IR 05000483/2020002

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Integrated Inspection Report 05000483/2020002
ML20211L743
Person / Time
Site: Callaway Ameren icon.png
Issue date: 07/29/2020
From: O'Keefe N
NRC/RGN-IV/DRP/RPB-B
To: Diya F
Ameren Missouri
References
IR 2020002
Download: ML20211L743 (21)
v • d • e


Text

July 29, 2020

SUBJECT:

CALLAWAY PLANT - INTEGRATED INSPECTION REPORT 05000483/2020002

Dear Mr. Diya:

On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Callaway Plant and 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.

No NRC-identified or self-revealing findings were identified during this inspection.

A licensee-identified violation which was determined to be of very low safety significance 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 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. 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,

/RA/

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: NPF-30 Report Number: 05000483/2020002 Enterprise Identifier: I-2020-002-0007 Licensee: Union Electric Company Facility: Callaway Plant Location: Steedman, MO Inspection Dates: April 1 to June 30, 2020 Inspectors: B. Baca, Health Physicist D. Bradley, Senior Resident Inspector G. George, Senior Reactor Inspector S. Janicki, Resident Inspector J. Melfi, Project Engineer D. Proulx, Senior Project Engineer E. Simpson, Health Physicist Approved By: Neil F. O'Keefe, Chief Reactor Projects Branch B Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at the 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. A licensee-identified non-cited violation is documented in report section 7115

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000483/2020-001-00 Emergency Exhaust Train 71153 Closed Inoperable Due to Fan Belt Degradation and Failure

PLANT STATUS

Callaway Plant began the inspection period at rated thermal power. On April 4, 2020, the unit automatically tripped on low steam generator water level due to a controller failure for a feedwater control valve. After replacing the failed controller and other similar controllers for the feedwater control valves, the licensee commenced a reactor startup on April 6, 2020. The licensee returned to rated thermal power on April 8 2020, and remained at or near rated thermal power 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 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

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures for the following systems:
  • Offsite power sources including the switchyard, alternate emergency power system, startup transformer, and engineered safety feature transformers
  • Diesel generators

71111.04 - 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) Feedwater regulating valves on April 8, 2020
(2) Residual heat removal injection valves on April 22, 2020
(3) Auxiliary feedwater flow control valves on May 4, 2020
(4) Supplemental cooling fans for Class 1E electrical switchgear on May 19, 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) Vital switchgear rooms, fire area C-9, on April 1, 2020
(2) Auxiliary building normal and alternate access pathways for fire brigade response, fire areas A-1, A-8, A-16, A-19, on May 4, 2020
(3) Diesel generator room A, fire area D-1, on June 5, 2020
(4) Essential service water pumphouse north and ultimate heat sink cooling tower north, fire areas UNPH and UNCT, on June 12, 2020

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Diesel generator rooms, including sumps, on May 11, 2020

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of the following systems on April 20, 2020:

(1)

  • Class 1E electrical equipment air conditioning unit A (SGK05A)
  • Class 1E electrical equipment air conditioning unit B (SGK05B)

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated simulator training for crew 6 on May 27, 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) Alternate emergency power supply system on April 24, 2020
(2) Toggle switch high resistance oxide formation in vital and non-vital 125 VDC control circuits on June 15, 2020

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSCs remain capable of performing their intended function:

(1) Time-based preventative maintenance for safety-related components in the high pressure and low pressure emergency core cooling systems, including quality control, on May 6, 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 and surveillances on vital inverter NN11, class 1E air conditioning unit SGK05A, and emergency diesel generator A on April 15, 2020
(2) Planned elevated risk for maintenance and surveillances on containment spray B room cooler and emergency diesel generator B on April 29, 2020
(3) Emergent maintenance and elevated risk for control room air conditioning system B on May 8, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Pressurizer level instrumentation drift, Condition Report 20201824, on April 7, 2020
(2) Hardened condensate storage tank supply valve opening during plant trip, Condition Reports 202001785 and 202001790, on April 7, 2020
(3) Residual heat removal motor-operated valve EJHV8716A and environmental qualification, Condition Report 202001938, on April 16, 2020
(4) Core exit thermocouple signal noise, Condition Report 202002021, on April 20, 2020
(5) Essential service water pump house and emergency diesel generator ventilation system damper performance in tornado scenarios, Condition Reports 202002185 and 202002160, on April 29, 2020
(6) Control room air conditioning system failures in July 2019, November 2019, and May 2020. Condition Reports 201905364, 201907363, and 202002325 on May 6, 2020.

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

(1 Sample)

The inspectors evaluated the following permanent modification:

(1) Essential service water B strainer backwash line replacement, MP 17-0010, on April 20, 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) Vital inverter NN18 following planned maintenance on April 24, 2020
(2) Containment spray B room cooler fan belts following planned replacement on April 30, 2020
(3) Class 1E electrical equipment air conditioning unit B following compressor replacement on May 25, 2020
(4) Pressurizer level instrument following planned replacement on June 18, 2020
(5) Motor-operated valves, EMHV8803B and BGHV8837B, following planned maintenance on June 18, 2020
(6) Containment cooler A fan time delay relay following replacement on June 22, 2020

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

Main article: IP 71111.22
(1) Reactor trip breaker train A actuating device test on May 8, 2020
(2) Spent fuel pool bridge and crane testing on June 15, 2020

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Containment escape hatch local leak rate test on June 7, 2020

FLEX Testing (IP Section 03.02) (1 Sample)

(1) Flex diesel generator testing and flex debris removal vehicle testing on May 28,

RADIATION SAFETY

71124.02 - Occupational ALARA Planning and Controls

Radiological Work Planning (IP Section 03.01) (4 Samples)

The inspectors evaluated the integration of as low as is reasonably achievable planning into the following work activities:

Radiation work permits (RWP):

(1) Specific RWP R23HDSTUD18, "Refuel 23 activities to remove reactor vessel stuck stud #18, including thread repairs, and inspect its stud hole. Includes cutting, boring, QC/Engineering inspections, and associated cavity work (except cavity decontamination)," Revision 0.
(2) Specific RWP R23HDSTUD18, "Refuel 23 activities to remove reactor vessel stuck stud #2 and repair reactor vessel stud hole #18. Includes thread repairs, inspecting stud hole, cutting, boring, QC/Engineering inspections, and associated cavity work (except cavity decontamination)," Revisions 1-3.
(3) Specific RWP R23STD18DECON, "RF23 preparation for/cleanup after removal of stuck stud #2 and repair of stud hole #18. Work includes gross wash and rinse upper cavity, decontamination stud #2 and stud hole #18 work areas, clean RV flange around stud #2 and stud hole #18, building playpen around the work area, clean upper cavity when work is complete. Includes RP coverage and surveys," Revision 0 and Revision 1.
(4) Specific RWP R23STUD2RECOV, "Refuel 23 activities repair and install reactor vessel stud hole #2. Includes thread repairs, inspecting stud hole, cutting, boring, sleeving, QC/Engineering inspections, and associated cavity work (except cavity decontamination)," Revision 0 Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (3 Samples)

The inspectors evaluated dose estimates and exposure tracking.

ALARA package number:

(1) R23-55220, "Reactor Head Work", dated September 18, 2019. This package contained radiation work permits which included stud de-tensioning, electrical interference removal/re-installation, reactor head lift, reactor head inspection, O-ring replacement, and insulation removal/re-installation.
(2) R23-55290, "Reactor Building Head Stud 18 Activities", dated March 4, 2020. This package contained radiation work permits which included the removal of stuck studs #2 and #18, thread repairs, stud hole inspection, sleeving activities for stud hole #2, and decontamination activities.
(3) R23-SCAFFOLD, "Scaffolding for Refueling Outage 23", dated May 24, 2019. This package contained radiation work permits for scaffolding activities which included insulation removal/re-installation, valve inspection and maintenance, snubber testing and maintenance/repair, reactor head inspection and maintenance, reactor coolant pump motor maintenance, and installations for work in the radiologically controlled area in non-high radiation areas and high radiation areas.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (1 Sample)

During the inspection period, the licensee did not have airborne radioactivity areas or personnel contaminations for which an internal dose assessment was made. The inspectors reviewed air sampling data, selected surveys, and all personnel contamination events from May 1, 2018, to May 29, 2020.

The inspectors reviewed whole body analysis reports of selected declared pregnant workers for the assignment of internal dose to the declared pregnant worker and the embryo/fetus:

(1) Analysis reports dated: June 6, 2018; November 27, 2018; July 15, 2019; and

February 18, 2020 Special Dosimetric Situations (IP Section 03.04) (2 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Dose Analysis 921 for a discrete radioactive particle identified on the chest in the left pectoral area of a worker
(2) Documentation for four declared pregnant workers from May 1, 2018, to May 29,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicator submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) ===

Main article: IP 71151
(1) April 1, 2019 through March 31, 2020

MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)

(1) April 1, 2019 through March 31, 2020

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) April 1, 2019 through March 31, 2020

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in safety-related ventilation that might be indicative of a more significant safety issue.

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) Administrative control of containment isolation valve technical specifications during maintenance on the containment spray system under Condition Report 202001556, on April 14, 2020

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

Main article: IP 71153

The inspectors evaluated the following licensee event report (LER):

(1) LER 05000483/2020-001-00, Emergency Exhaust Train Inoperable Due to Fan Belt Degradation and Failure, (ADAMS Accession No. ML20108F546) on April 20, 2020.

The inspectors reviewed the LER submittal. The conclusions associated with this LER are documented in the Inspection Results section of this report. This licensee event report is closed.

Personnel Performance (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the reactor trip on low steam generator water level due to a controller failure for a feedwater control valve and the licensees performance on April 4,

INSPECTION RESULTS

Observation: Semiannual Trend Review 71152 The inspectors reviewed the licensees corrective action program, performance indicators, system health reports, and other documentation to identify trends that might indicate the existence of a more significant safety issue for the following system: safety-related heating, ventilation, and air conditioning (HVAC).

As part of the cause evaluation for the issue described in Licensee Event Report (LER) 05000483/2020-001-00, Emergency Exhaust Train Inoperable Due to Fan Belt Degradation and Failure, (ADAMS Accession Number ML20108F546), the licensee performed an extent of condition review. This involved scheduling jobs to look at all 29 safety-related HVAC components that use fan belts. The job tasks included checking for belt tension, material condition, fan performance, and replacing belts as needed. The licensee placed a high priority on these tasks, starting the work in February 2020, and completing approximately 40 percent of the inspections by the end of May 2020. Although the scope and prioritization of the inspections were appropriate, the licensee encountered several types of issues during this work. The licensees inspections to-date identified the following:

  • Five fans were found with out-of-specification belt tension
  • Three belts were installed after they had exceeded the recommended shelf life
  • Two belts had been installed using an outdated revision of the work instructions
  • Eight components were found to have out-of-specification fan speed
  • One of the installation work orders failed to take as-found data before replacing/tensioning the fan belt Note that these results were not yet complete, but reflect the information available at the time of inspection. With the exception of the original emergency exhaust fan belt failure, none of the above issues resulted in an inoperability of the associated systems.

The examples of not completing the job to the correct revision represent gaps in coordination and planning for corrective actions. Similarly, the example of not taking as-found data represents errors in communication and results in missing data that is used in past operability assessments. The examples of installing a belt that has exceeded its shelf life, as-found belt tension being out of tolerance, and identifying fans that are outside their design for speed represent gaps in maintaining design control that the station was not sensitive to prior to the emergency exhaust fan belt failure. Specifically, the licensee was not aware of vendor information and operating experience at other stations, such that Callaway was not appropriately monitoring shelf life for belts, had been using an improper installation method that could damage the belts, and was not establishing the correct belt tension.

Condition Report 202002488 for the residual heat removal A room cooler (SGL10A) is of particular interest. When the belt inspection was completed using the incorrect revision of the job, the belts were improperly installed by rolling on under tension instead of after fan disassembly with minimal tension. This recreated a condition that the licensee was attempting to correct via this job. The licensee identified this issue through their post-work interviews, wrote the condition report, assessed operability, and scheduled the work to be done again correctly.

The licensee created several roll-up condition reports to capture the above issues. For example, Condition Report 202002763 describes the failure to collect data, inadequate communication, and a lack of a questioning attitude while performing these jobs. Condition Report 202002737 describes cross-functional weaknesses in teamwork including preparation, a lack of formality in assigning corrective actions, and not appropriately considering short-term vulnerabilities while performing fan belt work without a complete cause evaluation.

The original root cause, Condition Report 202000878, has also been updated with these issues and corrective actions assigned.

The inspectors acknowledge that the licensee identified the original broken fan belt through operator tours of the plant. Similarly, the issues described above are the results of an extensive and aggressive extent-of-condition and extent-of-cause review process by the licensee.

The inspectors area of concern for safety-related HVAC issues is the gap in knowledge that was available via operating experience and vendor information prior to the failure. Given the number of examples affecting several aspects of safety-related HVAC systems, the inspectors determined that this may be an emerging trend.

Overall, the inspectors concluded that the licensee demonstrated a low threshold for issue identification and documentation in the corrective action program. The licensee applied a risk-based approach to ensure corrective actions were scheduled commensurate with an issues safety significance. The inspectors did not identify any additional trends or concerns that might be indicative of a more significant issue.

Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Callaway Plant Technical Specification 5.4.1, Procedures, requires, 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 9, Procedures for Performing Maintenance, states, in part, that maintenance that can affect the performance of safety-related equipment should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.

Contrary to the above, from June 25, 2019, to February 18, 2020, the licensee failed to properly preplan and perform maintenance that can affect the performance of safety-related equipment in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. Specifically, work instructions to install and tension drive belts for safety-related fans were not appropriate to the circumstances because the maintenance instructions failed to incorporate vendor guidance and industry standards intended to ensure proper service life of fan belts. As a result, the licensee improperly installed drive belts in the emergency exhaust system fans by rolling them on under tension, installed belts that had exceeded their shelf life, and did not provide adequate belt tension values including post-run tension checks. These inadequate procedures and instructions for safety-related drive belts resulted in the emergency exhaust fan CGG02B inner belt failing which rendered the train B emergency exhaust system inoperable for several months. This was reported in LER 05000483/2020-001-00, Emergency Exhaust Train Inoperable Due to Fan Belt Degradation and Failure.

Significance/Severity: Green.

Significance: The inspectors determined the finding to be of very low safety significance (Green) because the finding only represented a degradation of the radiological barrier function provided for the auxiliary building and spent fuel building.

Corrective Action References: Condition Report

EXIT MEETINGS AND DEBRIEFS

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

  • On July 1, 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 Type Designation Description or title Revision or

Procedure Date

71111.01 Work Orders 19505163

Procedures OTN-EF-00001 Essential Service Water System 79

OTN-NB-0001A 4.16 kV Vital Electrical System 14

OTS-ZZ-00007 Plant Cold Weather 38

PSP-ZZ-00027 Seasonal Readiness Program 9

71111.04 Corrective Action Condition Reports 200801549, 201606169, 201006463, 201706283,

Documents 201905734, 202001783, 202001795

Procedures EDP-ZZ-01111 Vibration Predictive Maintenance 24

MPE-ZZ-QY105 Operational Test Sequence of Motor Driven Auxiliary Feed

Water Pumps

ODP-ZZ-00002 Equipment Status Control 93

OTN-AE-00001 Feedwater System 56

OTN-GK-00001 Control Building HVAC System 61

71111.05AQ Corrective Action Condition Reports 202001745, 202002617, 202002649, 202002650

Documents

Miscellaneous Fire Pre-Plan 40

71111.06 Corrective Action Condition Reports 201103241, 201707058, 201905291

Documents

Miscellaneous M-FL-10 Maximum Flood Level for Rooms in the Diesel Generator 2

Building

Procedures APA-ZZ-00395 Significant Operator Response Training 31

OTA-RK-00024, Diesel Generator Room A Sump Level Hi 2

Addendum 95B

71111.07 Corrective Action Condition Reports 201902874, 202001475, 202001748

Documents

Procedures ETP-ZZ-03001 GL89-13 Heat Exchanger Inspection 13

Miscellaneous TSB 3.7.30 Class 1E Electrical Equipment Air Conditioning System

71111.11 Corrective Action Condition Reports 202003053

Documents

Miscellaneous T61.0810 S-1 Cycle 20-3 Simulator Training 3/30/2020

Procedures E-1 Loss of Reactor or Secondary Coolant 21

E-3 Steam Generator Tube Rupture 24

ES-1.1 SI Termination 17

71111.12 Corrective Action Condition Reports 201806154, 201806860, 200000025, 202000297,

Documents 202000964, 202001429, 202002179, 202002301,

2002376

Miscellaneous AEPS DG PM List 5/1/2020

E-0518B Specifications for Transfer Switches

PRA-SY- At-Power Internal Events Probabilistic Risk Assessment 1

Electrical (PRA), Electrical Power System Analysis Notebook

RFR 20458 Battery Charger Float-Equalize Switch and Potentiometer B

RFR 4440 Post Maintenance Test Requirements for Batteries A

Procedures OTN-PA-00002 Loss of Coop Power to PA501 and PB05 14

MSE-ZZ-QB002A Quarterly Surveillance on NK11 Large Station Batteries 17

MTE-ZZ-QB012B Battery Charger Maintenance, Field Adjustments and 18

Troubleshooting

MTE-ZZ-QN005 Electrical Scheme Checkout 11

71111.13 Corrective Action Condition Reports 202002090, 202002243, 202002347, 202002374,

Documents 202002380, 202002412, 202002412, 202002539,

2002741, 202002855

Miscellaneous NUMARC 93-01 Industry Guidelines for Monitoring the Effectiveness of 4

Maintenance at Nuclear Power Plants

Procedures APA-ZZ-00322 Integrated Work Management Process Description 20

APA-ZZ-00322, Online Work Integrated Risk Management 18

Appendix F

APA-ZZ-01250 Operational Decision Making 18

EDP-ZZ-01128, SSCs in the Scope of the Maintenance Rule at Callaway 11

Appendix 1

ODP-ZZ-0002, Risk Management Actions for Planned Risk Significant 17

Appendix 2 Activities

71111.15 Corrective Action Condition Reports 200801549, 202000856, 202001030, 202001312,

Documents 202001064, 202001206, 202001824, 20201894,

2002021, 202002160, 202002185, 202002380,

2003030

Drawings M-627A-00097 DAA-P-7401 Multiblade Damper w/o Seals Q Listed 7

M-627A-00138 Dampers - 7401 Q List Schedule 9

M-627A-00144 Dampers Multiblade Q Listed Schedule 13

M-627A-00146 DAA-P-7401 Multiblade Damper Opp. Blade 'Q' Listed 7

Miscellaneous Pressurizer instrument level trend graphs

Final Safety Analysis Report 16.3.3.8

NSAL 95-06

M-627A Specifications for Dampers 16

EF-45 Acceptance Criteria Used in Essential Service Water Flow 8A

Balance Procedures

Job 20001272 Investigate Breaker SGK05BCCB Found Tripped

Job 20001708 PB0501 Will Not Open From PBXY0001

Procedures EOP HCST Alignment 2

Addendum 42

OTN-EJ-00001 Residual Heat Removal System 28

71111.18 Corrective Action Condition Reports 201904906, 201905348, 201905361

Documents

Miscellaneous MP 17-0010 Essential Service Water Strainer Backwash Pipe 4

Replacement

71111.19 Corrective Action Condition Reports 201705588, 201805136, 201865386, 202002725,

Documents 202002747, 202002999

Work Orders 15503046, 16512777, 16512791, 17505696, 19004910,

200522

Procedures MTE-ZZ-QA002 Troubleshooting General Controls Actuators 5

MTE-ZZ-00001 HVAC System Air Balancing 8

OSP-SH-00001 PAM Channel Check 30

ODP-ZZ-00020 Instrument Channel Deviations 19

71111.22 Corrective Action Condition Reports 201703268, 201705184

Documents

Work Orders 16502150, 19513758, 20503884

Miscellaneous C-151-01202 IM Escape Lock

PM1008590 Generator Full Load Test

PM1009242 Run Flex Diesel Backhoe

Procedures APA-ZZ-00003 Unloading and Storage of New Fuel Assemblies and 37

Inserts

APA-ZZ-00365 Callaway Lifting Operations 23

APA-ZZ-00750 Barrier Hazzard Program 46

OSP-EJ-V001A Train A RHR Valve Inservice Test 20

OSP-SB-0001A Reactor Trip Breaker A Trip Actuating Device Operational 24

Test

OTS-KE-00005 Operation of the New Fuel Elevator 13

71124.02 Corrective Action Condition Reports 201902760, 201902976, 201903033, 201904576,

Documents 201905580, 201904608, 201902688, 201904022,

201907036, 201907465, 201907807, 202000863,

2001820

Miscellaneous Callaway Energy Center Refuel 23: ALARA Outage Report 0

- April 1, 2019 to May 18, 2019

Procedures APA-ZZ-01000 Callaway Energy Center Radiation Protection Program 46

APA-ZZ-01001 Callaway Plant ALARA Program 27

HDP-ZZ-01100 ALARA Planning and Review 26

HDP-ZZ-01200 Radiation Work Permits 33

HDP-ZZ-03000 Radiological Survey Program 48

RP-DTI-ALARA- Routine On-Line ALARA Duties 37

ROUTINE

ACTIVITIES

Radiation Air Sample Log Air Samples: Refuel 23 Results from April 22, 2019 - May

Surveys 22, 2019

CA-M-20190406- RBHead - Reactor Head Lift 04/06/2019

CA-M-20190410- RB2047' Posting Change 04/10/2019

CA-M-20190411- Cavity Decontamination 04/11/2019

CA-M-20190412- RB2021' Upper Cavity Post Shielding 04/12/2019

CA-M-20190415- RB2021' Cavity-Post Shielding on #2 Stud Tent Survey 04/15/2019

CA-M-20190419- RB2021' Cavity General Area 04/19/2019

CA-M-20190423- R23 Reactor Head Stud Sleeve to 1333 - LDF 04/23/2019

CA-M-20190426- RB2021 Cavity post clean up 04/26/2019

CA-M-20190426- RB2068W - Post Decontamination of Reactor Head Shield 04/26/2019

Plate

CA-M-20190426- RB2090 - Post Decontamination of Handrail Deck Plate 04/26/2019

Self- AP19001 Audit Report: Radiation Protection (RP) Functional Area at 03/27/2019

Assessments the Callaway Energy Center

71124.04 Corrective Action Condition Reports 20180324, 201804063, 201804425, 201804901,

Documents 201900086 201901607, 201902484, 201904715,

201905049, 201905637, 201907498, 201907807,

200962, 20200104, 202002361, 202002363, 202002364

Miscellaneous Analysis Report - Background Check QA Count: Whole 05/18/2020

Body Counter - Chair

Analysis Report - Background Check QA Count: Whole 05/18/2020

Body Counter - CPFFastscan

09MAR200018- Nuclide Distribution Report: Dry Active Waste CYCLE 22 03/09/2018

DAW-1

HPCI 0202 Electronic Dosimeter Calibration Adjustment Factor 2

HPCI 1403 Use of PM-12 for Passive Monitoring 1

HPCI 1901 Correction Factor Analysis for Neutron Detection 0

Instruments, RadEyeNL/DMC3000GN

NVLAP LAB Certificate of Accreditation to I5O/IEC 17025:2005 - 01/01/2020

CODE: 100518-0 Landauer, Inc.; Effective 2020-01-01 through 2020-12-3.

PIN 140283 Radiation Dose Evaluation - DLR/SRD mismatch 02/21/2019

PIN 140283

PIN 140288 Radiation Dose Evaluation - DLR/SRD mismatch 02/13/2019

PIN 140288

Procedures APA-ZZ-01004 Radiological Work Standards 34

HDP-ZZ-01300 InterDescrinal Dosimetry Program 36

HTP-ZZ-01433 Personnel Exposure Records 67

HTP-ZZ-01462- Posted Dosimetry Program 13

DTI-POSTED

DOSIM

HTP-ZZ-01490 Determination of Beta Skin Dose 37

HTP-ZZ-06009 Personnel Contamination Assessment and 51

Decontamination

RP-DTI- Contamination Monitoring Using the FastScan Whole Body 3

FASTSCAN Counter

CONTAM

RP-DTI-TRU- Alpha Monitoring Facility Characterization 8

ASSESSMENT

Self- 201820044-064 NRC Pre-Inspection Self-Assessment: Radiation Safety 05/07/2018

Assessments ALARA Planning and Occupational Dose Assessment

AP19001 Radiation Protection (RP) Functional Area at the Callaway 03/27/2019

Energy Center

SA 202000212- NRC Pre-Inspection Self-Assessment: Occupational Dose 05/20/2020

013 Assessment

SBM 201820044- Cross Checks and Confirmations 01/31/2019

2

71151 Corrective Action Condition Reports 202000040, 202000277, 202000693, 202001933,

Documents 202001934, 202002084

Miscellaneous Performance Indicator Basis Document Various

Control Room Logs

RRA-ZZ-00001 NRC Performance Indicator Program 12

Procedures APA-ZZ-01111 Mitigating Systems Performance Index (MSPI) Program 7

Administration

MSPI Basis Document 8

KDP-ZZ-02000 NRC Performance Indicator (PI) Data Collection 19

71152 Corrective Action Condition Reports 202001121, 202001983, 202001464, 202002204,

Documents 202002475, 202002466, 202002488, 202002539,

2002569, 202002628, 202002653, 202002750,

2002840

71153 Corrective Action Condition Reports 202000878, 202001073, 202001464, 202002539,

Documents 202002569

Miscellaneous Job 19512263 Replace Belts, Clean and Inspect

RFR 5296B Replacement Belt for SGL13A

Procedures APA-ZZ-00013 Maintenance Department Skill of the Craft 9

APA-ZZ-00542 Event Review and Post Transient Evaluation 21

E-0 Reactor Trip or Safety Injection 26

ES-0.1 Reactor Trip Response 23

18

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