ML19303C894
| ML19303C894 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/30/2019 |
| From: | Jeffrey Josey NRC/RGN-IV/DRP/RPB-A |
| To: | Sawatzke B Energy Northwest |
| References | |
| IR 2019003 | |
| Download: ML19303C894 (21) | |
See also: IR 05000397/2019003
Text
October 30, 2019
Mr. Brad Sawatzke
Chief Executive Officer
Energy Northwest
MD 1023
P.O. Box 968
Richland, WA 99352-0968
SUBJECT: COLUMBIA GENERATING STATION - INTEGRATED INSPECTION
REPORT 05000397/2019003
Dear Mr. Sawatzke:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an
inspection at Columbia Generating Station. On October 10, 2019, the NRC inspectors
discussed the results of this inspection with Mr. David Brown, Plant General Manager, and other
members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. One Severity
Level IV violation without an associated finding is documented in this report. We are treating
this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement
Policy.
If you contest the violation or significance or severity of the violation documented in this
inspection report, 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 Columbia Generating Station.
If you disagree with a finding not associated with a regulatory requirement 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 Columbia Generating Station.
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, Exe mptions, Requests for
Withholding.
Sincerely,
/RA/
Jeffrey E. Josey, Chief
Reactor Projects Branch A
Division of Reactor Projects
Docket No. 05000397
License No. NPF-21
Enclosure:
As stated
cc w/ encl: Distribution via LISTSERV
X Non-Sensitive X Publicly Available
X SUNSI Review
Sensitive Non-Publicly Available
OFFICE SRI:DRP/A RI:DRP/A DRS/IPAT DRS/EB1
NAME GKolcum /GJK/ LMerker /LNM/ RAzua RVA VGaddy
DATE 10/28/2019 10/23/2019 10/27/2019 10/23/19
OFFICE DRS/EB2 DNMS/RXIB DRS/OB SPE:DRP/A
NAME NTaylor / NHT GWarnick GWerner GEW RAlexander /RDA/
DATE 10/25/2019 10/23/19 10/23/2019 10/23/2019
OFFICE DRS/RCB BC:DRP/A
NAME MHaire JJosey
DATE 10/28/19 10/30/2019
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number: 05000397
License Number: NPF-21
Report Number: 05000397/2019003
Enterprise Identifier: I-2019-003-0010
Licensee: Energy Northwest
Facility: Columbia Generating Station
Location: Richland, WA
Inspection Dates: July 1, 2019 to September 30, 2019
Inspectors: G. Kolcum, Senior Resident Inspector
L. Merker, Resident Inspector
R. Alexander, Senior Project Engineer
Approved By: Jeffrey E. Josey, Chief
Reactor Projects 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.
List of Findings and Violations
Failure to Follow Procedure Results in Open Current Transformer
Cornerstone Significance Cross-Cutting Report
Aspect Section
Initiating Events Green None (NPP) 71111.18
Open/Closed
The inspectors reviewed a self-revealed, Green finding for the licensee's failure to follow plant
Procedure 10.25.19, "Termination and Splicing Instruction," that ensures wire and cable
terminations, splices, and insulation are properly controlled. Specifically, on
February 16, 2015, the licensee did not re-terminate the current transformer wires for the low
voltage winding temperature circuit in main transformer 3 per the panel wiring termination
instructions. This resulted in the current transformer operating in an open circuit, arcing,
overheating the terminals, and damaging the feed through, which allowed transformer oil to
leak outside the transformer.
Announcement of an NRC Inspector's Presence by Station Personnel
Cornerstone Significance Cross-Cutting Report
Aspect Section
Not Applicable NCV 05000397/2019003-02 Not Applicable 71152
Open/Closed
The inspectors identified a Severity Level IV, non-cited violation (NCV) of 10 CFR 50.70(b)(4),
associated with the licensees failure to ensure the arrival and presence of an NRC inspector,
who had been properly authorized facility access, was not announced or otherwise
communicated by its employees or contractors to other persons at the facility unless
specifically requested by the NRC inspector. Specifically, a licensee employee entered the
protected area search train ahead of the NRC resident inspector and informed the nearby
security officers that the NRC resident inspector was about to enter the area without being
requested to do so by the inspector; this impacted the NRCs ability to perform its regulatory
oversight function to perform unannounced inspections.
Additional Tracking Items
Type Issue Number Title Report Section Status
LER 05000397/2017007-00 Valve Closure Results in 71153 Closed
Momentary Increase in
Pressure
2
PLANT STATUS
The reactor unit began the inspection period at rated thermal power. On July 7, 2019, plant
power was reduced to 72 percent due to high level trip of feedwater heater 1C with subsequent
trips of feedwater heaters 2A, 2B, 2C, and 3C. On July 9, 2019, the reactor was returned to
100 percent power. On September 13, 2019, plant power was reduced to 95 percent and then
returned to 100 percent due to condensate pump minimum flow maintenance. On
September 21, 2019, plant power was reduced to 73 percent to perform control rod sequence
exchange and bypass valve testing. Reactor power returned to 100 percent rated power on the
same day and stayed there for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors performed plant status activities described in
IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem
Identification and Resolution. The inspectors reviewed selected procedures and records,
observed activities, and interviewed personnel to assess licensee performance and compliance
with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to
the onset of seasonal high temperatures for the following systems on August 2, 2019:
- Standby service water A
- Standby service water B
- Division 1 switchgear
- Division 2 switchgear
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1) high pressure core spray system standby lineup following system maintenance on
July 26, 2019
(2) ac power panel 7AF lineup on August 7, 2019
(3) ac power panel 7A lineup on August 7, 2019
3
(4) high pressure core spray system standby lineup during planned reactor core isolation
cooling maintenance on September 10, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1) The inspectors evaluated system configurations during a complete walkdown of the
standby service water system A on August 16, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1) Fire Area DG-4/1, diesel generator 1 diesel fuel oil storage tank access room, on
July 17, 2019
(2) Fire Area DG-5/2, diesel generator 2 diesel fuel oil storage tank access room, on
July 17, 2019
(3) Fire Area DG-6/#, high pressure core spray diesel fuel oil storage tank access room,
on July 17, 2019
(4) Fire Area SW-1/1, standby service water pump house 1A, on July 18, 2019
(5) Fire Area SW-2/2, standby service water pump house 1B, on July 18, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
(1) emergency core cooling system pump rooms on August 16, 2019
71111.07A - Heat Sink Performance
Annual Review (IP Section 02.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1) reactor building closed cooling water system heat exchangers, RCC-HX-1A and
RCC-HX-1B, on August 23, 2019
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(2 Samples)
(1) The inspectors observed and evaluated licensed operator performance in the control
room during main turbine vibration changes on August 14, 2019.
4
(2) The inspectors observed and evaluated licensed operator performance in the control
room during the opening of the turbine miscellaneous drain valves on high differential
temperature on August 30, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1) The inspectors observed and evaluated the licensed operator requalification
evaluated scenario (Crew B) on August 5, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with
the following equipment and/or safety significant functions:
(1) high pressure core spray system on August 9, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work
activities:
(1) yellow risk for high pressure core spray system maintenance on July 25, 2019
(2) yellow risk for diesel generator 1 barover on August 7, 2019
(3) yellow risk for reactor core isolation cooling system maintenance on
September 10, 2019
(4) yellow risk for standby service water system B maintenance on September 17, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (3 Samples)
The inspectors evaluated the following operability determinations and functionality
assessments:
(1) electrical power panel E-PP-7AF low voltage on A phase on August 26, 2019
(2) diesel generator 3 mixed air fan failure on August 28, 2019
(3) diesel generator 3 starting air on September 25, 2019
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1) main condenser air removal suction valve permanently left in the open position on
August 1, 2019
5
(2) jumper installation across main transformer 3 low voltage winding temperature circuit
on August 29, 2019
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance tests:
(1) standby liquid control regulator on July 4, 2019
(2) diesel generator 3 standby service water pump on July 23, 2019
(3) high pressure core spray system on July 26, 2019
(4) diesel generator 4 annual and biannual preventative maintenance on
August 14, 2019
(5) electrical power panel E-PP-7AF following transformer replacement on
August 27, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01) (5 Samples)
(1) ISP-HPCS-X302, high pressure core spray minimum flow instrument calibration, on
July 30, 2019
(2) OSP-ELEC-W102, electrical distribution subsystem breaker alignment and power, on
August 2, 2019
(3) OSP-SW/IST-Q701, standby service water loop A operability, on August 6, 2019
(4) OSP-LPCS-M101, low pressure core spray fill verification, on August 7, 2019
(5) TSP-DG2-B502, diesel generator 2 load testing, on August 26, 2019
Inservice Testing (IP Section 03.01) (1 Sample)
(1) OSP-LPCS/IST-Q702, low pressure core spray system quarterly operability, on
August 7, 2019
FLEX Testing (IP Section 03.02) (1 Sample)
(1) OSP-FLEX-Q705, diesel generator 5 quarterly operability, on July 10, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
The inspectors evaluated:
(1) Team B Emergency Response Organization (ERO) drill on July 16, 2019.
Specifically, the inspectors evaluated the ERO's drill performance in the control room
simulator, emergency operations facility, alternate emergency operations facility, and
joint information center and assessed the overall drill critique results.
6
(2) Team A Emergency Response Organization (ERO) drill on September 10, 2019.
Specifically, the inspectors evaluated the ERO's drill performance in the control room
simulator and emergency operations facility and assessed the overall drill critique
results.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1) announcement of an NRC inspector's presence by station personnel on
August 28, 2019
(2) evaluation of the March 22, 2019, standby service water system B pump discharge
valve failure to open, on September 6, 2019
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71153 - Followup of Events and Notices of Enforcement Discretion
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
(1) LER 05000397/2017-007-00, Valve Closure Results in Momentary Increase in
Secondary Containment Pressure (ADAMS accession: ML17334B440)
The inspectors determined that the cause of the condition described in the LER was
not reasonably within the licensees ability to foresee and correct. No performance
deficiency or violation of NRC requirements was identified.
Personnel Performance (IP Section 03.03) (1 Sample)
(1) The inspectors evaluated the high level trip of feedwater heater 1C with subsequent
trips of feedwater heaters 2A, 2B, 2C, and 3C; resultant reactor downpower to
72 percent; and the licensees response on July 7, 2019.
INSPECTION RESULTS
Failure to Follow Procedure Results in Open Current Transformer
Cornerstone Significance Cross-Cutting Report
Aspect Section
Initiating Events Green None (NPP) 71111.18
Open/Closed
The inspectors reviewed a self-revealed, Green finding for the licensee's failure to follow plant
Procedure 10.25.19, "Termination and Splicing Instruction," that ensures wire and cable
terminations, splices, and insulation are properly controlled. Specifically, on
February 16, 2015, the licensee did not re-terminate the current transformer wires for the low
voltage winding temperature circuit in main transformer 3 per the panel wiring termination
instructions. This resulted in the current transformer operating in an open circuit, arcing,
overheating the terminals, and damaging the feed through, which allowed transformer oil to
leak outside the transformer.
Description: On May 14, 2019, during a transformer inspection, the licensee discovered
evidence of arcing inside the current transformer well of main transformer 3 and oil leaking to
the ground. Upon further inspection, the licensee discovered the low voltage winding
temperature current transformer wires were not connected to the current transformer terminal
block, resulting in an open current transformer. The current transformer provides an input
signal to the control logic for starting the main transformer 3 cooling fans to reduce the
temperature of the transformer during normal operation.
Plant Procedure 10.25.19, "Termination and Splicing Instruction," ensures that wire and cable
terminations, splices, and insulation are properly controlled. Step 7.11.2 states, in part, to
ensure all determ/re-term(s) [sic], splice installations, panel wiring terminations, and cable
terminations are properly completed. Attachment 9.10, "Determ/Reterm Data Sheet," of
8
Procedure 10.25.19 provides further guidance regarding determination and re-termination
data sheets. Steps 2.6 and 2.6.1 of Attachment 9.10 state, in part, that the performer lands
all required leads using Determ/Reterm Data Sheet, and after leads are landed, the verifier
checks the leads.
The licensee last determinated the current transformer wires on February 10, 2015. Work Order 02051297 provided instructions to terminate the wires to reassemble main
transformer 3. Step 4.4 of Work Order 02051297 states, in part, to terminate cables per
attached panel wiring termination instructions. This step was completed on
February 18, 2015; however, contrary to Step 7.11.2 of Procedure 10.25.19, not all
determ/reterm(s) were properly completed. Specifically, on February 16, 2015, the licensee
did not re-terminate the current transformer wires for the low voltage winding temperature
circuit in main transformer 3 per the panel wiring termination instructions. This resulted in the
current transformer operating in an open circuit, arcing, overheating the terminals, and
damaging the feed through, which allowed transformer oil to leak outside the transformer.
Corrective Actions: The licensee performed an extent of condition evaluation and verified all
other terminations on main transformers 1, 2, and 3 were configured as expected. The
licensee reconfigured the low voltage winding temperature circuit to put the transformer in a
safe condition, modified the winding temperature alarm, and put the transformer cooling in
manual until the low voltage winding temperature circuit can be repaired in the next Refueling
Outage R25.
Corrective Action References: Action Request 393438
Performance Assessment:
Performance Deficiency: The failure to follow plant Procedure 10.25.19, "Termination and
Splicing Instruction," that ensures wire and cable terminations, splices, and insulation are
properly controlled, was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor
because it was associated with the configuration control attribute of the Initiating Events
Cornerstone and adversely affected the cornerstone objective to limit the likelihood of events
that upset plant stability and challenge critical safety functions during shutdown as well as
power operations. Specifically, on February 16, 2015, the licensee did not re-terminate the
current transformer wires for the low voltage winding temperature circuit in main
transformer 3 per the panel wiring termination instructions. This resulted in the current
transformer operating in an open circuit, arcing, overheating the terminals, and damaging the
feed through, which allowed transformer oil to leak outside the transformer.
Significance: The inspectors assessed the significance of the finding using Appendix A, The
Significance Determination Process (SDP) for Findings At-Power. Using the questions in
Exhibit 1, Initiating Events Screening Questions, the inspectors determined the finding was
of very low safety significance (Green) because the finding did not cause a reactor trip and
the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to
a stable shutdown condition.
Cross-Cutting Aspect: Not Present Performance. No cross cutting aspect was assigned to
this finding because the inspectors determined the finding did not reflect present licensee
performance.
9
Enforcement: Inspectors did not identify a violation of regulatory requirements associated
with this finding.
Announcement of an NRC Inspector's Presence by Station Personnel
Cornerstone Severity Cross-Cutting Report
Aspect Section
Not Severity Level IV Not 71152
Applicable NCV 05000397/2019003-02 Applicable
Open/Closed
The inspectors identified a Severity Level IV, non-cited violation (NCV)
of 10 CFR 50.70(b)(4), associated with the licensees failure to ensure the arrival and
presence of an NRC inspector, who had been properly authorized facility access, was not
announced or otherwise communicated by its employees or contractors to other persons at
the facility unless specifically requested by the NRC inspector. Specifically, a licensee
employee entered the protected area search train ahead of the NRC resident inspector and
informed the nearby security officers that the NRC resident inspector was about to enter the
area without being requested to do so by the inspector; this impacted the NRCs ability to
perform its regulatory oversight function to perform unannounced inspections.
Description: On July 30, 2019, the resident inspector was walking towards the protected area
search train when the inspector was passed by a licensee employee. The resident inspector
observed the individual enter the search train and overheard the individual inform the nearby
security officers that the NRC resident inspector was on the way and about to enter the area.
The resident inspector had not asked the individual to announce their presence to the
security officers.
Procedure SWP-SEC-04, "Access of NRC Personnel," describes the methods used by the
licensee to control access of NRC personnel. Step 2.1.6 of Procedure SWP-SEC-04 states
that a licensee shall ensure that the arrival and presence of an NRC inspector, who has been
properly granted authorized facility access, is not announced or otherwise communicated by
its employees or contractors to other persons at the facility unless specifically requested by
an NRC inspector. The inspector noted that this encounter was in violation of Procedure
SWP-SEC-04 and constituted a minor performance deficiency.
Corrective Actions: The licensee entered this issue into the corrective action program and
provided coaching to the employee. The licensee also issued a site announcement regarding
the incident explaining that announcing the presence of an NRC inspector is highly
inappropriate and contrary to the requirements of 10 CFR 50.70.
Corrective Action References: Action Request 397451
Performance Assessment: The inspectors determined this violation was associated with a
minor performance deficiency.
Enforcement: The ROPs significance determination process does not specifically consider
the regulatory process impact in its assessment of licensee performance. Therefore, it is
necessary to address this violation which impedes the NRCs ability to regulate using
traditional enforcement to adequately deter non-compliance.
10
Severity: The inspectors evaluated the finding and determined the violation was of very low
safety significance, was not repetitive or willful, and was entered into the corrective action
program. Therefore, this violation is being treated as a Severity Level IV NCV, consistent
with the NRC Enforcement Policy.
Violation: Title 10 CFR 50.70(b)(4), requires, in part, that the licensee shall ensure that the
arrival and presence of an NRC inspector, who has been properly authorized facility access,
is not announced or otherwise communicated by its employees or contractors to other
persons at the facility unless specifically requested by the NRC inspector.
Contrary to the above, on July 30, 2019, the licensee failed to ensure that the arrival and
presence of an NRC inspector, who had been properly authorized facility access, was not
announced or otherwise communicated by its employees or contractors to other persons at
the facility unless specifically requested by the NRC inspector. Specifically, a licensee
employee entered the protected area search train ahead of the NRC resident inspector and
informed the nearby security officers that the NRC resident inspector was about to enter the
area without being requested to do so by the inspector; this impacted the NRCs ability to
perform its regulatory oversight function to perform unannounced inspections.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with
Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 10, 2019, the inspectors presented the integrated inspection results to
Mr. David Brown, Plant General Manager, and other members of the licensee staff.
11
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.01 Calculations ME-02-92-41 Calculation for Ultimate Heat Sink Analysis 007
71111.01 Calculations ME-02-92-43 Room Temperature Calculation for DG Building, Reactor 013
Building, Radwaste Building and Service Water
71111.01 Corrective Action Action Requests 381176, 382754, 385692, 391357, 392706, 393813,
Documents (ARs) 397509, 397579, 397587, 397588
71111.01 Procedures SOP- Hot Weather Operations 006
HOTWEATHER-
71111.01 Procedures SOP-SW-SPRAY Standby Service Water Spray Header Operations 000
71111.01 Procedures SOP- Warm Weather Operations 016
WARMWEATHER-
71111.01 Work Orders 02114379, 02109629/02109631
71111.04Q Drawings M520 HPCS and LPCS Systems Reactor Building Flow Diagram 105
71111.04Q Procedures ISP-HPCS-X302 HPCS Flow Rate Low (Minimum Flow) - CC 008
71111.04Q Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031
Power Availability Verification
71111.04Q Procedures OSP-HPCS-M102 HPCS Valve Lineup 005
71111.04Q Procedures SOP-ELEC-AC-LU AC Electrical Distribution System Breaker Lineup 074
71111.04Q Procedures SOP-HPCS-LU HPCS Valve and Breaker Lineup 004
71111.04Q Procedures SOP-HPCS-STBY Placing HPCS in Standby Status 004
71111.04S Miscellaneous FSAR Chapter 9.2
71111.04S Procedures SOP- Hot Weather Operations 006
HOTWEATHER-
71111.04S Procedures SOP-SW-DRAIN Standby Service Water Drain 008
71111.04S Procedures SOP-SW-FILL Standby Service Water System Fill 002, 007
71111.04S Procedures SOP-SW-LU Standby Service Water System Valve & Breaker Lineup 010
71111.04S Procedures SOP-SW-OPS Standby Service Water Operations 002, 009
71111.04S Procedures SOP-SW- Standby Service Water System Shutdown 002
SHUTDOWN
71111.04S Procedures SOP-SW-SPRAY Standby Service Water Spray Header Operations 000, 003
12
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.04S Procedures SOP-SW-START Standby Service Water System Start 008
71111.04S Procedures SOP-SW-STBY Placing Standby Service Water in Standby Status 002, 003
71111.04S Procedures SOP-SWCF-LU Service Water Chemical Addition System Valve Line-up 000
71111.05Q Corrective Action Action Requests 397011, 397014, 397016
Documents (ARs)
Resulting from
Inspection
71111.05Q Fire Plans PFP-DG- Power Block Pre-Fire Plan: Diesel Generator Building 004
BUILDING
71111.05Q Fire Plans PFP-MN-XFMR- Pre-Fire Plan: Standby Service Water Pumphouses 1A & 006
YD-MISC 1B
71111.05Q Procedures PPM 15.1.2 Fire Door Operability Surveillance 027
71111.05Q Procedures PPM 15.3.17 Fire Door Operability - Semiannual, Annual, Biennial 010
71111.06 Procedures 10.2.251 Installation of Temporary Flood Barriers 000, 001
71111.06 Procedures 15.4.6 Essential Fire Rated Penetration Seal and Essential Fire 010
and Flood Barrier Operability Inspection
71111.06 Procedures ABN-FLOODING Flooding 002, 020
71111.06 Procedures ISP-FDR-X301 ECCS Pump Room Flood Level - Calibration 003
71111.07A Corrective Action Action Requests 338360, 364270, 364288
Documents (ARs)
71111.07A Drawings M508-1 Plant Service Water System All Buildings Flow Diagram 129
71111.07A Miscellaneous 10.07.70 Calculation for TSW and RCC Heat Exchanger Steady Flow 000
71111.07A Miscellaneous ME-02-18-09 Tube Plugging Limits for RCC Heat Exchangers 000
71111.07A Miscellaneous ME-02-91-28 Calculation for Heat Exchanger Effectiveness Evaluation 000
71111.07A Miscellaneous SD000196 Reactor Closed Cooling Water 011
71111.07A Miscellaneous SPC 350 Plant Service Water (TSW) System Design Basis Document 006
71111.07A Procedures ABN-RCC Loss of RCC 006
71111.07A Procedures SOP-RCC-OPS RCC System Operations 007
71111.07A Procedures SYS-4-22 Maintenance Rule Program 014
71111.07A Work Orders 02074046, 02019119, 02031264, 01165204
71111.11Q Corrective Action Action Requests 397827, 398564, 398613, 398624, 398786
Documents (ARs)
71111.11Q Engineering 17964 Temporary Modification to Keep MD-V-87 Open and 000, 001
13
Inspection Type Designation Description or Title Revision or
Procedure Date
Changes Jumper Relay TG-RLY-TR/SMT Closed
71111.11Q Miscellaneous Crew B Evaluated 4.0 Critique Summary 000
Scenario Cycle 19-
3
71111.11Q Miscellaneous LR002465 Cycle 19-3 Evaluated Scenario 000
71111.11Q Procedures 1.19.3A Vibration Monitoring 003
71111.11Q Procedures 13.1.1 Classifying the Emergency 049
71111.11Q Procedures 13.1.1A Classifying the Emergency Technical Bases 034
71111.11Q Procedures 5.1.1 RPV Control 022
71111.11Q Procedures 5.1.2 RPV Control - ATWS 026
71111.11Q Procedures 5.1.3 Emergency RPV Depressurization 022
71111.11Q Procedures 5.2.1 Primary Containment Control 028
71111.11Q Procedures 5.5.1 Overriding ECCS Valve Logic to Allow Throttling RPV 006
Injection
71111.11Q Procedures 5.5.25 Alternate Injection Using the SLC System 006
71111.11Q Procedures ABN- Earthquake 015
71111.11Q Procedures ABN-FLOODING Flooding 020
71111.11Q Procedures ABN-LEAKAGE Reactor Coolant Leakage 007
71111.11Q Procedures OI-69 Time Critical Operator Actions 013
71111.11Q Procedures SOP-MT-START Main Turbine Start 029
71111.11Q Work Orders 02149788
71111.12 Corrective Action Action Requests 249204, 374239, 368837, 376172, 389755, 397093,
Documents (ARs) 397124, 397167, 397179, 397181, 397223, 397279
71111.12 Work Orders 02116085, 02116951, 02116991, 02118186, 02118456,
02131311, 02136227
71111.13 Corrective Action Action Requests 397227, 397294
Documents (ARs)
71111.13 Miscellaneous 19-0020 Fire Prevention Evaluation for RB 471 SW General Floor 07/22/2019
Area
71111.13 Miscellaneous 19-0021 Fire Prevention Evaluation for RB 522 General Floor Area; 07/22/2019
RMS 410-412; E-IR-P027
71111.13 Miscellaneous 19-0022 Fire Prevention Evaluation for R548; RM 512; RM 516 07/22/2019
14
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.13 Miscellaneous 19-0023 Fire Prevention Evaluation for RW437 C106; Behind SHLD 07/22/2019
Wall; C130/131
71111.13 Miscellaneous 19-0024 Fire Prevention Evaluation for Division 2 RM C213; Division 07/22/2019
2 RM C224
71111.13 Miscellaneous 19-0025 Fire Prevention Evaluation for RW 525 RM 502; RM C503, 07/22/2019
RM C510
71111.13 Miscellaneous 19-0026 Fire Prevention Evaluation for SM-7 SWGR RM C208 07/22/2019
71111.13 Procedures 1.3.10 Plant Fire Protection Program Implementation 034
71111.13 Procedures 1.3.76 Integrated Risk Management 055, 056
71111.13 Procedures 1.3.83 Protected Equipment Program 030
71111.13 Procedures 1.3.85 On-line Fire Risk Management 005
71111.13 Procedures ABN-SW Service Water Trouble 015
71111.13 Procedures SOP-RCIC- Placing RCIC in Standby Status 012
STANDBY
71111.13 Work Orders 02147259, 02111466, 02118499
71111.15 Corrective Action Action Requests 397437, 397507, 397548, 397608, 395246, 398540,
Documents (ARs) 393270, 360595, 399533, 399463, 369316, 369318
71111.15 Drawings EWD-46E-240 AC Electrical Distribution System Power Panel E-PP-7AF 019
Electrical Wiring Diagram
71111.15 Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031
Power Availability Verification
71111.15 Procedures SOP-ELEC-AC-LU AC Electrical Distribution System Breaker Lineup 074
71111.15 Work Orders 02136940, 02137174, 02137381, 02137558, 02147724
71111.18 Corrective Action Action Requests 370326, 371242, 397439, 397553, 397557, 393438,
Documents (ARs) 395744
71111.18 Drawings CVI 215-09, 7 Wafer Valve 24 in General Arrangement with Cylinder 002
71111.18 Drawings D-ARV1GAG-488 Mechanical Gag for AR-V-1 000
71111.18 Drawings EWD-46E-283 AC Electrical Distribution System Main Transformer E-TR- 015
M3 Power Supply and Auxiliary CKTS
71111.18 Drawings M511 Gas & Air Removal System Flow Diagram 058
71111.18 Engineering 16670 Bypass AR-SPV-1/1 to Open AR-V-1 and Keep It Open 002
Changes
71111.18 Engineering 17007 AR-V-1 Permanent Gag Open 001
Changes
15
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.18 Engineering 17761 Install Jumper Across M3 LV Temperature CT 000
Changes
71111.18 Procedures 10.25.19 Termination and Splicing Instruction 026
71111.18 Procedures 3.1.6C Instrument Rack Valve Lineup Turbine Generator Building 010
441' Elevation
71111.18 Work Orders 02118726, 02125129, 02051297, 02115677, 02115678,
02115679, 02144461
71111.19 Corrective Action Action Requests 397093, 397165, 397279, 381813, 397437
Documents (ARs)
71111.19 Drawings EWD-46E-240 AC Electrical Distribution System Power Panel E-PP-7AF 019
Electrical Wiring Diagram
71111.19 Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031
Power Availability Verification
71111.19 Procedures OSP-FLEX-M704
71111.19 Procedures OSP-HPCS/IST- HPCS System Operability Test 058
Q701
71111.19 Procedures OSP-INST-M101
71111.19 Procedures OSP-SW/IST-
Q703
71111.19 Procedures SOP-ELEC-AC-LU AC Electrical Distribution System Breaker Lineup 074
71111.19 Work Orders 02116085, 02116951, 02118186, 02118456, 02136227,
02138600, 02117111, 02117108, 02117109, 02126089,
02115248, 02147724
71111.22 Corrective Action Action Requests 322512, 325768, 368884, 388014, 391335, 398380,
Documents (ARs) 398388, 398402, 398403, 398405, 398408, 398410
71111.22 Drawings M520 HPCS and LPCS Systems Flow Diagram 105
71111.22 Miscellaneous 18-0428 E-IR-P024 Barrier Impairment Permit 07/22/2019
71111.22 Miscellaneous E/I-02-91-1060 Calculation for Setpoint Range and Allowable Value 001
Determination for Instrument Loop HPCS Flow Indicating
Switch 6
71111.22 Miscellaneous E/I-02-92-04 Calculation for Flow Calibration Curve Verification for HPCS 000
Flow Element 7 and Flow Transmitter 5 and Flow Indicating
Switch 6
71111.22 Miscellaneous EC QMR 13763 HELB Barrier Impairment for P001, P005, P018, P021, 004
16
Inspection Type Designation Description or Title Revision or
Procedure Date
P026, and P027
71111.22 Miscellaneous HPCS-FIS-6 Instrument Master Data Sheet 012
71111.22 Procedures 1.5.1 Surveillance Testing Program 040
71111.22 Procedures 1.5.19 Surveillance Frequency Control Program 000
71111.22 Procedures ISP-HPCS-X302 HPCS Flow Rate Low (Minimum Flow) -- CC 008
71111.22 Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031
Power Availability Verification
71111.22 Procedures OSP-FLEX-Q705 Diesel Generator 5 Quarterly Surveillance 000
71111.22 Procedures OSP-LPCS-M101 LPCS Fill Verification 015
71111.22 Procedures OSP-LPCS/IST- LPCS System Operability Test 044
Q702
71111.22 Procedures OSP-SW/IST- Standby Service Water Loop A Operability 032
Q701
71111.22 Procedures SOP-LPCS-STBY Placing LPCS in Standby Status 002
71111.22 Procedures TSP-DG2-B502 Standby Diesel Generator DG2 Load Testing 024
71111.22 Work Orders 02136320, 02106811, 02118313, 02113216, 021137715,
0213659901
71114.06 Corrective Action Action Requests 395491, 396909, 396911, 397283
Documents (ARs)
71114.06 Miscellaneous Columbia Generating Station Classification Notification 07/16/2019
Forms for July 2019 ERO Drill
71114.06 Miscellaneous Team B - ERO Drill July 2019: Drill Scenario Timeline 07/16/2019
71114.06 Miscellaneous After Action Report Columbia Generating Station ERO Team B Drill Report 08/06/2019
/ Improvement (July 16, 2019)
Plan
71114.06 Procedures PPM 13.1.1 Classifying the Emergency 049
71151 Miscellaneous MSPI Indicator Margin Remaining In Green Report 07/18/2019
71151 Miscellaneous MSPI Derivation Report: Emergency AC Power System 07/18/2019
71151 Miscellaneous MSPI Derivation Report: High Pressure Injection System 07/18/2019
71151 Miscellaneous MSPI Derivation Report: Heat Removal System 07/18/2019
71151 Miscellaneous MSPI Derivation Report: Residual Heat Removal System 07/18/2019
71151 Miscellaneous MSPI Derivation Report: Cooling Water System 07/18/2019
71151 Miscellaneous MSPI-01-BD-0001 Mitigating System Performance Index (MSPI) Basis 021
17
Inspection Type Designation Description or Title Revision or
Procedure Date
Document
71151 Procedures 1.10.10 Consolidated Data Entry Process Description 008
71151 Procedures SYS-4-34 PSA Configuration Control 007
71152 Corrective Action Action Requests 391347, 391334, 391352, 397451, 391337, 391347,
Documents (ARs) 391352, 398152
71152 Miscellaneous ACEMAN Thumbs Down Submission 08/01/2019
71152 Procedures 10.25.105 Motor Control Center and Switchgear Maintenance 036
71152 Procedures 10.25.13A 4.16KV Vacuum Breaker Maintenance with Stored Energy 020
Mechanism
71152 Procedures ABN-BKR-FAULT Failure of MOC Switch Activation for Safety Related 002
Breakers
71152 Procedures ABN-SW Service Water Trouble 015
71152 Procedures GBP-LIC-08 Preparation and Conduct of NRC Inspections 004
71152 Procedures SWP-SEC-04 Access of NRC Personnel 006
71152 Work Orders 02140678
71153 Corrective Action Action Requests 372103, 372134, 396522
Documents (ARs)
71153 Miscellaneous Operations Log: July 6 - July 7, 2019 07/07/2019
71153 Procedures ABN-FWH- Feedwater Heater High Level Trip 007
HILEVEL/TRIP
71153 Procedures ABN-POWER Unplanned Reactor Power Change 016
71153 Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031
Power Availability Verification
71153 Work Orders 02119476, 02010762, 29150355
18