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=Text=
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{{#Wiki_filter:July 24, 2018 Mr. Brad Sawatzke, Chief Executive Officer Energy Northwest MD 1023 P.O. Box 968 Richland, WA 99352 SUBJECT: COLUMBIA GENERATING STATION  
{{#Wiki_filter:uly 24, 2018
- NRC INTEGRATED INSPECTION REPORT 05000397/2018002 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200035/201800 1 Dear Mr. Sawatzke
 
: On June 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Columbia Generating Statio On July 12, 2018, the NRC inspectors discussed the results of this inspection with Mr. G. Hettel, and other members of your staf The results of this inspection are documented in the enclosed repor NRC inspectors documented one finding of very low safety significance (Green) in this repor This finding involved a violation of NRC requirements
==SUBJECT:==
. The NRC is treating this violation as a non-cited violation (NCV)
COLUMBIA GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000397/2018002 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200035/2018001
consistent with Section 2.3.2.a of the Enforcement Polic If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20 555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and th e NRC R esident Inspector at the Columbia Generating Station
 
. If you disagree with a cross-cutting aspect assignment in this report, you should provi de a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and t he NRC Resident Inspector at the Columbia Generating Station
==Dear Mr. Sawatzke:==
.
On June 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Columbia Generating Station. On July 12, 2018, the NRC inspectors discussed the results of this inspection with Mr. G. Hettel, and other members of your staff. The results of this inspection are documented in the enclosed report.
B. Sawatzke 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."
 
NRC inspectors documented one finding of very low safety significance (Green) in this report.
 
This 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 the 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 IV; the Director, Office of Enforcement; and the NRC Resident Inspector at the Columbia Generating Station.
 
If you disagree with a cross-cutting aspect assignment 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 IV; and the NRC Resident Inspector at the Columbia Generating Station. 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,
Sincerely,
/RA/ Mark S. Haire, Chief Project Branch A Division of Reactor Projects Docket Nos. 50-397; 72-035 License No. NPF-21  
/RA/
Mark S. Haire, Chief Project Branch A Division of Reactor Projects Docket Nos. 50-397; 72-035 License No. NPF-21


===Enclosure:===
===Enclosure:===
Line 34: Line 42:


==Inspection Report==
==Inspection Report==
Docket Numbers: 05000397; 07200035 License Number s: NPF-21 Report Number s: 05000397/2018002; 07200035/2018001 Enterprise Identifier:
Docket Numbers: 05000397; 07200035 License Numbers: NPF-21 Report Numbers: 05000397/2018002; 07200035/2018001 Enterprise Identifier: I-2018-002-0020; 1-2018-001-0091 Licensee: Energy Northwest Facility: Columbia Generating Station and Independent Spent Fuel Storage Installation Location: Richland, Washington Inspection Dates: April 1, 2018 to June 30, 2018 Inspectors: G. Kolcum, Senior Resident Inspector L. Brandt, Resident Inspector L. Brookhart, Senior Inspector L. Carson II, Senior Health Physicist J. ODonnell, CHP, Health Physicist Approved By: M. Haire, Branch Chief Project Branch A Division of Reactor Projects Enclosure
I-2018-002-0020; 1-2018-001-0091 Licensee: Energy Northwest Facility: Columbia Generating Station and Independent Spent Fuel Storage Installation Location: Richland, Washington Inspection Dates:
April 1, 2018 to June 30, 2018 Inspectors:
G. Kolcum, Senior Resident Inspector L. Brandt, Resident Inspector L. Brookhart, Senior Inspector L. Carson II, Senior Health Physicist J. O'Donnell, CHP, Health Physicist Approved By:
M. Haire, Branch Chief Project Branch A Division of Reactor Projects
 
2


=SUMMARY=
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensee's performance by conducting an integrated inspection at Columbia Generating Station in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Findings and violations being considered in the NRC's assessment are summarized in the table below.
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Columbia Generating Station 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.


List of Findings and Violations Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems Green NCV 05000397/2018002
List of Findings and Violations Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System Cornerstone     Significance                                     Cross-cutting   Report Aspect           Section Mitigating       Green                                             H.12 - Avoid     71111.15 Systems          NCV 05000397/2018002-01                          Complacency Closed The inspectors reviewed a self-revealed, Green, non-cited violation of Technical Specification 5.4.1.a for the licensees failure to perform maintenance in accordance with written procedures appropriate to the circumstances. Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW-V-8B2, while operating a nearby demineralized water valve, DW-V-14B2, as part of work activities under Work Request (WR) 29127677, and rendered diesel generator 2 inoperable and unavailable.
-01 Closed H.12 - Avoid Complacency 71111.15 The inspectors reviewed a self-revealed, Green, non-cited violation of Technical Specification 5.4.1.a for the licensee's failure to perform maintenance in accordance with written procedures appropriate to the circumstances. Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW
-V-8B2, while operating a nearby demineralized water valve, DW
-V-14B2, as part of work activities under Work Request (WR) 29127677
, and rendered diesel generator 2 inoperable and unavailable
.
3


=PLANT STATUS=
=PLANT STATUS=


===The plant began the inspection period at 100 percent rated thermal power.
===The plant began the inspection period at 100 percent rated thermal power. On April 19, 2018, the reactor unit was down powered to 98 percent due to feedwater heater 2C level control failure. On April 20, 2018, the unit was down powered further to 85 percent for troubleshooting.


On April 19, 2018, the reactor unit was down powered to 98 percent due to feedwater heater 2C level control failure. On April 20, 2018, the unit was down powered further to 85 percent for troubleshooting. The unit returned to rated thermal power on April 21, 2018.
The unit returned to rated thermal power on April 21, 2018.


On April 27, 2018, the reactor unit was down powered to 85 percent for economic dispatch from Bonneville Power Administration. The unit returned to rated thermal power on April 30, 2018.
On April 27, 2018, the reactor unit was down powered to 85 percent for economic dispatch from Bonneville Power Administration. The unit returned to rated thermal power on April 30, 2018.


On May 18, 2018, the reactor unit automatically scrammed due to a load reject from a grid disturbance
On May 18, 2018, the reactor unit automatically scrammed due to a load reject from a grid disturbance. The unit was restarted and synched to the grid on May 24, 2018. Reactor power was raised to 65 percent on May 25, 2018, and remained at 65 percent for economic dispatch from Bonneville Power Administration. The unit returned to rated thermal power on June 11, 2018.
. The unit was restarted and synched to the grid on May 24, 2018.


Reactor power was raised to 65 percent on May 25, 2018, and remained at 65 percent for economic dispatch from Bonneville Power Administration. The unit returned to rated thermal power on June 11, 2018.
On June 12, 2018, the unit was down powered to 98 percent due to trip of the 2C feedwater heater. On June 14, 2018, the unit was down powered to 85 percent to repair the 2C feedwater level controller. On June 15, 2018, the unit was down powered to 78 percent due to subsequent trips of the 3C and 4C feedwater heaters. After maintenance, the reactor returned to rated thermal power on June 15, 2018.
 
On June 12, 2018, the unit was down powered to 98 percent due to trip of the 2C feedwater heater. On June 14, 2018, the unit was down powered to 85 percent to repair the 2C feedwater level controller. On June 15, 2018, the unit was down powered to 78 percent due to subsequent trip s of the 3C and 4C feedwater heaters. After maintenance, the reactor returned to rated thermal power on June 15, 2018.


==INSPECTION SCOPES==
==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
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.
-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.
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==
==REACTOR SAFETY==


==71111.01 - Adverse Weather Protection==
===71111.01Adverse Weather Protection Summer Readiness ===
 
===Summer Readiness===
{{IP sample|IP=IP 71111.01|count=1}}
{{IP sample|IP=IP 71111.01|count=1}}
The inspectors evaluated summer readiness of offsite and alternate alternating current power systems.
The inspectors evaluated summer readiness of offsite and alternate alternating current power systems.


==71111.04 - Equipment Alignment==
===71111.04Equipment Alignment Partial Walkdown ===
 
===Partial Walkdown===
{{IP sample|IP=IP 71111.04|count=4}}
{{IP sample|IP=IP 71111.04|count=4}}
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
Line 96: Line 80:
: (4) low pressure core spray system on June 1, 2018
: (4) low pressure core spray system on June 1, 2018


==71111.05AQ - Fire Protection Annual/Quarterly==
===71111.05AQFire Protection Annual/Quarterly Quarterly Inspection ===
 
{{IP sample|IP=IP 71111.05|count=4}}
===Quarterly Inspection===
{{IP sample|IP=IP 71111.05AQ|count=4}}
The inspectors evaluated fire protection program implementation in the following selected areas:
The inspectors evaluated fire protection program implementation in the following selected areas:
: (1) Fire Areas RC-14/1, RC-8/2, RC-5/1, and RC
: (1) Fire Areas RC-14/1, RC-8/2, RC-5/1, and RC-6/2; Divisions 1 and 2 switchgear and battery rooms; on April 6, 2018
-6/2; Divisions 1 and 2 switchgear and battery rooms
: (2) Fire Areas RC-4/1, RC-7/2, RC-9/2, and RC-19/2; Divisions 1 and 2 electrical equipment and reactor protection system rooms, remote shutdown room, and vital island corridor; on April 6, 2018
; on April 6, 2018
: (3) Fire Area TG1/2, reactor feed pump rooms, on April 18, 2018
: (2) Fire Areas RC
: (4) Fire Area RC-2/1, cable spreading room, on May 10, 2018
-4/1, RC-7/2, RC-9/2 , and RC-19/2; Divisions 1 and 2 electrical equipment and reactor protection system rooms, remote shutdown room, and vital island corridor
; on April 6, 2018
: (3) Fire Area TG1/2, reactor feed pump rooms
, on April 18, 2018
: (4) Fire Area RC
-2/1, cable spreading room, on May 10, 2018


==71111.06 - Flood Protection Measures==
===71111.06Flood Protection Measures Internal Flooding ===
 
===Internal Flooding===
{{IP sample|IP=IP 71111.06|count=1}}
{{IP sample|IP=IP 71111.06|count=1}}
The inspectors evaluated internal flooding mitigation protections in the reactor building 471 ft. level on June 22, 2018
The inspectors evaluated internal flooding mitigation protections in the reactor building 471 ft. level on June 22, 2018.
.


==71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance==
===71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification ===
 
===Operator Requalification===
{{IP sample|IP=IP 71111.11|count=1}}
{{IP sample|IP=IP 71111.11|count=1}}
The inspectors observed and evaluated a licensed operator requalification evaluated scenario on April 16, 2018.
The inspectors observed and evaluated a licensed operator requalification evaluated scenario on April 16, 2018.


Operator Performance (1 Sample) The inspectors observed and evaluated
Operator Performance (1 Sample)===
:
The inspectors observed and evaluated:
: (1) down power to 85 percent due to failure of feedwater heater 2C
, on April 20, 2018
: (2) startup to power increase
, on May 24, 2018


==71111.12 - Maintenance Effectiveness==
===(1) down power to 85 percent due to failure of feedwater heater 2C, on April 20, 2018
: (2) startup to power increase, on May 24, 2018


===Routine Maintenance Effectiveness (3 Sample s)  The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
===71111.12Maintenance Effectiveness Routine Maintenance Effectiveness ===
{{IP sample|IP=IP 71111.12|count=3}}
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
: (1) HT-TE-SW71/2, high pressure core spray heat tracing replacement, on April 23, 2018
: (1) HT-TE-SW71/2, high pressure core spray heat tracing replacement, on April 23, 2018
: (2) E-RLY-86TM, main generator lockout relay, on May 22, 2018
: (2) E-RLY-86TM, main generator lockout relay, on May 22, 2018
: (3) RPS-RLY-K10F for EOC-RPT, maintenance to disable end of cycle recirculation pump trip relay, on May 30, 2018
: (3) RPS-RLY-K10F for EOC-RPT, maintenance to disable end of cycle recirculation pump trip relay, on May 30, 2018


==71111.13 - Maintenance Risk Assessments and Emergent Work Control==
===71111.13Maintenance Risk Assessments and Emergent Work Control ===
 
{{IP sample|IP=IP 71111.13|count=2}}
(2 Sample s)  The inspectors evaluated the risk assessments for the following planned and emergent work activities:
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
: (1) yellow risk for heavy lifts at circulating water pump house on April 26, 2018
: (1) yellow risk for heavy lifts at circulating water pump house on April 26, 2018
: (2) yellow risk for standby gas treatment train A maintenance, week of May 14, 2018
: (2) yellow risk for standby gas treatment train A maintenance, week of May 14, 2018


==71111.15 - Operability Determinations and Functionality Assessments==
===71111.15Operability Determinations and Functionality Assessments ===
{{IP sample|IP=IP 71111.15|count=8}}
{{IP sample|IP=IP 71111.15|count=8}}
The inspectors evaluated the following operability determinations and functionality assessments:
The inspectors evaluated the following operability determinations and functionality assessments:
: (1) diesel generator 1 fuel oil pump 1B on April 1, 2018
: (1) diesel generator 1 fuel oil pump 1B on April 1, 2018
: (2) diesel generator 2 unplanned inoperability and unavailability for drain of jacket water on April 9, 2018
: (2) diesel generator 2 unplanned inoperability and unavailability for drain of jacket water on April 9, 2018
: (3) standby service water
: (3) standby service water 'B' pump house door gearbox on April 17, 2018
'B' pump house door gearbox on April 17, 2018
: (4) high pressure core spray power panel 4A voltage near minimum 120VAC on April 17, 2018
: (4) high pressure core spray power panel 4A voltage near minimum 120VAC on April 17, 2018
: (5) residual heat removal pump 1B relief valve on May 4, 2018
: (5) residual heat removal pump 1B relief valve on May 4, 2018
: (6) main steam relief valve 1B dual indication on May 18, 2018
: (6) main steam relief valve 1B dual indication on May 18, 2018
: (7) standby service water  
: (7) standby service water A spray ring header on May 24, 2018
'A' spray ring header on May 24, 2018
: (8) condensate pump 2C elevated water in oil, on May 24, 2018
: (8) condensat e pump 2C elevated water in oil, on May 24, 2018


==71111.18 - Plant Modifications==
===71111.18Plant Modifications ===
{{IP sample|IP=IP 71111.18|count=2}}
{{IP sample|IP=IP 71111.18|count=2}}
The inspectors evaluated the following temporary or permanent modifications:
The inspectors evaluated the following temporary or permanent modifications:
: (1) EC 17224, main transformer 1, 2, 3 alarm and trip function, on May 22, 2018
: (1) EC 17224, main transformer 1, 2, 3 alarm and trip function, on May 22, 2018
: (2) EC 17227, main transformer horizontal links bolting
: (2) EC 17227, main transformer horizontal links bolting, on May 22, 2018
, on May 22, 2018
 
==71111.19 - Post Maintenance Testing==


(8 Sample s)  The inspectors evaluated the following post maintenance tests:
===71111.19Post Maintenance Testing ===
: (1) diesel generator 1 fuel oil pump 1B
{{IP sample|IP=IP 71111.19|count=8}}
, on April 1, 2018
The inspectors evaluated the following post maintenance tests:
: (1) diesel generator 1 fuel oil pump 1B, on April 1, 2018
: (2) residual heat removal loop B operability test on April 1, 2018
: (2) residual heat removal loop B operability test on April 1, 2018
: (3) reactor building ventilation system operation on April 3, 2018
: (3) reactor building ventilation system operation on April 3, 2018
Line 179: Line 145:
: (8) main transformer 1 Buchholz relay testing on May 22, 2018
: (8) main transformer 1 Buchholz relay testing on May 22, 2018


==71111.20 - Refueling and Other Outage Activities==
===71111.20Refueling and Other Outage Activities ===
{{IP sample|IP=IP 71111.20|count=1}}
{{IP sample|IP=IP 71111.20|count=1}}
The inspectors evaluated forced outage activities following the load reject grid disturbance from May 18, 2018 to May 25, 2018.
The inspectors evaluated forced outage activities following the load reject grid disturbance from May 18, 2018 to May 25, 2018.


==71111.22 - Surveillance Testing==
===71111.22Surveillance Testing The inspectors evaluated the following surveillance tests:
 
Routine ===
The inspectors evaluated the following surveillance tests:
{{IP sample|IP=IP 71111.22|count=3}}
Routine===
{{IP sample|IP=IP 71111.12|count=3}}
: (1) ISP-SEIS-M201, Seismic System Channel Check, Revision 6, on April 23, 2018
: (1) ISP-SEIS-M201, Seismic System Channel Check, Revision 6, on April 23, 2018
: (2) OSP-ELEC-M703, HPCS Diesel Generator Monthly Operability Test, Revision 66, on April 25, 2018
: (2) OSP-ELEC-M703, HPCS Diesel Generator Monthly Operability Test, Revision 66, on April 25, 2018
: (3) ISP-RPS-S901, RPS (Channel A1) and EOC Recirc Pump Trip  
: (3) ISP-RPS-S901, RPS (Channel A1) and EOC Recirc Pump Trip - TGV Fast Closure RPS-PS-5A - CFT/CC, Revision 0, on May 7, 2018; and ISP RPS-S902, RPS (Channel A2) and EOC Recirc Pump Trip - TGV Fast Closure RPS-PS-5C - CFT/CC, Revision 0, on May 9, 2018 In-service (1 Sample)===
- TGV Fast Closure RPS-PS-5A - CFT/CC, Revision 0, on May 7, 2018
: (1) OSP-HPCS/IST-Q701, HPCS System Operability Test, Revision 53, on April 23, 2018
; and ISP RPS-S902, RPS (Channel A2) and EOC Recirc Pump Trip  
 
- TGV Fast Closure RPS
===Reactor Coolant System Leak Detection (1 Sample)===
-PS-5C - CFT/CC, Revision 0, on May 9, 2018 In-service (1 Sample)
: (1) daily reactor coolant system leak checks, shift and daily instrument checks
: (1) OSP-HPCS/IST-Q701, HPCS System Operability Test, Revision 53, on April 23, 2018 Reactor Coolant System Leak Detection (1 Sample)
: (1) daily reactor coolant system leak checks , shift and daily instrument checks (Modes 1, 2, 3) on June 25, 2018


==71114.06 - Drill Evaluation==
===(Modes 1, 2, 3) on June 25, 2018


===Drill/Training Evolution===
===71114.06Drill Evaluation Drill/Training Evolution ===
{{IP sample|IP=IP 71114.06|count=1}}
{{IP sample|IP=IP 71114.06|count=1}}
The inspectors evaluated the emergency preparedness training drill on May 15, 2018
The inspectors evaluated the emergency preparedness training drill on May 15, 2018.


==RADIATION SAFETY==
==RADIATION SAFETY==


==71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls==
===71124.02Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Radiological Work Planning ===
 
===Radiological Work Planning===
{{IP sample|IP=IP 71124.02|count=1}}
{{IP sample|IP=IP 71124.02|count=1}}
The inspectors evaluated the licensees radiological work planning by reviewing the following activities:
: (1) RWP 30004209, EDR Tank-5 Desludge
: (2) RWP 30004210, EDR Tank-5 Desludge High Risk
: (3) RWP 30003882, Main Steam Relief Valves
: (4) RWP 30003098, Wetwell Cleanup and Inspection
: (5) RWP 30003873, Drywell Shielding Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)===
The inspectors evaluated dose estimates and exposure tracking.


The inspectors evaluated the licensee's radiological work planning by reviewing the following activities:
======71124.04Occupational Dose Assessment Source Term Characterization ===
: (1) RWP 30004209, EDR Tank
-5 Desludge
: (2) RWP 30004210
, EDR Tank-5 Desludge High Risk
: (3) RWP 30003882
, Main Steam Relief Valves
: (4) RWP 30003098
, Wetwell Cleanup and Inspection
: (5) RWP 30003873
, Drywell Shielding Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)===
The inspectors
 
===evaluated dose estimates and exposure tracking.
 
==71124.04 - Occupational Dose Assessment==
 
===Source Term Characterization===
{{IP sample|IP=IP 71124.04|count=1}}
{{IP sample|IP=IP 71124.04|count=1}}
The inspectors evaluated the licensees source term characterization.


The inspectors evaluated the licensee's source term characterization
External Dosimetry (1 Sample)===
. External Dosimetry (1 Sample)===
The inspectors evaluated the licensees external dosimetry program.
The inspectors


===evaluated the licensee's external dosimetry program
===Internal Dosimetry (1 Sample)===
. Internal Dosimetry (1 Sample)===
The inspectors evaluated the licensees internal dosimetry program.
The inspectors


===evaluated the licensee's internal dosimetry program
===Special Dosimetric Situations (1 Sample)===
.
The inspectors evaluated the licensees performance for special dosimetry situations.
Special Dosimetric Situations (1 Sample)===
The inspectors evaluated the licensee's performance for special dosimetr y situations


==OTHER ACTIVITIES  
=====OTHER ACTIVITIES - BASELINE==
- BASELINE==
71151-Performance Indicator Verification (5 Samples)  The inspectors verified licensee performance indicators submittals listed below:
: (1) MS06:  Emergency AC Power Systems (07/01/2017
-06/30/2018)
: (2) MS07:  High Pressure Injection System s (07/01/2017
-06/30/2018)
: (3) MS08:  Heat Removal Systems (07/01/2017
-06/30/2018)
: (4) MS09:  Residual Heat Removal Systems (07/01/2017
-06/30/2018)
: (5) MS10:  Cooling Water Support Systems (07/01/2017
-06/30/2018)


==71152 - Problem Identification and Resolution==
===71151Performance Indicator Verification ===
{{IP sample|IP=IP 71151|count=5}}
The inspectors verified licensee performance indicators submittals listed below:
: (1) MS06:    Emergency AC Power Systems (07/01/2017-06/30/2018)
: (2) MS07:    High Pressure Injection Systems (07/01/2017-06/30/2018)
: (3) MS08:    Heat Removal Systems (07/01/2017-06/30/2018)
: (4) MS09:    Residual Heat Removal Systems (07/01/2017-06/30/2018)
: (5) MS10:    Cooling Water Support Systems (07/01/2017-06/30/2018)


===Semiannual Trend Review===
===71152Problem Identification and Resolution Semiannual Trend Review ===
{{IP sample|IP=IP 71152|count=1}}
{{IP sample|IP=IP 71152|count=1}}
The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more significant safety issue. The inspectors reviewed a negative trend in human performance and documented one observation.


The inspectors reviewed the licensee's corrective action program for trends that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (1 Sample)===
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
: (1) Independent Spent Fuel Storage Installation cask stuck in reactor building, on April 7, 2018


The inspectors reviewed a negative trend in human performance and documented one observation.
===71153Follow-up of Events and Notices of Enforcement Discretion Events ===
{{IP sample|IP=IP 71153|count=1}}
The inspectors evaluated the plant scram from a load reject due to a grid disturbance and the licensees response on May 18, 2018.


Annual Follow
==OTHER ACTIVITIES==
-up of Selected Issues (1 Sample)  The inspectors reviewed the licensee's implementation of its corrective action program related to the following issues:
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants The inspectors evaluated the licensees operation of the Independent Spent Fuel Storage Installation (ISFSI) from April 2 through April 5, 2018, on-site at Columbia Generating Station (CGS).
: (1) Independent Spent Fuel Storage Installation cask stuck in reactor building
, on April 7, 2018 71153-Follow-up of Events and Notices of Enforcement Discretion Events (1 Sample) The inspectors evaluated the plant scram f rom a load reject due to a grid disturbance and the licensee's response on May 18, 2018
.


==OTHER ACTIVITIES==
The CGS ISFSI was licensed as a general Part 72 license and utilized the Holtec HI-STORM 100 System, approved under Certificate of Compliance 1014, License Amendment 9, Revision 1, and Final Safety Analysis Report (FSAR), Revision 13. The CGS had been loading HI-STORM 100S Version 243 overpacks containing the Multi-Purpose Canister, MPC-68, and more recently the MPC-68M. CGSs ISFSI contained a total of 39 HI-STORM overpacks at the time of the routine inspection. CGS was in the middle of its 2018 loading campaign. Inspectors were onsite to observe loading activities associated with cask Number 40. The CGS planned to complete an additional 5 canisters by the end of the campaign, increasing the total number of casks to 45 at the ISFSI.
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants The inspectors evaluated the licensee's operation of the Independent Spent Fuel Storage Installation (ISFSI) from April 2 through April 5, 2018
, on-site at Columbia Generating Station (CGS). The CGS ISFSI was licensed as a general Part 72 license and utilized the Holtec HI-STORM 100 System, approved under Certificate of Compliance 1014, License Amendment 9, Revision 1
, and Final Safety Analysis Report (FSAR), Revision 13. The CGS had been loading HI
-STORM 100S Version 243 overpacks containing the Multi
-Purpose Canister, MPC
-68, and more recently the MPC
-68M. CGS's ISFSI contained a total of 39 HI-STORM overpacks at the time of the routine inspection. CGS was in the middle of its 2018 loading campaign. Inspectors were onsite to observe loading activities associated with cask Number 40. The CGS planned to complete an additional 5 canisters by the end of the campaign, increasing the total number of casks to 45 at the ISFSI.


The ISFSI activities specifically reviewed during the on
The ISFSI activities specifically reviewed during the on-site inspection and the subsequent in-office review included:
-site inspection and the subsequent in-office review included:
: (1) Evaluated and observed cask transportation operations.
: (1) Evaluated and observed cask transportation operations.
: (2) Reviewed the licensee's loading, processing, and heavy load procedures associated with their current dry fuel storage campaign.
: (2) Reviewed the licensee's loading, processing, and heavy load procedures associated with their current dry fuel storage campaign.
: (3) Reviewed the licensee's corrective action program implementation for ISFSI operations since the last routine ISFSI inspection
: (3) Reviewed the licensees corrective action program implementation for ISFSI operations since the last routine ISFSI inspection, which was completed in July 2016.
, which was completed in July 201 6.
: (4) Reviewed quality assurance (QA) program implementation, including recent QA audits, surveillances, receipt inspection, and quality control activities.
: (4) Reviewed quality assurance (QA) program implementation, including recent QA audits, surveillances, receipt inspection, and quality control activities.
: (5) Reviewed documentation related to Technical Specification (TS) required operational surveillance activities and FSAR required annual maintenance activities.
: (5) Reviewed documentation related to Technical Specification (TS) required operational surveillance activities and FSAR required annual maintenance activities.
: (6) Reviewed the licensee's radiological monitoring data for the calendar years 2016 and 20 17.
: (6) Reviewed the licensees radiological monitoring data for the calendar years 2016 and 2017.
: (7) Reviewed spent fuel documentation for the canisters loaded since the last routine ISFSI inspection (Canisters 37
: (7) Reviewed spent fuel documentation for the canisters loaded since the last routine ISFSI inspection (Canisters 37-40) to confirm the fuel met all TS requirements for storage at the ISFSI.
-40) to confirm the fuel met all TS requirements for storage at the ISFSI.
: (8) Reviewed annual maintenance activities for heavy lifting components which included special lifting devices, the vertical cask transporter, and the sites single-failure proof cask handling crane.
: (8) Reviewed annual maintenance activities for heavy lifting components which included special lifting devices, the vertical cask transporter, and the site's single-failure proof cask handling crane.
: (9) Reviewed all 72.48 safety evaluations/screenings for changes made to the licensees ISFSI operations in accordance with Inspection Procedure 60857 since the last routine ISFSI inspection.
: (9) Reviewed all 72.48 safety evaluations/screenings for changes made to the licensee' s ISFSI operations in accordance with Inspection Procedure 60857 since the last routine ISFSI inspection.
: (10) Reviewed all changes made to the licensees 72.212 Report from Revision 9 to Revision 10 under the licensees 72.48 program in accordance with Inspection Procedure 60857.
: (10) Reviewed all changes made to the licensee's 72.212 Report from Revision 9 to Revision 10 under the licensee's 72.48 program in accordance with Inspection Procedure 60857.


The inspectors did not identify any issues of concerns requiring documentation.
The inspectors did not identify any issues of concerns requiring documentation.


==INSPECTION RESULTS==
==INSPECTION RESULTS==
Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems  Green NCV 05000397/2018002
Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System Cornerstone         Significance                                   Cross-cutting Report Aspect           Section Mitigating         Green                                         H.12 - Avoid     71111.15 Systems            NCV 05000397/2018002-01                        Complacency Closed The inspectors reviewed a self-revealed, Green, non-cited violation of Technical Specification 5.4.1.a for the licensees failure to perform maintenance in accordance with written procedures appropriate to the circumstances. Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW-V-8B2, while operating a nearby demineralized water valve, DW-V-14B2, as part of work activities under Work Request (WR) 29127677, and rendered diesel generator 2 inoperable and unavailable.
-01 Closed  H.12 - Avoid Complacency 71111.15 The inspectors reviewed a self
 
-revealed, Green, non
=====Description:=====
-cited violation of Technical Specification 5.4.1.a for the licensee's failure to perform maintenance in accordance with written procedures appropriate to the circumstances. Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW-V-8B2, while operating a nearby demineralized water valve, DW
On April 9, 2018, while operating demineralized water valve DW-V-14B2, maintenance personnel inadvertently bumped and partially opened diesel cooling water valve DCW-V-8B2. The maintenance personnel completed their work activities, cleaned up the work area, and returned to the shop, unaware that their actions resulted in the partial opening of DCW-V-8B2. Meanwhile, the accidental opening of this diesel cooling water valve caused the diesel generator 2 diesel cooling water expansion tank to drain into a nearby floor drain.
-V-14B2, as part of work activities under Work Request (WR) 29127677
 
, and rendered diesel generator 2 inoperable and unavailable
Approximately 40 minutes later, the main control room received a diesel generator 2 local panel trouble alarm. Operations personnel responded to the alarm, found the diesel cooling water valve out of position (partially open), and closed the valve. During this event, the tank level reached -4.5 inches, which is outside the normal standby lineup band of +2 to +6 inches.
. Description
 
:  On April 9, 2018, while operating demineralized water valve DW
This rendered diesel generator 2 inoperable and caused an unplanned entry into Technical Specification 3.8.1 for one required diesel generator inoperable. The licensee restored the required water level within 40 minutes of declaring the diesel inoperable. The licensee then verified the diesel was in the proper standby lineup and restored the diesel to operable status approximately 2 hours later. Subsequently, the licensee initiated an investigation of the event that stated the diesel generator was rendered unavailable because it would not have been able to complete its 24-hour mission time with the open diesel cooling water valve. The diesel generator would have started, loaded, and overheated in approximately 10 minutes without a credited cooling water makeup source. Total unavailability time accrued was 86 minutes.
-V-14B2, maintenance personnel inadvertently bumped and partially opened diesel cooling water valve DCW-V-8B2. The maintenance personnel completed their work activities, cleaned up the work area, and returned to the shop
 
, unaware that their actions resulted in the partial opening of DCW-V-8B2. Meanwhile, the accidental opening of this diesel cooling water valve caused the diesel generator 2 diesel cooling water expansion tank to drain into a nearby floor drain. Approximately 40 minutes later, the main control room received a diesel generator 2 local panel trouble alarm. Operations personnel responded to the alarm, found the diesel cooling water valve out of position (partially open), and closed the valve. During this event, the tank level reached  
Procedure 1.3.81, Maintaining Plant Component Status Control, Revision 12, ensures plant component status control is maintained. Step 5.5.2 states that personnel performing work in the plant that are given permission to manipulate the plant are required to accept responsibility for, and are accountable for, maintaining plant component status control. Step 6.6.2.d states, in part, that electrical, mechanical, and instrumentation and control maintenance personnel manipulate components only as specified in approved procedures and work packages that have been authorized by the shift manager or designee.
-4.5 inches, which is outside the normal standby lineup band of +2 to +6 inches. This rendered diesel generator 2 inoperable and caused an unplanned entry into Technical Specification 3.8.1 for one required diesel generator inoperable. The licensee restored the required water level within 40 minutes of declaring the diesel inoperable. The licensee then verified the diesel was in the proper standby lineup and restored the diesel to operable status approximately 2 hours later. Subsequently, the licensee initiated an investigation of the event that stated the diesel generator was rendered unavailable because it would not have been able to complete its 24
 
-hour mission time with the open diesel cooling water valve. The diesel generator would have started, loaded, and overheated in approximately 10 minutes without a credited cooling water makeup source. Total unavailability time accrued was 86 minutes. Procedure 1.3.81, "Maintaining Plant Component Status Control," Revision 12, ensures plant component status control is maintained. Step 5.5.2 states that personnel performing work in the plant that are given permission to manipulate the plant are required to accept responsibility for, and are accountable for
The inspectors noted that step 6.1 of Procedure MI-1.8, Conduct of Maintenance, Revision 70, directs all maintenance personnel to use and adhere to the station error prevention tools as described in Procedure STANDARD-01. Procedure STANDARD-01, Worker Error Prevention Tools, Revision 10, step 3.3 states, in part, that station personnel are responsible for performing work activities using the error prevention tools in accordance with this standard. Section 4.0 details the fundamental human performance tools workers apply during work activities to help them maintain positive control, regardless of their perception of the risk. For example, Section 4.2 describes the Take 2 error prevention tool.
, maintaining plant component status control. Step 6.6.2.d states, in part, that electrical, mechanical, and instrumentation and control maintenance personnel manipulate components only as specified in approved procedures and work packages that have been authorized by the shift manager or designee.


The inspectors noted that step 6.1 of Procedure MI-1.8, "Conduct of Maintenance," Revision 70, directs all maintenance personnel to use and adhere to the station error prevention tools as described in Procedure STANDARD
Step 4.2.1 states, in part, that Take 2 is a jobsite review done when first arriving at the jobsite.
-01. Procedure STANDARD
-01, "Worker Error Prevention Tools," Revision 10, step 3.3 states, in part, that station personnel are responsible for performing work activities using the error prevention tools in accordance with this standard. Section 4.0 details the fundamental human performance tools workers apply during work activities to help them maintain positive control, regardless of their perception of the risk. For example, Section 4.2 describes the Take 2 error prevention tool. Step 4.2.1 states, in part, that Take 2 is a jobsite review done when first arriving at the jobsite.


The worker develops an accurate understanding of- the work environment-by taking time to become acquainted with the immediate work area. Step 4.2.4.a instructs the worker to review the Take 2 lanyard or job aid. The Take 2 job aid lists several questions to engage the worker. Question 7 asks, "Is there a component misposition or bump hazard in the work area (2 ft zone)? If yes, engage Operations."  The licensee's event investigation indicated that the maintenance personnel conducted a Take 2 upon arriving at the jobsite but did not refer to their Take 2 job aid.
The worker develops an accurate understanding of the work environment by taking time to become acquainted with the immediate work area. Step 4.2.4.a instructs the worker to review the Take 2 lanyard or job aid. The Take 2 job aid lists several questions to engage the worker. Question 7 asks, Is there a component misposition or bump hazard in the work area (2 ft zone)? If yes, engage Operations. The licensees event investigation indicated that the maintenance personnel conducted a Take 2 upon arriving at the jobsite but did not refer to their Take 2 job aid.


Notwithstanding the plant procedure for preventing inadvertent operation of equipment, the inspectors noted that WR 29127677 did not contain the necessary controls to ensure that safety-related equipment was not adversely affected during maintenance.
Notwithstanding the plant procedure for preventing inadvertent operation of equipment, the inspectors noted that WR 29127677 did not contain the necessary controls to ensure that safety-related equipment was not adversely affected during maintenance.


Corrective Actions: The licensee's corrective actions included immediately closing the diesel cooling water valve, replenishing the diesel cooling water level, restoring diesel generator 2 to operable status, and completing an event investigation.
Corrective Actions: The licensees corrective actions included immediately closing the diesel cooling water valve, replenishing the diesel cooling water level, restoring diesel generator 2 to operable status, and completing an event investigation.
 
Corrective Action Reference(s): Action Request 378835


Corrective Action Reference(s):  Action Request 378835 Performance Assessment
=====Performance Assessment:=====
:  Performance Deficiency: The failure to perform maintenance in accordance with documented instructions appropriate to the circumstances was a performance deficiency.
Performance Deficiency: The failure to perform maintenance in accordance with documented instructions appropriate to the circumstances was a performance deficiency.


Screeni ng: The performance deficiency was more than minor, and therefore a finding, because it was associated with the configuration control attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage). Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW
Screening: The performance deficiency was more than minor, and therefore a finding, because it was associated with the configuration control attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage). Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW-V-8B2, while operating a nearby demineralized water valve, DW-V-14B2, as part of work activities under WR 29127677, and rendered diesel generator 2 inoperable and unavailable.
-V-8B2, while operating a nearby demineralized water valve, DW
-V-14B2, as part of work activities under WR 29127677 , and rendered diesel generator 2 inoperable and unavailable.


Significance:
Significance: The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609, Attachment 04, Initial Characterization of Findings, and Appendix A, The Significance Determination Process (SDP) for Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions, dated June 19, 2012. The inspectors determined the finding was of very low safety significance (Green) because all of the screening questions were answered in the negative.
The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609, Attachment 04, "Initial Characterization of Findings," and Appendix A, "The Significance Determination Process (SDP) for Findings At
-Power," Exhibit 2, "Mitigating Systems Screening Questions," dated June 19, 2012. The inspectors determined the finding was of very low safety significance (Green) because all of the screening questions were answered in the negative.


Cross-cutting Aspect: This finding has a cross
Cross-cutting Aspect: This finding has a cross-cutting aspect in the area of human performance, avoid complacency, in that the licensee failed to implement appropriate error reduction tools and recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Specifically, licensee staff failed to implement the guidance found in the Take 2 card which demonstrated complacency in the perceived lack of intrusiveness of the work [H.12].
-cutting aspect in the area of human performance, avoid complacency, in that the licensee failed to implement appropriate error reduction tools and recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes.


Specifically, licensee staff failed to implement the guidance found in the Take 2 card which demonstrated complacency in the perceived lack of intrusiveness of the work [H.12].
=====Enforcement:=====
Enforcement
Violation: Technical Specification 5.4.1.a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2. Section 9.a of Appendix A of Regulatory Guide 1.33, Revision 2, requires, in part, that maintenance that can affect the performance of safety-related equipment should be performed in accordance with documented instructions appropriate to the circumstances. The licensee established Procedure 1.3.81, Maintaining Plant Component Status Control, Revision 12, to meet the Regulatory Guide 1.33 requirement. Step 6.6.2.d states, in part, that electrical, mechanical, and instrumentation and control maintenance personnel manipulate components only as specified in approved procedures and work packages that have been authorized by the shift manager or designee.
:  Violation: Technical Specification 5.4.1.a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2. Section 9.a of Appendix A of Regulatory Guide 1.33, Revision 2, requires, in part, that maintenance that can affect the performance of safety-related equipment should be performed in accordance with documented instructions appropriate to the circumstances. The licensee established Procedure 1.3.81, "Maintaining Plant Component Status Control," Revision 12, to meet the Regulatory Guide 1.33 requirement.


Step 6.6.2.d states, in part, that electrical, mechanical, and instrumentation and control maintenance personnel manipulate components only as specified in approved procedures and work packages that have been authorized by the shift manager or designee.
Contrary to the above, on April 9, 2018, the licensee did not manipulate components only as specified in approved procedures and work packages that had been authorized by the shift manager or designee. Specifically, the licensee inadvertently bumped and partially opened diesel cooling water valve DCW-V-8B2 as part of work activities under WR 29127677, and rendered diesel generator 2 inoperable and unavailable.


Contrary to the above, on April 9, 2018, the licensee did not manipulate components only as specified in approved procedures and work packages that had been authorized by the shift manager or designee. Specifically, the licensee inadvertently bumped and partially opened diesel cooling water valve DCW
Disposition: This violation is being treated as a non-cited violation, consistent with Section 2.3.2.a of the NRC Enforcement Policy.
-V-8B2 as part of work activities under WR 29127677
, and rendered diesel generator 2 inoperable and unavailable
. Disposition: This violation is being treated as a non
-cited violation
, consistent with Section 2.3.2.a of the NRC Enforcement Policy
.


Observation
Observation


==71152 - Semiannual Trend Review The inspectors performed an in==
==71152 - Semiannual Trend==


-depth review of the licensee's evaluation and corrective actions related to human performance issues. Since the end of refueling outage RF23 in June 2017 , the licensee has initiated multiple condition reports documenting human performance errors.
Review The inspectors performed an in-depth review of the licensees evaluation and corrective actions related to human performance issues. Since the end of refueling outage RF23 in June 2017, the licensee has initiated multiple condition reports documenting human performance errors. The licensee had also identified an adverse trend as documented in Action Requests 377654, 377416, and 378892.


The licensee had also identified an adverse trend as documented in Action Request s 377654, 377416, and 378892
This review focused on condition reports that documented plant component status control errors and failures to follow procedures. While many of the human performance issues were of minor significance, several resulted in NRC documented findings:
.
* FIN 05000397/2017004-02, Failure to Follow Procedure Results in Isolation of Reactor Feedwater Minimum Flow Lines. (ADAMS Accession Number ML18036B104)
* NCV 05000397/2018001-01, Failure to Follow Procedure Leads to Loss of Secondary Containment. (ADAMS Accession Number ML18116A407)
* NCV 05000397/2018002-01, Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System. (Section 71111.15 of this report)
The inspectors noted that the licensee appropriately considered extent of condition and cause when scheduling corrective action assignments. These actions included a site-wide initiative to identify and eliminate any potential plant component status control hazards and a supervisor observation blitz that focused on human performance behaviors such as pre-job briefs, use of the Take 2 card, procedure use and adherence, and supervisory oversight. The inspectors assessed the licensees problem identification threshold, cause analyses, and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition.


This review focused on condition reports that documented plant component status control errors and failures to follow procedures. While many of the human performance issues were of minor significance, several resulted in NRC documented findings:  FIN 05000397/2017004
==EXIT MEETINGS AND DEBRIEFS==
-02, "Failure to Follow Procedure Results in Isolation of Reactor Feedwater Minimum Flow Lines."  (ADAMS Accession Number ML18036B104)
The inspectors verified no proprietary information was retained or documented in this report.
NCV 05000397/201 8001-01 , "Failure to Follow Procedure Leads to Loss of Secondary Containment." (ADAMS Accession Number ML18116A407)  NCV 05000397/2018002
-01, "Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System."  (Section 71111.15 of this report)
The inspectors noted that the licensee appropriately considered extent of condition and cause when scheduling corrective action assignments. These actions included a site-wide initiative to identify and eliminat e any potential plant component status control hazards and a supervisor observation "blitz" that focused on human performance behaviors such as pre
-job briefs, use of the Take 2 card, procedure use and adherence, and supervisory oversig ht. The inspectors assessed the licensee's problem identification threshold, cause analyses, and compensatory actions.


The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition.
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
 
EXIT MEETIN GS 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 April 5, 2018, the inspectors presented the results from the routine ISFSI inspection to Mr. G. Hettel, Vice President of Operations (title at the time of the ISFSI inspection, but subsequently assumed the title of Senior Vice President and Chief Nuclear Officer), and other members of the licensee staff.


On April 5, 2018, the inspector s presented the results from the routine ISFSI inspection to Mr. G. Hettel, Vice President of Operations (title at the time of the ISFSI inspection, but subsequently assumed the title of Senior Vice President and Chief Nuclear Officer
On May 24, 2018, the inspectors presented the baseline radiation protection inspection results to Mr. G. Hettel, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.
), and other members of the licensee staff.


On May 24, 2018, the inspector s presented the baseline radiation protection inspection results to Mr. G. Hettel, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff. On July 12, 2018, the inspector s presented the quarterly resident inspector inspection results to Mr. G. Hettel , Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.
On July 12, 2018, the inspectors presented the quarterly resident inspector inspection results to Mr. G. Hettel, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.


=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=
Line 383: Line 300:
71111.01 - Adverse Weather Protection
71111.01 - Adverse Weather Protection
Action Requests
Action Requests
379022 381176   Procedures
379022                 381176
  (Number) Title Revision 13.1.1 Classifying the Emergency
Procedures
4 9 13.1.1A Classifying the Emergency  
  (Number)                     Title                                           Revision
- Technical Bases
13.1.1                       Classifying the Emergency                         049
33 ABN-ELEC-GRID Degraded Off Site Power Grid
13.1.1A                     Classifying the Emergency - Technical Bases       033
10 SOP-HOTWEATHER
ABN-ELEC-GRID               Degraded Off Site Power Grid                     010
-OPS Hot Weather Operations
SOP-HOTWEATHER-OPS           Hot Weather Operations                           006
6 SOP-WARMWEATHER
SOP-WARMWEATHER-             Warm Weather Operations                           015
-OPS Warm Weather Operations
OPS
15  71111.04 - Equipment Alignment
71111.04 - Equipment Alignment
Procedures
Procedures
  (Number) Title Revision 5.5.1 Overriding ECCS Valve Logic to Allow
  (Number)                     Title                                           Revision
Throttling RPV Injection
5.5.1                       Overriding ECCS Valve Logic to Allow Throttling  006
006 OSP-LPCS-M102 LPCS Valve Lineup
RPV Injection
2 S OP-LPCS-LU LPCS Valve and Breaker Lineup
OSP-LPCS-M102               LPCS Valve Lineup                                 002
003 SOP-LPCS-STBY Placing LPCS in Standby Status
SOP-LPCS-LU                 LPCS Valve and Breaker Lineup                     003
2 SOP-DG-DCW Emergency Diesel Generator Jacket Water Cooling
SOP-LPCS-STBY               Placing LPCS in Standby Status                   002
014 SOP-DG1-LU Emergency Diesel
SOP-DG-DCW                   Emergency Diesel Generator Jacket Water Cooling   014
Generator (Div 1) Valve and Power Supply Lineup
SOP-DG1-LU                   Emergency Diesel Generator (Div 1) Valve and     006
006 SOP-DG2-LU Emergency Diesel Generator (Div 2) Valve and Power Supply Lineup
Power Supply Lineup
006 SOP-DG3-LU High Pressure Core Spray Diesel Generator Valve and Power Supply Lineup
SOP-DG2-LU                   Emergency Diesel Generator (Div 2) Valve and     006
007  Miscellaneous Documents  
Power Supply Lineup
(Number) Title Revision Final Safety Analysis Report
SOP-DG3-LU                   High Pressure Core Spray Diesel Generator Valve   007
064  71111.05AQ  
and Power Supply Lineup
- Fire Protection Annual/Quarterly
Miscellaneous Documents
(Number)                     Title                                         Revision
Final Safety Analysis Report                     064
71111.05AQ - Fire Protection Annual/Quarterly
Action Requests
Action Requests
378829 379167 379972
378829                 379167                 379972
Procedures
Procedures
  (Number) Title Revision 1.3.10C Control of Transient Combustibles
  (Number)                     Title                                             Revision
20 PFP-RW-467 Radwaste 467
1.3.10C                     Control of Transient Combustibles                   020
005 PFP-RW-484-487 Radwaste 484
PFP-RW-467                   Radwaste 467                                         005
-487 005 1.3.10A Control of Ignition Sources
PFP-RW-484-487               Radwaste 484-487                                     005
17 FPP-1.6 Combustible Loading Calculation Control
1.3.10A                     Control of Ignition Sources                         017
2 FPP-2.2.12 Annual Fire Door Operability Test 00 5 FPP-2.2.7 Fire Protection Water System Inspections
FPP-1.6                     Combustible Loading Calculation Control             002
6 PFP-TG-441-456 Turbine Generator 441
FPP-2.2.12                   Annual Fire Door Operability Test                   005
-456 008 Miscellaneous Documents  
FPP-2.2.7                   Fire Protection Water System Inspections             006
(Number) Title Revision FSAR Fire Hazards Analysis
PFP-TG-441-456               Turbine Generator 441-456                           008
BIP 17-0613 Barrier Impairment Permit
Miscellaneous Documents
BIP 17-0614 Barrier Impairment Permit
(Number)                     Title                                             Revision
BIP 17-0615 Barrier Impairment Permit
FSAR Fire Hazards Analysis
BIP 17-0616 Barrier Impairment Permit
BIP 17-0613                   Barrier Impairment Permit
BIP 17-0643 Barrier Impairment Permit
BIP 17-0614                   Barrier Impairment Permit
BIP 17-0662 Barrier Impairment Permit
BIP 17-0615                   Barrier Impairment Permit
BIP 18-0096 Barrier Impairment Permit
BIP 17-0616                   Barrier Impairment Permit
BIP 18-0097 Barrier Impairment Permit
BIP 17-0643                   Barrier Impairment Permit
BIP 18-0111 Barrier Impairment Permit
BIP 17-0662                   Barrier Impairment Permit
BIP 18-0017 Barrier Impairment Permit
BIP 18-0096                   Barrier Impairment Permit
BIP 18-0018 Barrier Impairment Permit
BIP 18-0097                   Barrier Impairment Permit
BIP 18-0019 Barrier Impairment Permit
BIP 18-0111                   Barrier Impairment Permit
BIP 18-0029 Barrier Impairment Permit
BIP 18-0017                   Barrier Impairment Permit
BIP 18-0031 Barrier Impairment Permit
BIP 18-0018                   Barrier Impairment Permit
BIP 18-0037 Barrier Impairment Permit BIP 18-0041 Barrier Impairment Permit
BIP 18-0019                   Barrier Impairment Permit
BIP 18-0050 Barrier Impairment Permit
BIP 18-0029                   Barrier Impairment Permit
CALC FP-02-85-03 Combustible Loading Calculation
BIP 18-0031                   Barrier Impairment Permit
010  71111.06 - Flood Protection Measures
BIP 18-0037                   Barrier Impairment Permit
BIP 18-0041                   Barrier Impairment Permit
BIP 18-0050                   Barrier Impairment Permit
CALC FP-02-85-03             Combustible Loading Calculation                     010
71111.06 - Flood Protection Measures
Action Requests
Action Requests
378764     Procedures
378764
  (Number) Title Revision ABN-FLOODING Flooding 0 20 ME-02-02-02 Calculation for Reactor Building Flooding Analysis
Procedures
4 PFP-RB-572 Reactor 572
  (Number)                     Title                                             Revision
4  71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
ABN-FLOODING                 Flooding                                             020
ME-02-02-02                 Calculation for Reactor Building Flooding Analysis   004
PFP-RB-572                   Reactor 572                                         004
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Action Requests
Action Requests
379240
379240
Procedures
Procedures
  (Number) Title Revision 13.1.1 Classifying the Emergency
  (Number)                     Title                                     Revision
048 OI-0 9 Operations Standards and Expectation
13.1.1                       Classifying the Emergency                   048
s 0 64 1.3.1 Operating Policy, Programs, and Practices
OI-09                        Operations Standards and Expectations      064
26 5.1.1 RPV Control
1.3.1                       Operating Policy, Programs, and Practices   126
21 5.2.1 Primary Containment Control
5.1.1                       RPV Control                                 021
2 7 5.3.1 Secondary Containment Control 0 20  Miscellaneous Documents  
5.2.1                       Primary Containment Control                 027
(Number) Title Revision LR002398 Cycle 18-2 Evaluated Scenario
5.3.1                       Secondary Containment Control               020
001  Crew F Evaluated Scenario Cycle 18
Miscellaneous Documents
-2 4.0 Critique Summary
(Number)                     Title                                   Revision
000  71111.12 - Maintenance Effectiveness
LR002398                     Cycle 18-2 Evaluated Scenario             001
Crew F Evaluated Scenario Cycle 18-2       000
4.0 Critique Summary
71111.12 - Maintenance Effectiveness
Action Requests
Action Requests
380427     Work Orders
380427
2094222 02128788 29142758   Procedures
Work Orders
  (Number) Title Revision 1.5.11 Maintenance Rule Program
2094222             02128788               29142758
1 5 OI-53 Offsite Power
Procedures
1 4 SOP-RPS-OPS Reactor Protection System Operation
  (Number)                     Title                                     Revision
15 SOP-RPS-START Reactor Protection System Startup
1.5.11                       Maintenance Rule Program                   015
7  71111.13 - Maintenance Risk Assessments and Emergent Work Control
OI-53                       Offsite Power                               014
SOP-RPS-OPS                 Reactor Protection System Operation         015
SOP-RPS-START               Reactor Protection System Startup           007
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Work Orders
Work Orders
2085935     Procedures
2085935
  (Number) Title Revision 1.3.83 Protected Equipment Program
Procedures
26 1.5.14 Risk Assessment and Management for Maintenance/Surveillance Activities
  (Number)                     Title                                     Revision
040 1.5.11 Maintenance Rule Program
1.3.83                       Protected Equipment Program                 026
15 WCI-4 Online Work Control Process
1.5.14                       Risk Assessment and Management for         040
48 1.3.76 Integrated Risk Management
Maintenance/Surveillance Activities
50
1.5.11                       Maintenance Rule Program                   015
Miscellaneous Documents  
WCI-4                       Online Work Control Process                 048
(Number) Title Date High Risk Work Plan for Underwater Diving in Support of CW
1.3.76                       Integrated Risk Management                 050
-P-1C 01/16/2018
Miscellaneous Documents
(Number)                       Title                                               Date
High Risk Work Plan for Underwater Diving in     01/16/2018
Support of CW-P-1C
71111.15 - Operability Determinations and Functionality Assessments
71111.15 - Operability Determinations and Functionality Assessments
Action Requests
Action Requests
306206 371516 378475 378835 378990 379120 379244 379504 380257 380307   Work Orders
306206                   371516                   378475               378835
2123413 02126245   Procedures
378990                   379120                   379244               379504
  (Number) Title Revision 1.3.66 Operability and Functionality Evaluation
380257                   380307
34 10.25.53 Inspection of Lighting Panels and Power Panels
Work Orders
13 OI-0 9 Operations Standards and Expectation
2123413               02126245
6 9 OI-14 Columbia Generating Station Operational Challenges and Risk Program
Procedures
1 6 OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and Power Availability Verification
  (Number)                       Title                                               Revision
31 OSP-ELEC-W10 1 Offsite Station Power Alignment Check
1.3.66                         Operability and Functionality Evaluation             034
31  Miscellaneous Documents  
10.25.53                       Inspection of Lighting Panels and Power Panels       013
(Number) Title Date EC 17110 EVAL DO-P-1B Failed to Start when Selected
OI-09                          Operations Standards and Expectation                 069
06/13/2018   71111.18 - Plant Modifications
OI-14                         Columbia Generating Station Operational               016
Challenges and Risk Program
OSP-ELEC-W102                 Electrical Distribution Subsystem Breaker             031
Alignment and Power Availability Verification
OSP-ELEC-W101                  Offsite Station Power Alignment Check                 031
Miscellaneous Documents
(Number)                       Title                                               Date
EC 17110 EVAL                   DO-P-1B Failed to Start when Selected           06/13/2018
71111.18 - Plant Modifications
Action Requests
Action Requests
380372 380404   Procedures
380372                   380404
  (Number) Title Revision ENG-DES-02 Columbia Generating Station Plant Modification Process 0 19 SWP-DES-01 Plant Modification and Configuration Control
Procedures
17  71111.19 - Post Maintenance Testing
  (Number)                       Title                                               Revision
ENG-DES-02                     Columbia Generating Station Plant Modification       019
Process
SWP-DES-01                     Plant Modification and Configuration Control         017
71111.19 - Post Maintenance Testing
Action Requests
Action Requests
378475 378488 378990 379191 379244
378475                   378488                   378990               379191
379244
Work Orders
Work Orders
2118434 02126245 02126307 0 2126372 02126372 02128700 02326309 29142042 Procedures
2118434               02126245                 02126307             02126372
(Number) Title  Revision OI-41 Operations Work Control Expectations
2126372               02128700                 02326309             29142042
63 SWP-TST-01 Post Maintenance Testing Program
17  71111.2 0 - Refueling and Other Outage Activities
Procedures
Procedures
  (Number) Title Revision 9.3.6 Estimated Critical Position Calculation
  (Number)                     Title                                             Revision
5  9.3.7 Reactor Shutdown and Startup Calculations
OI-41                        Operations Work Control Expectations                063
2  OCC-01 Outage Control Center Norms
SWP-TST-01                    Post Maintenance Testing Program                    017
6 OI-09 Operator Standards and Expectations
71111.20 - Refueling and Other Outage Activities
69 1.3.84 Reactivity Management Control
Procedures
4 3.1.1 Master Startup Checklist
(Number)                      Title                                              Revision
58 3.1.2 Reactor Plant Startup
9.3.6                         Estimated Critical Position Calculation             005
84 3.2.1 Normal Plant Shutdown
9.3.7                         Reactor Shutdown and Startup Calculations           002
88 3.3.1 Reactor Scram
OCC-01                       Outage Control Center Norms                         006
65 SOP-RHR-SDC RHR Shutdown Cooling
OI-09                         Operator Standards and Expectations                 069
28  71111.22 - Surveillance Testing
1.3.84                       Reactivity Management Control                       004
3.1.1                         Master Startup Checklist                             058
3.1.2                         Reactor Plant Startup                               084
3.2.1                         Normal Plant Shutdown                               088
3.3.1                         Reactor Scram                                       065
SOP-RHR-SDC                   RHR Shutdown Cooling                                 028
71111.22 - Surveillance Testing
Work Orders
Work Orders
2114669 02118974 02118950 02122396 02122397    Procedures
2114669               02118974                 02118950             02122396
  (Number) Title Revision RPS-PS-5A Instrument Master Data Sheet
2122397
013 OSP-INST-H101 Shift and Daily Instrument Checks (Modes 1,2,3)
Procedures
89  Miscellaneous Documents  
  (Number)                     Title                                             Revision
(Number) Title Revision CALC E/I-02-94-1334 Setting Range Determination for Instrument Loop
RPS-PS-5A                     Instrument Master Data Sheet                         013
MS-LIS-24B 001 LDCN 373682, LDCN-17-028 (LCS) License Document Change Notice SR 1.3.7.6.2 Frequency Change per SFCP
OSP-INST-H101                 Shift and Daily Instrument Checks (Modes 1,2,3)     089
STI-AR 365016 Surveillance Test Interval Change Form, Turbine Valve Surveillance
Miscellaneous Documents
 
(Number)                       Title                                             Revision
CALC E/I-02-94-1334           Setting Range Determination for Instrument Loop     001
MS-LIS-24B
LDCN 373682,                   License Document Change Notice SR 1.3.7.6.2
LDCN-17-028 (LCS)              Frequency Change per SFCP
STI-AR 365016                 Surveillance Test Interval Change Form, Turbine
Valve Surveillance
71114.06 - Drill Evaluation
71114.06 - Drill Evaluation
Procedures
Procedures
  (Number) Title Revision 13.10.1 Control Room Operation and Shift Manager Duties
  (Number)                       Title                                               Revision
35 13.10.2 TSC Manager Duties
13.10.1                         Control Room Operation and Shift Manager Duties         035
35 13.2.1 Emergency Exposure Levels, Protective Action Guides 0 22 13.2.2 Determining Protective Actions
13.10.2                         TSC Manager Duties                                     035
20 13.4.1 Emergency Notifications
13.2.1                         Emergency Exposure Levels, Protective Action           022
43 13.5.1 Local, Protected Area, or Site Evacuation
Guides
29 13.9.1 Environmental Field Monitoring Operations
13.2.2                         Determining Protective Actions                         020
45 13.10.9 Operations Support Center Manager and Staff Duties 0 49 13.11.1 EOF Manager Duties
13.4.1                         Emergency Notifications                                 043
44 13.13.1 Reentry Operations
13.5.1                         Local, Protected Area, or Site Evacuation               029
10 13.13.3 Intermediate Phase MUDAC Operations
13.9.1                         Environmental Field Monitoring Operations               045
18 13.13.4 After Action Reporting
13.10.9                         Operations Support Center Manager and Staff             049
10 13.14.9 Drill and Exercise Program
Duties
18  71124.02-Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
13.11.1                         EOF Manager Duties                                     044
13.13.1                         Reentry Operations                                     010
13.13.3                         Intermediate Phase MUDAC Operations                     018
13.13.4                         After Action Reporting                                 010
13.14.9                         Drill and Exercise Program                             018
71124.02Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
Action Requests
Action Requests
370540 377573 377743 377911 379078 354266 354320 375379 376734 365777   Procedures  
370540                 377573                   377743                 377911
  (Number) Title Revision 11.2.13.8 Airborne Radioactivity Surveys
379078                 354266                   354320                 375379
19 11.2.7.1 Area Posting
376734                 365777
43 HPI-0.19 Radiation Protection Standards and Expectations
Procedures
17 HPI-6.4 Administering an Occupational Radiation Exposure History File
  (Number)                   Title                                               Revision
25 SWP-RPP-01 Radiation Protection Program
11.2.13.8                   Airborne Radioactivity Surveys                         019
16 GEN-RPP-01 ALARA Program Description
11.2.7.1                   Area Posting                                           043
9 GEN-RPP-02 Radiological Planning and Control Process
HPI-0.19                   Radiation Protection Standards and                     017
34 GEN-RPP-13 Senior Site ALARA Committee
Expectations
13 GEN-RPP-14 Control of Temporary Shielding
HPI-6.4                     Administering an Occupational Radiation               025
14 PPM 11.2.2.7
Exposure History File
ALARA Procedure Analysis
SWP-RPP-01                 Radiation Protection Program                           016
12 PPM 11.2.2.8
GEN-RPP-01                 ALARA Program Description                             009
ALARA Engineering Analysis
GEN-RPP-02                 Radiological Planning and Control Process             034
7
GEN-RPP-13                 Senior Site ALARA Committee                           013
Procedures  
GEN-RPP-14                 Control of Temporary Shielding                         014
(Number) Title Revision PPM 11.2.2.11
PPM 11.2.2.7               ALARA Procedure Analysis                               012
Exposure Evaluations for Maintaining TEDE ALARA 00 8 PPM 11.2.2.12
PPM 11.2.2.8               ALARA Engineering Analysis                             007
Radiological Risk Assessment and Management
Procedures
8 PPM 11.2.2.13
(Number)                 Title                                       Revision
Flushing and Shielding Evaluations
PPM 11.2.2.11           Exposure Evaluations for Maintaining TEDE     008
2 PPM 11.2.2.14
ALARA
Radiological Planning and Reviews
PPM 11.2.2.12           Radiological Risk Assessment and               008
4 PPM 11.2.8.2
Management
Radiation Work Permit Preparation and Use
PPM 11.2.2.13           Flushing and Shielding Evaluations             002
1  Audits and Self
PPM 11.2.2.14           Radiological Planning and Reviews             004
-Assessments
PPM 11.2.8.2             Radiation Work Permit Preparation and Use     001
(Number) Title Date AR-SA No. 375350
Audits and Self-
Annual Radiation Protection Program Review
Assessments (Number)     Title                                         Date
03/30/2018 SR-18-01 Continuous Monitoring Report
AR-SA No. 375350         Annual Radiation Protection Program Review 03/30/2018
03/07/2018 SR-17-04 Continuous Monitoring Report
SR-18-01                 Continuous Monitoring Report               03/07/2018
11/02/2017 374279 Self-Assessment: 71124.02 ALARA
SR-17-04                 Continuous Monitoring Report               11/02/2017
2/15/2018 Radiation Work Permits  
374279                   Self-Assessment: 71124.02 ALARA           02/15/2018
(Number) Title Revision RWP 30004209
Radiation Work Permits
RWP 30004210
(Number)                 Title                                       Revision
RWP 30003882
RWP 30004209             2018 EDR Tank-5 Desludge                       001
RWP 30003098
RWP 30004210            2018 EDR Tank-5 Desludge High Risk             002
RWP 30003873
RWP 30003882            Main Steam Relief Valves                       001
2018 EDR Tank
RWP 30003098            Wetwell Cleanup and Inspection                 001
-5 Desludge
RWP 30003873            Drywell Shielding                             001
2018 EDR Tank
ALARA Planning,
-5 Desludge High Risk
In-Progress Reviews, and
Main Steam Relief Valves
Post-Job Reviews
Wetwell Cleanup and Inspection
(Number)                 Title                                         Date
Drywell Shielding
WO 2117848               Clean EDR Tank-5                           02/11/2018
1 00 2 00 1 00 1 00 1  ALARA Planning, In-Progress Reviews, and Post-Job Reviews  
WO 2088288              Suppression Pool Cleanup
(Number) Title Date WO 2117848
WO 2088287              Chemical Decon Cleanup
WO 2088288
WO 2077319              Drywell Shielding
WO 2088287
Miscellaneous Documents
WO 2077319
Senior Site ALARA Committee EDR Tank-5 Desludge
Clean EDR Tank
-5 Suppression Pool Cleanup
Chemical Decon
Cleanup Drywell Shielding
2/11/2018  Miscellaneous Documents
Senior Site ALARA Committee EDR Tank
-5 Desludge
2017 CGS Dose Report to the NRC
2017 CGS Dose Report to the NRC
05-2018 CGS 5 Year CRE Reduction Plan
05-2018 CGS 5 Year CRE Reduction Plan
R23 CRE Outage Report
R23 CRE Outage Report
 
71124.04Occupational Dose Assessment
71124.04-Occupational Dose Assessment
Action Requests
Action Requests
357564 360494 361631 365110 365545 365692 366701 367779 369181 374380 375624 376342 376403 377080 378436   Procedures  
357564               360494                 361631           365110
(Number) Title Revision 11.2.13.8 Airborne Radioactivity Surveys
365545               365692                 366701           367779
19 11.2.4.5 Whole Body Counts and Daily Checks Using the Renaissance FastScan
369181               374380                 375624           376342
16 11.2.6.7 Special Dosimetry
376403               377080                 378436
18 11.2.7.1 Area Posting
Procedures (Number)     Title                                         Revision
43 GEN-RPP-06 Dosimetry Program Description
11.2.13.8               Airborne Radioactivity Surveys                   019
13 HPI 4.30 Processing, Evaluation, and Reporting of DLR Exposure Data
11.2.4.5               Whole Body Counts and Daily Checks Using         016
14 HPI-0.19 Radiation Protection Standards and Expectations
the Renaissance FastScan
17 HPI-5.9 Evaluation of In
11.2.6.7               Special Dosimetry                               018
-Vivo Bioassay Results Following a Potential Intake
11.2.7.1               Area Posting                                     043
14 HPI-6.4 Administering an Occupational Radiation Exposure History File
GEN-RPP-06             Dosimetry Program Description                   013
25 SWP-RPP-01 Radiation Protection Program 0 16  Audits and Self
HPI 4.30               Processing, Evaluation, and Reporting of DLR     014
-Assessments
Exposure Data
(Number) Title Date 374271 Self-Assessment: 71124.04 Occupational Dose Assessment
HPI-0.19               Radiation Protection Standards and               017
2/15/2018 374020 Self-Assessment: Site Bioassay Program
Expectations
11/15/2017 Miscellaneous Documents  
HPI-5.9                 Evaluation of In-Vivo Bioassay Results           014
(Number) Title Date Data Verification (REIRS Submission)
Following a Potential Intake
03/12/2018
HPI-6.4                 Administering an Occupational Radiation         025
100518-0 NVLAP Scope and ISO 17025 Certificate for
Exposure History File
Landauer 01/01/2018
SWP-RPP-01             Radiation Protection Program                     016
15-02 Bases for Neutron Correction Factors for OSLN and Survey Instruments
Audits and Self-
04/03/2015
Assessments (Number)   Title                                           Date
 
Self-Assessment: 71124.04 Occupational Dose
Miscellaneous Documents  
374271                                                                02/15/2018
(Number) Title Date DAC-0446 Scaling Factor Determination at Columbia Generating Station
Assessment
- 2017 02/28/ 2018
374020                 Self-Assessment: Site Bioassay Program       11/15/2017
VSDS_Pros-M-20171223-2 RW 487 Monthly Survey
Miscellaneous Documents
2/23/2017
(Number)                 Title                                           Date
Data Verification (REIRS Submission)         03/12/2018
100518-0                 NVLAP Scope and ISO 17025 Certificate for   01/01/2018
Landauer
15-02                   Bases for Neutron Correction Factors for     04/03/2015
OSLN and Survey Instruments
Miscellaneous Documents
(Number)                     Title                                               Date
DAC-0446                     Scaling Factor Determination at Columbia       02/28/ 2018
Generating Station - 2017
VSDS_Pros-M-20171223-2 RW 487 Monthly Survey                                 12/23/2017
71151 - Performance Indicator Verification
71151 - Performance Indicator Verification
Action Requests
Action Requests
377435 378504 379269 379591 380459 380745   Procedures
377435                   378504                 379269               379591
  (Number) Title Revision 1.5.11 Maintenance Rule Program
380459                   380745
15 SYS-4-22 Maintenance Rule Program
Procedures
13 SYS-4-31 System and Equipment Performance Monitoring and Trending Program
  (Number)                       Title                                             Revision
12  71152 - Problem Identification and Resolution
1.5.11                         Maintenance Rule Program                             015
SYS-4-22                       Maintenance Rule Program                             013
SYS-4-31                       System and Equipment Performance Monitoring           012
and Trending Program
71152 - Problem Identification and Resolution
Action Requests
Action Requests
378489 378892 377416 376891 376894 375755 377654 377144 175386 373903 373313 378956 376921 372667 372847 373141 Work Orders
378489                   378892                 377416               376891
2108935     Procedures
376894                   375755                 377654               377144
  (Number) Title Revision 1.3.81 Maintaining Plant Component Status Control
175386                   373903                 373313               378956
2 1.5.14 Risk Assessment and Management for Maintenance/Surveillance Activities
376921                   372667                 372847               373141
040 6.6.5 Movement and Transfer Operations of HI
Work Orders
-TRAC and HI-STORM in the Reactor Building
2108935
017 SOP-DOOR/HATCH OPS
Procedures
Reactor Building, Turbine Building, Radwaste
  (Number)                       Title                                             Revision
Building, and Containment Personnel, Equipment Access Doors, and Hatches
1.3.81                         Maintaining Plant Component Status Control           012
013 SOP-FLOCCULATOR
1.5.14                         Risk Assessment and Management for                   040
-OPS Flocculator System Operation
Maintenance/Surveillance Activities
006 SWP-CAP-01 Corrective Action Program
6.6.5                         Movement and Transfer Operations of HI-TRAC           017
39 SWP-CAP-06 Corrective Action Review
and HI-STORM in the Reactor Building
24 GBP-CAP-04 Corrective Action Review Board 00 0 GBP-CAP-03 Trending Program
SOP-DOOR/HATCH OPS             Reactor Building, Turbine Building, Radwaste         013
0
Building, and Containment Personnel, Equipment
Miscellaneous Documents  
Access Doors, and Hatches
(Number) Title Revision /Date Ops Excellence Plan Cycle 24
SOP-FLOCCULATOR-OPS           Flocculator System Operation                         006
SWP-CAP-01                     Corrective Action Program                             039
SWP-CAP-06                     Corrective Action Review                             024
GBP-CAP-04                     Corrective Action Review Board                       000
GBP-CAP-03                     Trending Program                                     000
Miscellaneous Documents                                                           Revision
(Number)                     Title                                                 /Date
Ops Excellence Plan Cycle 24
60855.1-Operation of an Independent Spent Fuel Storage Installation
60855.1-Operation of an Independent Spent Fuel Storage Installation
Action Requests
Action Requests
00377488 00377489 00373321 00369032 00360032     Work Orders
00377488             00377489               00373321                 00369032
2100824-01 02088436-01 02119266-01 02119264-01 02119263-01 02119261-01 02115652-01 02101322-01 Procedures
00360032
  (Number) Title Revision PPM 6.6.4 HI-STORM System Site Transportation
Work Orders
015 PPM 6.6.5 Transfer Operations of
2100824-01           02088436-01           02119266-01             02119264-01
HI-Track/HI-STORM in the Reactor Building
2119263-01           02119261-01           02115652-01             02101322-01
017 PPM 6.6.6 MPC Fuel Loading
Procedures
015 PPM 6.6.7 MPC Processing
  (Number)                     Title                                               Revision
28 PPM 6.6.12
PPM 6.6.4                   HI-STORM System Site Transportation                     015
Vacuum Drying System Operations
PPM 6.6.5                   Transfer Operations of HI-Track/HI-STORM in the         017
006 PPM 6.6.13
Reactor Building
Helium Backfill System Operations
PPM 6.6.6                   MPC Fuel Loading                                       015
004 PPM 6.6.14
PPM 6.6.7                   MPC Processing                                         028
MPC Alternate Cooling Water System Operation
PPM 6.6.12                   Vacuum Drying System Operations                         006
2 PPM 6.6.15
PPM 6.6.13                   Helium Backfill System Operations                       004
Spent Fuel Cask Loading Verification
PPM 6.6.14                   MPC Alternate Cooling Water System Operation           002
006 PPM 6.3.23
PPM 6.6.15                   Spent Fuel Cask Loading Verification                   006
Handling Irradiated Fuel in the Spent Fuel Pool
PPM 6.3.23                   Handling Irradiated Fuel in the Spent Fuel Pool         010
010 SWP-LIC-02 Licensing Basis Impact Determinations
SWP-LIC-02                   Licensing Basis Impact Determinations                   014
014 OSP-SFS-D101 Storage Cask Heat Removal System Daily Checks
OSP-SFS-D101                 Storage Cask Heat Removal System Daily Checks           015
015 PPM 10.4.5 Reactor and Turbine Building Overhead Traveling Crane Inspection, Maintenance and Testing
PPM 10.4.5                   Reactor and Turbine Building Overhead Traveling         023
23 PPM 9.6.1 Spent Fuel Selection for Cask Storage
Crane Inspection, Maintenance and Testing
008 PPM 6.3.40
PPM 9.6.1                   Spent Fuel Selection for Cask Storage                   008
Determination of Fuel Assembly Condition for ISFSI 006  Design Basis
PPM 6.3.40                   Determination of Fuel Assembly Condition for           006
Documents  
ISFSI
(Number) Title Revision 72.212 ISFSI 10 CFR 72.212 Evaluation 72
Design Basis Documents
-35 0 10 ISFSI FSAR
(Number)                     Title                                               Revision
HI-STORM 100 ISFSI Final Safety Analysis Report
2.212                       ISFSI 10 CFR 72.212 Evaluation 72-35                   010
13 CoC 1014 CoC and Technical Specifications for HI
ISFSI FSAR                   HI-STORM 100 ISFSI Final Safety Analysis Report         013
-STORM 100 , Amendment 9
CoC 1014                     CoC and Technical Specifications for HI-STORM           001
1  Miscellaneous Documents  
100, Amendment 9
(Number) Title Revision /Date VSDS DIC 1517
Miscellaneous Documents                                                           Revision
Survey of ISFSI Pad and & Building 105 Quarterly
(Number)                     Title                                                 /Date
01/23/2018
VSDS DIC 1517       Survey of ISFSI Pad and & Building 105 Quarterly             01/23/2018
AU-DC-16 ISFSI Program QA Audit Report
AU-DC-16             ISFSI Program QA Audit Report                               04/20/2016
04/20/2016
17-VS-04             Source QA Surveillance Report - Holtec International         09/14/2017
17-VS-04 Source QA Surveillance Report  
16-VS-05             Source QA Surveillance Report - Holtec International         11/08/2016
- Holtec International
DIC 1814.5         Cask Loading Plan for Canisters 37 - 40                     March
09/14/2017
2018
16-VS-05 Source QA Surveillance Report  
PLM 003N2471       CGS Vacuum Sipping Final Report Fall 2015               12/07/2015
- Holtec International
Cal NE-02-00-08     Calculation for Fuel History Data                           006
11/08/2016
Cal CE-02-00-12     Analysis of the Reactor Building Railroad Bay 441 Ft         002
 
Elevation Slab
DIC 1814.5
Cal CE-02-01-08     HI-TRAC/HI-STORM Dolly Seismic Restraint @ EL 441           002
Cask Loading Plan for Canisters 37  
Cal SLENW-Calc-1   Cask Transport Road Design                               04/06/2001
- 40 March 2018 PLM 003N2471
GO2-17-091         GGS 2016 Annual Radiological Environmental Operating     05/09/2017
CGS Vacuum Sipping Final Report Fall 2015
Report
2/07/2015 Cal NE-02-00-08 Calculation for Fuel History Data
2. 48 Screenings
6 Cal CE-02-00-12 Analysis of the Reactor Building Railroad Bay 441 Ft Elevation Slab
16-009               17-001                   17-002             17-003
2 Cal CE-02-01-08 HI-TRAC/HI-STORM Dolly Seismic Restraint @ EL 441'
17-004               17-005                   17-006             17-007
2 Cal SLENW-Calc-1 Cask Transport Road Design
17-008               17-009                   17-010             17-011
04/06/2001 GO2-17-091 GGS 2016 Annual Radiological Environmental Operating Report  05/09/2017 72. 48 Screenings
17-012               17-013                   18-001             18-004
16-009 17-001 17-002 17-003 17-004 17-005 17-006 17-007 17-008 17-009 17-010 17-011 17-012 17-013 18-001 18-004 LDCN-14-024 LDCN-18-13       Engineering Changes
LDCN-14-024           LDCN-18-13
EC PDC 15708
Engineering Changes
EC EVAL 17126
EC PDC 15708         EC EVAL 17126
 
Attachment 2
The following items are requested for the
The following items are requested for the
Occupational Radiation Safety Inspection
Occupational Radiation Safety Inspection
Line 716: Line 691:
Inspection areas are listed in the attachments below.
Inspection areas are listed in the attachments below.
Please provide the requested information on or before May 11, 2018.
Please provide the requested information on or before May 11, 2018.
Please submit this information using the same lettering system as below. For example, all contacts and phone numbers for Inspection Procedure 71124.0
Please submit this information using the same lettering system as below. For example, all
should be in a file/folder titled  
contacts and phone numbers for Inspection Procedure 71124.01 should be in a file/folder titled
"1- A," applicable organization charts in file/folder "
1- A, applicable organization charts in file/folder 1- B, etc.
1- B," etc. If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at least 30 days later than the onsite
If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at
inspection dates, so the inspectors will have access to the information while writing the report.
least 30 days later than the onsite inspection dates, so the inspectors will have access to the
In addition to the corrective action document lists provided for each inspection procedure listed below, please provide updated lists of corrective action documents at the entrance meeting. The dates for these lists should range from the end dates of the original lists to the day of the entrance meeting.
information while writing the report.
If more than one inspection procedure is to be conducted and the information requests appear to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which file the information can be found.
In addition to the corrective action document lists provided for each inspection procedure listed
If you have any questions or comments, please contact Louis Carson at 817. 200.1221 or louis.carson@nrc.gov
below, please provide updated lists of corrective action documents at the entrance meeting.
and John O'Donnell at 817.200.1441 or John.O'Donnell@nrc.gov
The dates for these lists should range from the end dates of the original lists to the day of the
entrance meeting.
If more than one inspection procedure is to be conducted and the information requests appear
to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which
file the information can be found.
If you have any questions or comments, please contact Louis Carson at 817. 200.1221 or
louis.carson@nrc.gov and John ODonnell at 817.200.1441 or John.ODonnell@nrc.gov
PAPERWORK REDUCTION ACT STATEMENT
PAPERWORK REDUCTION ACT STATEMENT
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.
This letter does not contain new or amended information collection requirements subject
: [[contact::S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget]], control number 3150
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
-0011.
collection requirements were approved by the Office of Management and Budget,
control number 3150-0011.
Attachment 2
2. Occupational ALARA Planning and Controls (71124.02)
2. Occupational ALARA Planning and Controls (71124.02)
Date of Last Inspection:
Date of Last Inspection:         May 26, 2017
May 26, 2017
A. List of contacts and telephone numbers for ALARA program personnel
A. List of contacts and telephone numbers for ALARA program personnel
B. Applicable organization charts
B. Applicable organization charts
: [[contact::C. Copies of audits]], self
: [[contact::C. Copies of audits]], self-assessments, and LERs, written since date of last inspection,
-assessments, and LERs, written since date of last inspection
focusing on ALARA
, focusing on ALARA
D. Procedure index for ALARA Program
D. Procedure index for ALARA Program
E. Please provide specific procedures related to the following areas noted below. Additional Specific Procedures may be requested by number
E. Please provide specific procedures related to the following areas noted below.
after the inspector reviews the procedure indexes.
Additional Specific Procedures may be requested by number after the inspector reviews
the procedure indexes.
1. ALARA Program
1. ALARA Program
2. ALARA Committee
2. ALARA Committee
3. Radiation Work Permit Preparation
3. Radiation Work Permit Preparation
F. A summary list of corrective action documents (including corporate and sub
F. A summary list of corrective action documents (including corporate and sub-tiered
-tiered systems) written since date of last inspection, related to the ALARA program. In addition to ALARA, the summary should also address Radiation Work Permit violations, Electronic Dosimeter Alarms, and RWP Dose Estimates
systems) written since date of last inspection, related to the ALARA program. In addition
NOTE: The lists should indicate the significance level
to ALARA, the summary should also address Radiation Work Permit violations,
of each issue and the search criteria used. Please provide in document formats which are "searchable" so that the inspector can perform word searches.
Electronic Dosimeter Alarms, and RWP Dose Estimates
: [[contact::G. List of work activities greater than 1 rem]], since date of last inspection, Include original dose estimate and actual dose.
NOTE: The lists should indicate the significance level of each issue and the search
H. Site dose totals and 3
criteria used. Please provide in document formats which are searchable so that
-year rolling averages for the past 3 years (based on dose of record) I. Outline of source term reduction strategy
the inspector can perform word searches.
: [[contact::J. If available]], provide a copy of the ALARA outage report for the most recently completed outages for each unit
: [[contact::G. List of work activities greater than 1 rem]], since date of last inspection,
Include original dose estimate and actual dose.
H. Site dose totals and 3-year rolling averages for the past 3 years (based on dose of
record)
I. Outline of source term reduction strategy
: [[contact::J. If available]], provide a copy of the ALARA outage report for the most recently completed
outages for each unit
K. Please provide your most recent Annual ALARA Report.
K. Please provide your most recent Annual ALARA Report.
4. Occupational Dose Assessment (Inspection Procedure 71124.04)
4. Occupational Dose Assessment (Inspection Procedure 71124.04)
Date of Last Inspection:
Date of Last Inspection:       September 1, 2016
September 1, 2016
A. List of contacts and telephone numbers for the following areas:
A. List of contacts and telephone numbers for the following areas:
1. Dose Assessment personnel
1. Dose Assessment personnel
B. Applicable organization charts
B. Applicable organization charts
: [[contact::C. Audits]], self
: [[contact::C. Audits]], self-assessments, vendor or NUPIC audits of contractor support, and LERs
-assessments, vendor or NUPIC audits of contractor support, and LERs written since date of last inspection, related to:
written since date of last inspection, related to:
1. Occupational Dose Assessment
1. Occupational Dose Assessment
D. Procedure indexes for the following areas:
D. Procedure indexes for the following areas:
1. Occupational Dose Assessment
1. Occupational Dose Assessment
E. Please provide specific procedures related to the following areas noted below. Additional Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
E. Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures will be requested by number after the inspector reviews
the procedure indexes.
1. Radiation Protection Program
1. Radiation Protection Program
2. Radiation Protection Conduct of Operations
2. Radiation Protection Conduct of Operations
Line 773: Line 761:
7. Declared Pregnant Worker
7. Declared Pregnant Worker
8. Bioassay Program
8. Bioassay Program
F. List of corrective action documents (including corporate and sub
F. List of corrective action documents (including corporate and sub-tiered systems) written
-tiered systems) written since date of last inspection, associated with:
since date of last inspection, associated with:
1. National Voluntary Laboratory Accreditation Program (NVLAP)
1. National Voluntary Laboratory Accreditation Program (NVLAP)
2. Dosimetry (TLD/OSL, etc.) problems
2. Dosimetry (TLD/OSL, etc.) problems
3. Electronic alarming dosimeters
3. Electronic alarming dosimeters
4. Bioassays or internally deposited
4. Bioassays or internally deposited radionuclides or internal dose
radionuclides or internal dose
5. Neutron dose
5. Neutron dose
NOTE: The lists should indicate the significance level
NOTE: The lists should indicate the significance level of each issue and the search
of each issue and the search criteria used. Please provide in document formats which are "searchable" so that the inspector can perform word searches.
criteria used. Please provide in document formats which are searchable so that
: [[contact::G. List of positive whole body counts since date of last inspection]], names redacted if desired H. Part 61 analyses/scaling factors
the inspector can perform word searches.
: [[contact::I. The most recent National Voluntary Laboratory Accreditation Program (NVLAP) accreditation report or]], if dosimetry is provided by a vendor, the vendor's most recent results
: [[contact::G. List of positive whole body counts since date of last inspection]], names redacted if
ML18206A16
desired
SUNSI Review
H. Part 61 analyses/scaling factors
By: MSH/RDR Non-Sensitive Sensitive  Publicly Available
I. The most recent National Voluntary Laboratory Accreditation Program (NVLAP)
Non-Publicly Available
accreditation report or, if dosimetry is provided by a vendor, the vendors most recent
Keyword: NRC-002 OFFICE SRI:DRP/A RI:DRP/A DRS/EB1 DRS/EB2 DRS/PSB2 DRS/OB DNMS:FCDB NAME GKolcum LBrandt TFarnholtz
results
JD rake HGepford VGaddy JKatanic SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA-RSB for/ DATE 07/24/18 07/23/2018
 
07/19/2018
ML18206A167
07/19/2018 07/19/18 07/22/18 07/24/18 OFFICE DRS/IPAT SPE:DRP/A BC:DRP/A     NAME GGeorge RAlexander
SUNSI Review             Non-Sensitive          Publicly Available              Keyword:
MHaire    SIGNATURE /RA/ /RA/ /RA/     DATE 07/20/2018
By: MSH/RDR                 Sensitive             Non-Publicly Available         NRC-002
07/20/18 07/24/18
OFFICE       SRI:DRP/A     RI:DRP/A     DRS/EB1   DRS/EB2     DRS/PSB2   DRS/OB   DNMS:FCDB
NAME           GKolcum       LBrandt   TFarnholtz   JDrake      HGepford VGaddy     JKatanic
SIGNATURE       /RA/         /RA/       /RA/       /RA/         /RA/     /RA/   /RA-RSB for/
DATE           07/24/18   07/23/2018 07/19/2018 07/19/2018       07/19/18 07/22/18   07/24/18
OFFICE       DRS/IPAT SPE:DRP/A BC:DRP/A
NAME           GGeorge     RAlexander     MHaire
SIGNATURE       /RA/         /RA/       /RA/
DATE         07/20/2018     07/20/18     07/24/18
}}
}}

Revision as of 19:48, 20 October 2019

NRC Integrated Inspection Report 05000397/2018002 and Independent Spent Fuel Storage Installation Inspection Report 07200035/2018001
ML18206A167
Person / Time
Site: Columbia  Energy Northwest icon.png
Issue date: 07/24/2018
From: Mark Haire
NRC/RGN-IV/DRP/RPB-A
To: Sawatzke B
Energy Northwest
Haire M
References
IR 2018001, IR 2018002
Download: ML18206A167 (30)
v • d • e


Text

uly 24, 2018

SUBJECT:

COLUMBIA GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000397/2018002 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200035/2018001

Dear Mr. Sawatzke:

On June 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Columbia Generating Station. On July 12, 2018, the NRC inspectors discussed the results of this inspection with Mr. G. Hettel, 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.

This 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 the 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 IV; the Director, Office of Enforcement; and the NRC Resident Inspector at the Columbia Generating Station.

If you disagree with a cross-cutting aspect assignment 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 IV; and the NRC Resident Inspector at the Columbia Generating Station. 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/

Mark S. Haire, Chief Project Branch A Division of Reactor Projects Docket Nos. 50-397;72-035 License No. NPF-21

Enclosure:

Inspection Report 05000397/2018002 and 07200035/2018001 w/Attachments 1. Documents Reviewed 2. O

Inspection Report

Docket Numbers: 05000397; 07200035 License Numbers: NPF-21 Report Numbers: 05000397/2018002; 07200035/2018001 Enterprise Identifier: I-2018-002-0020; 1-2018-001-0091 Licensee: Energy Northwest Facility: Columbia Generating Station and Independent Spent Fuel Storage Installation Location: Richland, Washington Inspection Dates: April 1, 2018 to June 30, 2018 Inspectors: G. Kolcum, Senior Resident Inspector L. Brandt, Resident Inspector L. Brookhart, Senior Inspector L. Carson II, Senior Health Physicist J. ODonnell, CHP, Health Physicist Approved By: M. Haire, Branch Chief Project Branch A Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Columbia Generating Station 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.

List of Findings and Violations Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Green H.12 - Avoid 71111.15 Systems NCV 05000397/2018002-01 Complacency Closed The inspectors reviewed a self-revealed, Green, non-cited violation of Technical Specification 5.4.1.a for the licensees failure to perform maintenance in accordance with written procedures appropriate to the circumstances. Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW-V-8B2, while operating a nearby demineralized water valve, DW-V-14B2, as part of work activities under Work Request (WR) 29127677, and rendered diesel generator 2 inoperable and unavailable.

PLANT STATUS

===The plant began the inspection period at 100 percent rated thermal power. On April 19, 2018, the reactor unit was down powered to 98 percent due to feedwater heater 2C level control failure. On April 20, 2018, the unit was down powered further to 85 percent for troubleshooting.

The unit returned to rated thermal power on April 21, 2018.

On April 27, 2018, the reactor unit was down powered to 85 percent for economic dispatch from Bonneville Power Administration. The unit returned to rated thermal power on April 30, 2018.

On May 18, 2018, the reactor unit automatically scrammed due to a load reject from a grid disturbance. The unit was restarted and synched to the grid on May 24, 2018. Reactor power was raised to 65 percent on May 25, 2018, and remained at 65 percent for economic dispatch from Bonneville Power Administration. The unit returned to rated thermal power on June 11, 2018.

On June 12, 2018, the unit was down powered to 98 percent due to trip of the 2C feedwater heater. On June 14, 2018, the unit was down powered to 85 percent to repair the 2C feedwater level controller. On June 15, 2018, the unit was down powered to 78 percent due to subsequent trips of the 3C and 4C feedwater heaters. After maintenance, the reactor returned to rated thermal power on June 15, 2018.

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

71111.01Adverse Weather Protection Summer Readiness

Main article: IP 71111.01

The inspectors evaluated summer readiness of offsite and alternate alternating current power systems.

71111.04Equipment Alignment Partial Walkdown

Main article: IP 71111.04

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) diesel generator 1 jacket water system on April 9, 2018
(2) diesel generator 2 jacket water system on April 9, 2018
(3) diesel generator 3 jacket water system on April 9, 2018
(4) low pressure core spray system on June 1, 2018

71111.05AQFire Protection Annual/Quarterly Quarterly Inspection

Main article: IP 71111.05

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Fire Areas RC-14/1, RC-8/2, RC-5/1, and RC-6/2; Divisions 1 and 2 switchgear and battery rooms; on April 6, 2018
(2) Fire Areas RC-4/1, RC-7/2, RC-9/2, and RC-19/2; Divisions 1 and 2 electrical equipment and reactor protection system rooms, remote shutdown room, and vital island corridor; on April 6, 2018
(3) Fire Area TG1/2, reactor feed pump rooms, on April 18, 2018
(4) Fire Area RC-2/1, cable spreading room, on May 10, 2018

71111.06Flood Protection Measures Internal Flooding

Main article: IP 71111.06

The inspectors evaluated internal flooding mitigation protections in the reactor building 471 ft. level on June 22, 2018.

71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

Main article: IP 71111.11

The inspectors observed and evaluated a licensed operator requalification evaluated scenario on April 16, 2018.

Operator Performance (1 Sample)===

The inspectors observed and evaluated:

===(1) down power to 85 percent due to failure of feedwater heater 2C, on April 20, 2018

(2) startup to power increase, on May 24, 2018

71111.12Maintenance Effectiveness Routine Maintenance Effectiveness

Main article: IP 71111.12

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) HT-TE-SW71/2, high pressure core spray heat tracing replacement, on April 23, 2018
(2) E-RLY-86TM, main generator lockout relay, on May 22, 2018
(3) RPS-RLY-K10F for EOC-RPT, maintenance to disable end of cycle recirculation pump trip relay, on May 30, 2018

71111.13Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) yellow risk for heavy lifts at circulating water pump house on April 26, 2018
(2) yellow risk for standby gas treatment train A maintenance, week of May 14, 2018

71111.15Operability Determinations and Functionality Assessments

Main article: IP 71111.15

The inspectors evaluated the following operability determinations and functionality assessments:

(1) diesel generator 1 fuel oil pump 1B on April 1, 2018
(2) diesel generator 2 unplanned inoperability and unavailability for drain of jacket water on April 9, 2018
(3) standby service water 'B' pump house door gearbox on April 17, 2018
(4) high pressure core spray power panel 4A voltage near minimum 120VAC on April 17, 2018
(5) residual heat removal pump 1B relief valve on May 4, 2018
(6) main steam relief valve 1B dual indication on May 18, 2018
(7) standby service water A spray ring header on May 24, 2018
(8) condensate pump 2C elevated water in oil, on May 24, 2018

71111.18Plant Modifications

Main article: IP 71111.18

The inspectors evaluated the following temporary or permanent modifications:

(1) EC 17224, main transformer 1, 2, 3 alarm and trip function, on May 22, 2018
(2) EC 17227, main transformer horizontal links bolting, on May 22, 2018

71111.19Post Maintenance Testing

Main article: IP 71111.19

The inspectors evaluated the following post maintenance tests:

(1) diesel generator 1 fuel oil pump 1B, on April 1, 2018
(2) residual heat removal loop B operability test on April 1, 2018
(3) reactor building ventilation system operation on April 3, 2018
(4) high pressure core spray reactor coolant system interface valve leakage pressure monitor on April 5, 2018
(5) wetwell exhaust isolation valve 3A maintenance for post-accident monitoring position indication on April 13, 2018
(6) power panel 4A transformer replacement on May 4, 2018
(7) main transformer 1, 2, 3 relay testing on May 22, 2018
(8) main transformer 1 Buchholz relay testing on May 22, 2018

71111.20Refueling and Other Outage Activities

Main article: IP 71111.20

The inspectors evaluated forced outage activities following the load reject grid disturbance from May 18, 2018 to May 25, 2018.

===71111.22Surveillance Testing The inspectors evaluated the following surveillance tests:

Routine ===

Main article: IP 71111.22
(1) ISP-SEIS-M201, Seismic System Channel Check, Revision 6, on April 23, 2018
(2) OSP-ELEC-M703, HPCS Diesel Generator Monthly Operability Test, Revision 66, on April 25, 2018
(3) ISP-RPS-S901, RPS (Channel A1) and EOC Recirc Pump Trip - TGV Fast Closure RPS-PS-5A - CFT/CC, Revision 0, on May 7, 2018; and ISP RPS-S902, RPS (Channel A2) and EOC Recirc Pump Trip - TGV Fast Closure RPS-PS-5C - CFT/CC, Revision 0, on May 9, 2018 In-service (1 Sample)===
(1) OSP-HPCS/IST-Q701, HPCS System Operability Test, Revision 53, on April 23, 2018

Reactor Coolant System Leak Detection (1 Sample)

(1) daily reactor coolant system leak checks, shift and daily instrument checks

===(Modes 1, 2, 3) on June 25, 2018

71114.06Drill Evaluation Drill/Training Evolution

Main article: IP 71114.06

The inspectors evaluated the emergency preparedness training drill on May 15, 2018.

RADIATION SAFETY

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

Main article: IP 71124.02

The inspectors evaluated the licensees radiological work planning by reviewing the following activities:

(1) RWP 30004209, EDR Tank-5 Desludge
(2) RWP 30004210, EDR Tank-5 Desludge High Risk
(3) RWP 30003882, Main Steam Relief Valves
(4) RWP 30003098, Wetwell Cleanup and Inspection
(5) RWP 30003873, Drywell Shielding Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)===

The inspectors evaluated dose estimates and exposure tracking.

===71124.04Occupational Dose Assessment Source Term Characterization

Main article: IP 71124.04

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 dosimetry situations.

===OTHER ACTIVITIES - BASELINE

71151Performance Indicator Verification

Main article: IP 71151

The inspectors verified licensee performance indicators submittals listed below:

(1) MS06: Emergency AC Power Systems (07/01/2017-06/30/2018)
(2) MS07: High Pressure Injection Systems (07/01/2017-06/30/2018)
(3) MS08: Heat Removal Systems (07/01/2017-06/30/2018)
(4) MS09: Residual Heat Removal Systems (07/01/2017-06/30/2018)
(5) MS10: Cooling Water Support Systems (07/01/2017-06/30/2018)

71152Problem Identification and Resolution Semiannual Trend Review

Main article: IP 71152

The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more significant safety issue. The inspectors reviewed a negative trend in human performance and documented one observation.

Annual Follow-up of Selected Issues (1 Sample)===

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Independent Spent Fuel Storage Installation cask stuck in reactor building, on April 7, 2018

71153Follow-up of Events and Notices of Enforcement Discretion Events

Main article: IP 71153

The inspectors evaluated the plant scram from a load reject due to a grid disturbance and the licensees response on May 18, 2018.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants The inspectors evaluated the licensees operation of the Independent Spent Fuel Storage Installation (ISFSI) from April 2 through April 5, 2018, on-site at Columbia Generating Station (CGS).

The CGS ISFSI was licensed as a general Part 72 license and utilized the Holtec HI-STORM 100 System, approved under Certificate of Compliance 1014, License Amendment 9, Revision 1, and Final Safety Analysis Report (FSAR), Revision 13. The CGS had been loading HI-STORM 100S Version 243 overpacks containing the Multi-Purpose Canister, MPC-68, and more recently the MPC-68M. CGSs ISFSI contained a total of 39 HI-STORM overpacks at the time of the routine inspection. CGS was in the middle of its 2018 loading campaign. Inspectors were onsite to observe loading activities associated with cask Number 40. The CGS planned to complete an additional 5 canisters by the end of the campaign, increasing the total number of casks to 45 at the ISFSI.

The ISFSI activities specifically reviewed during the on-site inspection and the subsequent in-office review included:

(1) Evaluated and observed cask transportation operations.
(2) Reviewed the licensee's loading, processing, and heavy load procedures associated with their current dry fuel storage campaign.
(3) Reviewed the licensees corrective action program implementation for ISFSI operations since the last routine ISFSI inspection, which was completed in July 2016.
(4) Reviewed quality assurance (QA) program implementation, including recent QA audits, surveillances, receipt inspection, and quality control activities.
(5) Reviewed documentation related to Technical Specification (TS) required operational surveillance activities and FSAR required annual maintenance activities.
(6) Reviewed the licensees radiological monitoring data for the calendar years 2016 and 2017.
(7) Reviewed spent fuel documentation for the canisters loaded since the last routine ISFSI inspection (Canisters 37-40) to confirm the fuel met all TS requirements for storage at the ISFSI.
(8) Reviewed annual maintenance activities for heavy lifting components which included special lifting devices, the vertical cask transporter, and the sites single-failure proof cask handling crane.
(9) Reviewed all 72.48 safety evaluations/screenings for changes made to the licensees ISFSI operations in accordance with Inspection Procedure 60857 since the last routine ISFSI inspection.
(10) Reviewed all changes made to the licensees 72.212 Report from Revision 9 to Revision 10 under the licensees 72.48 program in accordance with Inspection Procedure 60857.

The inspectors did not identify any issues of concerns requiring documentation.

INSPECTION RESULTS

Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Green H.12 - Avoid 71111.15 Systems NCV 05000397/2018002-01 Complacency Closed The inspectors reviewed a self-revealed, Green, non-cited violation of Technical Specification 5.4.1.a for the licensees failure to perform maintenance in accordance with written procedures appropriate to the circumstances. Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW-V-8B2, while operating a nearby demineralized water valve, DW-V-14B2, as part of work activities under Work Request (WR) 29127677, and rendered diesel generator 2 inoperable and unavailable.

Description:

On April 9, 2018, while operating demineralized water valve DW-V-14B2, maintenance personnel inadvertently bumped and partially opened diesel cooling water valve DCW-V-8B2. The maintenance personnel completed their work activities, cleaned up the work area, and returned to the shop, unaware that their actions resulted in the partial opening of DCW-V-8B2. Meanwhile, the accidental opening of this diesel cooling water valve caused the diesel generator 2 diesel cooling water expansion tank to drain into a nearby floor drain.

Approximately 40 minutes later, the main control room received a diesel generator 2 local panel trouble alarm. Operations personnel responded to the alarm, found the diesel cooling water valve out of position (partially open), and closed the valve. During this event, the tank level reached -4.5 inches, which is outside the normal standby lineup band of +2 to +6 inches.

This rendered diesel generator 2 inoperable and caused an unplanned entry into Technical Specification 3.8.1 for one required diesel generator inoperable. The licensee restored the required water level within 40 minutes of declaring the diesel inoperable. The licensee then verified the diesel was in the proper standby lineup and restored the diesel to operable status approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> later. Subsequently, the licensee initiated an investigation of the event that stated the diesel generator was rendered unavailable because it would not have been able to complete its 24-hour mission time with the open diesel cooling water valve. The diesel generator would have started, loaded, and overheated in approximately 10 minutes without a credited cooling water makeup source. Total unavailability time accrued was 86 minutes.

Procedure 1.3.81, Maintaining Plant Component Status Control, Revision 12, ensures plant component status control is maintained. Step 5.5.2 states that personnel performing work in the plant that are given permission to manipulate the plant are required to accept responsibility for, and are accountable for, maintaining plant component status control. Step 6.6.2.d states, in part, that electrical, mechanical, and instrumentation and control maintenance personnel manipulate components only as specified in approved procedures and work packages that have been authorized by the shift manager or designee.

The inspectors noted that step 6.1 of Procedure MI-1.8, Conduct of Maintenance, Revision 70, directs all maintenance personnel to use and adhere to the station error prevention tools as described in Procedure STANDARD-01. Procedure STANDARD-01, Worker Error Prevention Tools, Revision 10, step 3.3 states, in part, that station personnel are responsible for performing work activities using the error prevention tools in accordance with this standard. Section 4.0 details the fundamental human performance tools workers apply during work activities to help them maintain positive control, regardless of their perception of the risk. For example, Section 4.2 describes the Take 2 error prevention tool.

Step 4.2.1 states, in part, that Take 2 is a jobsite review done when first arriving at the jobsite.

The worker develops an accurate understanding of the work environment by taking time to become acquainted with the immediate work area. Step 4.2.4.a instructs the worker to review the Take 2 lanyard or job aid. The Take 2 job aid lists several questions to engage the worker. Question 7 asks, Is there a component misposition or bump hazard in the work area (2 ft zone)? If yes, engage Operations. The licensees event investigation indicated that the maintenance personnel conducted a Take 2 upon arriving at the jobsite but did not refer to their Take 2 job aid.

Notwithstanding the plant procedure for preventing inadvertent operation of equipment, the inspectors noted that WR 29127677 did not contain the necessary controls to ensure that safety-related equipment was not adversely affected during maintenance.

Corrective Actions: The licensees corrective actions included immediately closing the diesel cooling water valve, replenishing the diesel cooling water level, restoring diesel generator 2 to operable status, and completing an event investigation.

Corrective Action Reference(s): Action Request 378835

Performance Assessment:

Performance Deficiency: The failure to perform maintenance in accordance with documented instructions appropriate to the circumstances was a performance deficiency.

Screening: The performance deficiency was more than minor, and therefore a finding, because it was associated with the configuration control attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage). Specifically, on April 9, 2018, the licensee inadvertently bumped and partially opened a diesel cooling water valve, DCW-V-8B2, while operating a nearby demineralized water valve, DW-V-14B2, as part of work activities under WR 29127677, and rendered diesel generator 2 inoperable and unavailable.

Significance: The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609, Attachment 04, Initial Characterization of Findings, and Appendix A, The Significance Determination Process (SDP) for Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions, dated June 19, 2012. The inspectors determined the finding was of very low safety significance (Green) because all of the screening questions were answered in the negative.

Cross-cutting Aspect: This finding has a cross-cutting aspect in the area of human performance, avoid complacency, in that the licensee failed to implement appropriate error reduction tools and recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Specifically, licensee staff failed to implement the guidance found in the Take 2 card which demonstrated complacency in the perceived lack of intrusiveness of the work [H.12].

Enforcement:

Violation: Technical Specification 5.4.1.a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2. Section 9.a of Appendix A of Regulatory Guide 1.33, Revision 2, requires, in part, that maintenance that can affect the performance of safety-related equipment should be performed in accordance with documented instructions appropriate to the circumstances. The licensee established Procedure 1.3.81, Maintaining Plant Component Status Control, Revision 12, to meet the Regulatory Guide 1.33 requirement. Step 6.6.2.d states, in part, that electrical, mechanical, and instrumentation and control maintenance personnel manipulate components only as specified in approved procedures and work packages that have been authorized by the shift manager or designee.

Contrary to the above, on April 9, 2018, the licensee did not manipulate components only as specified in approved procedures and work packages that had been authorized by the shift manager or designee. Specifically, the licensee inadvertently bumped and partially opened diesel cooling water valve DCW-V-8B2 as part of work activities under WR 29127677, and rendered diesel generator 2 inoperable and unavailable.

Disposition: This violation is being treated as a non-cited violation, consistent with Section 2.3.2.a of the NRC Enforcement Policy.

Observation

71152 - Semiannual Trend

Review The inspectors performed an in-depth review of the licensees evaluation and corrective actions related to human performance issues. Since the end of refueling outage RF23 in June 2017, the licensee has initiated multiple condition reports documenting human performance errors. The licensee had also identified an adverse trend as documented in Action Requests 377654, 377416, and 378892.

This review focused on condition reports that documented plant component status control errors and failures to follow procedures. While many of the human performance issues were of minor significance, several resulted in NRC documented findings:

  • NCV 05000397/2018002-01, Failure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System. (Section 71111.15 of this report)

The inspectors noted that the licensee appropriately considered extent of condition and cause when scheduling corrective action assignments. These actions included a site-wide initiative to identify and eliminate any potential plant component status control hazards and a supervisor observation blitz that focused on human performance behaviors such as pre-job briefs, use of the Take 2 card, procedure use and adherence, and supervisory oversight. The inspectors assessed the licensees problem identification threshold, cause analyses, and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition.

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 April 5, 2018, the inspectors presented the results from the routine ISFSI inspection to Mr. G. Hettel, Vice President of Operations (title at the time of the ISFSI inspection, but subsequently assumed the title of Senior Vice President and Chief Nuclear Officer), and other members of the licensee staff.

On May 24, 2018, the inspectors presented the baseline radiation protection inspection results to Mr. G. Hettel, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.

On July 12, 2018, the inspectors presented the quarterly resident inspector inspection results to Mr. G. Hettel, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01 - Adverse Weather Protection

Action Requests

379022 381176

Procedures

(Number) Title Revision

13.1.1 Classifying the Emergency 049

13.1.1A Classifying the Emergency - Technical Bases 033

ABN-ELEC-GRID Degraded Off Site Power Grid 010

SOP-HOTWEATHER-OPS Hot Weather Operations 006

SOP-WARMWEATHER- Warm Weather Operations 015

OPS

71111.04 - Equipment Alignment

Procedures

(Number) Title Revision

5.5.1 Overriding ECCS Valve Logic to Allow Throttling 006

RPV Injection

OSP-LPCS-M102 LPCS Valve Lineup 002

SOP-LPCS-LU LPCS Valve and Breaker Lineup 003

SOP-LPCS-STBY Placing LPCS in Standby Status 002

SOP-DG-DCW Emergency Diesel Generator Jacket Water Cooling 014

SOP-DG1-LU Emergency Diesel Generator (Div 1) Valve and 006

Power Supply Lineup

SOP-DG2-LU Emergency Diesel Generator (Div 2) Valve and 006

Power Supply Lineup

SOP-DG3-LU High Pressure Core Spray Diesel Generator Valve 007

and Power Supply Lineup

Miscellaneous Documents

(Number) Title Revision

Final Safety Analysis Report 064

71111.05AQ - Fire Protection Annual/Quarterly

Action Requests

378829 379167 379972

Procedures

(Number) Title Revision

1.3.10C Control of Transient Combustibles 020

PFP-RW-467 Radwaste 467 005

PFP-RW-484-487 Radwaste 484-487 005

1.3.10A Control of Ignition Sources 017

FPP-1.6 Combustible Loading Calculation Control 002

FPP-2.2.12 Annual Fire Door Operability Test 005

FPP-2.2.7 Fire Protection Water System Inspections 006

PFP-TG-441-456 Turbine Generator 441-456 008

Miscellaneous Documents

(Number) Title Revision

FSAR Fire Hazards Analysis

BIP 17-0613 Barrier Impairment Permit

BIP 17-0614 Barrier Impairment Permit

BIP 17-0615 Barrier Impairment Permit

BIP 17-0616 Barrier Impairment Permit

BIP 17-0643 Barrier Impairment Permit

BIP 17-0662 Barrier Impairment Permit

BIP 18-0096 Barrier Impairment Permit

BIP 18-0097 Barrier Impairment Permit

BIP 18-0111 Barrier Impairment Permit

BIP 18-0017 Barrier Impairment Permit

BIP 18-0018 Barrier Impairment Permit

BIP 18-0019 Barrier Impairment Permit

BIP 18-0029 Barrier Impairment Permit

BIP 18-0031 Barrier Impairment Permit

BIP 18-0037 Barrier Impairment Permit

BIP 18-0041 Barrier Impairment Permit

BIP 18-0050 Barrier Impairment Permit

CALC FP-02-85-03 Combustible Loading Calculation 010

71111.06 - Flood Protection Measures

Action Requests

378764

Procedures

(Number) Title Revision

ABN-FLOODING Flooding 020

ME-02-02-02 Calculation for Reactor Building Flooding Analysis 004

PFP-RB-572 Reactor 572 004

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance

Action Requests

379240

Procedures

(Number) Title Revision

13.1.1 Classifying the Emergency 048

OI-09 Operations Standards and Expectations 064

1.3.1 Operating Policy, Programs, and Practices 126

5.1.1 RPV Control 021

5.2.1 Primary Containment Control 027

5.3.1 Secondary Containment Control 020

Miscellaneous Documents

(Number) Title Revision

LR002398 Cycle 18-2 Evaluated Scenario 001

Crew F Evaluated Scenario Cycle 18-2 000

4.0 Critique Summary

71111.12 - Maintenance Effectiveness

Action Requests

380427

Work Orders

2094222 02128788 29142758

Procedures

(Number) Title Revision

1.5.11 Maintenance Rule Program 015

OI-53 Offsite Power 014

SOP-RPS-OPS Reactor Protection System Operation 015

SOP-RPS-START Reactor Protection System Startup 007

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Work Orders

2085935

Procedures

(Number) Title Revision

1.3.83 Protected Equipment Program 026

1.5.14 Risk Assessment and Management for 040

Maintenance/Surveillance Activities

1.5.11 Maintenance Rule Program 015

WCI-4 Online Work Control Process 048

1.3.76 Integrated Risk Management 050

Miscellaneous Documents

(Number) Title Date

High Risk Work Plan for Underwater Diving in 01/16/2018

Support of CW-P-1C

71111.15 - Operability Determinations and Functionality Assessments

Action Requests

306206 371516 378475 378835

378990 379120 379244 379504

380257 380307

Work Orders

2123413 02126245

Procedures

(Number) Title Revision

1.3.66 Operability and Functionality Evaluation 034

10.25.53 Inspection of Lighting Panels and Power Panels 013

OI-09 Operations Standards and Expectation 069

OI-14 Columbia Generating Station Operational 016

Challenges and Risk Program

OSP-ELEC-W102 Electrical Distribution Subsystem Breaker 031

Alignment and Power Availability Verification

OSP-ELEC-W101 Offsite Station Power Alignment Check 031

Miscellaneous Documents

(Number) Title Date

EC 17110 EVAL DO-P-1B Failed to Start when Selected 06/13/2018

71111.18 - Plant Modifications

Action Requests

380372 380404

Procedures

(Number) Title Revision

ENG-DES-02 Columbia Generating Station Plant Modification 019

Process

SWP-DES-01 Plant Modification and Configuration Control 017

71111.19 - Post Maintenance Testing

Action Requests

378475 378488 378990 379191

379244

Work Orders

2118434 02126245 02126307 02126372

2126372 02128700 02326309 29142042

Procedures

(Number) Title Revision

OI-41 Operations Work Control Expectations 063

SWP-TST-01 Post Maintenance Testing Program 017

71111.20 - Refueling and Other Outage Activities

Procedures

(Number) Title Revision

9.3.6 Estimated Critical Position Calculation 005

9.3.7 Reactor Shutdown and Startup Calculations 002

OCC-01 Outage Control Center Norms 006

OI-09 Operator Standards and Expectations 069

1.3.84 Reactivity Management Control 004

3.1.1 Master Startup Checklist 058

3.1.2 Reactor Plant Startup 084

3.2.1 Normal Plant Shutdown 088

3.3.1 Reactor Scram 065

SOP-RHR-SDC RHR Shutdown Cooling 028

71111.22 - Surveillance Testing

Work Orders

2114669 02118974 02118950 02122396

2122397

Procedures

(Number) Title Revision

RPS-PS-5A Instrument Master Data Sheet 013

OSP-INST-H101 Shift and Daily Instrument Checks (Modes 1,2,3) 089

Miscellaneous Documents

(Number) Title Revision

CALC E/I-02-94-1334 Setting Range Determination for Instrument Loop 001

MS-LIS-24B

LDCN 373682, License Document Change Notice SR 1.3.7.6.2

LDCN-17-028 (LCS) Frequency Change per SFCP

STI-AR 365016 Surveillance Test Interval Change Form, Turbine

Valve Surveillance

71114.06 - Drill Evaluation

Procedures

(Number) Title Revision

13.10.1 Control Room Operation and Shift Manager Duties 035

13.10.2 TSC Manager Duties 035

13.2.1 Emergency Exposure Levels, Protective Action 022

Guides

13.2.2 Determining Protective Actions 020

13.4.1 Emergency Notifications 043

13.5.1 Local, Protected Area, or Site Evacuation 029

13.9.1 Environmental Field Monitoring Operations 045

13.10.9 Operations Support Center Manager and Staff 049

Duties

13.11.1 EOF Manager Duties 044

13.13.1 Reentry Operations 010

13.13.3 Intermediate Phase MUDAC Operations 018

13.13.4 After Action Reporting 010

13.14.9 Drill and Exercise Program 018

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

Action Requests

370540 377573 377743 377911

379078 354266 354320 375379

376734 365777

Procedures

(Number) Title Revision

11.2.13.8 Airborne Radioactivity Surveys 019

11.2.7.1 Area Posting 043

HPI-0.19 Radiation Protection Standards and 017

Expectations

HPI-6.4 Administering an Occupational Radiation 025

Exposure History File

SWP-RPP-01 Radiation Protection Program 016

GEN-RPP-01 ALARA Program Description 009

GEN-RPP-02 Radiological Planning and Control Process 034

GEN-RPP-13 Senior Site ALARA Committee 013

GEN-RPP-14 Control of Temporary Shielding 014

PPM 11.2.2.7 ALARA Procedure Analysis 012

PPM 11.2.2.8 ALARA Engineering Analysis 007

Procedures

(Number) Title Revision

PPM 11.2.2.11 Exposure Evaluations for Maintaining TEDE 008

ALARA

PPM 11.2.2.12 Radiological Risk Assessment and 008

Management

PPM 11.2.2.13 Flushing and Shielding Evaluations 002

PPM 11.2.2.14 Radiological Planning and Reviews 004

PPM 11.2.8.2 Radiation Work Permit Preparation and Use 001

Audits and Self-

Assessments (Number) Title Date

AR-SA No. 375350 Annual Radiation Protection Program Review 03/30/2018

SR-18-01 Continuous Monitoring Report 03/07/2018

SR-17-04 Continuous Monitoring Report 11/02/2017

374279 Self-Assessment: 71124.02 ALARA 02/15/2018

Radiation Work Permits

(Number) Title Revision

RWP 30004209 2018 EDR Tank-5 Desludge 001

RWP 30004210 2018 EDR Tank-5 Desludge High Risk 002

RWP 30003882 Main Steam Relief Valves 001

RWP 30003098 Wetwell Cleanup and Inspection 001

RWP 30003873 Drywell Shielding 001

ALARA Planning,

In-Progress Reviews, and

Post-Job Reviews

(Number) Title Date

WO 2117848 Clean EDR Tank-5 02/11/2018

WO 2088288 Suppression Pool Cleanup

WO 2088287 Chemical Decon Cleanup

WO 2077319 Drywell Shielding

Miscellaneous Documents

Senior Site ALARA Committee EDR Tank-5 Desludge

2017 CGS Dose Report to the NRC

05-2018 CGS 5 Year CRE Reduction Plan

R23 CRE Outage Report

71124.04Occupational Dose Assessment

Action Requests

357564 360494 361631 365110

365545 365692 366701 367779

369181 374380 375624 376342

376403 377080 378436

Procedures (Number) Title Revision

11.2.13.8 Airborne Radioactivity Surveys 019

11.2.4.5 Whole Body Counts and Daily Checks Using 016

the Renaissance FastScan

11.2.6.7 Special Dosimetry 018

11.2.7.1 Area Posting 043

GEN-RPP-06 Dosimetry Program Description 013

HPI 4.30 Processing, Evaluation, and Reporting of DLR 014

Exposure Data

HPI-0.19 Radiation Protection Standards and 017

Expectations

HPI-5.9 Evaluation of In-Vivo Bioassay Results 014

Following a Potential Intake

HPI-6.4 Administering an Occupational Radiation 025

Exposure History File

SWP-RPP-01 Radiation Protection Program 016

Audits and Self-

Assessments (Number) Title Date

Self-Assessment: 71124.04 Occupational Dose

374271 02/15/2018

Assessment

374020 Self-Assessment: Site Bioassay Program 11/15/2017

Miscellaneous Documents

(Number) Title Date

Data Verification (REIRS Submission) 03/12/2018

100518-0 NVLAP Scope and ISO 17025 Certificate for 01/01/2018

Landauer

15-02 Bases for Neutron Correction Factors for 04/03/2015

OSLN and Survey Instruments

Miscellaneous Documents

(Number) Title Date

DAC-0446 Scaling Factor Determination at Columbia 02/28/ 2018

Generating Station - 2017

VSDS_Pros-M-20171223-2 RW 487 Monthly Survey 12/23/2017

71151 - Performance Indicator Verification

Action Requests

377435 378504 379269 379591

380459 380745

Procedures

(Number) Title Revision

1.5.11 Maintenance Rule Program 015

SYS-4-22 Maintenance Rule Program 013

SYS-4-31 System and Equipment Performance Monitoring 012

and Trending Program

71152 - Problem Identification and Resolution

Action Requests

378489 378892 377416 376891

376894 375755 377654 377144

175386 373903 373313 378956

376921 372667 372847 373141

Work Orders

2108935

Procedures

(Number) Title Revision

1.3.81 Maintaining Plant Component Status Control 012

1.5.14 Risk Assessment and Management for 040

Maintenance/Surveillance Activities

6.6.5 Movement and Transfer Operations of HI-TRAC 017

and HI-STORM in the Reactor Building

SOP-DOOR/HATCH OPS Reactor Building, Turbine Building, Radwaste 013

Building, and Containment Personnel, Equipment

Access Doors, and Hatches

SOP-FLOCCULATOR-OPS Flocculator System Operation 006

SWP-CAP-01 Corrective Action Program 039

SWP-CAP-06 Corrective Action Review 024

GBP-CAP-04 Corrective Action Review Board 000

GBP-CAP-03 Trending Program 000

Miscellaneous Documents Revision

(Number) Title /Date

Ops Excellence Plan Cycle 24

60855.1-Operation of an Independent Spent Fuel Storage Installation

Action Requests

00377488 00377489 00373321 00369032

00360032

Work Orders

2100824-01 02088436-01 02119266-01 02119264-01

2119263-01 02119261-01 02115652-01 02101322-01

Procedures

(Number) Title Revision

PPM 6.6.4 HI-STORM System Site Transportation 015

PPM 6.6.5 Transfer Operations of HI-Track/HI-STORM in the 017

Reactor Building

PPM 6.6.6 MPC Fuel Loading 015

PPM 6.6.7 MPC Processing 028

PPM 6.6.12 Vacuum Drying System Operations 006

PPM 6.6.13 Helium Backfill System Operations 004

PPM 6.6.14 MPC Alternate Cooling Water System Operation 002

PPM 6.6.15 Spent Fuel Cask Loading Verification 006

PPM 6.3.23 Handling Irradiated Fuel in the Spent Fuel Pool 010

SWP-LIC-02 Licensing Basis Impact Determinations 014

OSP-SFS-D101 Storage Cask Heat Removal System Daily Checks 015

PPM 10.4.5 Reactor and Turbine Building Overhead Traveling 023

Crane Inspection, Maintenance and Testing

PPM 9.6.1 Spent Fuel Selection for Cask Storage 008

PPM 6.3.40 Determination of Fuel Assembly Condition for 006

ISFSI

Design Basis Documents

(Number) Title Revision

2.212 ISFSI 10 CFR 72.212 Evaluation 72-35 010

ISFSI FSAR HI-STORM 100 ISFSI Final Safety Analysis Report 013

CoC 1014 CoC and Technical Specifications for HI-STORM 001

100, Amendment 9

Miscellaneous Documents Revision

(Number) Title /Date

VSDS DIC 1517 Survey of ISFSI Pad and & Building 105 Quarterly 01/23/2018

AU-DC-16 ISFSI Program QA Audit Report 04/20/2016

17-VS-04 Source QA Surveillance Report - Holtec International 09/14/2017

16-VS-05 Source QA Surveillance Report - Holtec International 11/08/2016

DIC 1814.5 Cask Loading Plan for Canisters 37 - 40 March

2018

PLM 003N2471 CGS Vacuum Sipping Final Report Fall 2015 12/07/2015

Cal NE-02-00-08 Calculation for Fuel History Data 006

Cal CE-02-00-12 Analysis of the Reactor Building Railroad Bay 441 Ft 002

Elevation Slab

Cal CE-02-01-08 HI-TRAC/HI-STORM Dolly Seismic Restraint @ EL 441 002

Cal SLENW-Calc-1 Cask Transport Road Design 04/06/2001

GO2-17-091 GGS 2016 Annual Radiological Environmental Operating 05/09/2017

Report

2. 48 Screenings16-009 17-001 17-002 17-003

17-004 17-005 17-006 17-007

17-008 17-009 17-010 17-011

17-012 17-013 18-001 18-004

LDCN-14-024 LDCN-18-13

Engineering Changes

EC PDC 15708 EC EVAL 17126

The following items are requested for the

Occupational Radiation Safety Inspection

at Columbia Generating Station

May 21 thru 25, 2018

Integrated Report 2018002

Inspection areas are listed in the attachments below.

Please provide the requested information on or before May 11, 2018.

Please submit this information using the same lettering system as below. For example, all

contacts and phone numbers for Inspection Procedure 71124.01 should be in a file/folder titled

1- A, applicable organization charts in file/folder 1- B, etc.

If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at

least 30 days later than the onsite inspection dates, so the inspectors will have access to the

information while writing the report.

In addition to the corrective action document lists provided for each inspection procedure listed

below, please provide updated lists of corrective action documents at the entrance meeting.

The dates for these lists should range from the end dates of the original lists to the day of the

entrance meeting.

If more than one inspection procedure is to be conducted and the information requests appear

to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which

file the information can be found.

If you have any questions or comments, please contact Louis Carson at 817. 200.1221 or

louis.carson@nrc.gov and John ODonnell at 817.200.1441 or John.ODonnell@nrc.gov

PAPERWORK REDUCTION ACT STATEMENT

This letter does not contain new or amended information collection requirements subject

to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information

collection requirements were approved by the Office of Management and Budget,

control number 3150-0011.

Attachment 2

2. Occupational ALARA Planning and Controls (71124.02)

Date of Last Inspection: May 26, 2017

A. List of contacts and telephone numbers for ALARA program personnel

B. Applicable organization charts

C. Copies of audits, self-assessments, and LERs, written since date of last inspection,

focusing on ALARA

D. Procedure index for ALARA Program

E. Please provide specific procedures related to the following areas noted below.

Additional Specific Procedures may be requested by number after the inspector reviews

the procedure indexes.

1. ALARA Program

2. ALARA Committee

3. Radiation Work Permit Preparation

F. A summary list of corrective action documents (including corporate and sub-tiered

systems) written since date of last inspection, related to the ALARA program. In addition

to ALARA, the summary should also address Radiation Work Permit violations,

Electronic Dosimeter Alarms, and RWP Dose Estimates

NOTE: The lists should indicate the significance level of each issue and the search

criteria used. Please provide in document formats which are searchable so that

the inspector can perform word searches.

G. List of work activities greater than 1 rem, since date of last inspection,

Include original dose estimate and actual dose.

H. Site dose totals and 3-year rolling averages for the past 3 years (based on dose of

record)

I. Outline of source term reduction strategy

J. If available, provide a copy of the ALARA outage report for the most recently completed

outages for each unit

K. Please provide your most recent Annual ALARA Report.

4. Occupational Dose Assessment (Inspection Procedure 71124.04)

Date of Last Inspection: September 1, 2016

A. List of contacts and telephone numbers for the following areas:

1. Dose Assessment personnel

B. Applicable organization charts

C. Audits, self-assessments, vendor or NUPIC audits of contractor support, and LERs

written since date of last inspection, related to:

1. Occupational Dose Assessment

D. Procedure indexes for the following areas:

1. Occupational Dose Assessment

E. Please provide specific procedures related to the following areas noted below.

Additional Specific Procedures will be requested by number after the inspector reviews

the procedure indexes.

1. Radiation Protection Program

2. Radiation Protection Conduct of Operations

3. Personnel Dosimetry Program

4. Radiological Posting and Warning Devices

5. Air Sample Analysis

6. Performance of High Exposure Work

7. Declared Pregnant Worker

8. Bioassay Program

F. List of corrective action documents (including corporate and sub-tiered systems) written

since date of last inspection, associated with:

1. National Voluntary Laboratory Accreditation Program (NVLAP)

2. Dosimetry (TLD/OSL, etc.) problems

3. Electronic alarming dosimeters

4. Bioassays or internally deposited radionuclides or internal dose

5. Neutron dose

NOTE: The lists should indicate the significance level of each issue and the search

criteria used. Please provide in document formats which are searchable so that

the inspector can perform word searches.

G. List of positive whole body counts since date of last inspection, names redacted if

desired

H. Part 61 analyses/scaling factors

I. The most recent National Voluntary Laboratory Accreditation Program (NVLAP)

accreditation report or, if dosimetry is provided by a vendor, the vendors most recent

results

ML18206A167

SUNSI Review Non-Sensitive Publicly Available Keyword:

By: MSH/RDR Sensitive Non-Publicly Available NRC-002

OFFICE SRI:DRP/A RI:DRP/A DRS/EB1 DRS/EB2 DRS/PSB2 DRS/OB DNMS:FCDB

NAME GKolcum LBrandt TFarnholtz JDrake HGepford VGaddy JKatanic

SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA-RSB for/

DATE 07/24/18 07/23/2018 07/19/2018 07/19/2018 07/19/18 07/22/18 07/24/18

OFFICE DRS/IPAT SPE:DRP/A BC:DRP/A

NAME GGeorge RAlexander MHaire

SIGNATURE /RA/ /RA/ /RA/

DATE 07/20/2018 07/20/18 07/24/18

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