATION OF VIRGIL C. SUMMER NUCLEAR STATION DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000395/2020010
INSPECTION REPORT 05000395/2020010


==Dear Mr. Lippard III:==
==Dear Mr. Lippard:==
On November 19, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Virgil C. Summer and 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 purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Summer Nuclear Station during the weeks of October 26 - 30, and November 16 - 20, 2020.


No findings or violations of more than minor significance were identified during this inspection.
Mr. Robert Patterson, a Senior Reactor Inspector from the NRCs Region II office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design Bases Assurance Inspection (Teams), dated December 8, 2016 (ADAMS ML16238A320).


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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
The inspection will evaluate the capability of components that have been modified and risk-significant/low-margin components to function as designed and to support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications.


Sincerely,
During a telephone conversation on July 13, 2020, with Mr. Justin Bouknight we confirmed arrangements for an information-gathering site visit and the two-week onsite inspection. The schedule is as follows:
/RA/
* Information-gathering visit: October 5, 2020
James B. Baptist, Chief Engineering Br 1 Div of Reactor Safety Docket No. 05000395 License No. NPF-12
* Onsite weeks: Weeks of October 26 - 30, and November 16 - 20, 2020 The purpose of the information-gathering visit is to meet with members of your staff to identify components that have been modified, risk-significant components, and operator actions.


===Enclosure:===
Information and documentation needed to support the inspection will also be identified.
As stated


==Inspection Report==
Mr. Shane Sandal, a Region II Senior Risk Analyst, will support Mr. Patterson during the information-gathering visit to review probabilistic risk assessment data and identify components to be examined during the inspection. Additionally, during the onsite weeks, time will be needed on the plant-referenced simulator in order to facilitate the development of operator action-based scenarios.
Docket Number: 05000395 License Number: NPF-12 Report Number: 05000395/2020010 Enterprise Identifier: I-2020-010-0047 Licensee: Dominion Energy Facility: Virgil C. Summer Location: Jenkinsville, SC Inspection Dates: October 26, 2020 to November 20, 2020 Inspectors: P. Braxton, Reactor Inspector J. Hamman, Reactor Inspector S. Ninh, Senior Project Engineer R. Patterson, Senior Reactor Inspector M. Riley, Reactor Inspector T. Su, Reactor Inspector Approved By: James B. Baptist, Chief Engineering Br 1 Div of Reactor Safety Enclosure


=SUMMARY=
The enclosure lists documents that will be needed prior to the information-gathering visit.
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Virgil C.


Summer, 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.
Please provide the referenced information to the Region II Office by Monday, October 5, 2020.


Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
Additional documents will be requested following the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information will be needed in the Region II office by Friday, October 19, 2020, to support the inspection teams preparation week. During the information-gathering trip, Mr. Patterson will also discuss the following inspection support administrative details: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; (2) method of tracking inspector requests during the inspection; (3) licensee computer access; (4) working space; (5) arrangements for site access; and (6) other applicable information.


===List of Findings and Violations===
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.


No findings or violations of more than minor significance were identified.
Thank you for your cooperation in this matter. If you have any questions, regarding the information requested or the inspection, please contact Mr. Patterson at 404-997-4667 or contact me at 404-997-4506.


===Additional Tracking Items===
Sincerely,
None.
/RA/
 
James Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket No.: 50-395 License No.: NPF-12 Enclosure:
=INSPECTION SCOPES=
Notification of Virgil C. Summer Nuclear Station, Design Bases Assurance Inspection (Teams)
 
cc: Distribution via Listserv
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. 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.
 
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
 
==REACTOR SAFETY==
 
===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (4 Samples)
: (1) 480V MCC (XMC1DA2Y)
* Compliance with Updated Final Safety Analysis (UFSAR), Technical Specifications (TS), and TS Bases
* Conformance with manufacturer instructions for installation, maintenance, and operation
* Material condition and configuration
* Environmental Conditions
* Design requirements (loading, short circuit analysis, etc.)
* Verification that System Health Reports accurately reflect current system conditions
* Protective device settings
* Circuit breaker preventive maintenance inspection and testing procedures
: (2) 1A EDG and Support Systems
* Compliance with UFSAR, including applicable design and licensing basis requirements
* Material condition and configuration
* Maintenance effectiveness
* System health reports
* Surveillance test results
* Calculations verifying system design requirements (e.g., loading and fuel tank capacity)
: (3) DC Battery Bus (1HA9B)
* Battery and bus material condition and configuration
* Battery and bus maintenance effectiveness
* System health reports
* Worked maintenance and surveillance test reviews
* Calculations verifying system design requirements
: (4) MDEFW Pump (XPP-21A)
* Compliance with UFSAR, TS, and Design Basis Document (DBD)
* Material condition and configuration (e.g., visual inspection during a walkdown)
* Consistency between station documentation (e.g. procedures) and Vendor Specifications
* Operating, Abnormal and Emergency Procedures
* Training Manual and System Description
* Operator Critical Actions
* Maintenance effectiveness
* Component Health System reports, corrective maintenance records, and corrective action history
* Consistency between design bases calculations and test procedure acceptance criteria
* Surveillance Test results
* Operating Industry Experience Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) ===
{{IP sample|IP=IP 71111.21|count=1}}
: (1) Steam Generator (SG) Power Operated Relief Valve (PORV) IPV-2000
* UFSAR, including applicable design and licensing basis requirements
* Material condition and configuration
* Maintenance effectiveness, including review of maintenance procedures
* Surveillance test results
* Review of related condition reports (CR)
* System review of the supporting instrument air system
* Verification that the Equipment Reliability (ER) tracking list accurately reflects current system configuration
 
===Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)===
: (1) 50883A - Safety Related Inverter Replacement
: (2) 50567S - Major Revision - XVB3107A/B Closing Time Watchdog Permissive
: (3) 70290C - Steam Generator Tube Rupture (SGTR) Enhancements
: (4) 50933G - Component Cooling Heat Exchanger Service Water Return Throttle Valve Installation - B Train
 
===Review of Operating Experience Issues (IP Section 02.06) (1 Sample)===
: (1) NRC Information Notice 2019-02, Emergency Diesel Generator Excitation System          Diode Failures
 
==INSPECTION RESULTS==
No findings were identified.
 
==EXIT MEETINGS AND DEBRIEFS==
The inspectors verified no proprietary information was retained or documented in this report.
* On November 19, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to George Lippard III and other members of the licensee staff.
 
=DOCUMENTS REVIEWED=
 
Inspection Type              Designation      Description or Title                                    Revision or
Procedure                                                                                            Date
71111.21M Calculations      DC09610-056      Assessment of Instrument Error Flow Measurement in SW  Rev. 2
Pump IST
0.13.10          Review of Skew Hilti Bolt Non-Conformance on Pipe      Rev. 0
Support Anchors
DC0011A-012      Qualified Life of Rosemount 1153 Series A Transmitters Rev. 5
                                              (Qual Key 309)
DC04330-085      Sizing of SW Throttle Valves                            Rev. 0
DC05220-083      MDEFW Pump Surveillance Test Requirements              Rev. 2
DC05220-091      EF Hydraulic Analyses                                  Rev. 3
DC06630-001      EDG Fuel Oil Consumption                                Rev. 14
DC08040-012      Protective Device Coordination                          Rev. 8
DC08050-002      Load Study of ESF 7.2KV and 480V                        Rev. 8
DC08200-001      ESF Degraded Voltage Logic and Settings                Rev. 29
DC082220-010    1E Fault Current Study                                  Rev. 6
DC08240-003      480V System Protection                                  Rev. 4
DC08320-005      ESF Battery 1A & 1B Capacity                            Rev. 14
DC08320-005      ESF Battery 1A & 1B Capacity                            10/16/2015
DC08320-010      Class 1E 125 Volt DC System Voltages & Voltage Drop    Rev. 18
DC09310-066      Service Water from CC Heat Exchanger B Flow (IFT04490)  Rev. 1
DC09610-001      Accuracy of Totalized Service Water System Flow        Rev. 2
DC09610-048      IFE04460/04490 SW Scaling for CCW Heat Exchanger        Rev. 3
Thermal Performance (GL 89-13)
EF-000-2        Piping: Emergency Feedwater Flow Control Valve          04/17/1987
SW002            Pipe Analysis SW002                                    Rev. 6.2
Sw008            SW008 Piping Analysis                                  10/14/2014
Corrective Action 17-02093, 17-    Various                                                Various
Documents        02586, 17-05464,
17-05877, 20-
2840, 16-00972,
17-05464,17-
05526,17-05530,
17-05588,17-
Inspection Type              Designation      Description or Title                                          Revision or
Procedure                                                                                                  Date
05877, 18-
208,18-
05853,19-00223,
19-04060,19-
222, 20-01075,
20-01115, 20-
01791, 20-02840,
20-03029, 14-
03039
17-04148, 18-
01032, 18-01033,
20-01681, 20-
2394
CR-19-02065,    Various                                                      Various
CR-17-05376,
CR-17-05224,
CR-17-03153
Corrective Action 20-03588        The cover band assembly for the B MDEFW pump flow            11/02/2020
Documents                          control valve is loose and resting circumferentially around
Resulting from                    the valve body.
Inspection        CR-20-03529      PM Not Generated Per Plant Procedure                          10/26/2020
CR-20-03546      A computational error for dead weight associated with        10/28/2020
W6x15.5 (GA-W6) beams
CR-20-03591      There was no grout beneath the support (Hanger ID:           11/03/2020
EFH2007) for XVR03531-EF Air Supply Relief Valve for
IFV03531-EF
CR-20-03630      AGASTAT Catalog Pages Included in Error                      11/05/2020
CR-20-03674      Discrepancy between UFSAR Table 8.3-3 Part A1 and            11/10/2020
Design Calculation DC08360-006
CR-20-03676      During extent of condition review for CR-20-03591, which      11/12/2020
identified base plate for support EFH2007 was missing
grout, it was identified that the condition was typical for 5
additional supports.
CR-20-03725      Discrepancy between UFSAR Table 8.3-3 Part A2 and            11/16/2020
Inspection Type          Designation      Description or Title                                    Revision or
Procedure                                                                                          Date
Design Calculation DC08360-006
Drawings      321-085-        Piping Support                                          Rev. 0
EFH2007A
04-4461-SS- 200-  480V Load Centers Relay and Breaker Settings            Rev 10
27
1MS-50-161        8X6 Body 80 Actuator 667-EWP Diaphragm Actuated          11
Control Valve
21-085-          Piping Support,                                          Rev. 0
EFH2007B
D-302-011        Main Steam Nuclear                                       41
Engineering  70290            Steam Generator Tube Rupture Procedure Enhancements      Rev. D
Changes      ECR 50933G        CC HX SW Return Throttle Valve Installation - B Train  Rev. 6
ECR50965M        EF Flow Margin Improvement                              Rev. 5
Miscellaneous 0310-0025-        Power & Rectifier Chassis Temperature Rise Test Results  Rev. 0
MEMO-006
10CFR50.59        10CFR50.59 Review for ECR-70290                          05/23/2012
Review
1MS-94B-0390      Vendor Manual- Model 4 Motor Control Center
Design Basis      Diesel Generator Engine Support and Control Systems (DG) Rev. 15
Document
Design Basis      Main Steam (MS)                                          Rev. 12
Document
ECR 50733, Att. I Replace the Emergency Diesel Generator Excitation System Rev. 4
ECR 50933G -      XVA43182B-SW Status Indication Discussion                Rev. 3
Technical Work
Record -ES-104
Enhanced Design   Emergency Feedwater System                              Rev. 17
Basis Document,
Health System    Emergency Feedwater System Health Report 2nd Half-2019  03/13/2020
Report
Health System    Emergency Feedwater System (EF) Health Report 1st Half-  08/12/2020
Reports          2020
Inspection Type      Designation      Description or Title                                          Revision or
Procedure                                                                                            Date
RPM 2015624      XVB3107A Lockout Control Panel                                10/29/2020
System Health    Emergency Diesel Generator 2020 Period 1                      08/12/2020
Report
Time Critical    Steam Line Break Outside RB with Loss of Bus 1HA and          05/02/2018
Action Validation Offsite Power 05/02/18
Scenario Form
Time Critical    Steam Generator Tube Rupture Dated 02/26/19                  02/26/2019
Action Validation
Scenario Form S
VCSNS - DBD      VCSNS - DBD 125 Volt DC Electrical System                    Rev. 6
25 Volt DC
Electrical System
Vendor Manual    Bingham Emergency Feedwater Pump                              Rev. 5
Vendor Manual    BNL Industries. Inc.: Operating and Maintenance              Rev. 5
Number 1MS-      Instructions for 3/4-inch. 1-inch, and 2-inch (reduced port )
94B-1425          Ball Valves
Vendor Manual    Fisher Vee-Ball V150 Rotary Control Valves                    Rev. 0
Number 1MS-
94B-1870
Procedures STP-123.001      Service Water System Valve Lineup Verification                Rev. 7
AOP-112.2        ARG-3, Steam Generator Tube Leak not Requiring SI            Rev. 7
ARP-001-XCP-      Main Control Board                                            Rev. 7
605 Revision 7
EC-03            Processing Engineering Change Packages                        Rev. 6
EMP 280.004      Molded Case Circuit Breaker Testing                          Rev. 22
EMP 280.006      Molded Case Circuit Breaker and Controller Inspection and    Rev. 8
Preventative Maintenance
EMP-115.029      Battery Main Distribution Panel Inspection                    Rev. 1
EMP-295.011      Motor Rotor Bar Check,                                        Rev. 4
EOP-1.0          E-1, Reactor Trip or Safety Injection                        Rev. 0
EOP-3.0, E-2      Faulted Steam Generator Isolation                            Rev. 13
EOP-4.0          E-3, Steam Generator Tube Rupture                            Rev. 26
EOP-4.0          E-3, Steam Generator Tube Rupture                            Rev. 26
Inspection Type        Designation  Description or Title                                    Revision or
Procedure                                                                                    Date
ES-0120      Operability or Functionality Recommendation Development  Rev. 1
ICP-345.064  Functional Test and Replacement of Train A SW to EF      Rev. 0
Cross Connect Time Delay Relays,
ICP-345.065  Functional Test and Replacement of Train B SW to EF      Rev. 0
Cross Connect Time Delay Relays
ICP-400.004  Service Water from CC HX B FlowIFT04490                  Rev. 9
MMP-300.013  Main Steam Power Relief Valve and Actuator Maintenance  Rev. 12
Change A
MMP-300.022  General Air Actuator Diaphragm and O-Ring Replacement    Rev. 7
Change C
MMP-300.033  Changing Oil in Pumps Equipped With TRICO OPTO-          Rev. 8
MATIC oilers,
PTP-173.001  Backflushing Service Water side of Component Cooling    Rev. 3
Heat Exchanger A(B),
SAP-0133      Design Control /Implementation and Interface            Rev. 16
SAP-0999      Correction Action Program                                Rev. 19,
Change A
SAP-0999B    CR Review Team (CRRT)                                    Rev. 1.
Change D
SAP-0999C    Management Review Team (MRT)                            Rev. 1,
Change G
SAP-0999E    Corrective Action Review Board (CARB)                    Rev. 5
SAP-143      Preventive Maintenance Program                          Rev. 16,
Change B
SOP-211      Emergency Feedwater System                              Rev. 14
STP-0220.001A Motor Driven Emergency Feedwater Pump and Valve Test    Rev. 2
STP-0220.008  Motor Driven Emergency Driven Feedwater Pump Full Flow  Rev. 7
Test
STP-120.005A  Motor Driven Emergency Feedwater Pump A Actuation Test  Rev. 1
STP-121.002A  Steam Generator PORV Operability Test                    Rev. 0
Change D
STP-223.003  Service Water Pump Performance Test Flow vs Differential Rev. 1
Pressure
Work Orders 1706308,      Various                                                  Various
Inspection Type Designation  Description or Title Revision or
Procedure                                        Date
1711623,
1711906,
1716342,
1716679,
1717001,
1802065,
1808781,
1813048,
1817424,
1900454,
1903296,
1903353,
1903712,
1903717,
1904607,
1905905,
1910786,
1912131,
1913504,
1913702,
1917892,
1918061,
2000979,
2006228,
2008938,
2012520,
2012524,
2012525,
2015732
1706952-001, Various              Various
1708804-001,
1712322-001,
1717581-001,
1717582-001,
Inspection Type Designation  Description or Title Revision or
Procedure                                        Date
1718241-001,
1800393-001,
1808401-001,
1809718-001,
1812287-001,
1815929-001,
20606-001,
1903132-001,
1904919-001,
1909684-001,
1911168-001,
1913117-001,
1913131-001,
1914543-001,
1915269-001,
1915269-002,
1916648-001,
2001053-001,
2004941-001,
2006059-001
1903851-001, Various              Various
1903852-001,
1711884-001,
1718225-001,
1903133-001,
1903136-001,
0105321-001,
1611168-001,
1611168-002,
1710182-001,
1710182-002,
1900232-001
2
}}
}}

Revision as of 01:57, 9 December 2021

Notification of Virgil C. Summer Nuclear Station Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000395/2020010
ML20196L778
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 07/13/2020
From: Baptiste J
NRC/RGN-II
To: Lippard G
South Carolina Electric & Gas Co
References
IR 2020010
Download: ML20196L778 (5)
v • d • e


Text

July 13, 2020

SUBJECT:

NOTIFICATION OF VIRGIL C. SUMMER NUCLEAR STATION DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000395/2020010

Dear Mr. Lippard:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Summer Nuclear Station during the weeks of October 26 - 30, and November 16 - 20, 2020.

Mr. Robert Patterson, a Senior Reactor Inspector from the NRCs Region II office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design Bases Assurance Inspection (Teams), dated December 8, 2016 (ADAMS ML16238A320).

The inspection will evaluate the capability of components that have been modified and risk-significant/low-margin components to function as designed and to support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications.

During a telephone conversation on July 13, 2020, with Mr. Justin Bouknight we confirmed arrangements for an information-gathering site visit and the two-week onsite inspection. The schedule is as follows:

  • Information-gathering visit: October 5, 2020
  • Onsite weeks: Weeks of October 26 - 30, and November 16 - 20, 2020 The purpose of the information-gathering visit is to meet with members of your staff to identify components that have been modified, risk-significant components, and operator actions.

Information and documentation needed to support the inspection will also be identified.

Mr. Shane Sandal, a Region II Senior Risk Analyst, will support Mr. Patterson during the information-gathering visit to review probabilistic risk assessment data and identify components to be examined during the inspection. Additionally, during the onsite weeks, time will be needed on the plant-referenced simulator in order to facilitate the development of operator action-based scenarios.

The enclosure lists documents that will be needed prior to the information-gathering visit.

Please provide the referenced information to the Region II Office by Monday, October 5, 2020.

Additional documents will be requested following the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information will be needed in the Region II office by Friday, October 19, 2020, to support the inspection teams preparation week. During the information-gathering trip, Mr. Patterson will also discuss the following inspection support administrative details: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; (2) method of tracking inspector requests during the inspection; (3) licensee computer access; (4) working space; (5) arrangements for site access; and (6) other applicable information.

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.

Thank you for your cooperation in this matter. If you have any questions, regarding the information requested or the inspection, please contact Mr. Patterson at 404-997-4667 or contact me at 404-997-4506.

Sincerely,

/RA/

James Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket No.: 50-395 License No.: NPF-12 Enclosure:

Notification of Virgil C. Summer Nuclear Station, Design Bases Assurance Inspection (Teams)

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