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{{#Wiki_filter:February 13, 2019
{{#Wiki_filter:February 13, 2019  
Mr. George A. Lippard III
Vice President, Nuclear Operations
South Carolina Electric & Gas Company
Virgil C. Summer Nuclear Station
Mr. George A. Lippard III  
Bradham Blvd & Hwy 215
Vice President, Nuclear Operations  
P.O. Box 88, Mail Code 800
South Carolina Electric & Gas Company  
Jenkinsville, SC 29065
Virgil C. Summer Nuclear Station  
SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - NUCLEAR REGULATORY
Bradham Blvd & Hwy 215  
            COMMISSION INTEGRATED INSPECTION REPORT 05000395/2018004
P.O. Box 88, Mail Code 800  
Dear Mr. Lippard:
Jenkinsville, SC 29065  
On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an
inspection at your Virgil C. Summer Nuclear Station, Unit 1. On February 29, 2019, the NRC
SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - NUCLEAR REGULATORY
inspectors discussed the results of this inspection with you and other members of your staff.
                    COMMISSION INTEGRATED INSPECTION REPORT 05000395/2018004  
The results of this inspection are documented in the enclosed report.
Dear Mr. Lippard:  
NRC inspectors documented one finding of very low safety significance (Green) in this report.
The finding involved a violation of NRC requirements. The NRC is treating this violation as a
On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an  
non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
inspection at your Virgil C. Summer Nuclear Station, Unit 1. On February 29, 2019, the NRC  
If you contest the violation or significance of this NCV, you should provide a response within
inspectors discussed the results of this inspection with you and other members of your staff.
30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear
The results of this inspection are documented in the enclosed report.  
Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with
copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the
NRC inspectors documented one finding of very low safety significance (Green) in this report.
NRC resident inspector at the Virgil C. Summer Nuclear Station.
The finding involved a violation of NRC requirements. The NRC is treating this violation as a  
If you disagree with the cross-cutting aspects assigned to the findings in this report, you should
non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.  
provide a response within 30 days of the date of this inspection report, with the basis for your
disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk,
If you contest the violation or significance of this NCV, you should provide a response within  
Washington DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC
30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear  
resident inspector at the Virgil C. Summer Nuclear Station.
Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with  
copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the  
NRC resident inspector at the Virgil C. Summer Nuclear Station.  
If you disagree with the cross-cutting aspects assigned to the findings in this report, you should  
provide a response within 30 days of the date of this inspection report, with the basis for your  
disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk,  
Washington DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC  
resident inspector at the Virgil C. Summer Nuclear Station.  


G. Lippard                                         2
G. Lippard  
This letter, its enclosure, and your response (if any) will be made available for public inspection
2  
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room
This letter, its enclosure, and your response (if any) will be made available for public inspection  
in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room  
                                              Sincerely,
in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.  
                                                        /RA/
                                              Randall A. Musser, Chief
                                              Reactor Projects Branch 3
                                              Division of Reactor Projects
Docket No.: 50-395
License No.: NPF-12
Enclosure:
IR 05000395/2018004
Sincerely,
cc: Distribution via ListServ
/RA/  
Randall A. Musser, Chief  
Reactor Projects Branch 3  
Division of Reactor Projects  
Docket No.: 50-395  
License No.: NPF-12  
Enclosure:  
IR 05000395/2018004  
cc: Distribution via ListServ  




  ML19044A634
  ML19044A634  
OFFICE   RII/DRP         RII/DRP       RII/DRP       RII/DR         RII/DRS     RII/DRS
OFFICE  
NAME     JReece         EHilton       RTaylor       JDiaz         SDowney       WLoo
RII/DRP  
DATE       2 / 11 /2019   2 / 11 /2019  2 / 12 /2019   2 / 6 /2019   2 / 5 /2019 2 / 5 /2019
RII/DRP  
OFFICE   RII/DRS         RII/DRS       RII/DRS       RII/DRP       RII/DRP
RII/DRP  
  NAME       WPursley       RWilliams     ANielsen     AWilson       RMusser
RII/DR  
  DATE       2 / 5 /2019   2 / 5 /2019   2 / 5 /2019   2 / 5 /2019   2 / 13 /2019
RII/DRS  
                                         
RII/DRS  
                          U.S. NUCLEAR REGULATORYCOMMISSION
NAME  
                                            REGION II
JReece  
Docket No:            50-395
EHilton  
License No:            NPF-12
RTaylor  
Report No:            05000395/2018004
JDiaz  
Enterprise Identifier: I-2018-004-0046
SDowney  
Licensee:              South Carolina Electric & Gas (SCE&G) Company
WLoo  
Facility:              Virgil C. Summer Nuclear Station, Unit 1
DATE  
Location:              Jenkinsville, SC 29065
  2 / 11 /2019  
Dates:                October 1, 2018 through December 31, 2018
2 / 11 /2019  
Inspectors:            J. Reece, Senior Resident Inspector
  2 / 12 /2019  
                      E. Hilton, Resident Inspector
  2 / 6 /2019  
                      J. Diaz-Velez, Senior Health Physicist (Sections 71124.04 and 71151)
  2 / 5 /2019  
                      S. Downey, Senior Reactor Inspector (Sections 7111108)
2 / 5 /2019  
                      C. Dykes, Health Physicist (Section 71124.05)
OFFICE  
                      D. Lanyi, Senior Operations Engineer (Section 1R11)
RII/DRS  
                      W. Loo, Senior Health Physicist (Sections 71124.02 and 71124.03)
RII/DRS  
                      A. Nielsen, Senior Health Physicist (Sections 71124.01 and 71124.03)
RII/DRS  
                      W. Pursley, Health Physicist (Section 71124.02)
RII/DRP  
                      R. Williams, Senior Reactor Inspector (Section 71111.08)
RII/DRP  
Approved by:          Randall A. Musser, Chief
   
                      Reactor Projects Branch 3
NAME  
                      Division of Reactor Projects
WPursley  
                                                                                      Enclosure
RWilliams  
ANielsen  
AWilson  
RMusser  
   
DATE  
  2 / 5 /2019  
2 / 5 /2019
2 / 5 /2019  
2 / 5 /2019  
2 / 13 /2019  
   


                                              SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance
by conducting a baseline inspection and radiation protection inspection 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
Enclosure
information. NRC and self- revealed findings, violations, and additional items are summarized
U.S. NUCLEAR REGULATORYCOMMISSION
in the table below. A licensee-identified non-cited violation was documented in report Section
71124.01.
REGION II
                                    List of Findings and Violations
  Inadequate Procedure Leading to A EDG Fire Event
  Cornerstone          Significance              Cross-cutting Aspect Report Section
  Mitigating          Green NCV                  [P.3] - Resolution  71111.13 - Maintenance
Docket No:
   Systems              05000395/2018004-02                            Risk Assessments and
50-395
                      Opened/Closed                                  Emergent Work Control &
                                                                      71111.19 - Post
                                                                      Maintenance Testing
License No:
  A self-revealing, Green NCV of Technical Specification 6.8, Procedures and Programs, was
NPF-12
  identified for the failure to ensure procedures for performing maintenance on the A EDG
  were adequately established which led to a leak in the A EDG exhaust manifold and a
  consequent fire event.
Report No:
                                                    2
05000395/2018004
Enterprise Identifier:
I-2018-004-0046
Licensee:
South Carolina Electric & Gas (SCE&G) Company 
Facility:
Virgil C. Summer Nuclear Station, Unit 1  
Location:
Jenkinsville, SC 29065
Dates:
October 1, 2018 through December 31, 2018
Inspectors:  
J. Reece, Senior Resident Inspector
E. Hilton, Resident Inspector
J. Diaz-Velez, Senior Health Physicist (Sections 71124.04 and 71151)
S. Downey, Senior Reactor Inspector (Sections 7111108)
C. Dykes, Health Physicist (Section 71124.05)
D. Lanyi, Senior Operations Engineer (Section 1R11)
W. Loo, Senior Health Physicist (Sections 71124.02 and 71124.03)
A. Nielsen, Senior Health Physicist (Sections 71124.01 and 71124.03)
W. Pursley, Health Physicist (Section 71124.02)
R. Williams, Senior Reactor Inspector (Section 71111.08)
    
Approved by:
Randall A. Musser, Chief
Reactor Projects Branch 3 
Division of Reactor Projects


PLANT STATUS
Unit 1 operated at rated thermal power (RTP) until October 5, 2018, when the unit entered
2
refueling outage 24. The unit return to service on November 28, 2018, and reached RTP on
November 29, 2018, and remained at or near RTP for the remainder of the quarter.
SUMMARY
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
by conducting a baseline inspection and radiation protection inspection 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.  NRC and self- revealed findings, violations, and additional items are summarized
in the table below.  A licensee-identified non-cited violation was documented in report Section
71124.01.
List of Findings and Violations
 
Inadequate Procedure Leading to A EDG Fire Event
Cornerstone
Significance
Cross-cutting Aspect Report Section
Mitigating
Systems
Green NCV
05000395/2018004-02
Opened/Closed
[P.3] - Resolution
71111.13 - Maintenance
Risk Assessments and
Emergent Work Control &
71111.19 - Post
Maintenance Testing 
A self-revealing, Green NCV of Technical Specification 6.8, Procedures and Programs, was
identified for the failure to ensure procedures for performing maintenance on the A EDG
were adequately established which led to a leak in the A EDG exhaust manifold and a
consequent fire event. 
 
3
PLANT STATUS  
Unit 1 operated at rated thermal power (RTP) until October 5, 2018, when the unit entered  
refueling outage 24. The unit return to service on November 28, 2018, and reached RTP on  
November 29, 2018, and remained at or near RTP for the remainder of the quarter.  
INSPECTION SCOPES  
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-
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
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
complete when the IP requirements most appropriate to the inspection activity were met  
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection  
Program - Operations Phase. The inspectors performed plant status activities described in
Program - Operations Phase. The inspectors performed plant status activities described in  
IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem
IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem  
Identification and Resolution. The inspectors reviewed selected procedures and records,
Identification and Resolution. The inspectors reviewed selected procedures and records,  
observed activities, and interviewed personnel to assess licensee performance and compliance
observed activities, and interviewed personnel to assess licensee performance and compliance  
with Commission rules and regulations, license conditions, site procedures, and standards.
with Commission rules and regulations, license conditions, site procedures, and standards.  
REACTOR SAFETY
71111.01 - Adverse Weather Protection
REACTOR SAFETY  
    Seasonal Extreme Weather (1 Sample)
    The inspectors evaluated readiness of the condensate storage tank on December 18, 2018,
71111.01 - Adverse Weather Protection  
    and the emergency diesel generators (EDG) on December 19, 2018, for seasonal extreme
    weather conditions prior to the onset of cold temperatures associated with the fall and early
Seasonal Extreme Weather (1 Sample)  
    winter seasons.
    Impending Severe Weather (1 Sample)
The inspectors evaluated readiness of the condensate storage tank on December 18, 2018,  
    The inspectors evaluated readiness for impending adverse weather conditions for
and the emergency diesel generators (EDG) on December 19, 2018, for seasonal extreme  
    Hurricane Michael on October 10, 2018.
weather conditions prior to the onset of cold temperatures associated with the fall and early  
71111.04 - Equipment Alignment
winter seasons.  
    Partial Walkdown (1 Sample)
    The inspectors evaluated system configurations during partial walkdowns of the following
Impending Severe Weather (1 Sample)  
    systems/trains:
    (1) A and B motor driven emergency feedwater (MDEFW) pumps during emergent
The inspectors evaluated readiness for impending adverse weather conditions for  
        work on turbine driven emergency feedwater (TDEFW) pump flow control valve;
Hurricane Michael on October 10, 2018.  
        inspection was completed on December 13, 2018
71111.04 - Equipment Alignment Detailed Walkdown (1 Sample)
71111.04 - Equipment Alignment  
    The inspectors evaluated system configurations during a complete walkdown of the A and
                                                  3
Partial Walkdown (1 Sample)  
The inspectors evaluated system configurations during partial walkdowns of the following  
systems/trains:  
(1) A and B motor driven emergency feedwater (MDEFW) pumps during emergent  
work on turbine driven emergency feedwater (TDEFW) pump flow control valve;  
inspection was completed on December 13, 2018  
71111.04 - Equipment Alignment Detailed Walkdown (1 Sample)  
The inspectors evaluated system configurations during a complete walkdown of the A and  


  B trains of the emergency feedwater (EFW) system inside containment; inspection was
  completed on November 18, 2018.
4
71111.05AQ - Fire Protection Annual/Quarterly
  Quarterly Inspection (5 Samples)
B trains of the emergency feedwater (EFW) system inside containment; inspection was  
  The inspectors evaluated fire protection program implementation in the following
completed on November 18, 2018.  
  selected areas. A licensee identified violation is documented in the Inspection Results
  section below.
71111.05AQ - Fire Protection Annual/Quarterly  
  (1) Intermediate building 436 elevation (fire zones IB01.25.05.01, and .02,
        IB01.25.06.01, and .02, IB01.14); inspection was completed on October 17, 2018
Quarterly Inspection (5 Samples)  
  (2) Turbine building (fire zone TB01.01); inspection was completed on October 17,
        2018
The inspectors evaluated fire protection program implementation in the following  
  (3) Reactor building containment (fire zone RB01); inspection was completed on
selected areas. A licensee identified violation is documented in the Inspection Results  
        November 15, 2018
section below.  
  (4) Control building 482 elevation (fire zones CB22, CB23); inspection was completed on
        December 28, 2018
(1) Intermediate building 436 elevation (fire zones IB01.25.05.01, and .02,  
  (5) Fire service (FS) pumps and alternate FS pumps (fire zones AFSPH01, CWPH01,
IB01.25.06.01, and .02, IB01.14); inspection was completed on October 17, 2018  
        CWPH02); inspection was completed on December 28, 2018
(2) Turbine building (fire zone TB01.01); inspection was completed on October 17,  
  Annual Inspection (1 Sample)
2018  
  The inspectors evaluated fire brigade performance during a fire drill; inspection was
(3) Reactor building containment (fire zone RB01); inspection was completed on
  completed on December 12, 2018.
November 15, 2018  
71111.07A - Heat Sink Performance (1 Sample)
(4) Control building 482 elevation (fire zones CB22, CB23); inspection was completed on            
  On October 28, 2018, the inspectors evaluated the readiness and availability of B
December 28, 2018  
  component cooling water (CCW) heat exchanger (HX) during inspection and cleaning.
(5) Fire service (FS) pumps and alternate FS pumps (fire zones AFSPH01, CWPH01,  
71111.08 - Inservice Inspection Activities (1 Sample)
CWPH02); inspection was completed on December 28, 2018  
        The inspectors evaluated pressurized water reactor non-destructive testing by reviewing
        the following examinations from October 15, 2018 to October 25, 2018:
Annual Inspection (1 Sample)  
        (1) Eddy Current Examination
                a) Steam Generator A - ET for tubes R02C25, R110C91, R110C51, ASME
The inspectors evaluated fire brigade performance during a fire drill; inspection was  
                    Class 1
completed on December 12, 2018.  
                b) Steam Generator B - ET for tubes R19C40, R02C39, ASME Class 1
                c) Steam Generator C - ET for tube R115C62, ASME Class 1
71111.07A - Heat Sink Performance (1 Sample)  
        (2) Liquid Penetrant Examination
                a) Weld MW-13, pipe to valve weld, ASME Class 2. This included a review of
On October 28, 2018, the inspectors evaluated the readiness and availability of B  
                    associated welding activities
component cooling water (CCW) heat exchanger (HX) during inspection and cleaning.  
                b) Weld MW-14, pipe to valve weld, ASME Class 2.
                c) Weld MW-30, pipe to flange weld, ASME Class 3. This included a review of
71111.08 - Inservice Inspection Activities (1 Sample)  
                    associated welding activities
                d) Weld MW-31, pipe to flange weld, ASME Class 3
The inspectors evaluated pressurized water reactor non-destructive testing by reviewing  
                                                  4
the following examinations from October 15, 2018 to October 25, 2018:  
(1) Eddy Current Examination  
a) Steam Generator A - ET for tubes R02C25, R110C91, R110C51, ASME  
Class 1
b) Steam Generator B - ET for tubes R19C40, R02C39, ASME Class 1
c) Steam Generator C - ET for tube R115C62, ASME Class 1
(2) Liquid Penetrant Examination  
a) Weld MW-13, pipe to valve weld, ASME Class 2. This included a review of  
associated welding activities  
b) Weld MW-14, pipe to valve weld, ASME Class 2.
c) Weld MW-30, pipe to flange weld, ASME Class 3. This included a review of  
associated welding activities  
d) Weld MW-31, pipe to flange weld, ASME Class 3  


      (3) Magnetic Particle Examination
              a) Weld MW-24, pipe to flange weld, ASME Class 3. This included a review of
5
                  associated welding activities.
              b) Weld MW-25, pipe to pipe weld, ASME Class 3.
(3) Magnetic Particle Examination  
              c) Weld MW-32, pipe to flange weld, ASME Class 3
a) Weld MW-24, pipe to flange weld, ASME Class 3. This included a review of  
      (4) Ultrasonic Examination
associated welding activities.  
              a) Weld CGR-1-4308-3, pipe to elbow weld, ASME Class 1
b) Weld MW-25, pipe to pipe weld, ASME Class 3.
              b) Weld CGR-1-4308-4, pipe to elbow weld, ASME Class 1
c) Weld MW-32, pipe to flange weld, ASME Class 3  
              c) Weld CGE-1-4104-19, pipe to elbow weld, ASME Class 1
      The Inspectors evaluated the licensees boric acid control program performance.
(4) Ultrasonic Examination  
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
a) Weld CGR-1-4308-3, pipe to elbow weld, ASME Class 1  
  Operator Requalification (1 Sample)
b) Weld CGR-1-4308-4, pipe to elbow weld, ASME Class 1  
  The inspectors observed and evaluated an operator requalification simulator exam scenario
c) Weld CGE-1-4104-19, pipe to elbow weld, ASME Class 1  
  occurring on December 10, 2018.
  Operator Performance (3 Samples)
The Inspectors evaluated the licensees boric acid control program performance.
  The inspectors observed and evaluated:
  (1) Unit 1 shutdown for refueling outage; observation was completed on October 5, 2018
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance  
  (2) Unit reactor coolant system (RCS) cooldown and operator response to letdown alarms;
      observation was completed on October 6, 2018
Operator Requalification (1 Sample)  
  (3) Operators performing transformer lockout testing, maintaining level in steam
      generators (SG) and secured B EFW pump; observation was completed on
The inspectors observed and evaluated an operator requalification simulator exam scenario  
      October 12, 2018
occurring on December 10, 2018.  
  Annual Review of Licensee Requalification Examination Results (1 Sample)
  On August 16, 2018, the licensee completed the annual requalification
Operator Performance (3 Samples)  
  operating examinations required to be administered to all licensed operators
  in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2),
The inspectors observed and evaluated:  
  Requalification Requirements, of the NRCs Operators Licenses. The
  inspectors performed an in-office review of the overall pass/fail results of the
(1) Unit 1 shutdown for refueling outage; observation was completed on October 5, 2018  
  individual operating examinations and the crew simulator operating
(2) Unit reactor coolant system (RCS) cooldown and operator response to letdown alarms;  
  examinations in accordance with Inspection Procedure (IP) 71111.11,
observation was completed on October 6, 2018  
  Licensed Operator Requalification Program. These results were compared
(3) Operators performing transformer lockout testing, maintaining level in steam  
  to the thresholds established in Section 3.02, Requalification Examination
generators (SG) and secured B EFW pump; observation was completed on  
  Results, of IP 71111.11.
October 12, 2018
71111.12 - Maintenance Effectiveness
  Routine Maintenance Effectiveness (2 Samples)
Annual Review of Licensee Requalification Examination Results (1 Sample)  
  The inspectors evaluated the effectiveness of routine maintenance activities
  associated with the following equipment and/or safety significant functions:
On August 16, 2018, the licensee completed the annual requalification  
                                                5
operating examinations required to be administered to all licensed operators  
in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2),  
Requalification Requirements, of the NRCs Operators Licenses. The  
inspectors performed an in-office review of the overall pass/fail results of the  
individual operating examinations and the crew simulator operating  
examinations in accordance with Inspection Procedure (IP) 71111.11,  
Licensed Operator Requalification Program. These results were compared  
to the thresholds established in Section 3.02, Requalification Examination  
Results, of IP 71111.11.  
71111.12 - Maintenance Effectiveness  
Routine Maintenance Effectiveness (2 Samples)  
The inspectors evaluated the effectiveness of routine maintenance activities  
associated with the following equipment and/or safety significant functions:  


  (1) B EDG service water (SW) return piping pinhole leak and subsequent
      repairs; inspection was completed on November 7, 2018
6
  (2) Maintenance Rule (a)(1) evaluation for risk significant function, AH08d, EDG
      ventilation; inspection was completed on December 11, 2018
(1) B EDG service water (SW) return piping pinhole leak and subsequent  
71111.13 - Maintenance Risk Assessments and Emergent Work Control (4 Samples)
repairs; inspection was completed on November 7, 2018  
  The inspectors evaluated the risk assessments for the following planned and
(2) Maintenance Rule (a)(1) evaluation for risk significant function, AH08d, EDG  
  emergent work activities:
ventilation; inspection was completed on December 11, 2018  
  (1) Yellow risk condition for RCS lowered inventory for reactor vessel head removal;
      inspection was completed on November 17, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control (4 Samples)  
  (2) Emergent work for repairs on A EDG exhaust system fire; inspection was completed
      on November 5, 2018
The inspectors evaluated the risk assessments for the following planned and  
  (3) Emergent work for repairs on digital control system cabinet for moisture separator re-
emergent work activities:  
      heaters and feedwater heaters; inspection was completed on November 27, 2018
  (4) Emergent work on TDEFW pump flow control valve; inspection was completed on
(1) Yellow risk condition for RCS lowered inventory for reactor vessel head removal;  
      December 13, 2018
inspection was completed on November 17, 2018  
71111.15 - Operability Determinations and Functionality Assessments (3 Samples)
(2) Emergent work for repairs on A EDG exhaust system fire; inspection was completed  
  The inspectors evaluated the following operability determinations and functionality
on November 5, 2018  
  assessments in review of Condition Reports:
(3) Emergent work for repairs on digital control system cabinet for moisture separator re-
  (1) CR-18-03296, B EDG SW pinhole leaks; inspection was completed on November 17,
heaters and feedwater heaters; inspection was completed on November 27, 2018  
      2018
(4) Emergent work on TDEFW pump flow control valve; inspection was completed on  
  (2) CR-18-01032, Past operability review for SG PORV failure to open; inspection was
December 13, 2018  
      completed on October 23, 2018
  (3) CR-18-04866, Past operability review for RBCU flow switch IFS1900B; inspection
71111.15 - Operability Determinations and Functionality Assessments (3 Samples)  
      was completed on December 11, 2018
71111.18 - Plant Modifications (1 Sample)
The inspectors evaluated the following operability determinations and functionality  
  The inspectors evaluated procedure controlled temporary modification, Work Order (WO)
assessments in review of Condition Reports:  
  1711177, install temporary power to A spent fuel pool (SFP) pump motor; inspection was
  completed on November 13, 2018
(1) CR-18-03296, B EDG SW pinhole leaks; inspection was completed on November 17,  
71111.19 - Post Maintenance Testing (PMT) (7 Samples)
2018  
  The inspectors evaluated the following post maintenance tests:
(2) CR-18-01032, Past operability review for SG PORV failure to open; inspection was  
  (1) WO1709582, A component cooling water (CCW) heat exchanger hydrolase or
completed on October 23, 2018  
      clean tubes, leak test; inspection was completed on October 30, 2018
(3) CR-18-04866, Past operability review for RBCU flow switch IFS1900B; inspection  
  (2) WO1816658, Implement ECR50933B to repair cavitation damage at XVB03121A-
was completed on December 11, 2018  
      SW, SW discharge butterfly valve for A EDG ; inspection was completed on
      October 29, 2018
71111.18 - Plant Modifications (1 Sample)  
  (3) WO1815079, Repair A EDG exhaust fire damage; inspection was completed on
      November 5, 2018
The inspectors evaluated procedure controlled temporary modification, Work Order (WO)  
  (4) WO1711625, B and C charging pump flow test after maintenance; inspection was
1711177, install temporary power to A spent fuel pool (SFP) pump motor; inspection was  
      completed on November 8, 2018
completed on November 13, 2018  
  (5) WO1711495, Perform as found testing of breaker APN1FB-15; inspection was
                                                6
71111.19 - Post Maintenance Testing (PMT) (7 Samples)  
The inspectors evaluated the following post maintenance tests:  
(1) WO1709582, A component cooling water (CCW) heat exchanger hydrolase or  
clean tubes, leak test; inspection was completed on October 30, 2018  
(2) WO1816658, Implement ECR50933B to repair cavitation damage at XVB03121A-
SW, SW discharge butterfly valve for A EDG ; inspection was completed on
October 29, 2018  
(3) WO1815079, Repair A EDG exhaust fire damage; inspection was completed on
November 5, 2018  
(4) WO1711625, B and C charging pump flow test after maintenance; inspection was  
completed on November 8, 2018  
(5) WO1711495, Perform as found testing of breaker APN1FB-15; inspection was  


      completed on November 13, 2018
  (6) WO1820647, Repair air leak on IFV03556-PRZ-EF for TDEFW flow control valve;
7
      inspection was completed on December 27, 2018
  (7) WO1711728, Repair relief valve with seat leakage on XVR03146C-SW; inspection
completed on November 13, 2018  
      completed on December 31, 2018
(6) WO1820647, Repair air leak on IFV03556-PRZ-EF for TDEFW flow control valve;  
71111.20 - Refueling and Other Outage Activities (1 Sample)
inspection was completed on December 27, 2018  
  The inspectors evaluated Unit 1 refueling outage activities from October 5, 2018, until
(7) WO1711728, Repair relief valve with seat leakage on XVR03146C-SW; inspection  
  reactor startup was completed on November 24, 2018. The inspection was completed on
completed on December 31, 2018  
  November 24, 2018.
71111.22 - Surveillance Testing
71111.20 - Refueling and Other Outage Activities (1 Sample)  
  The inspectors evaluated the following surveillance tests:
  Routine (2 Samples)
The inspectors evaluated Unit 1 refueling outage activities from October 5, 2018, until  
  (1) Surveillance Test Procedure (STP) 206.001, Integrated Leak Rate Test, Revision
reactor startup was completed on November 24, 2018. The inspection was completed on  
      5; inspection was completed on October 11, 2018
November 24, 2018.  
  (2) STP-220.001A, Motor Driven Emergency Feedwater Pump and Valve Test,
      Revision 12, and STP 220.008, Motor Driven Emergency Feedwater Pump Full
71111.22 - Surveillance Testing  
      Flow Test, Revision 7C; inspection was completed on October 2, 2018
  Reactor Coolant System Leakage Detection Testing (1 Sample)
The inspectors evaluated the following surveillance tests:  
  STP-114.002, Operational Leakage Calculation, Revision 12G; inspection was
  completed on November 28, 2018
Routine (2 Samples)  
  Containment Isolation Valve(s) (1 Sample)
  STP-215-003A, Containment Isolation Valve Leakage Test for the CVCS, ND, RC, SF,
(1) Surveillance Test Procedure (STP) 206.001, Integrated Leak Rate Test, Revision  
  ST, SP and WL Systems, Revision 7B; inspection was completed on November 15,
5; inspection was completed on October 11, 2018  
  2018
(2) STP-220.001A, Motor Driven Emergency Feedwater Pump and Valve Test,  
  In-service (1 Sample)
Revision 12, and STP 220.008, Motor Driven Emergency Feedwater Pump Full  
  STP 230.006A, ECCS Charging Pump Operability Testing (Refueling), Revision 8E;
Flow Test, Revision 7C; inspection was completed on October 2, 2018  
  inspection was completed on November 21, 2018
RADIATION SAFETY
Reactor Coolant System Leakage Detection Testing (1 Sample)  
71124.01 - Radiological Hazard Assessment and Exposure Controls
  Radiological Hazard Assessment (1 Sample)
STP-114.002, Operational Leakage Calculation, Revision 12G; inspection was  
  The inspectors evaluated radiological hazards assessments and controls.
completed on November 28, 2018  
  Instructions to Workers (1 Sample)
  The inspectors evaluated worker instructions.
Containment Isolation Valve(s) (1 Sample)  
                                              7
STP-215-003A, Containment Isolation Valve Leakage Test for the CVCS, ND, RC, SF,  
ST, SP and WL Systems, Revision 7B; inspection was completed on November 15,  
2018  
In-service (1 Sample)  
STP 230.006A, ECCS Charging Pump Operability Testing (Refueling), Revision 8E;  
inspection was completed on November 21, 2018  
RADIATION SAFETY  
71124.01 - Radiological Hazard Assessment and Exposure Controls  
Radiological Hazard Assessment (1 Sample)  
The inspectors evaluated radiological hazards assessments and controls.  
Instructions to Workers (1 Sample)  
The inspectors evaluated worker instructions.  


  Contamination and Radioactive Material Control (1 Sample)
  The inspectors evaluated contamination and radioactive material controls.
8
  Radiological Hazards Control and Work Coverage (1 Sample)
  The inspectors evaluated radiological hazards control and work coverage.
  High Radiation Area and Very High Radiation Area Controls (1 Sample)
Contamination and Radioactive Material Control (1 Sample)  
  The inspectors evaluated risk-significant high radiation area and very high radiation area
  controls.
The inspectors evaluated contamination and radioactive material controls.  
  Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)
  The inspectors evaluated radiation worker performance and radiation protection technician
Radiological Hazards Control and Work Coverage (1 Sample)  
  proficiency.
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
The inspectors evaluated radiological hazards control and work coverage.  
  Radiological Work Planning (2 Samples)
  The inspectors evaluated the licensees radiological work planning by reviewing the
High Radiation Area and Very High Radiation Area Controls (1 Sample)  
  following activities:
  (1) Primary Side Steam Generator Work, RWP: 18-04900, RF-24 Primary Steam Generator
The inspectors evaluated risk-significant high radiation area and very high radiation area  
        Work
controls.  
  (2) Secondary Steam Generator Work, RWP: 18-04902, RF-24 Secondary Side Steam
        Generator Work
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)  
  Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)
  The inspectors evaluated dose estimates and exposure tracking.
The inspectors evaluated radiation worker performance and radiation protection technician  
  Implementation of ALARA and Radiological Work Controls (4 Samples)
proficiency.  
  The inspectors reviewed ALARA practices and radiological work controls by reviewing the
  following activities:
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls  
  (1) Fuel Movement, RWP-18-4200, RF24 Refuel Activities
  (2) Primary Steam Generator Prep Activities, RWP-4900, RF-24 Primary
Radiological Work Planning (2 Samples)  
        Manways/Diaphragms/Weld Exam
  (3) Scaffold Installation, RWP-18-4003, Outage Scaffold Installation
The inspectors evaluated the licensees radiological work planning by reviewing the  
  (4) HP Activities, RWP-18-4006, Health Physics Activities for RF24
following activities:  
  Radiation Worker Performance (1 Sample)
  The inspectors evaluated radiation worker and radiation protection technician performance.
(1) Primary Side Steam Generator Work, RWP: 18-04900, RF-24 Primary Steam Generator  
                                                8
Work  
(2) Secondary Steam Generator Work, RWP: 18-04902, RF-24 Secondary Side Steam  
Generator Work  
Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)  
The inspectors evaluated dose estimates and exposure tracking.  
Implementation of ALARA and Radiological Work Controls (4 Samples)  
The inspectors reviewed ALARA practices and radiological work controls by reviewing the  
following activities:  
(1) Fuel Movement, RWP-18-4200, RF24 Refuel Activities  
(2) Primary Steam Generator Prep Activities, RWP-4900, RF-24 Primary  
Manways/Diaphragms/Weld Exam  
(3) Scaffold Installation, RWP-18-4003, Outage Scaffold Installation  
(4) HP Activities, RWP-18-4006, Health Physics Activities for RF24  
Radiation Worker Performance (1 Sample)  
The inspectors evaluated radiation worker and radiation protection technician performance.  


71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
  Engineering Controls (1 Sample)
9
  The inspectors evaluated airborne controls and monitoring.
  Use of Respiratory Protection Devices (1 Sample)
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation  
  The inspectors evaluated respiratory protection.
  Self-Contained Breathing Apparatus for Emergency Use (1 Sample)
Engineering Controls (1 Sample)  
  The inspectors evaluated the licensees self-contained breathing apparatus program.
71124.04 - Occupational Dose Assessment
The inspectors evaluated airborne controls and monitoring.  
  Source Term Characterization (1 Sample)
  The inspectors evaluated the licensees source term characterization.
Use of Respiratory Protection Devices (1 Sample)  
  External Dosimetry (1 Sample)
  The inspectors evaluated the licensees external dosimetry program.
The inspectors evaluated respiratory protection.  
  Internal Dosimetry (1 Sample)
  The inspectors evaluated the licensees internal dosimetry program.
Self-Contained Breathing Apparatus for Emergency Use (1 Sample)  
  Special Dosimetric Situations (1 Sample)
  The inspectors evaluated the licensees performance for special dosimetric situations.
The inspectors evaluated the licensees self-contained breathing apparatus program.  
71124.05 - Radiation Monitoring Instrumentation
  Walk Downs and Observations (1 Sample)
71124.04 - Occupational Dose Assessment  
  The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.
  Calibration and Testing Program (1 Sample)
Source Term Characterization (1 Sample)  
  The inspectors evaluated the licensees calibration and testing program.
OTHER ACTIVITIES - BASELINE
The inspectors evaluated the licensees source term characterization.  
71151 - Performance Indicator Verification (3 Samples)
  The inspectors verified licensee performance indicators submittals listed below for the period
External Dosimetry (1 Sample)  
  from October 1, 2017 through September 30, 2018. Inspection was completed on
  November 15, 2018.
The inspectors evaluated the licensees external dosimetry program.  
                                              9
Internal Dosimetry (1 Sample)  
The inspectors evaluated the licensees internal dosimetry program.  
Special Dosimetric Situations (1 Sample)  
The inspectors evaluated the licensees performance for special dosimetric situations.  
71124.05 - Radiation Monitoring Instrumentation  
Walk Downs and Observations (1 Sample)  
The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.  
Calibration and Testing Program (1 Sample)  
The inspectors evaluated the licensees calibration and testing program.  
OTHER ACTIVITIES - BASELINE  
71151 - Performance Indicator Verification (3 Samples)  
The inspectors verified licensee performance indicators submittals listed below for the period  
from October 1, 2017 through September 30, 2018. Inspection was completed on  
November 15, 2018.  


      (1) Mitigating System Performance Index (MSPI) - Heat Removal System
      (2) MSPI - Cooling Water Systems
10
      (3) Safety System Functional Failures
71151 - Performance Indicator Verification from Radiation Protection Inspection (2 Samples)
  The inspectors verified licensee performance indicators submittals listed below for the
(1) Mitigating System Performance Index (MSPI) - Heat Removal System  
  period from April 1, 2017 through September 30, 2018.
(2) MSPI - Cooling Water Systems  
      (1) OR01: Occupational Exposure Control Effectiveness
(3) Safety System Functional Failures  
      (2) PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation
          Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent
71151 - Performance Indicator Verification from Radiation Protection Inspection (2 Samples)  
          Occurrences
71152 - Problem Identification and Resolution
The inspectors verified licensee performance indicators submittals listed below for the  
  Semiannual Trend Review (1 Sample)
period from April 1, 2017 through September 30, 2018.  
  The inspectors reviewed the licensees corrective action program for trends that might be
  indicative of a more significant safety issue. Specifically, the inspectors reviewed
(1) OR01: Occupational Exposure Control Effectiveness
  CR-18-02820, Service water pinhole leaks. Inspections were completed on December 12,
(2) PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation  
  2018.
Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent  
                                                10
Occurrences
71152 - Problem Identification and Resolution  
Semiannual Trend Review (1 Sample)  
The inspectors reviewed the licensees corrective action program for trends that might be  
indicative of a more significant safety issue. Specifically, the inspectors reviewed
CR-18-02820, Service water pinhole leaks. Inspections were completed on December 12,  
2018.  


INSPECTION RESULTS
Inadequate Procedure Leading to A EDG Fire Event
11
Cornerstone         Significance             Cross-cutting Aspect   Report Section
Mitigating         Green NCV                 [P.3] - Resolution     71111.13 - Maintenance
Systems            05000395/2018004-02                              Risk Assessments and
INSPECTION RESULTS  
                    Opened/Closed                                    Emergent Work Control &
                                                                      71111.19 - Post
Inadequate Procedure Leading to A EDG Fire Event  
                                                                      Maintenance Testing
Cornerstone  
A self-revealing, Green NCV of Technical Specification 6.8, Procedures and Programs, was
Significance  
identified for the failure to ensure procedures for performing maintenance on the A EDG
Cross-cutting Aspect  
were adequately established which led to a leak in the A EDG exhaust manifold and a
Report Section  
consequent fire event.
Mitigating  
Description:
Systems
On November 4, 2018, during a surveillance test of the A EDG, exhaust fumes were
Green NCV  
reported by the operator. Following review by maintenance personnel, the licensee made the
05000395/2018004-02
determination that this was a normal condition and the decision to load the EDG was made.
Opened/Closed
Approximately 16 minutes into the full load run, the operators identified visible flames near the
exhaust manifold in the vicinity of the turbochargers. The A EDG was immediately unloaded,
[P.3] - Resolution  
shutdown, and declared inoperable; operators extinguished the fire using an extinguisher.
71111.13 - Maintenance  
The licensee initiated CR-18-05016 to document the event, perform an investigation of the
Risk Assessments and  
cause, and implement repairs.
Emergent Work Control &  
The inspectors reviewed the licensees corrective action program (CAP) database and noted
71111.19 - Post  
that on August 23, 2018, the licensee initiated CR-18-03451 to document an exhaust leak on
Maintenance Testing  
the A EDG near the turbochargers during a post-maintenance run. The CR was updated on
A self-revealing, Green NCV of Technical Specification 6.8, Procedures and Programs, was  
the following day to state that exhaust fumes were no longer visible when the EDG was
identified for the failure to ensure procedures for performing maintenance on the A EDG  
loaded to greater than 3000 kilo-watts due to suspected gasket leakage prior to exhaust
were adequately established which led to a leak in the A EDG exhaust manifold and a  
manifold warming up. The inspectors reviewed maintenance history and noted that the
consequent fire event.  
exhaust manifold assembly on A EDG was replaced during the Fall refueling outage in 2015,
Description:  
due to cracks in circumferential welds. Additionally, the B EDG exhaust manifold was
replaced during the Spring refueling outage in 2017, for similar reasons.
On November 4, 2018, during a surveillance test of the A EDG, exhaust fumes were  
The inspectors reviewed the results of the investigation documented in CR-18-05016 and
reported by the operator. Following review by maintenance personnel, the licensee made the  
noted the following comments: it was determined the exhaust manifold bellows flange
determination that this was a normal condition and the decision to load the EDG was made.
serving the #8, #9, and #12 cylinders nearest the right bank turbo was almost completely
Approximately 16 minutes into the full load run, the operators identified visible flames near the  
disassembled and was the source of the significant exhaust leakage. Five of the six bellows
exhaust manifold in the vicinity of the turbochargers. The A EDG was immediately unloaded,  
flange bolts had worked loose and had fallen off into the exhaust manifold shroud and/or
shutdown, and declared inoperable; operators extinguished the fire using an extinguisher.
cover which provided approximately a 1/4 wide circumferential gap allowing exhaust gas
The licensee initiated CR-18-05016 to document the event, perform an investigation of the  
leakage. The inspectors noted the hot gas leakage along with residual oil led to the fire.
cause, and implement repairs.  
While the licensee did not perform an apparent cause evaluation, the inspectors noted that
related vendor drawing P12620219, Sheet 1 of 3, specified a torque value of 35 - 50 foot
The inspectors reviewed the licensees corrective action program (CAP) database and noted  
pounds for the bolts which had loosened and fallen out of the exhaust bellows flanges. The
that on August 23, 2018, the licensee initiated CR-18-03451 to document an exhaust leak on  
inspectors reviewed safety-related mechanical maintenance procedure, MMP-180.050,
the A EDG near the turbochargers during a post-maintenance run. The CR was updated on  
Diesel Generator Exhaust Manifold Maintenance, XEG0001A/B-E, Revision 1, and noted
the following day to state that exhaust fumes were no longer visible when the EDG was  
that step 7.2.4 stated, Tighten exhaust joints and bellows bolts wrench tight verifying bolts do
loaded to greater than 3000 kilo-watts due to suspected gasket leakage prior to exhaust  
not protrude through the nut plate and contact the bellows. The inspectors noted there was
manifold warming up. The inspectors reviewed maintenance history and noted that the  
                                                11
exhaust manifold assembly on A EDG was replaced during the Fall refueling outage in 2015,  
due to cracks in circumferential welds. Additionally, the B EDG exhaust manifold was  
replaced during the Spring refueling outage in 2017, for similar reasons.  
The inspectors reviewed the results of the investigation documented in CR-18-05016 and  
noted the following comments: it was determined the exhaust manifold bellows flange  
serving the #8, #9, and #12 cylinders nearest the right bank turbo was almost completely  
disassembled and was the source of the significant exhaust leakage. Five of the six bellows  
flange bolts had worked loose and had fallen off into the exhaust manifold shroud and/or  
cover which provided approximately a 1/4 wide circumferential gap allowing exhaust gas  
leakage. The inspectors noted the hot gas leakage along with residual oil led to the fire.  
While the licensee did not perform an apparent cause evaluation, the inspectors noted that  
related vendor drawing P12620219, Sheet 1 of 3, specified a torque value of 35 - 50 foot  
pounds for the bolts which had loosened and fallen out of the exhaust bellows flanges. The  
inspectors reviewed safety-related mechanical maintenance procedure, MMP-180.050,  
Diesel Generator Exhaust Manifold Maintenance, XEG0001A/B-E, Revision 1, and noted  
that step 7.2.4 stated, Tighten exhaust joints and bellows bolts wrench tight verifying bolts do  
not protrude through the nut plate and contact the bellows. The inspectors noted there was  


no torque specification for the bolting.
The inspectors concluded the licensee failed to adequately establish MMP-180.050 to
12
stipulate required torque specifications contrary to the requirements of TS 6.8.1a, which
states in part that written procedures shall be established covering the activities referenced in
no torque specification for the bolting.  
Appendix A of Regulatory Guide 1.33, Revision 2, Section 9, Procedures for Performing
Maintenance. Although the failure occurred during a refueling outage with the unit in a
The inspectors concluded the licensee failed to adequately establish MMP-180.050 to  
defueled mode in which the A EDG was not required by TS or for risk mitigation, the
stipulate required torque specifications contrary to the requirements of TS 6.8.1a, which  
inspectors also concluded that had the A EDG been depended upon during its mission time
states in part that written procedures shall be established covering the activities referenced in  
of 24 hours during the previous operating cycle, the resulting vibration, loss of bolting
Appendix A of Regulatory Guide 1.33, Revision 2, Section 9, Procedures for Performing  
material, and resultant exhaust leakage most likely would have led to a fire event.
Maintenance. Although the failure occurred during a refueling outage with the unit in a  
Additionally, the inspectors concluded that the licensee had opportunities for more timely
defueled mode in which the A EDG was not required by TS or for risk mitigation, the  
corrective action prior to the fire event when identified previously in CR-18-03451.
inspectors also concluded that had the A EDG been depended upon during its mission time  
Corrective Action(s): The licensee implemented CR-18-05016 to identify causes and
of 24 hours during the previous operating cycle, the resulting vibration, loss of bolting  
appropriate corrective actions.
material, and resultant exhaust leakage most likely would have led to a fire event.
Corrective Action Reference(s): The licensee entered this issue into their CAP as CR-18-
Additionally, the inspectors concluded that the licensee had opportunities for more timely  
05016. CR-18-03451 was also previously initiated for an exhaust leak on A EDG. WO
corrective action prior to the fire event when identified previously in CR-18-03451.  
1818803 was initiated to correct the similar condition adverse to quality (CAQ) on B EDG.
Performance Assessment:
Corrective Action(s): The licensee implemented CR-18-05016 to identify causes and  
Performance Deficiency: The licensees failure to adequately establish MMP-180.050 with
appropriate corrective actions.  
required torque values which led to exhaust leakage and consequent fire event was a
performance deficiency (PD).
Corrective Action Reference(s): The licensee entered this issue into their CAP as CR-18-
Screening: The inspectors determined the PD was more than minor because it adversely
05016. CR-18-03451 was also previously initiated for an exhaust leak on A EDG. WO  
affected the mitigating systems cornerstone objective to ensure the availability, reliability, and
1818803 was initiated to correct the similar condition adverse to quality (CAQ) on B EDG.  
capability of systems that respond to initiating events to prevent undesirable consequences
and the respective attribute of equipment performance relative to maintenance. Specifically,
Performance Assessment:  
the licensee failed to adequately establish MMP-180.050 with required torque values for
exhaust manifold bolting material.
Performance Deficiency: The licensees failure to adequately establish MMP-180.050 with  
Significance: The inspectors used IMC 0609, Significant Determination Process,
required torque values which led to exhaust leakage and consequent fire event was a  
Attachment 4, dated October 7, 2016, and Appendix A - Exhibit 2, dated July 1, 2012, and
performance deficiency (PD).  
determined the finding was of very low safety significance or Green because the finding was
not a design deficiency or loss of function.
Screening: The inspectors determined the PD was more than minor because it adversely  
Cross-cutting Aspect: The inspectors reviewed IMC 0310, Aspects Within Cross Cutting
affected the mitigating systems cornerstone objective to ensure the availability, reliability, and  
capability of systems that respond to initiating events to prevent undesirable consequences  
and the respective attribute of equipment performance relative to maintenance. Specifically,  
the licensee failed to adequately establish MMP-180.050 with required torque values for  
exhaust manifold bolting material.  
Significance: The inspectors used IMC 0609, Significant Determination Process,
Attachment 4, dated October 7, 2016, and Appendix A - Exhibit 2, dated July 1, 2012, and  
determined the finding was of very low safety significance or Green because the finding was  
not a design deficiency or loss of function.  
Cross-cutting Aspect: The inspectors reviewed IMC 0310, Aspects Within Cross Cutting  
Areas, dated December 4, 2014, and determined the cause of this finding involved the cross-
Areas, dated December 4, 2014, and determined the cause of this finding involved the cross-
cutting area of problem identification and resolution and the aspect of resolution, P.3,
cutting area of problem identification and resolution and the aspect of resolution, P.3,  
because the licensee failed to take effective corrective actions commensurate with an issues
because the licensee failed to take effective corrective actions commensurate with an issues  
safety significance in that they failed to correct a CAQ involving the A EDG exhaust leak
safety significance in that they failed to correct a CAQ involving the A EDG exhaust leak  
documented in CR-18-03451.
documented in CR-18-03451.  
Enforcement:
Violation: TS 6.8.1a states in part that written procedures shall be established covering the
Enforcement:
activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Section 9 of RG 1.33 requires procedures for performing maintenance on safety related
Violation: TS 6.8.1a states in part that written procedures shall be established covering the  
                                                12
activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Section 9 of RG 1.33 requires procedures for performing maintenance on safety related  


13
equipment. MMP-180.050, Diesel Generator Exhaust Manifold Maintenance, XEG0001A/B-
equipment. MMP-180.050, Diesel Generator Exhaust Manifold Maintenance, XEG0001A/B-
E, Revision 1, was established to perform maintenance on the EDG exhaust manifolds.
E, Revision 1, was established to perform maintenance on the EDG exhaust manifolds.  
Contrary to the above, on November 4, 2018, the licensee failed to adequately establish
MMP-180.050 to stipulate required torque specifications for bolting materials which led to
Contrary to the above, on November 4, 2018, the licensee failed to adequately establish  
exhaust leakage and consequent fire event
MMP-180.050 to stipulate required torque specifications for bolting materials which led to  
Disposition: This violation is being treated as an NCV consistent with Section 2.3.2.a of the
exhaust leakage and consequent fire event  
Enforcement Policy.
                Observation and Minor Violation for SW Pinhole Leaks                     71152
Disposition: This violation is being treated as an NCV consistent with Section 2.3.2.a of the  
                                                                                          Trend
Enforcement Policy.  
                                                                                        Review
Minor Violation: 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, for failure to
Observation and Minor Violation for SW Pinhole Leaks  
promptly identify and correct a condition adverse to quality (CAQ). Specifically, the licensee
did not initiate corrective actions related to cavitation damage on the downstream pipe tees for
71152  
the component cooling water heat exchanger discharge butterfly valves, XVB03123A&B-SW,
Trend  
which are normally throttled for flow control. As a result, the piping tees were damaged to the
Review  
extent that multiple pinhole leaks developed requiring the licensee to seek NRC approval for
Minor Violation: 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, for failure to  
multiple relief requests and non-code repairs.
promptly identify and correct a condition adverse to quality (CAQ). Specifically, the licensee  
Screening: Because the licensee implemented prompt corrective actions during the
did not initiate corrective actions related to cavitation damage on the downstream pipe tees for  
subsequent refueling outage and the components remained in an operable but degraded
the component cooling water heat exchanger discharge butterfly valves, XVB03123A&B-SW,  
condition, the inspectors identified this as a minor violation of Criterion XVI.
which are normally throttled for flow control. As a result, the piping tees were damaged to the  
Enforcement: This failure to comply with 10 CFR 50, Appendix B, Criterion XVI constitutes a
extent that multiple pinhole leaks developed requiring the licensee to seek NRC approval for  
minor violation that is not subject to enforcement action in accordance with the NRCs
multiple relief requests and non-code repairs.
Screening: Because the licensee implemented prompt corrective actions during the  
subsequent refueling outage and the components remained in an operable but degraded  
condition, the inspectors identified this as a minor violation of Criterion XVI.  
Enforcement: This failure to comply with 10 CFR 50, Appendix B, Criterion XVI constitutes a  
minor violation that is not subject to enforcement action in accordance with the NRCs  
Enforcement Policy. The licensee entered the multiple problems into their CAP as trend CR-
Enforcement Policy. The licensee entered the multiple problems into their CAP as trend CR-
18-02820.
18-02820.  
The inspectors performed a corrective action program (CAP) trend review for problems
related to service water (SW) pinhole leaks after facilitating multiple licensee requests for
The inspectors performed a corrective action program (CAP) trend review for problems  
temporary non-code repairs for SW pinhole leaks for emergency diesel generators (EDGs)
related to service water (SW) pinhole leaks after facilitating multiple licensee requests for  
and component cooling water (CCW) heat exchangers (Hx) over the previous inspection
temporary non-code repairs for SW pinhole leaks for emergency diesel generators (EDGs)  
quarters. Additionally, the inspectors noted the licensee initiated CR-18-02820 for a similar
and component cooling water (CCW) heat exchangers (Hx) over the previous inspection  
trend and to also perform a common cause evaluation. Specifically, the inspectors identified
quarters. Additionally, the inspectors noted the licensee initiated CR-18-02820 for a similar  
14 CRs for SW pinhole leaks and are listed in the documents attachment.
trend and to also perform a common cause evaluation. Specifically, the inspectors identified  
The inspectors had previously documented CAP observations and a minor violation regarding
14 CRs for SW pinhole leaks and are listed in the documents attachment.  
cavitation damage downstream of throttled butterfly valves in NRC Integrated Inspection
Report 05000395/2018001. The observations discuss historical aspects of cavitation damage
relating to the downstream SW piping for the EDGs. The inspectors identified additional
The inspectors had previously documented CAP observations and a minor violation regarding  
historical information relating to the licensees awareness of the cavitation issues associated
cavitation damage downstream of throttled butterfly valves in NRC Integrated Inspection  
with throttle butterfly valves, XVB03123A&B-SW.
Report 05000395/2018001. The observations discuss historical aspects of cavitation damage  
    *   An engineering Technical Work Record, TWR-LS11312, dated May 18, 2005,
relating to the downstream SW piping for the EDGs. The inspectors identified additional  
        evaluated wall thinning downstream of a butterfly valve, XVB03125A-SW, throttled for
historical information relating to the licensees awareness of the cavitation issues associated  
        back-flushing of CCW Hxs. The TWR stated, The CC Hx valves are manufactured
with throttle butterfly valves, XVB03123A&B-SW.  
        by Henry Pratt and the Henry Pratt Company recommends that their butterfly valve not
                                                13
*  
An engineering Technical Work Record, TWR-LS11312, dated May 18, 2005,  
evaluated wall thinning downstream of a butterfly valve, XVB03125A-SW, throttled for  
back-flushing of CCW Hxs. The TWR stated, The CC Hx valves are manufactured  
by Henry Pratt and the Henry Pratt Company recommends that their butterfly valve not  


        be used for throttling with less than a 15 degree opening or when cavitation can
        occur.
14
    *   An engineering services procedure, ES-505, Service Water System Corrosion Control
        and Monitoring Program, inspection of XVB03123B-SW on May 6, 2008, had pictures
be used for throttling with less than a 15 degree opening or when cavitation can  
        of the gate valve which exhibited cavitation damage.
occur.  
    *   An ES-505 inspection of XVB03123A-SW on October 27, 2009, had pictures of the
*  
        gate valve and downstream piping. The inspectors noted both components exhibited
An engineering services procedure, ES-505, Service Water System Corrosion Control  
        indications of cavitation damage when compared to other components with known
and Monitoring Program, inspection of XVB03123B-SW on May 6, 2008, had pictures  
        cavitation damage. The inspectors noted the licensee documented the inspection was
of the gate valve which exhibited cavitation damage.  
        performed for suspected cavitation but there were no indications of cavitation.
*  
    *   An ES-505 inspection conducted on the same valve on October 27, 2012, stated, The
An ES-505 inspection of XVB03123A-SW on October 27, 2009, had pictures of the  
        valve body and disc had areas of moderate cavitation damage from years of throttling.
gate valve and downstream piping. The inspectors noted both components exhibited  
        The inspectors identified pictures with similar cavitation damage as shown in the 2009
indications of cavitation damage when compared to other components with known  
        pictures of the same component. The inspectors also noted the licensee failed to
cavitation damage. The inspectors noted the licensee documented the inspection was  
        provide any documentation of the downstream piping tee.
performed for suspected cavitation but there were no indications of cavitation.  
    *   The inspectors identified historical operating experience (OE) documents within the
*  
        licensees OE files discussing the cavitation phenomenon with one of the primary
An ES-505 inspection conducted on the same valve on October 27, 2012, stated, The  
        causes as the throttling of butterfly valves for flow control.
valve body and disc had areas of moderate cavitation damage from years of throttling.
                        Licensee Identified Non-Cited Violation                       71124.01
The inspectors identified pictures with similar cavitation damage as shown in the 2009  
                                                                                      Inspection
pictures of the same component. The inspectors also noted the licensee failed to  
                                                                                      Results
provide any documentation of the downstream piping tee.  
This violation of very low safety significant was identified by the licensee and has been
*  
entered into the licensee corrective action program and is being treated as a Non-Cited
The inspectors identified historical operating experience (OE) documents within the  
Violation, consistent with Section 2.3.2 of the Enforcement Policy.
licensees OE files discussing the cavitation phenomenon with one of the primary  
Violation: TS 6.8.1, Procedures and Programs, requires, in part, that written procedures be
causes as the throttling of butterfly valves for flow control.  
implemented covering the activities recommended in Appendix A of Regulatory Guide 1.33,
Rev. 2, Section 7(e), Radiation Protection Procedures. Specifically, VCS-HPP-0160.001,
Licensee Identified Non-Cited Violation  
71124.01  
Inspection  
Results  
This violation of very low safety significant was identified by the licensee and has been  
entered into the licensee corrective action program and is being treated as a Non-Cited  
Violation, consistent with Section 2.3.2 of the Enforcement Policy.  
Violation: TS 6.8.1, Procedures and Programs, requires, in part, that written procedures be  
implemented covering the activities recommended in Appendix A of Regulatory Guide 1.33,  
Rev. 2, Section 7(e), Radiation Protection Procedures. Specifically, VCS-HPP-0160.001,  
Radiological Posting and Labeling, Revision 1, Attachment II, HRA, LHRA, and VHRA Down-
Radiological Posting and Labeling, Revision 1, Attachment II, HRA, LHRA, and VHRA Down-
Posting Checklist, states in part, that prior to actual down posting, HP survey the area to
Posting Checklist, states in part, that prior to actual down posting, HP survey the area to  
confirm radiation levels do not exceed criteria for down-posted conditions prior to worker
confirm radiation levels do not exceed criteria for down-posted conditions prior to worker  
access.
access.  
Contrary to the above, on November 3, 2018, prior to an actual down posting, the licensee did
not conduct a survey of the area to confirm that radiation levels did not exceed criteria for
Contrary to the above, on November 3, 2018, prior to an actual down posting, the licensee did  
down-posted conditions prior to worker access. Specifically, after the HRA boundary around
not conduct a survey of the area to confirm that radiation levels did not exceed criteria for  
the reactor head was moved on November 3, 2018, a survey was not performed until the next
down-posted conditions prior to worker access. Specifically, after the HRA boundary around  
shift by an HP who identified dose rates up to 110 mr/hr at 30 cm outside the posted HRA
the reactor head was moved on November 3, 2018, a survey was not performed until the next  
boundary.
shift by an HP who identified dose rates up to 110 mr/hr at 30 cm outside the posted HRA  
Significance/Severity Level: The inspectors reviewed Inspection Manual Chapter 0609,
boundary.  
Appendix C, Occupational Radiation Safety Significance Determination Process, dated
August 19, 2008, and determined the finding was of very low safety significance, Green,
Significance/Severity Level: The inspectors reviewed Inspection Manual Chapter 0609,  
because the finding was not related to the As Low As Reasonably Achievable (ALARA)
Appendix C, Occupational Radiation Safety Significance Determination Process, dated  
planning, did not involve an overexposure or substantial potential for overexposure, and the
August 19, 2008, and determined the finding was of very low safety significance, Green,  
ability to assess dose was not compromised.
because the finding was not related to the As Low As Reasonably Achievable (ALARA)  
Corrective Action Reference: The licensee has documented this problem in their CAP as CR-
planning, did not involve an overexposure or substantial potential for overexposure, and the  
18-05037.
ability to assess dose was not compromised.  
                                                  14
Corrective Action Reference: The licensee has documented this problem in their CAP as CR-
18-05037.  


EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
15
The inspectors confirmed that proprietary information was controlled to protect from
public disclosure.
On October 25, 2018, the inspector presented the in-service inspection results to George
EXIT MEETINGS AND DEBRIEFS  
Lippard, Site Vice President, and other members of the licensee staff.
On November 9, 2018, the inspectors presented the baseline radiation protection inspection
The inspectors verified no proprietary information was retained or documented in this report.  
results to Mr. George Lippard and other members of the licensee staff.
On January 29, 2019, the inspectors presented the quarterly resident inspector inspection
The inspectors confirmed that proprietary information was controlled to protect from  
results to Mr. George Lippard and other members of the licensee staff.
public disclosure.  
                                                15
On October 25, 2018, the inspector presented the in-service inspection results to George
Lippard, Site Vice President, and other members of the licensee staff.  
On November 9, 2018, the inspectors presented the baseline radiation protection inspection  
results to Mr. George Lippard and other members of the licensee staff.  
On January 29, 2019, the inspectors presented the quarterly resident inspector inspection  
results to Mr. George Lippard and other members of the licensee staff.  


DOCUMENTS REVIEWED
71111.01 - Adverse Weather Protection
16
OAP 109.1, Guidelines for Severe Weather
71111.04 - Equipment Alignment
DOCUMENTS REVIEWED  
SOP-211, EMERGENCY FEEDWATER SYSTEM, Rev 14I
Drawing number C-314-081 sheet 25, Rev 8
71111.01 - Adverse Weather Protection  
Drawing number C-314-081 sheet 23, Rev 9
OAP 109.1, Guidelines for Severe Weather  
Drawing number C-314-081 sheet 27, Rev 7
Drawing number E-001-031, Rev 53
71111.04 - Equipment Alignment  
Drawing number E-001-021, Rev 62
SOP-211, EMERGENCY FEEDWATER SYSTEM, Rev 14I  
Drawing number D-302-083, Rev 54
Drawing number C-314-081 sheet 25, Rev 8  
CR-18-04827, NRC Identified paint flaking on EFW piping in containment
Drawing number C-314-081 sheet 23, Rev 9  
CR-18-04828, NRC Identified rotated pipe support on EFW piping in containment
Drawing number C-314-081 sheet 27, Rev 7  
71111.05A/Q - Fire Protection Annual/Quarterly
Drawing number E-001-031, Rev 53  
29-CFR-1910.1200, Hazard Communications
Drawing number E-001-021, Rev 62  
29-CFR-1910.120, Hazardous Waste Operations and Emergency Response
Drawing number D-302-083, Rev 54  
AOP-900.01, Fire Response Initial Actions, Rev 3
CR-18-04827, NRC Identified paint flaking on EFW piping in containment  
AOP-900.011, Yard Fire Zone Response Actions, Rev 0
CR-18-04828, NRC Identified rotated pipe support on EFW piping in containment  
MSDS Exxon Univolt 60
MSDS DIALA Oil AX
71111.05A/Q - Fire Protection Annual/Quarterly  
Specification, SP-0326, Main Power Transformer, Rev 1
29-CFR-1910.1200, Hazard Communications  
VCS-ERP-0020, ERU Preplan Development and Control, Rev 0
29-CFR-1910.120, Hazardous Waste Operations and Emergency Response  
VCS-ERP-0080, ERU Emergency Response Drill Management, Rev 1
AOP-900.01, Fire Response Initial Actions, Rev 3  
CR-18-05943, Station Fire Preplan for Transformer Yard Not Adequate
AOP-900.011, Yard Fire Zone Response Actions, Rev 0  
STP-728.030, Reactor Building Fire Barrier Inspection, Rev 5B
MSDS Exxon Univolt 60  
STP-728.033, Turbine Building Fire Barrier Inspection, Rev 5J
MSDS DIALA Oil AX  
STP-728.048, Intermediate Building Elevation 436 Fire Barrier Inspection, Rev 4G
Specification, SP-0326, Main Power Transformer, Rev 1  
STP-728.041 Control Building Elevation 505 & 482 Fire Barrier Inspection, Rev 5D
VCS-ERP-0020, ERU Preplan Development and Control, Rev 0  
STP-728.032, Fire Service Pump House Building Fire Barrier Inspection, Rev 5B
VCS-ERP-0080, ERU Emergency Response Drill Management, Rev 1  
71111.08 - Inservice Inspection Activities
CR-18-05943, Station Fire Preplan for Transformer Yard Not Adequate  
Procedures
STP-728.030, Reactor Building Fire Barrier Inspection, Rev 5B  
54-ISI-400-022, Multi-Frequency Eddy Current Examination of Tubing, Rev 22
STP-728.033, Turbine Building Fire Barrier Inspection, Rev 5J  
Examination Technique Specification Sheet: ETSS1, ETSS2, ETSS3
STP-728.048, Intermediate Building Elevation 436 Fire Barrier Inspection, Rev 4G  
PSEG-19, Boric Acid Corrosion Evaluation, Rev 2
STP-728.041 Control Building Elevation 505 & 482 Fire Barrier Inspection, Rev 5D  
QSP-504, Magnetic Particle Testing, Rev 9
STP-728.032, Fire Service Pump House Building Fire Barrier Inspection, Rev 5B  
SAP-1100, Boric Acid Corrosion Control Program, Rev 3
SGMP-100.006, Steam Generator Tube Inspection Eddy Current Data Analyst Guidelines, Rev 4
71111.08 - Inservice Inspection Activities  
VCS-PTP-151.001A, Inspection for Boric Acid Corrosion, Rev 0
VCS-QSP-501, Solvent Removable Liquid Penetrant, Rev 1
Procedures  
WD-STD-1036, Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds in
54-ISI-400-022, Multi-Frequency Eddy Current Examination of Tubing, Rev 22  
Accordance with PDI-UT-2, Rev 4
Examination Technique Specification Sheet: ETSS1, ETSS2, ETSS3  
WM-1.0, Welding Manual Procedure, Rev 16
PSEG-19, Boric Acid Corrosion Evaluation, Rev 2  
                                              16
QSP-504, Magnetic Particle Testing, Rev 9  
SAP-1100, Boric Acid Corrosion Control Program, Rev 3  
SGMP-100.006, Steam Generator Tube Inspection Eddy Current Data Analyst Guidelines, Rev 4  
VCS-PTP-151.001A, Inspection for Boric Acid Corrosion, Rev 0  
VCS-QSP-501, Solvent Removable Liquid Penetrant, Rev 1  
WD-STD-1036, Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds in  
Accordance with PDI-UT-2, Rev 4  
WM-1.0, Welding Manual Procedure, Rev 16  


NDE Examiner Qualifications:
Certificate of Personnel Qualification for Examiners: C3340, D4825, M6664, F1726, R3716
17
Curtiss-Wright Personnel Certification Statement (Pearson), dated 03/18/2017
Curtiss-Wright Personnel Certification Statement (Weidner), dated 11/7/2016
NDE Examiner Qualifications:  
Sonic Systems International Certificate of Qualification (Michael), dated 08/16/2018
Certificate of Personnel Qualification for Examiners: C3340, D4825, M6664, F1726, R3716  
Sonic Systems International Certificate of Qualification (Shaugabay), dated 08/22/2018
Curtiss-Wright Personnel Certification Statement (Pearson), dated 03/18/2017  
System One Certificate of Method Qualification (Stone), Level II - Magnetic Particle, dated
Curtiss-Wright Personnel Certification Statement (Weidner), dated 11/7/2016  
01/04/2017
Sonic Systems International Certificate of Qualification (Michael), dated 08/16/2018  
Condition Reports
Sonic Systems International Certificate of Qualification (Shaugabay), dated 08/22/2018  
CR-17-02169                         CR-18-02857                        CR-18-04458
System One Certificate of Method Qualification (Stone), Level II - Magnetic Particle, dated  
CR-17-02244                          CR-18-03144                        CR-18-04459
01/04/2017  
CR-17-04662                          CR-18-03647                         CR-18-04644
CR-18-00305                          CR-18-04456
Condition Reports  
CR-18-02808                          CR-18-04457
CR-17-02169  
Miscellaneous Documents
CR-17-02244
51-9289098, VC Summer 1RF24 Steam Generator Degradation Assessment (Fall 2018), Rev 1
CR-17-04662 
51-9289100, Site Validation of Eddy Current Techniques for V C Summer 1RF24, Rev 0
CR-18-00305
51-9289124, VC Summer Unit 1 - RF24 ECT Inspection Plan, Rev 0
CR-18-02808 
Certificate of Performance for Eddy Current Probe SNs: 754362, 754385
CR-18-02857 
ECR 50933B, SW Cooler Return Piping Replacement
CR-18-03144 
SAP-0158 Steam Generator Management Program, Rev 3
CR-18-03647  
SG-SGMP-14-15, V.C. Summer Unit 1 Steam Generator Cycle 21 Condition Monitoring and
CR-18-04456 
Cycles 22, 23 and 24 Operational Assessment, Rev 0
CR-18-04457
UT Report No. RF24-UT-001, dated 10/16/2018
CR-18-04458 
Work Orders: 1703793-002, 1704591-002, 1814841-001
CR-18-04459 
71111.12 - Maintenance Effectiveness
CR-18-04644
WO 1814841, Implement ECR 50933B to repair SW piping pinhole leaks
ECR 50933B, Modification to change SW piping configuration to reduce cavitation
Miscellaneous Documents  
FSAR Sections: 1.2.3.8.1, 3.7, 3.9.2, 9.2.1, 9.4.7, 18.2.33
51-9289098, VC Summer 1RF24 Steam Generator Degradation Assessment (Fall 2018), Rev 1  
Drawing, 302-222, sheets 1 & 3
51-9289100, Site Validation of Eddy Current Techniques for V C Summer 1RF24, Rev 0  
CR-18-03942, XFN0045B failed to start on 9/26/18
51-9289124, VC Summer Unit 1 - RF24 ECT Inspection Plan, Rev 0  
71111.20 - Refueling and Other Outage Activities
Certificate of Performance for Eddy Current Probe SNs: 754362, 754385  
GOP-2, Plant Startup and Heat-up (Mode 5 To Mode 3), Rev 18
ECR 50933B, SW Cooler Return Piping Replacement  
GOP-3, Reactor Startup From Hot Standby To Startup (Mode 3 To Mode 2), Rev 13G
SAP-0158 Steam Generator Management Program, Rev 3  
GOP-4B, Power Operation (Mode 1 - DESCENDING), Rev 1F
SG-SGMP-14-15, V.C. Summer Unit 1 Steam Generator Cycle 21 Condition Monitoring and  
GOP-5, Reactor Shutdown From Startup To Hot Standby (Mode 2 To Mode 3), Rev 12C
Cycles 22, 23 and 24 Operational Assessment, Rev 0  
GOP-6 Plant Shutdown From Hot Standby To Cold Shutdown (Mode 3 To Mode 5), Rev 14C
UT Report No. RF24-UT-001, dated 10/16/2018  
GOP-7 Core Refueling (Mode 5 To Mode 6 Defuel and Refuel To Mode 6), Rev 11G
Work Orders: 1703793-002, 1704591-002, 1814841-001  
SOP-101, Reactor Coolant System, Rev 30K
SOP-115, Residual Heat Removal, Rev 22E
71111.12 - Maintenance Effectiveness  
SOP-117, Service Water System, Rev 24E
WO 1814841, Implement ECR 50933B to repair SW piping pinhole leaks  
SOP-118, Component Cooling Water, Rev 19A
ECR 50933B, Modification to change SW piping configuration to reduce cavitation  
SOP-123, Spent Fuel Cooling System, Rev 16I
FSAR Sections: 1.2.3.8.1, 3.7, 3.9.2, 9.2.1, 9.4.7, 18.2.33  
SOP-211, Emergency Feedwater System, Rev 14I
Drawing, 302-222, sheets 1 & 3  
SOP-304,115KV 7.2KV OPERATIONS, Rev 14B
CR-18-03942, XFN0045B failed to start on 9/26/18  
                                                17
71111.20 - Refueling and Other Outage Activities  
GOP-2, Plant Startup and Heat-up (Mode 5 To Mode 3), Rev 18  
GOP-3, Reactor Startup From Hot Standby To Startup (Mode 3 To Mode 2), Rev 13G  
GOP-4B, Power Operation (Mode 1 - DESCENDING), Rev 1F  
GOP-5, Reactor Shutdown From Startup To Hot Standby (Mode 2 To Mode 3), Rev 12C  
GOP-6 Plant Shutdown From Hot Standby To Cold Shutdown (Mode 3 To Mode 5), Rev 14C  
GOP-7 Core Refueling (Mode 5 To Mode 6 Defuel and Refuel To Mode 6), Rev 11G  
SOP-101, Reactor Coolant System, Rev 30K  
SOP-115, Residual Heat Removal, Rev 22E  
SOP-117, Service Water System, Rev 24E  
SOP-118, Component Cooling Water, Rev 19A  
SOP-123, Spent Fuel Cooling System, Rev 16I  
SOP-211, Emergency Feedwater System, Rev 14I  
SOP-304,115KV 7.2KV OPERATIONS, Rev 14B  


SOP-305, 480 Volt Engineered Safety Features Distribution, Rev 9F
SOP-306, Emergency Diesel Generator, Rev 19E
18
SOP-307, Diesel Generator Fuel Oil System, Rev 13D
SOP-310, Engineered Safety Features 120 VAC Instrumentation and Control Power System, Rev 12A
SOP-305, 480 Volt Engineered Safety Features Distribution, Rev 9F  
SOP-311, 125 VDC System, Rev 13
SOP-306, Emergency Diesel Generator, Rev 19E  
SSP-002, Planning and Scheduling of Outage Activities, Rev 6H
SOP-307, Diesel Generator Fuel Oil System, Rev 13D  
SSP-004, Outage Safety Review Guidelines, Rev 5D
SOP-310, Engineered Safety Features 120 VAC Instrumentation and Control Power System, Rev 12A  
SSP-010, Control of Critical Work Activities, Rev 1B
SOP-311, 125 VDC System, Rev 13  
Core Reload Verification
SSP-002, Planning and Scheduling of Outage Activities, Rev 6H  
MTF 18-13, Core Offload
SSP-004, Outage Safety Review Guidelines, Rev 5D  
MTF 18-15, Core Reload
SSP-010, Control of Critical Work Activities, Rev 1B  
SAP-0152, Fatigue Management and Work Hour Limits, Rev 10A
Core Reload Verification  
OAP-108.4, Operations Outage Control of Containment Penetrations, Rev 2D
MTF 18-13, Core Offload  
DC00020-252, V.C. SUMMER Time To Boil Following Loss of Decay Heat Cooling in Mode 5
MTF 18-15, Core Reload  
DC00020-198, Heat-Up Model for Water in the SFP, Reactor Cavity, and Reactor Vessel
SAP-0152, Fatigue Management and Work Hour Limits, Rev 10A  
71111.18 - Plant Modifications
OAP-108.4, Operations Outage Control of Containment Penetrations, Rev 2D  
EMP-100.004, Installation of Temporary Alternate Feed Cable for Spent Fuel Pumps, Rev 6b
DC00020-252, V.C. SUMMER Time To Boil Following Loss of Decay Heat Cooling in Mode 5  
SAP-364, Control of Temporary Cables, Rev
DC00020-198, Heat-Up Model for Water in the SFP, Reactor Cavity, and Reactor Vessel  
SS-200-927, Sheet 3, 480 Volt Load Center Relay and Breaker Settings (Breaker 1A3)
SS-200-927, Sheet 15, 480 Volt Load Center Relay and Breaker Settings (Breaker 1DA2)
71111.18 - Plant Modifications  
SS-200-927, Sheet 17, 480 Volt Load Center Relay and Breaker Settings (Breaker DB2)
EMP-100.004, Installation of Temporary Alternate Feed Cable for Spent Fuel Pumps, Rev 6b  
Request for Engineering Evaluation, REE22572, Emergency Power for SF Cooling Pumps
SAP-364, Control of Temporary Cables, Rev  
71151 - Performance Indicator Verification
SS-200-927, Sheet 3, 480 Volt Load Center Relay and Breaker Settings (Breaker 1A3)  
Control Room Logs for October 1, 2017 through September 30, 2018
SS-200-927, Sheet 15, 480 Volt Load Center Relay and Breaker Settings (Breaker 1DA2)  
Licensee raw MSPI data for Months of October, 2017 through September, 2018
SS-200-927, Sheet 17, 480 Volt Load Center Relay and Breaker Settings (Breaker DB2)  
Procedures
Request for Engineering Evaluation, REE22572, Emergency Power for SF Cooling Pumps  
VCS-EPAP-0106 Emergency Preparedness Performance Indicator Procedure. Rev. 2
Records and Data
71151 - Performance Indicator Verification  
DEP opportunities documentation for 4th quarter 2017, and 1st and 2nd quarters 2018
Control Room Logs for October 1, 2017 through September 30, 2018  
Siren test data for 4th quarter 2017, and 1st and 2nd quarters 2018
Licensee raw MSPI data for Months of October, 2017 through September, 2018  
Drill & exercise participation records of ERO personnel for 4th quarter 2017, and 1st and 2nd
quarters 2018
Procedures  
Corrective Action Program Documents
VCS-EPAP-0106 Emergency Preparedness Performance Indicator Procedure. Rev. 2  
CR-18-02305, EP to evaluate the process for selecting DEP opportunities
71152 - Problem Identification and Resolution
Records and Data  
NAMCO Cavitation Analysis
DEP opportunities documentation for 4th quarter 2017, and 1st and 2nd quarters 2018  
Engineering Information Request 80756: Provide operational criteria for S-321- 001 (Pipe
Siren test data for 4th quarter 2017, and 1st and 2nd quarters 2018  
Support Erection Standards) that provides an angular tolerance of +/- 3 degrees for liner
Drill & exercise participation records of ERO personnel for 4th quarter 2017, and 1st and 2nd  
supports
quarters 2018  
                                                  18
Corrective Action Program Documents  
CR-18-02305, EP to evaluate the process for selecting DEP opportunities  
71152 - Problem Identification and Resolution  
NAMCO Cavitation Analysis  
Engineering Information Request 80756: Provide operational criteria for S-321- 001 (Pipe
Support Erection Standards) that provides an angular tolerance of +/- 3 degrees for liner
supports  


71124.01 - Radiological Hazard Assessment and Exposure Controls
Procedures, Guidance Documents and Manuals
19
CMP-400.001, Excavation Backfill and Earthwork, Rev. 10
VCS-HPP-0160.002, Access Control of High Radiation, Locked High Radiation, and Very High
71124.01 - Radiological Hazard Assessment and Exposure Controls  
      Radiation Areas, Rev. 1
VCS-HPP-0302, Radiation and Contamination Survey Techniques, Rev. 2
Procedures, Guidance Documents and Manuals  
VCS-HPP-0303, Airborne Activity Sampling Techniques, Rev. 1
CMP-400.001, Excavation Backfill and Earthwork, Rev. 10  
VCS-HPP-0158, Radioactive Material Control, Rev. 0
VCS-HPP-0160.002, Access Control of High Radiation, Locked High Radiation, and Very High  
Records and Data
Radiation Areas, Rev. 1  
Air Sample Results, A S/G Platform, 10/21/18
VCS-HPP-0302, Radiation and Contamination Survey Techniques, Rev. 2  
Gamma Spec Analysis 21_2018-03-22_005, SB Pit Dirt
VCS-HPP-0303, Airborne Activity Sampling Techniques, Rev. 1  
Gamma Spec Analysis 24_2018-03-06_001, Soil Sample #1 SE Corner
VCS-HPP-0158, Radioactive Material Control, Rev. 0  
Gamma Spec Analysis 25_2018-03-06_001, Soil Sample #2 NE Corner
Gamma Spec Analysis 24_2018-10-24_004, Rock Sample From Under EQ Hatch
Records and Data  
HPSS Administrative Instruction No. 17-002, Fuel Cycle 24 Alpha Characterization, 08/10/17
Air Sample Results, A S/G Platform, 10/21/18  
Lapel Air Sample Results, Reactor Building Sump, Serial No. 25739, 10/12/18
Gamma Spec Analysis 21_2018-03-22_005, SB Pit Dirt  
National Source Tracking System Annual Inventory Reconciliation, 01/25/18
Gamma Spec Analysis 24_2018-03-06_001, Soil Sample #1 SE Corner
Radiological Survey VCS1-M-20181006-28, Auxiliary Building 463-02, 10/6/18
Gamma Spec Analysis 25_2018-03-06_001, Soil Sample #2 NE Corner  
Radiological Survey VCS1-M-20180830-2, Auxiliary Building 463-02, 08/30/18
Gamma Spec Analysis 24_2018-10-24_004, Rock Sample From Under EQ Hatch  
Radiological Survey VCS1-M-20180927-2, ISFSI, 09/27/18
HPSS Administrative Instruction No. 17-002, Fuel Cycle 24 Alpha Characterization, 08/10/17  
Radiological Survey VCS1-M-20180730-3, ISFSI, 07/30/18
Lapel Air Sample Results, Reactor Building Sump, Serial No. 25739, 10/12/18  
Radiological Survey VCS1-M-20181023-42, S/G Primary Platform and Bullpens, 10/23/18
National Source Tracking System Annual Inventory Reconciliation, 01/25/18  
Radiological Survey VCS1-M-20181022-5, RCDT-A Tagout, 10/21/18
Radiological Survey VCS1-M-20181006-28, Auxiliary Building 463-02, 10/6/18  
RWP 18-04900, RF-24 S/G Eddy Current Activities, Rev. 1
Radiological Survey VCS1-M-20180830-2, Auxiliary Building 463-02, 08/30/18  
RWP 18-04081, Aggressive Work in Posted Alpha Level 2 Areas - All Alpha Level 3 Work
Radiological Survey VCS1-M-20180927-2, ISFSI, 09/27/18  
      Activities, Rev. 1
Radiological Survey VCS1-M-20180730-3, ISFSI, 07/30/18  
Source Inventory Sheet, Unit 1, 05/31/18
Radiological Survey VCS1-M-20181023-42, S/G Primary Platform and Bullpens, 10/23/18  
VC Summer Nuclear Station Work Order (W/O) 1802399-055
Radiological Survey VCS1-M-20181022-5, RCDT-A Tagout, 10/21/18  
CAP Documents
RWP 18-04900, RF-24 S/G Eddy Current Activities, Rev. 1  
CR-18-04734
RWP 18-04081, Aggressive Work in Posted Alpha Level 2 Areas - All Alpha Level 3 Work  
CR-18-05037
Activities, Rev. 1  
71124.02 - ALARA
Source Inventory Sheet, Unit 1, 05/31/18  
Procedures, Guidance Documents, and Manuals
VC Summer Nuclear Station Work Order (W/O) 1802399-055  
SAP-0121, ALARA Committee, Revision 10, Change B
Records and Data
CAP Documents  
ALARA Committee Minutes, RVHR ALARA Plan Review
CR-18-04734  
ALARA Plan, RF-24 Primary Steam Generator Work, RWP: 18-04900
CR-18-05037  
ALARA Plan, RF-24 Secondary Steam Generator Work, RWP: 18-04902
ALARA Plan, RF-24 Primary Manways/Diaphragms/Weld Exam, RWP 18-4901
71124.02 - ALARA
ALARA Post Job Review, RWP 17-04950, Reactor Vessel Head Replacement, 04/03/17
VCS ALARA Group Excellence Plan
Procedures, Guidance Documents, and Manuals  
V.C. Summer, RF-23 Post Outage Critique, ORVCH Disposal, June 28, 2017
SAP-0121, ALARA Committee, Revision 10, Change B  
                                              19
Records and Data  
ALARA Committee Minutes, RVHR ALARA Plan Review
ALARA Plan, RF-24 Primary Steam Generator Work, RWP: 18-04900  
ALARA Plan, RF-24 Secondary Steam Generator Work, RWP: 18-04902
ALARA Plan, RF-24 Primary Manways/Diaphragms/Weld Exam, RWP 18-4901
ALARA Post Job Review, RWP 17-04950, Reactor Vessel Head Replacement, 04/03/17  
VCS ALARA Group Excellence Plan  
V.C. Summer, RF-23 Post Outage Critique, ORVCH Disposal, June 28, 2017  


71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Procedures, Guidance Documents, and Manuals
20
SAP-0999, Corrective Action Program, Rev. 18, Change A
VCS-HPP-0154, Issuance and Control of Respiratory Protection Equipment, Rev. 0, Change A
VCS-HPP-0303, Airborne Activity Sampling Techniques, Rev. 1
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation  
VCS-HPP-0403, Radiological Controls for Nuclear Work Activities, Rev. 0
VCS-HPP-0416, Use and Control of HEPA Filtration Units, Vacuum Equipment, Fans, and
Procedures, Guidance Documents, and Manuals  
        Portable A/C Units, Rev. 0
SAP-0999, Corrective Action Program, Rev. 18, Change A
VCS-HPP-0163, Qualification Process for the Use of Respiratory Protection Equipment, Rev. 0,
VCS-HPP-0154, Issuance and Control of Respiratory Protection Equipment, Rev. 0, Change A  
        Change C
VCS-HPP-0303, Airborne Activity Sampling Techniques, Rev. 1  
VCS-HPP-0602, Fit Testing, Rev. 0, Change B
VCS-HPP-0403, Radiological Controls for Nuclear Work Activities, Rev. 0  
VCS-HPP-0633, Inspection, Maintenance, and Storage of Respiratory Protective Devices,
VCS-HPP-0416, Use and Control of HEPA Filtration Units, Vacuum Equipment, Fans, and  
        Rev. 0
Portable A/C Units, Rev. 0  
VCS-HPP-0924, Operation and Maintenance of High Pressure SCBA Compressor, Rev. 0
VCS-HPP-0163, Qualification Process for the Use of Respiratory Protection Equipment, Rev. 0,  
Records and Data
Change C
EPT-11, C-Q-EP-SCBA, SCBA Qualification Records for selected personnel in Health Physics,
VCS-HPP-0602, Fit Testing, Rev. 0, Change B  
        Instrumentation and Controls, and Mechanical Maintenance for 2018
VCS-HPP-0633, Inspection, Maintenance, and Storage of Respiratory Protective Devices,  
HEPA Filter Integrity Test Results, HEPA Unit 17, 5/15/18
HEPA Filter Integrity Test Results, HEPA Unit 43, 10/10/18
Rev. 0  
Hydrostatic Retest Data Sheets and Visual Inspection Data Sheets for Bottles OP333747,
VCS-HPP-0924, Operation and Maintenance of High Pressure SCBA Compressor, Rev. 0  
        OP333748, and OP342361
Scott Air Supplied Products, Specialist Level Course certificates for personnel, 11/02/17
Records and Data  
Scott Air Supplied Products Technician, Maintenance and Overhaul certificates for personnel,
EPT-11, C-Q-EP-SCBA, SCBA Qualification Records for selected personnel in Health Physics,  
        01/12/18
Instrumentation and Controls, and Mechanical Maintenance for 2018  
SCOTT PosiChek3, Visual / Functional Test Results, for the following SCBA Nos.: 6, 01/22/16;
HEPA Filter Integrity Test Results, HEPA Unit 17, 5/15/18  
        33, 07/27/15 and 06/21/17; and 64, 04/28/15 and 06/26/17
HEPA Filter Integrity Test Results, HEPA Unit 43, 10/10/18  
TRI Air Testing, Laboratory Reports, Compressed Air/Gas Quality Testing, Grade D Air, Bauer
Hydrostatic Retest Data Sheets and Visual Inspection Data Sheets for Bottles OP333747,  
        Compressor # 30542, 07/27/17 and 08/02/18
OP333748, and OP342361  
VCS-HPP-0633, Attachment VI, Rev. 0, SCBA Inspection Log, 3rd Quarter 2018
Scott Air Supplied Products, Specialist Level Course certificates for personnel, 11/02/17  
VCS-HPP-0633, Attachment VII, Rev. 0, Monthly Breathing Air Cylinder Inspection Logs, June -
Scott Air Supplied Products Technician, Maintenance and Overhaul certificates for personnel,  
        October 2018
01/12/18  
CAP Documents
SCOTT PosiChek3, Visual / Functional Test Results, for the following SCBA Nos.: 6, 01/22/16;  
CR-17-03981
33, 07/27/15 and 06/21/17; and 64, 04/28/15 and 06/26/17  
CR-18-01276
TRI Air Testing, Laboratory Reports, Compressed Air/Gas Quality Testing, Grade D Air, Bauer  
CR-18-01974
Compressor # 30542, 07/27/17 and 08/02/18  
71124.04 - Occupational Dose Assessment
VCS-HPP-0633, Attachment VI, Rev. 0, SCBA Inspection Log, 3rd Quarter 2018  
Procedures, Guidance Documents, and Manuals
VCS-HPP-0633, Attachment VII, Rev. 0, Monthly Breathing Air Cylinder Inspection Logs, June -  
TWR 2.1.3-17-017, Calibration Bias for Electronic Dosimetry (SRDs), 12/07/17
October 2018  
VCS-HPP-0157, Personnel Monitoring, Decontamination, and Skin Dose Determination, Rev. 1
VCS-HPP-0411, Monitoring Exposure with Multibadging, Rev. 0
CAP Documents  
VCS-HPP-0505, Issuance and Termination of Personnel Dosimetry, Rev. 0, Change B
CR-17-03981  
VCS-HPP-0509, Leak Test and Calibration of Self-Reading Dosimetry, Rev. 0
CR-18-01276  
                                                20
CR-18-01974  
71124.04 - Occupational Dose Assessment  
Procedures, Guidance Documents, and Manuals  
TWR 2.1.3-17-017, Calibration Bias for Electronic Dosimetry (SRDs), 12/07/17  
VCS-HPP-0157, Personnel Monitoring, Decontamination, and Skin Dose Determination, Rev. 1  
VCS-HPP-0411, Monitoring Exposure with Multibadging, Rev. 0  
VCS-HPP-0505, Issuance and Termination of Personnel Dosimetry, Rev. 0, Change B  
VCS-HPP-0509, Leak Test and Calibration of Self-Reading Dosimetry, Rev. 0  


VCS-HPP-0515, Interpretation of Bioassay Analysis, Rev 0, Change B
VCS-HPP-0517, Multiple Whole Body and Extremity Badging Exposure Calculations, Rev. 0
21
VCS-HPP-0518, Exposure Documentation Control, Rev. 0, Change B
VCS-HPP-0523, Quality Control and Whole Body Counting with the Chair Whole Body Counter,
VCS-HPP-0515, Interpretation of Bioassay Analysis, Rev 0, Change B  
        Rev. 0
VCS-HPP-0517, Multiple Whole Body and Extremity Badging Exposure Calculations, Rev. 0  
VCS-HPP-0717, Sample Collection, Preparation, and Analysis Techniques for Assuring
VCS-HPP-0518, Exposure Documentation Control, Rev. 0, Change B  
        Compliance with 10 CFR 61
VCS-HPP-0523, Quality Control and Whole Body Counting with the Chair Whole Body Counter,  
Records and Data
Rev. 0  
10 CFR 61 Analysis of 2017 DAW, December 17, 2017
VCS-HPP-0717, Sample Collection, Preparation, and Analysis Techniques for Assuring  
2017 PCOs and PCEs report (undated)
Compliance with 10 CFR 61  
2018 PCEs report (undated)
Dosimetry Self-Assessment, dated 10/23/2017
Records and Data  
NVLAP, Certificate of Accreditation to ISO/IEC 17025:2005, Valid from January 7, 2018 to June
10 CFR 61 Analysis of 2017 DAW, December 17, 2017  
        30, 2019
2017 PCOs and PCEs report (undated)  
CAP Documents
2018 PCEs report (undated)  
CR-17-02677                         CR-18-00244                        CR-18-04305
Dosimetry Self-Assessment, dated 10/23/2017  
CR-17-02994                        CR-18-00484                        CR-18-04306
NVLAP, Certificate of Accreditation to ISO/IEC 17025:2005, Valid from January 7, 2018 to June  
CR-17-03725                        CR-18-01957                         CR-18-05090
30, 2019  
CR-17-04838                        CR-18-03344
CR-17-05410                        CR-18-04227
CAP Documents  
71124.05 - Radiation Monitoring Instrumentation
CR-17-02677  
Procedures, Guidance Documents, and Manuals
CR-17-02994
VCS-HPP-0522, Set-Up, Calibration, Quality Control and Operation of Gamma Spectroscopy
CR-17-03725
        Systems with ORTEC Software, Rev. 0, Change C
CR-17-04838
VCS-HPP-0801, Counting Statistics and QC Testing for Health Physics Counting Systems,
CR-17-05410
        Rev. 0, Change A
CR-18-00244
Data and Records
CR-18-00484
10CFR61 Analysis of 2017 DAW
CR-18-01957  
ARGOS Personnel Contamination Monitor #1803-094, 05/25/18Calibration Review and Approval:
CR-18-03344
Gamma Det #25, 1LML0 07/09/18, #23 1LML 09/18/16, and
CR-18-04227
        #23 CHAR-01 08/13/18
CR-18-04305
HPP-0818 Attachment III HIDEX 02/18 - 03/18, 04/18 - 06/18
CR-18-04306
Quality Control: BC-4 #1029, 01/01 - 03/31/18, and 04/01 - 06/30/18
CR-18-05090
Thermo Fisher Scientific Calibration Certificates: Telepole II #428016-053 02/16/17; and
        Telepole II #428016-015, 02/16/17
71124.05 - Radiation Monitoring Instrumentation  
VCS-HPP-0522, Set-Up, Calibration, and Generation of Quality Control Bands for the Chair
        Whole Body Counter ENCLOSURE A: Upper Energy Calibration 08/25/17 and 09/19/17,
Procedures, Guidance Documents, and Manuals  
        and Stand-up Calibration Count 09/19/17
VCS-HPP-0522, Set-Up, Calibration, Quality Control and Operation of Gamma Spectroscopy  
VCS-HPP-0611 Calibration Certificate: Ludlum 9-3 #333134, 09/13/18; Ludlum L-177 #266938
Systems with ORTEC Software, Rev. 0, Change C  
        07/10/17, 07/02/18; and Thermo Fisher RO-20AA 02/08/17, 02/08/18
VCS-HPP-0801, Counting Statistics and QC Testing for Health Physics Counting Systems,  
VCS-HPP-0648, Operation and Calibration of the Eberline PM-7: #585 11/09/17; #264 08/9/16,
Rev. 0, Change A  
        07/17/17, and 11/30/17
                                                21
Data and Records  
10CFR61 Analysis of 2017 DAW  
ARGOS Personnel Contamination Monitor #1803-094, 05/25/18Calibration Review and Approval:  
Gamma Det #25, 1LML0 07/09/18, #23 1LML 09/18/16, and  
#23 CHAR-01 08/13/18  
HPP-0818 Attachment III HIDEX 02/18 - 03/18, 04/18 - 06/18  
Quality Control: BC-4 #1029, 01/01 - 03/31/18, and 04/01 - 06/30/18  
Thermo Fisher Scientific Calibration Certificates: Telepole II #428016-053 02/16/17; and  
Telepole II #428016-015, 02/16/17  
VCS-HPP-0522, Set-Up, Calibration, and Generation of Quality Control Bands for the Chair  
Whole Body Counter ENCLOSURE A: Upper Energy Calibration 08/25/17 and 09/19/17,  
and Stand-up Calibration Count 09/19/17  
VCS-HPP-0611 Calibration Certificate: Ludlum 9-3 #333134, 09/13/18; Ludlum L-177 #266938  
07/10/17, 07/02/18; and Thermo Fisher RO-20AA 02/08/17, 02/08/18  
VCS-HPP-0648, Operation and Calibration of the Eberline PM-7: #585 11/09/17; #264 08/9/16,  
07/17/17, and 11/30/17  


VCS-HPP-0648, PM7 Calibration Data Sheet: #264, 08/09/16 and 08/09/17
VCS-HPP-0649, Calibration and Operation of the SAM Tool; #334 08/10/18,
22
VCS-HPP-0649, Small Articles Monitor Calibration Report: #334, 03/03/17, 08/08/17, and
        08/08/18
VCS-HPP-0648, PM7 Calibration Data Sheet: #264, 08/09/16 and 08/09/17  
VCS-HPP-0653, Calibration Certificates: Hand and Foot Monitor #490, 11/03/18 and 11/02/16
VCS-HPP-0649, Calibration and Operation of the SAM Tool; #334 08/10/18,
VCS-SAP-0501, Defective Instrument Report, ASP-1 #2194, 02/13/18; and ASP2E #1376,
VCS-HPP-0649, Small Articles Monitor Calibration Report: #334, 03/03/17, 08/08/17, and  
        06/15/18
08/08/18  
CAP Documents
VCS-HPP-0653, Calibration Certificates: Hand and Foot Monitor #490, 11/03/18 and 11/02/16
17-03725                           18-02770                            18-00377
VCS-SAP-0501, Defective Instrument Report, ASP-1 #2194, 02/13/18; and ASP2E #1376,  
17-04099                          18-03590
06/15/18  
18-02292                          18-03068
71151 - Performance Indicator Verification
CAP Documents  
Procedures, Guidance Documents, and Manuals
17-03725  
SPIG-01, Station Performance Indicator Guidelines, Rev. 1
17-04099
VCS-HPP-0242, Reporting NRC Performance Indicators, Rev. 0
18-02292 
Records and Data Reviewed
18-02770
Annual Radioactive Effluent Release Report, Virgil C. Summer Nuclear Station, Unit 1, January 1 -
18-03590  
        December 31, 2017
18-03068
ED Dose and Dose Rate Alarm Summary Report (CY2017)
18-00377
ED Dose and Dose Rate Alarm Summary Report (YTD2018)
ED DOSE RATE ALARM EVALUATION LOG (VCS_HPP-04 Enclosure B), March 2017 - October
71151 - Performance Indicator Verification  
        2018
Gaseous and liquid effluent release report summaries for January 2018 - September 2018
Procedures, Guidance Documents, and Manuals  
  Performance Indicator Data Radiation Safety, July 2017 - July 2018
SPIG-01, Station Performance Indicator Guidelines, Rev. 1  
71152 - Problem Identification and Resolution Trend Review
VCS-HPP-0242, Reporting NRC Performance Indicators, Rev. 0  
CR-17-00198, Operator identified a pinhole leak in the flange downstream of XVB03121A-
SW (A train EDG)
Records and Data Reviewed  
CR-18-02364, Operator identified a pinhole leak in field weld below XVB03123B-SW (B
Annual Radioactive Effluent Release Report, Virgil C. Summer Nuclear Station, Unit 1, January 1 -  
train CCW Hx)
December 31, 2017  
CR-18-02706, Operator identified a pinhole leak in pipe tee downstream of XVB03123B-SW
ED Dose and Dose Rate Alarm Summary Report (CY2017)  
CR-18-02797, NRC identified a pinhole leak in the pipe tee downstream of XVB03123A-SW
ED Dose and Dose Rate Alarm Summary Report (YTD2018)  
(A train CCW Hx)
ED DOSE RATE ALARM EVALUATION LOG (VCS_HPP-04 Enclosure B), March 2017 - October  
CR-18-02857, An additional pinhole leak was identified in the pipe tee downstream of
2018  
XVB03123A-SW
Gaseous and liquid effluent release report summaries for January 2018 - September 2018  
CR-18-03296, Operator identified a pinhole leak in the flange downstream of XVB03121B-
Performance Indicator Data Radiation Safety, July 2017 - July 2018
SW (B train EDG)
CR-18-03561, Operator identified 3 additional pinhole leaks (Total of 4) near XVB03121B-
71152 - Problem Identification and Resolution Trend Review  
SW
CR-18-03577, Operator identified 1 additional pinhole leak (Total of 5) near XVB03121B-SW
CR-17-00198, Operator identified a pinhole leak in the flange downstream of XVB03121A-  
CR-18-03579, Operator identified 1 additional pinhole leak (Total of 6) near XVB03121B-SW
SW (A train EDG)  
CR-18-03735, Operator identified 1 additional leak (Total of 7) near XVB03121B-SW
CR-18-02364, Operator identified a pinhole leak in field weld below XVB03123B-SW (B
CR-18-03736, Operator identified 1 additional leak (Total of 8) near XVB03121B-SW
train CCW Hx)  
                                                22
CR-18-02706, Operator identified a pinhole leak in pipe tee downstream of XVB03123B-SW  
CR-18-02797, NRC identified a pinhole leak in the pipe tee downstream of XVB03123A-SW
(A train CCW Hx)  
CR-18-02857, An additional pinhole leak was identified in the pipe tee downstream of
XVB03123A-SW  
CR-18-03296, Operator identified a pinhole leak in the flange downstream of XVB03121B-  
SW (B train EDG)  
CR-18-03561, Operator identified 3 additional pinhole leaks (Total of 4) near XVB03121B-  
SW  
CR-18-03577, Operator identified 1 additional pinhole leak (Total of 5) near XVB03121B-SW  
CR-18-03579, Operator identified 1 additional pinhole leak (Total of 6) near XVB03121B-SW  
CR-18-03735, Operator identified 1 additional leak (Total of 7) near XVB03121B-SW  
CR-18-03736, Operator identified 1 additional leak (Total of 8) near XVB03121B-SW  


CR-18-03887, Flange downstream of XVB03121A-SW is not expected to survive another
operating cycle without pinhole leaks and requires replacement
23
CR-18-04083, Multiple SW pinhole leaks downstream of throttle butterfly valves created
operable but degraded conditions; corrective actions and bridging strategies required.
CR-18-03887, Flange downstream of XVB03121A-SW is not expected to survive another
operating cycle without pinhole leaks and requires replacement  
CR-18-04083, Multiple SW pinhole leaks downstream of throttle butterfly valves created
operable but degraded conditions; corrective actions and bridging strategies required.  
CR-18-04354, Additional pinhole leak identified on pipe tee below XVB03123A-SW
CR-18-04354, Additional pinhole leak identified on pipe tee below XVB03123A-SW
                                                23
}}
}}

Latest revision as of 05:00, 5 January 2025

Nuclear Regulatory Commission Integrated Inspection Report 05000395/2018004
ML19044A634
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 02/13/2019
From: Randy Musser
NRC/RGN-II/DRP/RPB3
To: Lippard G
South Carolina Electric & Gas Co
Geanette D
References
IR 2018004
Download: ML19044A634 (26)
v • d • e


See also: IR 05000395/2018004

Text

February 13, 2019

Mr. George A. Lippard III

Vice President, Nuclear Operations

South Carolina Electric & Gas Company

Virgil C. Summer Nuclear Station

Bradham Blvd & Hwy 215

P.O. Box 88, Mail Code 800

Jenkinsville, SC 29065

SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - NUCLEAR REGULATORY

COMMISSION INTEGRATED INSPECTION REPORT 05000395/2018004

Dear Mr. Lippard:

On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an

inspection at your Virgil C. Summer Nuclear Station, Unit 1. On February 29, 2019, 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.

NRC inspectors documented one finding of very low safety significance (Green) in this report.

The finding involved a violation of NRC requirements. The NRC is treating this violation as a

non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of this NCV, you should provide a response within

30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear

Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with

copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the

NRC resident inspector at the Virgil C. Summer Nuclear Station.

If you disagree with the cross-cutting aspects assigned to the findings in this report, you should

provide a response within 30 days of the date of this inspection report, with the basis for your

disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk,

Washington DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC

resident inspector at the Virgil C. Summer Nuclear Station.

G. Lippard

2

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/

Randall A. Musser, Chief

Reactor Projects Branch 3

Division of Reactor Projects

Docket No.: 50-395

License No.: NPF-12

Enclosure:

IR 05000395/2018004

cc: Distribution via ListServ

ML19044A634

OFFICE

RII/DRP

RII/DRP

RII/DRP

RII/DR

RII/DRS

RII/DRS

NAME

JReece

EHilton

RTaylor

JDiaz

SDowney

WLoo

DATE

2 / 11 /2019

2 / 11 /2019

2 / 12 /2019

2 / 6 /2019

2 / 5 /2019

2 / 5 /2019

OFFICE

RII/DRS

RII/DRS

RII/DRS

RII/DRP

RII/DRP

NAME

WPursley

RWilliams

ANielsen

AWilson

RMusser

DATE

2 / 5 /2019

2 / 5 /2019

2 / 5 /2019

2 / 5 /2019

2 / 13 /2019

Enclosure

U.S. NUCLEAR REGULATORYCOMMISSION

REGION II

Docket No:

50-395

License No:

NPF-12

Report No:

05000395/2018004

Enterprise Identifier:

I-2018-004-0046

Licensee:

South Carolina Electric & Gas (SCE&G) Company

Facility:

Virgil C. Summer Nuclear Station, Unit 1

Location:

Jenkinsville, SC 29065

Dates:

October 1, 2018 through December 31, 2018

Inspectors:

J. Reece, Senior Resident Inspector

E. Hilton, Resident Inspector

J. Diaz-Velez, Senior Health Physicist (Sections 71124.04 and 71151)

S. Downey, Senior Reactor Inspector (Sections 7111108)

C. Dykes, Health Physicist (Section 71124.05)

D. Lanyi, Senior Operations Engineer (Section 1R11)

W. Loo, Senior Health Physicist (Sections 71124.02 and 71124.03)

A. Nielsen, Senior Health Physicist (Sections 71124.01 and 71124.03)

W. Pursley, Health Physicist (Section 71124.02)

R. Williams, Senior Reactor Inspector (Section 71111.08)

Approved by:

Randall A. Musser, Chief

Reactor Projects Branch 3

Division of Reactor Projects

2

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance

by conducting a baseline inspection and radiation protection inspection 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. NRC and self- revealed findings, violations, and additional items are summarized

in the table below. A licensee-identified non-cited violation was documented in report Section

71124.01.

List of Findings and Violations

Inadequate Procedure Leading to A EDG Fire Event

Cornerstone

Significance

Cross-cutting Aspect Report Section

Mitigating

Systems

Green NCV 05000395/2018004-02

Opened/Closed

[P.3] - Resolution

71111.13 - Maintenance

Risk Assessments and

Emergent Work Control &

71111.19 - Post

Maintenance Testing

A self-revealing, Green NCV of Technical Specification 6.8, Procedures and Programs, was

identified for the failure to ensure procedures for performing maintenance on the A EDG

were adequately established which led to a leak in the A EDG exhaust manifold and a

consequent fire event.

3

PLANT STATUS

Unit 1 operated at rated thermal power (RTP) until October 5, 2018, when the unit entered

refueling outage 24. The unit return to service on November 28, 2018, and reached RTP on

November 29, 2018, and remained at or near RTP for the remainder of the quarter.

INSPECTION SCOPES

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 performed plant status activities described in

IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem

Identification and Resolution. 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.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather (1 Sample)

The inspectors evaluated readiness of the condensate storage tank on December 18, 2018,

and the emergency diesel generators (EDG) on December 19, 2018, for seasonal extreme

weather conditions prior to the onset of cold temperatures associated with the fall and early

winter seasons.

Impending Severe Weather (1 Sample)

The inspectors evaluated readiness for impending adverse weather conditions for

Hurricane Michael on October 10, 2018.

71111.04 - Equipment Alignment

Partial Walkdown (1 Sample)

The inspectors evaluated system configurations during partial walkdowns of the following

systems/trains:

(1) A and B motor driven emergency feedwater (MDEFW) pumps during emergent

work on turbine driven emergency feedwater (TDEFW) pump flow control valve;

inspection was completed on December 13, 2018

71111.04 - Equipment Alignment Detailed Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the A and

4

B trains of the emergency feedwater (EFW) system inside containment; inspection was

completed on November 18, 2018.

71111.05AQ - Fire Protection Annual/Quarterly

Quarterly Inspection (5 Samples)

The inspectors evaluated fire protection program implementation in the following

selected areas. A licensee identified violation is documented in the Inspection Results

section below.

(1) Intermediate building 436 elevation (fire zones IB01.25.05.01, and .02,

IB01.25.06.01, and .02, IB01.14); inspection was completed on October 17, 2018

(2) Turbine building (fire zone TB01.01); inspection was completed on October 17,

2018

(3) Reactor building containment (fire zone RB01); inspection was completed on

November 15, 2018

(4) Control building 482 elevation (fire zones CB22, CB23); inspection was completed on

December 28, 2018

(5) Fire service (FS) pumps and alternate FS pumps (fire zones AFSPH01, CWPH01,

CWPH02); inspection was completed on December 28, 2018

Annual Inspection (1 Sample)

The inspectors evaluated fire brigade performance during a fire drill; inspection was

completed on December 12, 2018.

71111.07A - Heat Sink Performance (1 Sample)

On October 28, 2018, the inspectors evaluated the readiness and availability of B

component cooling water (CCW) heat exchanger (HX) during inspection and cleaning.

71111.08 - Inservice Inspection Activities (1 Sample)

The inspectors evaluated pressurized water reactor non-destructive testing by reviewing

the following examinations from October 15, 2018 to October 25, 2018:

(1) Eddy Current Examination

a) Steam Generator A - ET for tubes R02C25, R110C91, R110C51, ASME

Class 1

b) Steam Generator B - ET for tubes R19C40, R02C39, ASME Class 1

c) Steam Generator C - ET for tube R115C62, ASME Class 1

(2) Liquid Penetrant Examination

a) Weld MW-13, pipe to valve weld, ASME Class 2. This included a review of

associated welding activities

b) Weld MW-14, pipe to valve weld, ASME Class 2.

c) Weld MW-30, pipe to flange weld, ASME Class 3. This included a review of

associated welding activities

d) Weld MW-31, pipe to flange weld, ASME Class 3

5

(3) Magnetic Particle Examination

a) Weld MW-24, pipe to flange weld, ASME Class 3. This included a review of

associated welding activities.

b) Weld MW-25, pipe to pipe weld, ASME Class 3.

c) Weld MW-32, pipe to flange weld, ASME Class 3

(4) Ultrasonic Examination

a) Weld CGR-1-4308-3, pipe to elbow weld, ASME Class 1

b) Weld CGR-1-4308-4, pipe to elbow weld, ASME Class 1

c) Weld CGE-1-4104-19, pipe to elbow weld, ASME Class 1

The Inspectors evaluated the licensees boric acid control program performance.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification (1 Sample)

The inspectors observed and evaluated an operator requalification simulator exam scenario

occurring on December 10, 2018.

Operator Performance (3 Samples)

The inspectors observed and evaluated:

(1) Unit 1 shutdown for refueling outage; observation was completed on October 5, 2018

(2) Unit reactor coolant system (RCS) cooldown and operator response to letdown alarms;

observation was completed on October 6, 2018

(3) Operators performing transformer lockout testing, maintaining level in steam

generators (SG) and secured B EFW pump; observation was completed on

October 12, 2018

Annual Review of Licensee Requalification Examination Results (1 Sample)

On August 16, 2018, the licensee completed the annual requalification

operating examinations required to be administered to all licensed operators

in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2),

Requalification Requirements, of the NRCs Operators Licenses. The

inspectors performed an in-office review of the overall pass/fail results of the

individual operating examinations and the crew simulator operating

examinations in accordance with Inspection Procedure (IP) 71111.11,

Licensed Operator Requalification Program. These results were compared

to the thresholds established in Section 3.02, Requalification Examination

Results, of IP 71111.11.

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness (2 Samples)

The inspectors evaluated the effectiveness of routine maintenance activities

associated with the following equipment and/or safety significant functions:

6

(1) B EDG service water (SW) return piping pinhole leak and subsequent

repairs; inspection was completed on November 7, 2018

(2) Maintenance Rule (a)(1) evaluation for risk significant function, AH08d, EDG

ventilation; inspection was completed on December 11, 2018

71111.13 - Maintenance Risk Assessments and Emergent Work Control (4 Samples)

The inspectors evaluated the risk assessments for the following planned and

emergent work activities:

(1) Yellow risk condition for RCS lowered inventory for reactor vessel head removal;

inspection was completed on November 17, 2018

(2) Emergent work for repairs on A EDG exhaust system fire; inspection was completed

on November 5, 2018

(3) Emergent work for repairs on digital control system cabinet for moisture separator re-

heaters and feedwater heaters; inspection was completed on November 27, 2018

(4) Emergent work on TDEFW pump flow control valve; inspection was completed on

December 13, 2018

71111.15 - Operability Determinations and Functionality Assessments (3 Samples)

The inspectors evaluated the following operability determinations and functionality

assessments in review of Condition Reports:

(1) CR-18-03296, B EDG SW pinhole leaks; inspection was completed on November 17,

2018

(2) CR-18-01032, Past operability review for SG PORV failure to open; inspection was

completed on October 23, 2018

(3) CR-18-04866, Past operability review for RBCU flow switch IFS1900B; inspection

was completed on December 11, 2018

71111.18 - Plant Modifications (1 Sample)

The inspectors evaluated procedure controlled temporary modification, Work Order (WO)

1711177, install temporary power to A spent fuel pool (SFP) pump motor; inspection was

completed on November 13, 2018

71111.19 - Post Maintenance Testing (PMT) (7 Samples)

The inspectors evaluated the following post maintenance tests:

(1) WO1709582, A component cooling water (CCW) heat exchanger hydrolase or

clean tubes, leak test; inspection was completed on October 30, 2018

(2) WO1816658, Implement ECR50933B to repair cavitation damage at XVB03121A-

SW, SW discharge butterfly valve for A EDG ; inspection was completed on

October 29, 2018

(3) WO1815079, Repair A EDG exhaust fire damage; inspection was completed on

November 5, 2018

(4) WO1711625, B and C charging pump flow test after maintenance; inspection was

completed on November 8, 2018

(5) WO1711495, Perform as found testing of breaker APN1FB-15; inspection was

7

completed on November 13, 2018

(6) WO1820647, Repair air leak on IFV03556-PRZ-EF for TDEFW flow control valve;

inspection was completed on December 27, 2018

(7) WO1711728, Repair relief valve with seat leakage on XVR03146C-SW; inspection

completed on December 31, 2018

71111.20 - Refueling and Other Outage Activities (1 Sample)

The inspectors evaluated Unit 1 refueling outage activities from October 5, 2018, until

reactor startup was completed on November 24, 2018. The inspection was completed on

November 24, 2018.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine (2 Samples)

(1) Surveillance Test Procedure (STP) 206.001, Integrated Leak Rate Test, Revision

5; inspection was completed on October 11, 2018

(2) STP-220.001A, Motor Driven Emergency Feedwater Pump and Valve Test,

Revision 12, and STP 220.008, Motor Driven Emergency Feedwater Pump Full

Flow Test, Revision 7C; inspection was completed on October 2, 2018

Reactor Coolant System Leakage Detection Testing (1 Sample)

STP-114.002, Operational Leakage Calculation, Revision 12G; inspection was

completed on November 28, 2018

Containment Isolation Valve(s) (1 Sample)

STP-215-003A, Containment Isolation Valve Leakage Test for the CVCS, ND, RC, SF,

ST, SP and WL Systems, Revision 7B; inspection was completed on November 15,

2018

In-service (1 Sample)

STP 230.006A, ECCS Charging Pump Operability Testing (Refueling), Revision 8E;

inspection was completed on November 21, 2018

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (1 Sample)

The inspectors evaluated radiological hazards assessments and controls.

Instructions to Workers (1 Sample)

The inspectors evaluated worker instructions.

8

Contamination and Radioactive Material Control (1 Sample)

The inspectors evaluated contamination and radioactive material controls.

Radiological Hazards Control and Work Coverage (1 Sample)

The inspectors evaluated radiological hazards control and work coverage.

High Radiation Area and Very High Radiation Area Controls (1 Sample)

The inspectors evaluated risk-significant high radiation area and very high radiation area

controls.

Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)

The inspectors evaluated radiation worker performance and radiation protection technician

proficiency.

71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls

Radiological Work Planning (2 Samples)

The inspectors evaluated the licensees radiological work planning by reviewing the

following activities:

(1) Primary Side Steam Generator Work, RWP: 18-04900, RF-24 Primary Steam Generator

Work

(2) Secondary Steam Generator Work, RWP: 18-04902, RF-24 Secondary Side Steam

Generator Work

Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)

The inspectors evaluated dose estimates and exposure tracking.

Implementation of ALARA and Radiological Work Controls (4 Samples)

The inspectors reviewed ALARA practices and radiological work controls by reviewing the

following activities:

(1) Fuel Movement, RWP-18-4200, RF24 Refuel Activities

(2) Primary Steam Generator Prep Activities, RWP-4900, RF-24 Primary

Manways/Diaphragms/Weld Exam

(3) Scaffold Installation, RWP-18-4003, Outage Scaffold Installation

(4) HP Activities, RWP-18-4006, Health Physics Activities for RF24

Radiation Worker Performance (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician performance.

9

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Engineering Controls (1 Sample)

The inspectors evaluated airborne controls and monitoring.

Use of Respiratory Protection Devices (1 Sample)

The inspectors evaluated respiratory protection.

Self-Contained Breathing Apparatus for Emergency Use (1 Sample)

The inspectors evaluated the licensees self-contained breathing apparatus program.

71124.04 - Occupational Dose Assessment

Source Term Characterization (1 Sample)

The inspectors evaluated the licensees source term characterization.

External Dosimetry (1 Sample)

The inspectors evaluated the licensees external dosimetry program.

Internal Dosimetry (1 Sample)

The inspectors evaluated the licensees internal dosimetry program.

Special Dosimetric Situations (1 Sample)

The inspectors evaluated the licensees performance for special dosimetric situations.

71124.05 - Radiation Monitoring Instrumentation

Walk Downs and Observations (1 Sample)

The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.

Calibration and Testing Program (1 Sample)

The inspectors evaluated the licensees calibration and testing program.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification (3 Samples)

The inspectors verified licensee performance indicators submittals listed below for the period

from October 1, 2017 through September 30, 2018. Inspection was completed on

November 15, 2018.

10

(1) Mitigating System Performance Index (MSPI) - Heat Removal System

(2) MSPI - Cooling Water Systems

(3) Safety System Functional Failures

71151 - Performance Indicator Verification from Radiation Protection Inspection (2 Samples)

The inspectors verified licensee performance indicators submittals listed below for the

period from April 1, 2017 through September 30, 2018.

(1) OR01: Occupational Exposure Control Effectiveness

(2) PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation

Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent

Occurrences

71152 - Problem Identification and Resolution

Semiannual Trend Review (1 Sample)

The inspectors reviewed the licensees corrective action program for trends that might be

indicative of a more significant safety issue. Specifically, the inspectors reviewed

CR-18-02820, Service water pinhole leaks. Inspections were completed on December 12,

2018.

11

INSPECTION RESULTS

Inadequate Procedure Leading to A EDG Fire Event

Cornerstone

Significance

Cross-cutting Aspect

Report Section

Mitigating

Systems

Green NCV 05000395/2018004-02

Opened/Closed

[P.3] - Resolution

71111.13 - Maintenance

Risk Assessments and

Emergent Work Control &

71111.19 - Post

Maintenance Testing

A self-revealing, Green NCV of Technical Specification 6.8, Procedures and Programs, was

identified for the failure to ensure procedures for performing maintenance on the A EDG

were adequately established which led to a leak in the A EDG exhaust manifold and a

consequent fire event.

Description:

On November 4, 2018, during a surveillance test of the A EDG, exhaust fumes were

reported by the operator. Following review by maintenance personnel, the licensee made the

determination that this was a normal condition and the decision to load the EDG was made.

Approximately 16 minutes into the full load run, the operators identified visible flames near the

exhaust manifold in the vicinity of the turbochargers. The A EDG was immediately unloaded,

shutdown, and declared inoperable; operators extinguished the fire using an extinguisher.

The licensee initiated CR-18-05016 to document the event, perform an investigation of the

cause, and implement repairs.

The inspectors reviewed the licensees corrective action program (CAP) database and noted

that on August 23, 2018, the licensee initiated CR-18-03451 to document an exhaust leak on

the A EDG near the turbochargers during a post-maintenance run. The CR was updated on

the following day to state that exhaust fumes were no longer visible when the EDG was

loaded to greater than 3000 kilo-watts due to suspected gasket leakage prior to exhaust

manifold warming up. The inspectors reviewed maintenance history and noted that the

exhaust manifold assembly on A EDG was replaced during the Fall refueling outage in 2015,

due to cracks in circumferential welds. Additionally, the B EDG exhaust manifold was

replaced during the Spring refueling outage in 2017, for similar reasons.

The inspectors reviewed the results of the investigation documented in CR-18-05016 and

noted the following comments: it was determined the exhaust manifold bellows flange

serving the #8, #9, and #12 cylinders nearest the right bank turbo was almost completely

disassembled and was the source of the significant exhaust leakage. Five of the six bellows

flange bolts had worked loose and had fallen off into the exhaust manifold shroud and/or

cover which provided approximately a 1/4 wide circumferential gap allowing exhaust gas

leakage. The inspectors noted the hot gas leakage along with residual oil led to the fire.

While the licensee did not perform an apparent cause evaluation, the inspectors noted that

related vendor drawing P12620219, Sheet 1 of 3, specified a torque value of 35 - 50 foot

pounds for the bolts which had loosened and fallen out of the exhaust bellows flanges. The

inspectors reviewed safety-related mechanical maintenance procedure, MMP-180.050,

Diesel Generator Exhaust Manifold Maintenance, XEG0001A/B-E, Revision 1, and noted

that step 7.2.4 stated, Tighten exhaust joints and bellows bolts wrench tight verifying bolts do

not protrude through the nut plate and contact the bellows. The inspectors noted there was

12

no torque specification for the bolting.

The inspectors concluded the licensee failed to adequately establish MMP-180.050 to

stipulate required torque specifications contrary to the requirements of TS 6.8.1a, which

states in part that written procedures shall be established covering the activities referenced in

Appendix A of Regulatory Guide 1.33, Revision 2, Section 9, Procedures for Performing

Maintenance. Although the failure occurred during a refueling outage with the unit in a

defueled mode in which the A EDG was not required by TS or for risk mitigation, the

inspectors also concluded that had the A EDG been depended upon during its mission time

of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the previous operating cycle, the resulting vibration, loss of bolting

material, and resultant exhaust leakage most likely would have led to a fire event.

Additionally, the inspectors concluded that the licensee had opportunities for more timely

corrective action prior to the fire event when identified previously in CR-18-03451.

Corrective Action(s): The licensee implemented CR-18-05016 to identify causes and

appropriate corrective actions.

Corrective Action Reference(s): The licensee entered this issue into their CAP as CR-18-

05016. CR-18-03451 was also previously initiated for an exhaust leak on A EDG. WO 1818803 was initiated to correct the similar condition adverse to quality (CAQ) on B EDG.

Performance Assessment:

Performance Deficiency: The licensees failure to adequately establish MMP-180.050 with

required torque values which led to exhaust leakage and consequent fire event was a

performance deficiency (PD).

Screening: The inspectors determined the PD was more than minor because it adversely

affected the mitigating systems cornerstone objective to ensure the availability, reliability, and

capability of systems that respond to initiating events to prevent undesirable consequences

and the respective attribute of equipment performance relative to maintenance. Specifically,

the licensee failed to adequately establish MMP-180.050 with required torque values for

exhaust manifold bolting material.

Significance: The inspectors used IMC 0609, Significant Determination Process,

Attachment 4, dated October 7, 2016, and Appendix A - Exhibit 2, dated July 1, 2012, and

determined the finding was of very low safety significance or Green because the finding was

not a design deficiency or loss of function.

Cross-cutting Aspect: The inspectors reviewed IMC 0310, Aspects Within Cross Cutting

Areas, dated December 4, 2014, and determined the cause of this finding involved the cross-

cutting area of problem identification and resolution and the aspect of resolution, P.3,

because the licensee failed to take effective corrective actions commensurate with an issues

safety significance in that they failed to correct a CAQ involving the A EDG exhaust leak

documented in CR-18-03451.

Enforcement:

Violation: TS 6.8.1a states in part that written procedures shall be established covering the

activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Section 9 of RG 1.33 requires procedures for performing maintenance on safety related

13

equipment. MMP-180.050, Diesel Generator Exhaust Manifold Maintenance, XEG0001A/B-

E, Revision 1, was established to perform maintenance on the EDG exhaust manifolds.

Contrary to the above, on November 4, 2018, the licensee failed to adequately establish

MMP-180.050 to stipulate required torque specifications for bolting materials which led to

exhaust leakage and consequent fire event

Disposition: This violation is being treated as an NCV consistent with Section 2.3.2.a of the

Enforcement Policy.

Observation and Minor Violation for SW Pinhole Leaks

71152

Trend

Review

Minor Violation: 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, for failure to

promptly identify and correct a condition adverse to quality (CAQ). Specifically, the licensee

did not initiate corrective actions related to cavitation damage on the downstream pipe tees for

the component cooling water heat exchanger discharge butterfly valves, XVB03123A&B-SW,

which are normally throttled for flow control. As a result, the piping tees were damaged to the

extent that multiple pinhole leaks developed requiring the licensee to seek NRC approval for

multiple relief requests and non-code repairs.

Screening: Because the licensee implemented prompt corrective actions during the

subsequent refueling outage and the components remained in an operable but degraded

condition, the inspectors identified this as a minor violation of Criterion XVI.

Enforcement: This failure to comply with 10 CFR 50, Appendix B, Criterion XVI constitutes a

minor violation that is not subject to enforcement action in accordance with the NRCs

Enforcement Policy. The licensee entered the multiple problems into their CAP as trend CR-

18-02820.

The inspectors performed a corrective action program (CAP) trend review for problems

related to service water (SW) pinhole leaks after facilitating multiple licensee requests for

temporary non-code repairs for SW pinhole leaks for emergency diesel generators (EDGs)

and component cooling water (CCW) heat exchangers (Hx) over the previous inspection

quarters. Additionally, the inspectors noted the licensee initiated CR-18-02820 for a similar

trend and to also perform a common cause evaluation. Specifically, the inspectors identified

14 CRs for SW pinhole leaks and are listed in the documents attachment.

The inspectors had previously documented CAP observations and a minor violation regarding

cavitation damage downstream of throttled butterfly valves in NRC Integrated Inspection

Report 05000395/2018001. The observations discuss historical aspects of cavitation damage

relating to the downstream SW piping for the EDGs. The inspectors identified additional

historical information relating to the licensees awareness of the cavitation issues associated

with throttle butterfly valves, XVB03123A&B-SW.

An engineering Technical Work Record, TWR-LS11312, dated May 18, 2005,

evaluated wall thinning downstream of a butterfly valve, XVB03125A-SW, throttled for

back-flushing of CCW Hxs. The TWR stated, The CC Hx valves are manufactured

by Henry Pratt and the Henry Pratt Company recommends that their butterfly valve not

14

be used for throttling with less than a 15 degree opening or when cavitation can

occur.

An engineering services procedure, ES-505, Service Water System Corrosion Control

and Monitoring Program, inspection of XVB03123B-SW on May 6, 2008, had pictures

of the gate valve which exhibited cavitation damage.

An ES-505 inspection of XVB03123A-SW on October 27, 2009, had pictures of the

gate valve and downstream piping. The inspectors noted both components exhibited

indications of cavitation damage when compared to other components with known

cavitation damage. The inspectors noted the licensee documented the inspection was

performed for suspected cavitation but there were no indications of cavitation.

An ES-505 inspection conducted on the same valve on October 27, 2012, stated, The

valve body and disc had areas of moderate cavitation damage from years of throttling.

The inspectors identified pictures with similar cavitation damage as shown in the 2009

pictures of the same component. The inspectors also noted the licensee failed to

provide any documentation of the downstream piping tee.

The inspectors identified historical operating experience (OE) documents within the

licensees OE files discussing the cavitation phenomenon with one of the primary

causes as the throttling of butterfly valves for flow control.

Licensee Identified Non-Cited Violation

71124.01

Inspection

Results

This violation of very low safety significant was identified by the licensee and has been

entered into the licensee corrective action program and is being treated as a Non-Cited

Violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: TS 6.8.1, Procedures and Programs, requires, in part, that written procedures be

implemented covering the activities recommended in Appendix A of Regulatory Guide 1.33,

Rev. 2, Section 7(e), Radiation Protection Procedures. Specifically, VCS-HPP-0160.001,

Radiological Posting and Labeling, Revision 1, Attachment II, HRA, LHRA, and VHRA Down-

Posting Checklist, states in part, that prior to actual down posting, HP survey the area to

confirm radiation levels do not exceed criteria for down-posted conditions prior to worker

access.

Contrary to the above, on November 3, 2018, prior to an actual down posting, the licensee did

not conduct a survey of the area to confirm that radiation levels did not exceed criteria for

down-posted conditions prior to worker access. Specifically, after the HRA boundary around

the reactor head was moved on November 3, 2018, a survey was not performed until the next

shift by an HP who identified dose rates up to 110 mr/hr at 30 cm outside the posted HRA

boundary.

Significance/Severity Level: The inspectors reviewed Inspection Manual Chapter 0609,

Appendix C, Occupational Radiation Safety Significance Determination Process, dated

August 19, 2008, and determined the finding was of very low safety significance, Green,

because the finding was not related to the As Low As Reasonably Achievable (ALARA)

planning, did not involve an overexposure or substantial potential for overexposure, and the

ability to assess dose was not compromised.

Corrective Action Reference: The licensee has documented this problem in their CAP as CR-

18-05037.

15

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

The inspectors confirmed that proprietary information was controlled to protect from

public disclosure.

On October 25, 2018, the inspector presented the in-service inspection results to George

Lippard, Site Vice President, and other members of the licensee staff.

On November 9, 2018, the inspectors presented the baseline radiation protection inspection

results to Mr. George Lippard and other members of the licensee staff.

On January 29, 2019, the inspectors presented the quarterly resident inspector inspection

results to Mr. George Lippard and other members of the licensee staff.

16

DOCUMENTS REVIEWED

71111.01 - Adverse Weather Protection

OAP 109.1, Guidelines for Severe Weather

71111.04 - Equipment Alignment

SOP-211, EMERGENCY FEEDWATER SYSTEM, Rev 14I

Drawing number C-314-081 sheet 25, Rev 8

Drawing number C-314-081 sheet 23, Rev 9

Drawing number C-314-081 sheet 27, Rev 7

Drawing number E-001-031, Rev 53

Drawing number E-001-021, Rev 62

Drawing number D-302-083, Rev 54

CR-18-04827, NRC Identified paint flaking on EFW piping in containment

CR-18-04828, NRC Identified rotated pipe support on EFW piping in containment

71111.05A/Q - Fire Protection Annual/Quarterly

29-CFR-1910.1200, Hazard Communications

29-CFR-1910.120, Hazardous Waste Operations and Emergency Response

AOP-900.01, Fire Response Initial Actions, Rev 3

AOP-900.011, Yard Fire Zone Response Actions, Rev 0

MSDS Exxon Univolt 60

MSDS DIALA Oil AX

Specification, SP-0326, Main Power Transformer, Rev 1

VCS-ERP-0020, ERU Preplan Development and Control, Rev 0

VCS-ERP-0080, ERU Emergency Response Drill Management, Rev 1

CR-18-05943, Station Fire Preplan for Transformer Yard Not Adequate

STP-728.030, Reactor Building Fire Barrier Inspection, Rev 5B

STP-728.033, Turbine Building Fire Barrier Inspection, Rev 5J

STP-728.048, Intermediate Building Elevation 436 Fire Barrier Inspection, Rev 4G

STP-728.041 Control Building Elevation 505 & 482 Fire Barrier Inspection, Rev 5D

STP-728.032, Fire Service Pump House Building Fire Barrier Inspection, Rev 5B

71111.08 - Inservice Inspection Activities

Procedures

54-ISI-400-022, Multi-Frequency Eddy Current Examination of Tubing, Rev 22

Examination Technique Specification Sheet: ETSS1, ETSS2, ETSS3

PSEG-19, Boric Acid Corrosion Evaluation, Rev 2

QSP-504, Magnetic Particle Testing, Rev 9

SAP-1100, Boric Acid Corrosion Control Program, Rev 3

SGMP-100.006, Steam Generator Tube Inspection Eddy Current Data Analyst Guidelines, Rev 4

VCS-PTP-151.001A, Inspection for Boric Acid Corrosion, Rev 0

VCS-QSP-501, Solvent Removable Liquid Penetrant, Rev 1

WD-STD-1036, Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds in

Accordance with PDI-UT-2, Rev 4

WM-1.0, Welding Manual Procedure, Rev 16

17

NDE Examiner Qualifications:

Certificate of Personnel Qualification for Examiners: C3340, D4825, M6664, F1726, R3716

Curtiss-Wright Personnel Certification Statement (Pearson), dated 03/18/2017

Curtiss-Wright Personnel Certification Statement (Weidner), dated 11/7/2016

Sonic Systems International Certificate of Qualification (Michael), dated 08/16/2018

Sonic Systems International Certificate of Qualification (Shaugabay), dated 08/22/2018

System One Certificate of Method Qualification (Stone), Level II - Magnetic Particle, dated

01/04/2017

Condition Reports

CR-17-02169

CR-17-02244

CR-17-04662

CR-18-00305

CR-18-02808

CR-18-02857

CR-18-03144

CR-18-03647

CR-18-04456

CR-18-04457

CR-18-04458

CR-18-04459

CR-18-04644

Miscellaneous Documents

51-9289098, VC Summer 1RF24 Steam Generator Degradation Assessment (Fall 2018), Rev 1

51-9289100, Site Validation of Eddy Current Techniques for V C Summer 1RF24, Rev 0

51-9289124, VC Summer Unit 1 - RF24 ECT Inspection Plan, Rev 0

Certificate of Performance for Eddy Current Probe SNs: 754362, 754385

ECR 50933B, SW Cooler Return Piping Replacement

SAP-0158 Steam Generator Management Program, Rev 3

SG-SGMP-14-15, V.C. Summer Unit 1 Steam Generator Cycle 21 Condition Monitoring and

Cycles 22, 23 and 24 Operational Assessment, Rev 0

UT Report No. RF24-UT-001, dated 10/16/2018

Work Orders: 1703793-002, 1704591-002, 1814841-001

71111.12 - Maintenance Effectiveness

WO 1814841, Implement ECR 50933B to repair SW piping pinhole leaks

ECR 50933B, Modification to change SW piping configuration to reduce cavitation

FSAR Sections: 1.2.3.8.1, 3.7, 3.9.2, 9.2.1, 9.4.7, 18.2.33

Drawing, 302-222, sheets 1 & 3

CR-18-03942, XFN0045B failed to start on 9/26/18

71111.20 - Refueling and Other Outage Activities

GOP-2, Plant Startup and Heat-up (Mode 5 To Mode 3), Rev 18

GOP-3, Reactor Startup From Hot Standby To Startup (Mode 3 To Mode 2), Rev 13G

GOP-4B, Power Operation (Mode 1 - DESCENDING), Rev 1F

GOP-5, Reactor Shutdown From Startup To Hot Standby (Mode 2 To Mode 3), Rev 12C

GOP-6 Plant Shutdown From Hot Standby To Cold Shutdown (Mode 3 To Mode 5), Rev 14C

GOP-7 Core Refueling (Mode 5 To Mode 6 Defuel and Refuel To Mode 6), Rev 11G

SOP-101, Reactor Coolant System, Rev 30K

SOP-115, Residual Heat Removal, Rev 22E

SOP-117, Service Water System, Rev 24E

SOP-118, Component Cooling Water, Rev 19A

SOP-123, Spent Fuel Cooling System, Rev 16I

SOP-211, Emergency Feedwater System, Rev 14I

SOP-304,115KV 7.2KV OPERATIONS, Rev 14B

18

SOP-305, 480 Volt Engineered Safety Features Distribution, Rev 9F

SOP-306, Emergency Diesel Generator, Rev 19E

SOP-307, Diesel Generator Fuel Oil System, Rev 13D

SOP-310, Engineered Safety Features 120 VAC Instrumentation and Control Power System, Rev 12A

SOP-311, 125 VDC System, Rev 13

SSP-002, Planning and Scheduling of Outage Activities, Rev 6H

SSP-004, Outage Safety Review Guidelines, Rev 5D

SSP-010, Control of Critical Work Activities, Rev 1B

Core Reload Verification

MTF 18-13, Core Offload

MTF 18-15, Core Reload

SAP-0152, Fatigue Management and Work Hour Limits, Rev 10A

OAP-108.4, Operations Outage Control of Containment Penetrations, Rev 2D

DC00020-252, V.C. SUMMER Time To Boil Following Loss of Decay Heat Cooling in Mode 5

DC00020-198, Heat-Up Model for Water in the SFP, Reactor Cavity, and Reactor Vessel

71111.18 - Plant Modifications

EMP-100.004, Installation of Temporary Alternate Feed Cable for Spent Fuel Pumps, Rev 6b

SAP-364, Control of Temporary Cables, Rev

SS-200-927, Sheet 3, 480 Volt Load Center Relay and Breaker Settings (Breaker 1A3)

SS-200-927, Sheet 15, 480 Volt Load Center Relay and Breaker Settings (Breaker 1DA2)

SS-200-927, Sheet 17, 480 Volt Load Center Relay and Breaker Settings (Breaker DB2)

Request for Engineering Evaluation, REE22572, Emergency Power for SF Cooling Pumps

71151 - Performance Indicator Verification

Control Room Logs for October 1, 2017 through September 30, 2018

Licensee raw MSPI data for Months of October, 2017 through September, 2018

Procedures

VCS-EPAP-0106 Emergency Preparedness Performance Indicator Procedure. Rev. 2

Records and Data

DEP opportunities documentation for 4th quarter 2017, and 1st and 2nd quarters 2018

Siren test data for 4th quarter 2017, and 1st and 2nd quarters 2018

Drill & exercise participation records of ERO personnel for 4th quarter 2017, and 1st and 2nd

quarters 2018

Corrective Action Program Documents

CR-18-02305, EP to evaluate the process for selecting DEP opportunities

71152 - Problem Identification and Resolution

NAMCO Cavitation Analysis

Engineering Information Request 80756: Provide operational criteria for S-321- 001 (Pipe

Support Erection Standards) that provides an angular tolerance of +/- 3 degrees for liner

supports

19

71124.01 - Radiological Hazard Assessment and Exposure Controls

Procedures, Guidance Documents and Manuals

CMP-400.001, Excavation Backfill and Earthwork, Rev. 10

VCS-HPP-0160.002, Access Control of High Radiation, Locked High Radiation, and Very High

Radiation Areas, Rev. 1

VCS-HPP-0302, Radiation and Contamination Survey Techniques, Rev. 2

VCS-HPP-0303, Airborne Activity Sampling Techniques, Rev. 1

VCS-HPP-0158, Radioactive Material Control, Rev. 0

Records and Data

Air Sample Results, A S/G Platform, 10/21/18

Gamma Spec Analysis 21_2018-03-22_005, SB Pit Dirt

Gamma Spec Analysis 24_2018-03-06_001, Soil Sample #1 SE Corner

Gamma Spec Analysis 25_2018-03-06_001, Soil Sample #2 NE Corner

Gamma Spec Analysis 24_2018-10-24_004, Rock Sample From Under EQ Hatch

HPSS Administrative Instruction No.17-002, Fuel Cycle 24 Alpha Characterization, 08/10/17

Lapel Air Sample Results, Reactor Building Sump, Serial No. 25739, 10/12/18

National Source Tracking System Annual Inventory Reconciliation, 01/25/18

Radiological Survey VCS1-M-20181006-28, Auxiliary Building 463-02, 10/6/18

Radiological Survey VCS1-M-20180830-2, Auxiliary Building 463-02, 08/30/18

Radiological Survey VCS1-M-20180927-2, ISFSI, 09/27/18

Radiological Survey VCS1-M-20180730-3, ISFSI, 07/30/18

Radiological Survey VCS1-M-20181023-42, S/G Primary Platform and Bullpens, 10/23/18

Radiological Survey VCS1-M-20181022-5, RCDT-A Tagout, 10/21/18

RWP 18-04900, RF-24 S/G Eddy Current Activities, Rev. 1

RWP 18-04081, Aggressive Work in Posted Alpha Level 2 Areas - All Alpha Level 3 Work

Activities, Rev. 1

Source Inventory Sheet, Unit 1, 05/31/18

VC Summer Nuclear Station Work Order (W/O) 1802399-055

CAP Documents

CR-18-04734

CR-18-05037

71124.02 - ALARA

Procedures, Guidance Documents, and Manuals

SAP-0121, ALARA Committee, Revision 10, Change B

Records and Data

ALARA Committee Minutes, RVHR ALARA Plan Review

ALARA Plan, RF-24 Primary Steam Generator Work, RWP: 18-04900

ALARA Plan, RF-24 Secondary Steam Generator Work, RWP: 18-04902

ALARA Plan, RF-24 Primary Manways/Diaphragms/Weld Exam, RWP 18-4901

ALARA Post Job Review, RWP 17-04950, Reactor Vessel Head Replacement, 04/03/17

VCS ALARA Group Excellence Plan

V.C. Summer, RF-23 Post Outage Critique, ORVCH Disposal, June 28, 2017

20

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Procedures, Guidance Documents, and Manuals

SAP-0999, Corrective Action Program, Rev. 18, Change A

VCS-HPP-0154, Issuance and Control of Respiratory Protection Equipment, Rev. 0, Change A

VCS-HPP-0303, Airborne Activity Sampling Techniques, Rev. 1

VCS-HPP-0403, Radiological Controls for Nuclear Work Activities, Rev. 0

VCS-HPP-0416, Use and Control of HEPA Filtration Units, Vacuum Equipment, Fans, and

Portable A/C Units, Rev. 0

VCS-HPP-0163, Qualification Process for the Use of Respiratory Protection Equipment, Rev. 0,

Change C

VCS-HPP-0602, Fit Testing, Rev. 0, Change B

VCS-HPP-0633, Inspection, Maintenance, and Storage of Respiratory Protective Devices,

Rev. 0

VCS-HPP-0924, Operation and Maintenance of High Pressure SCBA Compressor, Rev. 0

Records and Data

EPT-11, C-Q-EP-SCBA, SCBA Qualification Records for selected personnel in Health Physics,

Instrumentation and Controls, and Mechanical Maintenance for 2018

HEPA Filter Integrity Test Results, HEPA Unit 17, 5/15/18

HEPA Filter Integrity Test Results, HEPA Unit 43, 10/10/18

Hydrostatic Retest Data Sheets and Visual Inspection Data Sheets for Bottles OP333747,

OP333748, and OP342361

Scott Air Supplied Products, Specialist Level Course certificates for personnel, 11/02/17

Scott Air Supplied Products Technician, Maintenance and Overhaul certificates for personnel,

01/12/18

SCOTT PosiChek3, Visual / Functional Test Results, for the following SCBA Nos.: 6, 01/22/16;

33, 07/27/15 and 06/21/17; and 64, 04/28/15 and 06/26/17

TRI Air Testing, Laboratory Reports, Compressed Air/Gas Quality Testing, Grade D Air, Bauer

Compressor # 30542, 07/27/17 and 08/02/18

VCS-HPP-0633, Attachment VI, Rev. 0, SCBA Inspection Log, 3rd Quarter 2018

VCS-HPP-0633, Attachment VII, Rev. 0, Monthly Breathing Air Cylinder Inspection Logs, June -

October 2018

CAP Documents

CR-17-03981

CR-18-01276

CR-18-01974

71124.04 - Occupational Dose Assessment

Procedures, Guidance Documents, and Manuals

TWR 2.1.3-17-017, Calibration Bias for Electronic Dosimetry (SRDs), 12/07/17

VCS-HPP-0157, Personnel Monitoring, Decontamination, and Skin Dose Determination, Rev. 1

VCS-HPP-0411, Monitoring Exposure with Multibadging, Rev. 0

VCS-HPP-0505, Issuance and Termination of Personnel Dosimetry, Rev. 0, Change B

VCS-HPP-0509, Leak Test and Calibration of Self-Reading Dosimetry, Rev. 0

21

VCS-HPP-0515, Interpretation of Bioassay Analysis, Rev 0, Change B

VCS-HPP-0517, Multiple Whole Body and Extremity Badging Exposure Calculations, Rev. 0

VCS-HPP-0518, Exposure Documentation Control, Rev. 0, Change B

VCS-HPP-0523, Quality Control and Whole Body Counting with the Chair Whole Body Counter,

Rev. 0

VCS-HPP-0717, Sample Collection, Preparation, and Analysis Techniques for Assuring

Compliance with 10 CFR 61

Records and Data

10 CFR 61 Analysis of 2017 DAW, December 17, 2017

2017 PCOs and PCEs report (undated)

2018 PCEs report (undated)

Dosimetry Self-Assessment, dated 10/23/2017

NVLAP, Certificate of Accreditation to ISO/IEC 17025:2005, Valid from January 7, 2018 to June

30, 2019

CAP Documents

CR-17-02677

CR-17-02994

CR-17-03725

CR-17-04838

CR-17-05410

CR-18-00244

CR-18-00484

CR-18-01957

CR-18-03344

CR-18-04227

CR-18-04305

CR-18-04306

CR-18-05090

71124.05 - Radiation Monitoring Instrumentation

Procedures, Guidance Documents, and Manuals

VCS-HPP-0522, Set-Up, Calibration, Quality Control and Operation of Gamma Spectroscopy

Systems with ORTEC Software, Rev. 0, Change C

VCS-HPP-0801, Counting Statistics and QC Testing for Health Physics Counting Systems,

Rev. 0, Change A

Data and Records

10CFR61 Analysis of 2017 DAW

ARGOS Personnel Contamination Monitor #1803-094, 05/25/18Calibration Review and Approval:

Gamma Det #25, 1LML0 07/09/18, #23 1LML 09/18/16, and

  1. 23 CHAR-01 08/13/18

HPP-0818 Attachment III HIDEX 02/18 - 03/18, 04/18 - 06/18

Quality Control: BC-4 #1029, 01/01 - 03/31/18, and 04/01 - 06/30/18

Thermo Fisher Scientific Calibration Certificates: Telepole II #428016-053 02/16/17; and

Telepole II #428016-015, 02/16/17

VCS-HPP-0522, Set-Up, Calibration, and Generation of Quality Control Bands for the Chair

Whole Body Counter ENCLOSURE A: Upper Energy Calibration 08/25/17 and 09/19/17,

and Stand-up Calibration Count 09/19/17

VCS-HPP-0611 Calibration Certificate: Ludlum 9-3 #333134, 09/13/18; Ludlum L-177 #266938

07/10/17, 07/02/18; and Thermo Fisher RO-20AA 02/08/17, 02/08/18

VCS-HPP-0648, Operation and Calibration of the Eberline PM-7: #585 11/09/17; #264 08/9/16,

07/17/17, and 11/30/17

22

VCS-HPP-0648, PM7 Calibration Data Sheet: #264, 08/09/16 and 08/09/17

VCS-HPP-0649, Calibration and Operation of the SAM Tool; #334 08/10/18,

VCS-HPP-0649, Small Articles Monitor Calibration Report: #334, 03/03/17, 08/08/17, and

08/08/18

VCS-HPP-0653, Calibration Certificates: Hand and Foot Monitor #490, 11/03/18 and 11/02/16

VCS-SAP-0501, Defective Instrument Report, ASP-1 #2194, 02/13/18; and ASP2E #1376,

06/15/18

CAP Documents

17-03725

17-04099

18-02292

18-02770

18-03590

18-03068

18-00377

71151 - Performance Indicator Verification

Procedures, Guidance Documents, and Manuals

SPIG-01, Station Performance Indicator Guidelines, Rev. 1

VCS-HPP-0242, Reporting NRC Performance Indicators, Rev. 0

Records and Data Reviewed

Annual Radioactive Effluent Release Report, Virgil C. Summer Nuclear Station, Unit 1, January 1 -

December 31, 2017

ED Dose and Dose Rate Alarm Summary Report (CY2017)

ED Dose and Dose Rate Alarm Summary Report (YTD2018)

ED DOSE RATE ALARM EVALUATION LOG (VCS_HPP-04 Enclosure B), March 2017 - October

2018

Gaseous and liquid effluent release report summaries for January 2018 - September 2018

Performance Indicator Data Radiation Safety, July 2017 - July 2018

71152 - Problem Identification and Resolution Trend Review

CR-17-00198, Operator identified a pinhole leak in the flange downstream of XVB03121A-

SW (A train EDG)

CR-18-02364, Operator identified a pinhole leak in field weld below XVB03123B-SW (B

train CCW Hx)

CR-18-02706, Operator identified a pinhole leak in pipe tee downstream of XVB03123B-SW

CR-18-02797, NRC identified a pinhole leak in the pipe tee downstream of XVB03123A-SW

(A train CCW Hx)

CR-18-02857, An additional pinhole leak was identified in the pipe tee downstream of

XVB03123A-SW

CR-18-03296, Operator identified a pinhole leak in the flange downstream of XVB03121B-

SW (B train EDG)

CR-18-03561, Operator identified 3 additional pinhole leaks (Total of 4) near XVB03121B-

SW

CR-18-03577, Operator identified 1 additional pinhole leak (Total of 5) near XVB03121B-SW

CR-18-03579, Operator identified 1 additional pinhole leak (Total of 6) near XVB03121B-SW

CR-18-03735, Operator identified 1 additional leak (Total of 7) near XVB03121B-SW

CR-18-03736, Operator identified 1 additional leak (Total of 8) near XVB03121B-SW

23

CR-18-03887, Flange downstream of XVB03121A-SW is not expected to survive another

operating cycle without pinhole leaks and requires replacement

CR-18-04083, Multiple SW pinhole leaks downstream of throttle butterfly valves created

operable but degraded conditions; corrective actions and bridging strategies required.

CR-18-04354, Additional pinhole leak identified on pipe tee below XVB03123A-SW

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