IR 05000483/2020003
| ML20307A663 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/02/2020 |
| From: | O'Keefe N NRC/RGN-IV/DRP/RPB-B |
| To: | Diya F Ameren Missouri |
| References | |
| IR 2020003 | |
| Download: ML20307A663 (21) | |
Text
November 2, 2020
SUBJECT:
CALLAWAY PLANT - INTEGRATED INSPECTION REPORT 05000483/2020003
Dear Mr. Diya:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Callaway Plant. On October 7, 2020, the NRC discussed the results of this inspection with Mr. B. Cox, Site Vice President, 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. This finding involved a violation of NRC requirements. 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 the 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 Callaway Plant.
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 Callaway Plant. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Neil F. O'Keefe, Chief Reactor Projects Branch B Division of Reactor Projects
Docket No. 05000483 License No. NPF-30
Enclosure:
As stated
Inspection Report
Docket Number:
05000483
License Number:
Report Number:
Enterprise Identifier: I-2020-003-0007
Licensee:
Union Electric Company
Facility:
Callaway Plant
Location:
Steedman, MO
Inspection Dates:
July 1, 2020 to September 30, 2020
Inspectors:
D. Bradley, Senior Resident Inspector
S. Janicki, Resident Inspector
R. Alexander, Senior Emergency Preparedness Inspector
K. Clayton, Senior Operations Engineer
Approved By:
Neil F. O'Keefe, Chief
Reactor Projects Branch B
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Callaway Plant, 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 Implement Emergency Diesel Generator Surveillance Procedures Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000483/2020003-01 Open/Closed
[H.12] - Avoid Complacency 71111.04 The inspectors reviewed a self-revealed Green, non-cited violation of Technical Specification 5.4.1.a, Procedures, for the licensees failure to implement Procedure OSP-NE-0001B, Standby Diesel Generator B Periodic Tests. Specifically, the operator did not comply with the caution statement to raise generator load greater than 109 KW within three seconds to prevent actuating the reverse power relay and tripping emergency diesel generator output breaker NB0211. This resulted in emergency diesel generator B being inoperable for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while the licensee ruled out other causes through troubleshooting.
Additional Tracking Items
None.
PLANT STATUS
Callaway Plant began the inspection period at rated thermal power. The unit operated at or near rated thermal power through September 24, 2020. On September 24, 2020, the licensee began a coast-down of reactor power into the planned refueling outage. On September 27, 2020, the licensee experienced an automatic reactor trip due to a main generator trip. The unit remained shut down through the end 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed onsite portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment for safety-related structures, including roofs, are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on August 20, 2020.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Emergency diesel generator output circuit breakers, including trip features, on July 24, 2020
- (2) Motor-driven auxiliary feedwater system, train B, on August 25, 2020
- (3) Rod control on September 7, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of train A of component cooling water on August 31, 2020.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Auxiliary building 1974' elevation, fire area A-1, on August 19, 2020
- (2) Control building 2016' elevation including electrical equipment air conditioning room, switchboard and battery rooms, fire areas C-13 and C-15, on August 24, 2020
- (3) Control building 2000' elevation including vital switchgear, fire area C-10, on September 12, 2020
- (4) Spent fuel pool area, fire area FB-1, on September 14, 2020
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during the following drills:
- Unannounced fire drill in the lower cable spreading room, fire area C-21, on July 2, 2020
- Announced fire drill in the north electrical penetration room, fire area A-18, on July 20, 2020
71111.06 - Flood Protection Measures
Cable Degradation (IP Section 03) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Essential service water cable vaults MH01A and MH01B, on July 1, 2020
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
Annual Requalification Exam Results are reviewed.
- (1) On July 28, 2020, the inspectors completed one sample by reviewing and evaluating the licensed operator examination failure rates for the requalification annual operating exam administered for the exam cycle. There were no failures on the annual examinations.
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 planned work on the train B motor-driven auxiliary feedwater system on August 12, 2020.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during post-maintenance testing on the turbine-driven auxiliary feedwater pump and restoration of an intake pump on August 26, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed control room operator training in the simulator on July 6, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Auxiliary feedwater system, including issues during valve closure tests and pneumatic controls, on August 4, 2020
- (2) Emergency diesel generator system, including issues with the air start system and output circuit breaker, on September 25, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Planned elevated risk for maintenance on train B components including the control room air conditioner and containment coolers on July 29, 2020
- (2) Planned elevated risk for maintenance on train A essential service water and emergency diesel generator on August 3, 2020
- (3) Unplanned elevated risk for maintenance on the alternate emergency power supply system on August 7, 2020.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Nuclear instrument surveillance testing results, Condition Report 202003415, on July 22, 2020
- (2) Essential service water pump room supply fan damper failure to close, Condition Report 202003794, on August 6, 2020
- (3) Control room emergency ventilation system opening, Condition Report 202003819, on August 25, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) Emergency exhaust system train A following planned maintenance on July 6, 2020
- (2) Control room air conditioning system train B following planned maintenance on July 22, 2020
- (3) Containment spray system train B following planned maintenance on July 27, 2020
- (4) Emergency diesel generator train A following planned maintenance on August 4, 2020
- (5) Motor-driven auxiliary feedwater train B following planned maintenance on August 11, 2020
- (6) Turbine-driven auxiliary feedwater pump following planned maintenance on August 25, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
- (1) The inspectors evaluated refueling outage RF24 activities from September 27-30, 2020 (Partial).
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Control room emergency ventilation system air filtration unit B on August 10, 2020
- (2) Emergency exhaust system - fuel building ventilation isolation test on August 17, 2020
- (3) Ultimate heat sink train B cooling tower fan performance testing on August 19, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Essential service water train B inservice test, including flow balance, on August 25, 2020
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system between April 1, 2018, and June 30, 2020.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Preparedness Organization between April 1, 2018, and June 30, 2020.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes:
- Radiological Emergency Response Plan (RERP), Revision 52; issued on April 30, 2020
This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program between April 1, 2018, and June 30, 2020.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the emergency response organization team 5 training drill on September 10, 2020.
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the emergency response organization team 4 training drill on September 15,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (IP Section 02.12)===
- (1) April 1, 2019, through March 31, 2020
EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)
- (1) April 1, 2019, through March 31, 2020
EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)
- (1) April 1, 2019, through March 31, 2020
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) (1 Sample)
- (1) July 1, 2019, through June 30, 2020
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) July 1, 2019, through June 30, 2020
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) July 1, 2019, through June 30, 2020
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Extent of condition inspection results for safety-related ventilation fan systems from Condition Report 202001783 on July 20, 2020
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01)
- (1) The inspectors evaluated a security diesel generator issue, Condition Report 20200494, and licensees response on September 29, 2020.
Personnel Performance (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the reactor trip caused by a main generator breaker trip and licensees performance on September 27,
INSPECTION RESULTS
Failure to Implement Emergency Diesel Generator Surveillance Procedures Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems
Green NCV 05000483/2020003-01 Open/Closed
[H.12] - Avoid Complacency 71111.04 The inspectors reviewed a self-revealed Green, non-cited violation of Technical Specification 5.4.1.a, Procedures, for the licensees failure to implement Procedure OSP-NE-0001B, Standby Diesel Generator B Periodic Tests. Specifically, the operator did not comply with the caution statement to raise generator load greater than 109 KW within three seconds to prevent actuating the reverse power relay and tripping the emergency diesel generator output breaker. This resulted in emergency diesel generator B being inoperable for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while the licensee ruled out other causes through troubleshooting.
Description:
On June 24, 2020, operations personnel were performing a startup of emergency diesel generator (EDG) B in accordance with Procedure OSP-NE-0001B, Standby Diesel Generator B Periodic Tests, Revision 67. After closing EDG B output circuit breaker NB0211, step 6.3.17 directed the operator to transfer load to the EDG greater than 0.2 MW. A caution statement prior to step 6.3.17 directed the operator to raise generator load greater than 109 KW within three seconds to prevent the EDG B reverse power relay from tripping the generator output breaker.
After closing the generator output breaker, the control room operator performed step 6.3.17 to raise EDG B loading. The first load adjustment failed to provide sufficient load requiring the operator to perform a second adjustment. During the second load adjustment, the generator output breaker tripped open on reverse power. The licensee declared EDG B inoperable and placed the EDG B hand switch in pull-to-lock.
Following the circuit breaker trip, the licensee conducted interviews and performed troubleshooting including a system walk-down of the diesel generator to identify the cause of the trip. The licensee determined the most probable cause of the trip was a legacy procedure issue regarding initial EDG loading given meter accuracy. The minimum required loading in the procedure, combined with the accuracy of the meter, places the generator loading near the 109 KW with little margin between the generator output and reverse power relay setpoints. To restore the EDG to operable, the licensee issued a night order to increase the initial loading of the EDG and re-performed the surveillance test successfully. The EDG was returned to operable 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the initial trip.
The licensee benchmarked other utilities and determined initial EDG loading of 0.7 to 1.0 MW are commonly used values at other nuclear stations. The inspectors determined this initial loading range was appreciably higher than Callaways original value. Although the low margin to a reverse power trip existed in the surveillance procedure and contributed to the trip, the inspectors did not find the procedure guidance to be the primary cause of the output breaker trip.
The inspectors assessment found that the most likely cause of the EDG output breaker trip was a human performance error where the operator failed to properly implement the EDG startup procedure contained in Procedure OSP-NE-0001B in a timely manner. The inspectors noted that the EDG start up procedure has been used successfully without challenging the reverse power trip setpoint on initial loading for over 10 years. Additionally, the operator performing the EDG startup was standing a proficiency watch and not a normal member of the on-shift crew. As a result, the operator challenged the setpoints for the reverse power trip by performing two small load adjustments after closing the generator output breaker rather than a single timely load increase large enough to clear the reverse power setpoint. Further, the inspectors determined that, although the licensee discussed the lack of proficiency during the EDG surveillance pre-job brief, the human performance and error reduction tools of peer checker and switch flagging were not adequate to prevent the event.
Corrective Actions: The licensee declared EDG B inoperable, performed troubleshooting to identify the cause of the output breaker trip, interviewed the operating crew, issued a night order to increase the initial EDG loading requirements, completed the EDG B surveillance test successfully, and generated a condition report.
Corrective Action References: Condition Report 202003091
Performance Assessment:
Performance Deficiency: The failure of licensed operators to adequately load the emergency diesel generator upon initial startup is a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance 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. Specifically, the performance deficiency resulted in the EDG being declared inoperable for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> including being placed in pull-to-lock while troubleshooting was performed to identify the cause of the breaker tripping.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The finding was determined to be of very low safety significance (Green) because it
- (1) was not a design deficiency,
- (2) did not represent a loss of system and/or function,
- (3) did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time,
- (4) did not represent a loss of the probabilistic risk assessment (PRA)function of two separate technical specification systems for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- (5) did not represent a loss of a PRA system and/or function for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
- (6) did not result in the loss of a high safety-significant, nontechnical specification train.
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. The finding had a human performance cross-cutting aspect associated with avoiding complacency, in that the watch team did not implement appropriate error reductions tools (H.12). Specifically, while it was acknowledged at the pre-job brief that the operator performing the startup was not a normal member of the watch team and was standing a proficiency watch, additional error reduction measures were not used. As a result, the operators initial loading caused the EDG output breaker to trip on the reverse power relay.
Enforcement:
Violation: Technical Specification 5.4.1.a, Procedures, states in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978.
Regulatory Guide 1.33, Revision 2, Appendix A, Section 3.s, requires procedures for startup, operation, and shutdown of safety-related pressurized water reactor systems, including emergency power sources such as diesel generators. The licensee established Procedure OSP-NE-0001B, in part, to meet this requirement. Procedure OSP-NE-0001B requires operators to raise EDG loading above 109 KW within three seconds of closing the EDG output breaker to prevent a reverse power trip.
Contrary to the above, on June 24, 2020, the licensee failed to implement required procedures for startup, operation, and shutdown of safety-related PWR systems for emergency power sources such as diesel generators. Specifically, the licensee failed to raise EDG loading above 109 KW within three seconds of closing the EDG output breaker. As a result, EDG B loading was inadequate and EDG output breaker tripped on reverse power.
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 August 4, 2020, the inspectors presented the emergency preparedness program inspection results to Mr. B. Cox, Site Vice President, and other members of the licensee staff.
- On September 24, 2020, the inspectors presented the annual operator requalification results to Mr. P. Swan, Operations Supervisor, and other members of the licensee staff.
- On October 7, 2020, the inspectors presented the integrated inspection results to Mr. B. Cox, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Reports 201706767, 201701110, 201806495, 201901917,
2002834
Miscellaneous
27
Control Building and Communications Corridor Floor Plan @
Elevation 2073'6" and Roof Plan @ Elevation 2087'2"
Hydrologic Engineering
OL-13
M-07LF02
Plumbing and Drainage System
RFR 170332
Approve a Flat Diesel Building Roof Drain Cover
RMT-1.PMB
Repetitive Maintenance Tasks
Procedures
PMDI0825412
Clean Debris from Auxiliary Building Roof Drains
PMID0825413
Clean Debris from D/G Roof Drains
PMID25415
Clean Debris from RQ Roof Drains
PMID25416
Clean Debris from FB Roof Drains
Corrective Action
Documents
Condition Reports 199902065, 200001964, 20408637, 200602565,
200608195, 200908596, 201008319, 2012002567,
201208276, 2013003338, 201406950, 201502012,
201806495
Miscellaneous
M-22EG02
Piping and Instrumentation Diagram - Component Cooling
Water System
M-763-00831
Full Length Rod Control System
MP 07-0010
Modify MCB Switches for ECHV0011, ECHV0012,
EGHV0101 and EGHV0102
0.1
Relay.BID
Protective Relays
RFR 019265A
Valves Locked/Surveilled per TS 4.7.4.A
A
RFR 4794
Diesel Generator Breakers NB0111 and NB0211
A
Procedures
CTP-EG-06080
Component Cooling Water System Chemical Addition
MSE-NB-QY003
Operational Test Sequence of 4.16 kV Diesel Generator
NE02 Air Circuit Breaker 152NB021
Component Cooling Water Train A Valve Alignment
Surveillance
Component Cooling Water Train B Valve Alignment
Surveillance
Shutdown Margin Calculations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Control Rod Partial Movement
OTO-SF-00001
Control Rod Malfunctions
Corrective Action
Documents
Condition Reports 201707147, 201804247, 20190305, 201904398, 202003512
Miscellaneous
Fire Pre-Plan
Performance-Based Standard for Fire Protection for Light
Water Reactor Electric Generating Plants
2001
Procedures
APA-ZZ-00700
APA-ZZ-00701
Control of Fire Permits
APA-ZZ-00750
Hazard Barrier Program
Fire Protection Training Program
Corrective Action
Documents
Condition Reports 202003131, 202003220
Work Orders
19510909, 19509056
71111.11Q Corrective Action
Documents
Condition Reports 202003932
Miscellaneous
T61.08108
Simulator Scenario
2/04/2020
Procedures
Turbine-Driven Auxiliary Feedwater Pump Inservice Test
Motor-Driven Auxiliary Feedwater Pump Inservice Test
ODP-ZZ-00001
Operations Department - Code of Conduct
107
Work Orders
19003560, 18502371
Corrective Action
Documents
Condition Reports 200308233, 201506272, 201703831, 201905886,
2002091, 202004225, 202004331
Miscellaneous
NN-03
System Voltage Drop
RFR 20117
Offsite Source Verification
B
RFR 6844
Diesel Generator Technical Specification Interpretation
A
ULDBD-NE/KJ-
001
Procedures
OSP-NE-00001B
Standby Diesel Generator B Periodic Tests
Technical Specification Actions - A.C. Sources
EDP-ZZ-01128
EDP-ZZ-01128,
Appendix 4
Maintenance Rule System Functions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OTG-ZZ-00005
Plant Shutdown 20% Power to Hot Standby
Train A Auxiliary Feedwater Valve Inservice Test
Corrective Action
Documents
Condition Reports 202002470, 202002696, 202003483, 202003375
Miscellaneous
Industry Guideline for Monitoring the Effectiveness of
Maintenance at Nuclear Power Plants
4A
AC Sources - Operating
Procedures
APA-ZZ-00312
APA-ZZ-00312,
Appendix F
Online Work Integrated Risk Management
EDP-GK-0113
Heat Exchanger Predictive Performance Manual
PRA-ZZ-00001
PRA Model Updates and Maintenance
Corrective Action
Documents
Condition Reports 202001602, 202003794
Condition Reports 201701745, 201804482, 202003819
Drawings
M-U2GD-1 (Q)
Piping and Instrumentation Diagram Essential Service Water
Pumphouse & Ultimate Heat Sink Elec. Rm. HVAC
Procedures
APA-ZZ-00013
Conduct of Maintenance
PDP-ZZ-00017
Fix-it-Now Team Process 12/3/2019
Work Orders
16005679.900
Corrective Action
Documents
Condition Reports 202003334, 202003518, 202003531
Condition Reports 201400345, 201407748, 201408914, 201701135,
201805449, 201905399, 202000047, 202004285
Miscellaneous
A210.0083
Valve Retest Manual
Job 19003907
MR633276
Material Request - Charcoal
RFR 18621
IST TDAFP Speed Reference Acceptance Range
B
Procedures
APA-ZZ-00356
Pump and Valve Inservice Test Program
Turbine Driven Auxiliary Feedwater Pump Inservice Test -
Group B
Train B Containment Spray Pump Inservice Test
OTN-GK-00001
Control Building HVAC System
Work Orders
19004892; 12502273; 20000658
Corrective Action
Condition Reports 202004895
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Procedures
E-0
Reactor Trip or Safety Injection
Reactor Trip Response
OTG-ZZ-00005
Plant Shutdown 20% Power to Hot Standby
Procedures
Emergency Exhaust System FBVIS Test
Corrective Action
Documents
Condition Reports 201803901, 201805003, 201806927, 201806954,
201905853, 201907255, 202001673, 202001710,
2001773, 202002446, 202002656
Miscellaneous
Letter from FEMA Region VII, Approved January 2020 ANS
Design Report
03/23/2020
Siren Service Letter - Movement of Siren 53 and
replacement of pole for Siren 51
05/27/2020
K260.0010
Callaway Plant Alert and Notification System Design Report
January
20
Procedures
Vendor Document - Callaway Semi-Annual Preventative
Maintenance & Repair Checklist (for Sirens)
2/2019
KSP-ZZ-00008
KSP-ZZ-00110
Siren Alerting System Testing
KSP-ZZ-00602
Verification of Emergency Instruction Postings
Corrective Action
Documents
Condition Reports 201802480, 201803508, 201805536, 201805537,
201901089, 201907623, 202000729, 202003776
Miscellaneous
SNUPPS RERP (Revision 5A), Section 8.2
2/1983
Licensing Impact Review (including RERP Evaluation Form)
for RERP, Revision 11
01/22/1988
Surveillance
18507225
Augmentation Drill Report (touch the wall drill starting at
23 on 10/19/2018)
10/22/2018
Surveillance
19502304
Augmentation Drill Report (call-in drill starting at 0842 on
06/08/2019)
06/10/2019
Surveillance
20502588
Augmentation Drill Report (call-in drill starting at 0954 on
05/08/2020)
05/11/2020
ULNRC-1732
Callaway Plant Radiological Emergency Response Plan,
Revision 11
2/26/1988
Procedures
EIP-ZZ-00200
Augmentation of the Emergency Response Organization
KOA-ZZ-00200
Activation of the Callaway Plant Emergency Callout System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
KSP-ZZ-00201
Emergency Augmentation Drill/Test
Corrective Action
Documents
Resulting from
Inspection
Condition Reports 202003573
Miscellaneous
Radiological Emergency Response Plan (RERP)
EP Tracking No.
2018011
50.54(q) Screen - EIP-ZZ-00101 Add2, Revision 14
03/19/2018
EP Tracking No.
2018055
50.54(q) Evaluation - EIP-ZZ-01211, Accident Dose
Assessment, Revision 38; URI Version 3.4 upgrade changes
2/26/2019
EP Tracking No.
20003
50.54(q) Screen - EIP-ZZ-A00001, ERO, Revision 21;
addition of POL0049 to Off-Normal Hours Definition
03/12/2020
EP Tracking No.
20006
50.54(q) Effectiveness Evaluation: CR 202001773,
Relocation of Emergency Siren 053 & Radiological
Emergency Response Plan (RERP), Revision 52
04/13/2020
EP Tracking No.
20009
50.54(q) Evaluation - Response time impact for JIC ERO
members (CR 202002249)
05/04/2020
Procedures
KDP-ZZ-00400
RERP Impact Evaluations and Changes
Corrective Action
Documents
Condition Reports 201802127, 201802748, 201803020, 201803725,
201803901, 201803903, 201803905, 201804072,
201804685, 201805481, 201904169, 201904375,
201905453, 201906349, 201906484, 201906661,
201906688, 201906718, 201906844, 201906852,
201906984, 201907878, 202000040, 202000869,
2002057, 202003581, 202003582
Miscellaneous
Callaway Energy Center Muster Meeting Drill Report Third
Quarter 2018
07/30/2018
Contaminated Victim Drill Report
10/21/2019
Callaway Energy Center Annual ERO Drill (AED) Report
11/12/2019
AP18007
Nuclear Oversight Audit of Emergency Preparedness
09/06/2018
AP20007
Emergency Preparedness Audit (Plan)
06/17/2020
Job 17504120
2018 Population Update Analysis
04/10/2018
Job 17506751-
500
Mini Scenario # 6 - Field Monitoring Team Report
05/24/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Job 17507545
2018 Letter of Agreement Information Surveillance:
09/10/2018
Job 18503865
2019 Population Update Analysis
03/25/2019
Job 18506769
Mini Scenario #8 Field Monitoring Team Drill Report
07/09/2019
Job 18509626
Mini-Scenario Team Drill 6/6/19 Health Physics Drill Report
06/10/2019
Job 18510002
2019 Letter of Agreement Information Surveillance:
07/16/2019
Job 19503524
2019 Population Update Analysis (Part 2)
05/22/2019
Job 19507106
20 Population Update Analysis
05/26/2020
Job 19511162
20 Health Physics Drill Report
06/23/2020
NES2019002
Notice of Closure Criteria to Escalation Letter OQC2019002
(GTRE0032)
08/15/2019
OQC20180010
Escalation of Emergency Action Level Classification
Weaknesses
08/23/2018
OQC2019002
Escalation of lack of a comprehensive plan to restore
GTREOO32 to full compliance
03/27/2019
OQC2019005
NOS Closure of Escalation on Emergency Action Level
Classification Weaknesses
04/01/2019
RERP, Appendix
G
Evacuation Time Estimates (ETE) for the Callaway Nuclear
Plant Emergency Planning Zone
(June
2012)
SP19006
2-Month Regulatory Required Review of the Emergency
Preparedness Program in accordance with
CFR 50.54(t)(1)(ii)
06/25/2019
Procedures
EIP-ZZ-00212
Protective Action Recommendations
EIP-ZZ-A0020
Maintaining Emergency Preparedness
Self-Assessments 201900029-044
Exercise Readiness and Modified Program Inspection
03/26/2019
Work Orders
Job 18003592
TSC Filter Absorber Unit Issue, TSC Non-Functional - Adjust
Air Dampers
09/13/2018
Job 19005574
Investigate ABRE0114 Lost Communication with RM-11 and
RM-23
2/15/2019
Corrective Action
Documents
Condition Reports
Miscellaneous
Drill Guide - ERO Team - 9/10/20
Drill Guide - ERO Team - 9/15/20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71151
Miscellaneous
Drill and Exercise Performance (DEP) PI Records (Annual
ERO Drill Crew 3/Team 2, Crew 5/Controller Team, 19-05
LORT Crew 1), and related ERO Participation PI Records
4Q/2019
Drill and Exercise Performance (DEP) PI Records (ERO
Training Drill Team 5, Proficiency DEP 20-1 Crew 6), and
related ERO PI Participation Records
1Q/2020
Drill and Exercise Performance (DEP) PI Records
(Proficiency DEP 20-3 Crew 1 & Crew 5), and related ERO
PI Participation Records
2Q/2020
Performance Indicator Basis Document
Various
Alert & Notification System (ANS) PI - Weekly and Siren
Tests Results
3Q/2019,
4Q/2019,
1Q/2020, &
2Q/2020
Drill and Exercise Performance (DEP) PI Records (19-04
LORT, 2019 WANO drill), and related ERO PI Participation
Records
3Q/2019
Procedures
KDP-ZZ-02000
NRC Performance Indicator (PI) Data Collection
& 19
Corrective Action
Documents
Condition Reports 202002097; 202003313; 202003346; 202003421;
2003567; 202003819; 202004179; 202004225;
2004243; 202004448; 202004496; 202004495