IR 05000331/2019004
ML20028D691 | |
Person / Time | |
---|---|
Site: | Duane Arnold |
Issue date: | 01/28/2020 |
From: | Billy Dickson NRC/RGN-III/DRP/B2 |
To: | Dean Curtland NextEra Energy Duane Arnold |
References | |
IR 2019004 | |
Download: ML20028D691 (26) | |
Text
ary 28, 2020
SUBJECT:
DUANE ARNOLD ENERGY CENTER - INTEGRATED INSPECTION REPORT 05000331/2019004
Dear Mr. Curtland:
On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Duane Arnold Energy Center. On January 9, 2020, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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/
Billy C. Dickson, Jr, Chief Branch 2 Division of Reactor Projects Docket No. 05000331 License No. DPR-49
Enclosure:
As stated
Inspection Report
Docket Number: 05000331 License Number: DPR-49 Report Number: 05000331/2019004 Enterprise Identifier: I-2019-004-0065 Licensee: NextEra Energy Duane Arnold, LLC Facility: Duane Arnold Energy Center Location: Palo, Iowa Inspection Dates: October 01, 2019 to December 31, 2019 Inspectors: G. Hansen, Senior Emergency Preparedness Inspector V. Myers, Senior Health Physicist C. Norton, Senior Resident Inspector T. Ospino, Reactor Engineer G. Roach, Senior Operations Engineer J. Seymour, Operations Engineer Approved By: Billy C. Dickson, Jr, Chief Branch 2 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Duane Arnold Energy Center, 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 No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
PLANT STATUS
The unit began the inspection period at rated thermal power. On November 2, 2019, the unit was down powered to 60 percent power for a control rod sequence exchange. The unit was returned to full power on November 3, 2019 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 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) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems on November 4, 2019:
- FLEX buildings
- Control building heating ventilation and air conditioning (HVAC)
- Reactor building HVAC
71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)
The inspectors evaluated system configurations during a partial walkdowns of the following areas:
- (1) 'A' emergency service water system on October 2, 2019
- (2) High pressure coolant injection system on October 8, 2019
- (3) Standby liquid control system on October 9, 2019
- (4) Control rod drive system on October 15, 2019
- (5) 'A' residual heat removal system on November 5, 2019
- (6) 'A' core spray system on November 7, 2019
71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Torus basement on October 7, 2019 Inspection Activities - Underground Cables (IP Section 02.02c.) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Cable vaults MH106 and MH107 on October 9, 2019
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from November 4 through December 12, 2019
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on November 21, 2019 Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46 Problem Identification and Resolution The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
- (1) The inspectors observed and evaluated a reactor plant power evolution and rod sequence exchange on November 3, 2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification training and activities on October 1, 2019
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Electric fire pump minimum flow valve on October 25, 2019
- (2) Control room annunciator horn on November 5, 2019
Quality Control (IP Section 02.02) (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:
- (1) Quality control sample for an emergency service water exchange of a differential pressure indicator switch on November 7, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) A small spurious increase in reactor power on October 24, 2019
- (2) The unplanned unavailability of the 'A' control building chiller on December 20, 2019
- (3) Reactor core isolation coolant unavailability for operability test and system walkdown on December 3, 2019
71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Condition Report (CR) 02329060, emergency service water and well water abnormal indication on October 16, 2019
71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)
The inspectors evaluated the following post maintenance tests:
- (1) Following 'A' and 'B' rod block monitor repairs after receiving spurious alarms when selecting control rods on October 3, 2019
- (2) Following calibrations of the LOW LOW pressure set point channels on October 15, 2019
- (3) Following repack of CV1956A, essential service water to 'A' control building chiller on October 29, 2019
- (4) Following 'A' containment spray logic calibration on October 30, 2019
- (5) Following repair of 'C' residual heat removal pump torus suction isolation valve on November 7, 2019
- (6) Following repairs to 'A' diesel generator air start check CV 32-0043 on November 19, 2019
71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)
- (1) The inspectors evaluated forced outage readiness on November 5, 2019
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)
- (1) High pressure coolant injection system operability test on October 23, 2019
- (2) In field activities associated with reactor core isolation coolant system operability test on December 3, 2019
- (3) In field activities associated with standby liquid control operability test on December 5, 2019
71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03)
- (1) The inspector completed the evaluation of submitted Emergency Action Level and Emergency Plan changes on November 21, 2019. This evaluation does not constitute NRC approval.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 02.01)
The inspectors evaluated radiological hazards assessments and controls.
- (1) The inspectors reviewed the following:
Radiological Surveys
- Refuel floor
- Reactor water clean up pump room
- Heater bay
- Torus rooms Risk Significant Radiological Work Activities
- Tri-nuke filter removal from spent fuel pool
- Reactor water clean up pump removal
- Steam leak repair on the moisture separator reheater drain tank Air Sample Survey Records
- Sample 19-145, refuel floor
- Sample 19-19, reactor water clean up pump room
- Sample 19-150, high pressure coolant injection room
Instructions to Workers (IP Section 02.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors reviewed the following:
Radiation Work Packages
- 19-0112, Refuel Floor Pool Work
- 19-0051, Routine Work and Inspections
- 19-0600, High Steam Areas at Power Electronic Alarming Dosimeter Alarms
- Dose rate alarm on dosimeter serial number 029216 on 11/12/2018
- Dose rate alarm on dosimeter serial number 048617 on 06/03/2019
- Dose rate alarm on dosimeter serial number 897998 on 08/15/2019 Labeling of Containers
- Rebuild equipment on the turbine operating deck
- Refuel floor spare rigging container
- 55 gallon drums in the radioactive waste building
- Dry active waste storage area containers Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors verified the following sealed sources are accounted for and are intact:
- Source 3826
- Source 734 Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors also reviewed the following radiological work package for areas with airborne radioactivity:
- None were available for review during this inspection.
High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)
- (1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)
- (1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency.
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Walk Downs and Observations (IP Section 02.01)
The inspectors walked down the following gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design:
(1)
- Reactor building ventilation system
- Low level radioactive waste building ventilation system
- Ground water mitigation systems Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02) (1 Sample)
The inspectors reviewed the following gaseous and liquid effluent monitor instrument calibrations and tests:
(1)
- Reactor building Kaman 6
- Residual heat removal service water system monitor
Sampling and Analysis (IP Section 02.03) (1 Sample)
The inspectors reviewed the following:
- (1) Radioactive Effluent Sampling and Analysis Activities
- Permanent ground water mitigation system sampling
- Temporary ground water mitigation system sampling
- Reactor building gaseous effluent system sampling
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
The inspectors reviewed the following radioactive effluent discharge system surveillance test results:
Dose Calculations (IP Section 02.05) (1 Sample)
The inspectors reviewed the following to asses public dose:
- (1) Liquid and Gaseous Discharge Permits
- Liquid discharges made 10/23/2019 through 10/28/2019 for the temporary ground water mitigation system
- Liquid discharges made 10/23/2019 through 10/30/2019 for the permanent ground water mitigation system
- Gaseous discharges made 11/06/2019 through 11/13/2019 for off gas and reactor building ventilation systems Annual Radiological Effluent Release Reports
- 2017 Annual Radioactive Material Release Report
- 2018 Annual Radioactive Material Release Report Abnormal Gaseous or Liquid Tank Discharges
- None were available for review during this inspection.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) ===
- (1) Unit 1 (October 1, 2018 to September 30, 2019)
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) Unit 1 (October 1, 2018 to September 30, 2019)
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) Unit 1 (October 1, 2018 to September 30, 2019)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
- (1) Unit 1 (October 1, 2018 to September 30, 2019)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) October 1, 2018 to September 30, 2019
71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in integrated process radiation monitor issues that might be indicative of a more significant safety issue on December 27, 2019 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) The inspectors reviewed the licensee's corrective action program for potential adverse trends in addressing risk and risk communication on December 27,
INSPECTION RESULTS
Observation: Addressing Risk and Risk Communication 71152 In August of 2019, the inspectors identified a negative trend in addressing risk and risk communication. Examples include:
- During the 2018 refueling outage, the risk associated with work on the condensate demineralizer instrument air filter housing was not communicated to the workers. This resulted in the workers improvising a repair to the severely damaged and degraded condensate demineralizer air filter housing. The improvised repair failed while the plant was at full power. Demineralizer flow was lost. Subsequently, operators manually scrammed the reactor due to rapidly lowering reactor water level. The inspectors documented this event in Inspection Report 05000331/2019002 and the licensee reported this as detailed in License Event Report 05000331/2019-001-00.
- In July 2019, the licensee did not adequately communicate identified risks associated with fuel mixture adjustments on the diesel fire pump engine during a maintenance inspection. The licensee did not provide adequate oversight over an inexperienced vendor technician during the fuel mixture adjustment portion of the inspection. The technician made inappropriate adjustments and created an over rich fuel mixture that deposited combustibles in the exhaust line. This resulted in an exhaust line fire that spread to the non-safety related side of the pump house roof. The inspector evaluated this minor event during the 3rd Quarter of 2019.
- Other minor examples included an inadequate brief for work on the well water flow recorder and an inadequate brief associated with taking an oil sample on an instrument air compressor. In the first example, a technician inadvertently allowed a loose wire to make contact which blew a fuse in the recorder circuit. This resulted in well water isolating from loads and unplanned entries into abnormal and emergency operating procedures. In the second example, an operator unfamiliar with the sample location breached the instrument air system causing a control room alarm for low instrument air pressure.
The inspectors monitored licensee actions to address risk and risk communication. The inspectors observed increased emphasis on risk communications during plan-of-day meetings and shop briefings. Duane Arnold Nuclear Assurance observed communications and wrote action requests to address substandard communications. This resulted in discussions that increased sensitivity to the importance of addressing risk and risk communication. The inspectors concluded that the licensee's increased emphasis on risk and risk communication resulted in improvements in station performance and a reduction in near miss occurrences.
Observation: Integrated Process Radiation Monitor Maintenance Issues and 71152 Post Accident Sampling Early in 2019, the inspectors observed an increasing trend in process radiation monitor issues. The inspectors noted several minor equipment and human performance related issues.
Equipment related issues, the result of component aging and spare part availability, included:
- reoccurring off-gas detector failure alarms
- multiple momentary radiation detector alarms with nothing recorded
- control building intake radiation monitor trouble alarms and spurious standby filter unit actuations
- recurring fuel pool exhaust radiation monitor downscale alarms
- incorrect background on effluent ventilation radiation monitor Human performance issues, the result of inadequate work focus in the field or procedure unfamiliarity, included:
- incorrect background programmed into radiation monitors
- using incorrect background values while calibrating a reactor building vent shaft radiation monitor
- mispositioning components when calibrating effluent radiation monitors
- lack of familiarity with emergency alternate sampling procedures for when accident range process radiation monitors are unavailable The inspectors determined that the equipment related issues identified in this inspection sample, although many, were minor and adequately addressed. The inspectors determined that the human performance issues identified in this sample were adequately addressed.
The inspectors evaluated the licensee's readiness to do post-accident manual sampling, analysis and assessment of offsite releases with a concurrent loss of accident range effluent radiation monitors. The inspectors reviewed procedures, training records, walked down sample locations with technicians, and conducted interviews with supervisors and technicians. The inspectors concluded for the scenarios discussed, licensee staff have the training and supervisory skills to collect, analyze and assess post-accident releases with post-accident effluent radiation monitors unavailable.
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
- On January 9, 2020, the inspectors presented the integrated inspection results to
- Mr. D. Curtland, Director of Site Operations and other members of the licensee staff.
- On October 24, 2019, the inspectors presented the radiation protection program inspection results to Mr. D. Curtland, Director of Site Operations and other members of the licensee staff.
- On November 21, 2019, the inspectors presented the Emergency Action Level and Emergency Plan Changes Inspection inspection results to Mr. M. Davis, Licensing Manager and other members of the licensee staff.
- On November 21, 2019, the inspectors presented the radiation protection program inspection results to Mr. D. Curtland, Director of Site Operations and other members of the licensee staff.
- On November 22, 2019, the inspectors presented the Biennial inspection of the licensed operator requalification program inspection results to Mr. R. Spading, Operations Director and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.01 Miscellaneous Seasonal Winter 2019 Memo Curtland to Moul 09/24/2019
Readiness
71111.04Q Corrective Action Condition Report 1P230B Standby Liquid Control (SBLC) Pump Leakage 08/17/2017
Documents (CR) 02220863 Update
CR 02253601 'B' SBLC Pump Seal Leak 03/10/2018
CR 02258728 Sodium Penta Borate Crystal Under 1P230B 04/10/2018
CR 02261588 (Previously Identified) 1P230B SBLC Leak Rate 04/26/2018
Update-2dpm
Drawings BECH-M117 Control Rod Drive Hydraulic System 66
Miscellaneous 'A' Emergency Diesel Generator Outage Work Plan Spread 0
Sheet
Procedures OI 149 Residual Heat Removal (RHR) System 170
OI 149A2 'A' RHR System Valve Lineup 15
OI 151 Core Spray System 0
OI 151A2 'A' Core Spray System Valve Lineup 0
OI 151A6 Core Spray System Control Panel Lineup 0
OI 152 High Pressure Coolant Injection (HPCI) System 120
OI 152A2 HPCI System Valve Lineup 20
OI 153 SBLC 0
OI 153A1 SBLC System Electrical Lineup 0
OI 153A2 SBLC System Valve Lineup 0
OI 255 Control Rod Drive Hydraulic System 97
OI 255A3 Control Rod Drive System HCU Valve Lineup 3
OI 416 RHR Service Water System 0
OI 416A6 Residual Heat Removal Service Water System Control Panel 5
Lineup
OI 454 Emergency Service Water System 70
STP 3.5.1-05 HPCI System Operability Test 83
STP NS540002-A 'A' Emergency Service Water Operability Test 43
STP NS550003 Surveillance Test Procedure (STP) ASME CDR Accumulator 3
Check Valve test
Inspection Type Designation Description or Title Revision or
Procedure Date
Work Orders 40637955-01 GWPP Mitigation System / 'A' Emergency Service Water 09/26/2019
Operability test
71111.06 Drawings GMP-ELEC-39 Electrical Man-Hole Inspection 8
71111.11B Corrective Action CR 2263827 PDA Interim Report - Operations 05/11/2018
Documents CR 2281632 Tech Spec 3.0.4 Question 09/22/2018
CR 2287125 IRM Upscale Activated and Reset 10/21/2018
CR 2303207 Invoked T.S. 5.2.2.C 02/23/2019
CR 2305415 Near Miss - Exam Validation Session on Simulator Printer 03/12/2019
Engineering 278899 Replace River Water Make-up System Controllers 0
Changes 284591 Replacing Transverse Incore Probe Drawers and Removing 0
XY Plotters from Panel 1C13
288619 Replacing and Removing Switchyard Breaker Handswitches 0
and Indicating Lights from Panel 1C08
Miscellaneous Simulator Review Committee Meeting Minutes 06/05/2019
Simulator Review Committee Meeting Minutes 10/11/2018
2018 DAEC NRC Examination Summary 08/08/2018
Annual Operating
Exam Report
2018 Operability 21.4% Power Test 10/01/2018
and Steady State
Test Data
2018 Operability 53.7% Power Test 10/01/2018
and Steady State
Test Data
2018 Operability 78.9% Power Test 10/02/2018
and Steady State
Test Data
2018 Operability 99.1% Power Test 10/02/2018
and Steady State
Test Data
2018 Operability Stability Test @ 100% Power 10/02/2018
and Steady State
Test Data
2019 Written Written Examination Sample Plan 2019
Inspection Type Designation Description or Title Revision or
Procedure Date
Sample Plan
DAEC 2017 Examination Summary 12/15/2017
LOCT Biennial
Exam
DAEC BRE Written Exam Development Methodology Matrix 2017
DAEC LOCT Two Training Plan 2018-2019
Year Plan
ESG and JPM Operating Test Sample Plan 2019
Sample Plan
JPM 2.4.35-01 Job Performance Measure 7
JPM 2.4.41-23 Job Performance Measure 0
JPM 201003-03 Job Performance Measure 11
JPM 215001-01 Job Performance Measure 3
JPM 217000-01 Job Performance Measure 8
JPM 259001-12 Job Performance Measure 1
JPM 264000-10 Job Performance Measure 4
JPM 295004-02 Job Performance Measure 2
JPM 304.2-07.02- Job Performance Measure 2
JPM 304.2-07.02- Job Performance Measure 1
Normal Evolution Reactor Core Reload and Core Performance Testing 11/12/2018
3.4.3.3
Normal Evolution Core Spray System Operability Test 04/12/2018
STP 3.5.1-01
ODI-009 Individual Status Change Letter (Active) 08/13/2018
ODI-009 Individual Status Change Letter (Active) 08/28/2018
OP-302 Quarterly Personnel Watchstanding Verifications, Various 2017-2019
PDA OPS 50008 2019 LOCT Biennial Comprehensive Written Exam (RO) 0
Week 1
PDA OPS 50008 2019 LOCT Biennial Comprehensive Written Exam (RO) 0
Week 3
PDA OPS 50008 2019 LOCT Biennial Comprehensive Written Exam (SRO) 0
Week 3
Inspection Type Designation Description or Title Revision or
Procedure Date
PDA OPS ESG Simulator Exercise Guide 0
350
PDA OPS ESG Simulator Exercise Guide 0
351
PDA OPS ESG Simulator Exercise Guide 0
354
PDA OPS ESG Simulator Exercise Guide 0
356
Post Event 'B' FRV Closure and Scram 01/18/2019
Simulator Testing
Post Event Feedwater Pumps Suction Pressure Trip and Manual Scram 06/18/2019
Simulator Testing
Scenario Based OPS 19-1 NRC Scenario 1 04/19/2019
Testing
Scenario Based OPS 19-1 NRC Scenario 2 04/19/2019
Testing
Scenario Based OPS 19-1 NRC Scenario 3 04/19/2019
Testing
Simulator Testing 2018 Real Time and Repeatability Test 09/24/2018
Simulator Loss of All Feedwater 10/17/2018
Transient Test
Simulator Trip of One Recirculation Pump 10/17/2018
Transient Test
Simulator Unisolable Main Steam Line Break 10/17/2018
Transient Test
TR-AA-220-1004- LOCT Annual/Biennial Exam Results Summaries, Various 11/20/2019
F01
TR-AA-230-1000- Remediation 11/16/2017
F10
TR-AA-230-1007- Crew Simulator Evaluation Form 11/19/2019
F01
TR-AA-230-1007- Individual Simulator Evaluation Forms, Various 11/19/2019
F02
TR-AA-230-1007- STA Simulator Evaluation Forms, Various 11/19/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
F03
TR-AA-230-1007- Crew Grading Attachments, Various 11/19/2019
F13
TR-AA-230-J405 Training Review Board 11/13/2017
Training Curricula Item Status Matrices, 2017-2019 11/18/2019
Attendance
Records
Procedures 1801.4 Simulator Configuration Management 28
OI 152 High Pressure Coolant Injection System 120
OP-AA-100-1001 License Maintenance and Activation 6
SA-AA-101-1000 NRC Operator License Application and Renewal 3
Requirements
TR-AA-201-1000- Licensed Operator Continuing Training 2018-2019 Training 06/29/2018
F01 Plan
TR-AA-201-1000- DAEC Licensed Operator Continuing Training Program 10/13/2019
F02 Description
TR-AA-201-1000- Training Program Description 2
F02
TR-AA-220-1002 NRC Licensed Operator Exam Security 4
TR-AA-220-1004 Licensed Operator Continuing Training Annual Operating 5
and Biennial Written Exams
TR-AA-221-1000 Simulator Change Control 5
TR-AA-230-1007 Conduct of Simulator Training and Evaluation 12
TR-AA-230-1009 Training Examination Security 4
Self-Assessments 2019 DAEC Simulator Annual Report 11/13/2019
AR - L2A #: Pre-NRC Licensed Operator Requalification Program 08/30/2019
NAMS 2287755 / Assessment
276322
NG-18-0141 2018 DAEC Simulator Annual Report 11/27/2018
Work Orders SWR 2010 PEST Issue: Total Core Flow, Core Plate DP, Jet Pump DP 01/17/2019
SWR 2011 PEST Issue: B024 RWCU System Cooldown Issue 01/17/2019
SWR 2012 PEST Issue: Main Steamline Flowrates Issue 01/17/2019
SWR 2013 PEST Issue: Containment Pressure/Temperature Response 01/17/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
to Scram/ Recirc Trips
SWR 2014 PEST Issue: Torus Water Level Response to HPCI, RCIC 01/17/2019
Running Issues
SWR 2066 Meteorological Recorder YR-9400 Multiple Issues 0
SWR 2067 Turbine Vibes too Elevated at Critical Turbine RPMs After 0
Trip
SWR 2248343 HPCI Auxiliary Oil Pump Handswitch Wobbly 0
SWR 2257397 Hardened Containment Vent System Radiation Monitor 0
Display Inoperable
SWR 2306441 3 Primary Containment Isolation System Valve Closing Time 0
not within Specification
71111.11Q Corrective Action CR 02334071 RPS Relays did not Cycle as Expected for 'B' Inboard Main 11/03/2019
Documents Steam Isolation Valve
Miscellaneous Evaluated Scenario ESG 2019D-01E 0
Scenario
Procedures NS930002 Main Turbine Stop and Combined Intermediate Valves Test 5
STP 3.3.1.1-13 Turbine Control Valve Recirculation Pump Trip Logic and 15
Reactor Protection System Instruments Functional Test
STP 3.3.1.1-17 Main Steam Line Isolation Valve Functional Test 15
STP 3.3.1.1-19 Functional Test of Turbine Stop Valve Closure Input to 23
Reactor Protection System Recirculation Pump Trip
71111.12 Corrective Action CR 02331615 PSV3302 Internal Parts Degradation 10/15/2019
Documents
Miscellaneous Roy Hanson Email: Electric Fire Pump Unavailability 10/17/2019
Operations Shift Log 10/22/2019
NG-006M Electrical Termination Sheet 10
NG-006M Electrical Termination Sheet 10
NG-015K Shift Manager, CRS, WCCS, and STA Turnover Form dated 44
October 22, 2019
Work Orders 40478652-01 Replace and Calibrate Stilling Basin Differential Pressure 11/07/2019
Indicator LIS4935A
4068329-01 PSV3301; Rebuild and Repack 10/15/2019
71111.13 Corrective Action Shift Operations Log 12/03/2019
Documents CR 02327515 Observed Step Rise in Reactor Power 1
Inspection Type Designation Description or Title Revision or
Procedure Date
Miscellaneous Shift Operations Logs 12/03/2019
Risk Analysis White Paper on 'A' Control Building Chiller Risk 00
Work Plan Calibrate I/I 6924A, as part of 'A' CB Chiller AC to DC 12/05/2019
40644666 Converter Issue
Work Orders 40194425 Calibrate I/16924B 08/29/2013
236612 Calibrate I/I6924A 'A' CB Chiller AC to DC Converter Card 03/23/2014
Work Plan 'A' CB Chiller AC to DC Converter Card 12/05/2019
40644666
71111.15 Corrective Action CR 02329060 Emergency Service Water Abnormal Indication 09/24/2019
Documents
71111.19 Corrective Action CR 02329584 Rod Block Monitor (RBM) Issues when Selecting a Rod 09/28/2019
Documents CR 02329585 RBM Alarms when Selecting Control Rod 09/28/2019
CR 02333339 CV1956A Packing Leak has Risen to 30 dpm 10/28/2019
CR 02333812 MO 2015 Tripped on Thermal Overload When Timing Open 10/31/2019
Per STP
Drawings BECH-M132<1> Diesel Generator Systems 21
Miscellaneous Work Plan Air Receiver 1T-115A Outlet Check Valve 09/17/2019
40682200-01
Work Plan Air Receiver 1T-115A Outlet Check Valve 09/18/2019
40682200-01
Work Plan Air Receiver 1T-115A Outlet Check Valve 11/08/2019
40682200-01
Work Plan Air Receiver 1T-115A Outlet Check Valve 11/19/2019
40682200-05
Work Plan Air Receiver 1T-115A Outlet Check Valve 11/20/2019
40682200-05
Procedures CAL-M01-071 Valve Number CV1956A 5
ER-AA-122-1001 Printed Circuit Board Life Cycle Management Plan 0
ER-AA-122-1001 Printed Circuit Board Life Cycle Management Plan 0
GMP-Test-58 Air Operated Valve Diagnostic Testing 9
OI 878.5 Rod Block Monitoring System 0
STP 3.1.3-01 Control Rod Exercises 0
STP 3.3.2.1-01 Rod Block Monitor Functional Check 9
Inspection Type Designation Description or Title Revision or
Procedure Date
STP 3.3.2.1-01 Rod Block Monitor Functional Check 9
STP 3.3.2.1-02 Rod Block Monitor Calibration 0
STP 3.3.2.1-02 Rod Block Monitor Calibration 0
STP 3.3.5.1-29A 'A' Containment Spray Logic System Functional Test and 3
RHR Timer Calibration
STP 3.3.6.3-03 Low-Low Set Pressure Set Point Channels Functional Test 13
STP 3.8.1-11A Standby Diesel Generator Air Compressor and Air Start 11
Check Valve Test
STP NS540002A 'A' Emergency Service Water 43
Work Orders 40609798-01 CV-1959A-0 Perform AOV Diagnostic Testing 10/28/2019
40619490-01 'A' Containment Spray Logic System Functional Test and 10/29/2019
RHR Timer Calibration
40642865-01 Low-Low Set Pressure Setpoint Chan Functional test 10/14/2019
40649752-02 'B' RBM Clean Cards and Cabinet in RBMS 10/03/2019
40690161-05 C-RHR Pump Torus Suction Isolation Valve Post 11/07/2019
Maintenance Test
WR 94198480 Work Request for V-32-043, 'A' Emergency Diesel Starting 09/03/2019
Air Check Valve, Failed Surveillance Test
71111.20 Miscellaneous Forced Outage Scope List 05/08/2019
71111.22 Procedures NS500001 Reactor Core Isolation Cooling System Leakage Inspection 5
Walkdown
NS530001 Standby Liquid Control System Leakage Inspection 10
Walkdown
STP 3.1.7-01 Standby Liquid Control Pump Operability Test 44
STP 3.5.1-05 HPCI System Operability Test 83
STP 3.5.3-02 Reactor Core Isolation Cooling Operability Test 56
71114.04 Miscellaneous 10 CFR 50.54(q) Screening and Evaluation Personnel 07/03/2019
Training and Qualification Records
PCR 2269673 10 CFR 50.54(q) Screening and Evaluation Forms, Joint 07/17/2018
Information Center (JIC) Relocation and Staff
Reorganization Screen and Evaluation
PCR 2277166 10 CFR 50.54(q) Screening Form, Emergency Plan, 04/22/2019
Appendix 6 - Correct Typo"
PCR 2290125 10 CFR 50.54(q) Screening Form, Emergency Procedures 02/19/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
Update due to NRC Approval of LAR 308 - EAL Scheme
Revision - Editorial Changes
PCR 2299716 10 CFR 50.54(q) Screening and Evaluation Forms, 02/05/2019
Emergency Plan, Section G Revision - Public Information
Requirements and Education Screen and Evaluation
PCR 2302439 10 CFR 50.54(q) Screening and Evaluation Forms, 04/02/2019
Emergency Plan, Section B Revision to Reflect
Reorganization of EOF and JIC Screen and Evaluation
PCR 2310522 10 CFR 50.54(q) Screening and Evaluation Forms, 05/14/2019
Emergency Plan, Section B Revision - TSC Staff
Reorganization Screen and Evaluation
PCR 2313357 10 CFR 50.54(q) Screening and Evaluation Forms, EAL 05/14/2019
Matrix and EAL Technical Bases Document Revisions
Screen and Evaluation
Procedures DAEC Emergency Plan, Section B - Emergency Response 42
Organization
DAEC Emergency Plan, Section B - Emergency Response 43
Organization
DAEC Emergency Plan, Appendix 6 - Definitions 29
DAEC Emergency Plan, Appendix 6 - Definitions 30
DAEC Emergency Plan, Section G - Public Education and 26
Information
DAEC Emergency Plan, Section G - Public Education and 27
Information
2310525 10 CFR 50.54(q) Screening and Evaluation Forms, 05/14/2019
Emergency Plan, Section B Revision - TSC Staff
Reorganization Screen and Evaluation
EP-AA-100-1007 Evaluation of Changes to the Emergency Plan, Supporting 8
Documents and Equipment [10 CFR 50.54(Q)]
PCR 2299718 10 CFR 50.54(q) Screening and Evaluation Forms, 0
Emergency Plan, Section G Revision - Public Information
Requirements and Education Screen and Evaluation
71124.01 Miscellaneous Radiation Protection Work Plan For HPCI/RCIC Runs 01/10/2019
Procedures HPP 3104.03 Radiological Air Sample Collection and Analysis 28
Inspection Type Designation Description or Title Revision or
Procedure Date
Radiation Form HP-48 Air Sample Record For Tri-Nuke Filter Removal 10/15/2019
Surveys Form HP-48 Air Sample Record For Reactor Water Clean Up Pump Work 02/18/2019
Form HP-48 Air Sample Record For High Pressure Coolant Injection 10/23/2019
Surveillance
PDA-M- Surveys For High Pressure Coolant Injection and Torus 01/12/2017
20170112-2 Rooms
PDA-M- Reactor Water Clean Up Pump Removal Surveys 02/18/2019
20190218-2
PDA-M- Reactor Water Clean Up Pump Removal Surveys 02/19/2019
20190219-1
PDA-M- Heater Bay Surveys For Camera Installation 05/30/2019
20190530-2
PDA-M- Heater Bay Surveys For Steam Leak Isolation 06/03/2019
20190603-7
PDA-M- Refuel Floor Tri-Nuke Filter Removal Surveys 10/15/2019
20191015-1
PDA-M- Refuel Floor Tri-Nuke Filter Removal Surveys 10/16/2019
20191016-2
PDA-M- Surveys For Torus Rooms 10/23/2019
20191023-2
PDA-M- Surveys For High Pressure Coolant Injection Rooms 10/23/2019
20191023-3
Radiation Work 19-0051 Routine Work and Inspections 01
Permits (RWPs) 19-0112 Refuel Floor Pool Work 01
19-0600 High Steam Areas At Power 01
Work Orders 40624340 Sealed Source Leakage Test 07/17/2019
71124.06 Corrective Action 02298709 Kaman 5 Mid-Range Conversion Factor Incorrectly 01/21/2019
Documents Calculated
Procedures NS790601 Effluent Particulate and Iodine Sampling and Analysis 33
NS790708 Offsite Effluent Dose Calculations 6
NS790709 Ground Water Protection Program Mitigation System 4
PCP 10.1 MIDAS - Offsite Radiation Dose Assessment 10
Work Orders 40562421 Kaman 5 Calibration 01/03/2019
40608222 Standby Gas Treatment System Filter Efficiency 02/04/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
40617861 RE 1997: Replacement Detector 08/31/2018
40626760 Kaman 6 Calibration 10/17/2019
71151 Miscellaneous Reactor Radiological Effluent Technical Specifications/Offsite Dose 0
Oversight Calculation Manual NRC PI Data Calculation, Review and
Process Approval, 3rd Quarter 2019
Reactor Residual Heat Removal NRC PI Data Calculation, Review 0
Oversight and Approval, 2nd Quarter 2019
Process
Reactor Cooling Water Support Systems NRC PI Data Calculation, 0
Oversight Review and Approval, 1st Quarter 2019
Process
Reactor Reactor Coolant Systems Specific Activity Samples NRC PI 0
Oversight Data Calculation, Review and Approval, 4th Quarter 2018
Process
71152 Corrective Action CR 02308485 Received Multiple Momentary Reactor Building Kaman 04/02/2019
Documents Alarms
CR 02310749 RIM6101B Control Building Radiation Monitor Trouble and 04/16/2019
'B' Standby Filter Unit Auto-Start
Procedures PSAP 6.1 Emergency Procedures for Effluent Sample Retrieval 6
24