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
January 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:
Report Number:
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
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 Sample)
- (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) (6 Samples)
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.) (1 Sample)
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 Sample)
- (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 Sample)
- (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 Sample)
- (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) (2 Samples)
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) (3 Samples)
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) (1 Sample)
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) (6 Samples)
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 Sample)
- (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 Sample)
- (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) (1 Sample)
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) (1 Sample)
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 Sample)
- (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 Post Accident Sampling 71152 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Seasonal
Readiness
Winter 2019 Memo Curtland to Moul
09/24/2019
71111.04Q Corrective Action
Documents
Condition Report
(CR) 02220863
1P230B Standby Liquid Control (SBLC) Pump Leakage
Update
08/17/2017
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
Update-2dpm
04/26/2018
Drawings
BECH-M117
Control Rod Drive Hydraulic System
Miscellaneous
'A' Emergency Diesel Generator Outage Work Plan Spread
Sheet
Procedures
OI 149
Residual Heat Removal (RHR) System
170
OI 149A2
'A' RHR System Valve Lineup
OI 151
Core Spray System
OI 151A2
'A' Core Spray System Valve Lineup
OI 151A6
Core Spray System Control Panel Lineup
OI 152
High Pressure Coolant Injection (HPCI) System
20
OI 152A2
HPCI System Valve Lineup
OI 153
SBLC
OI 153A1
SBLC System Electrical Lineup
OI 153A2
SBLC System Valve Lineup
OI 255
Control Rod Drive Hydraulic System
OI 255A3
Control Rod Drive System HCU Valve Lineup
OI 416
RHR Service Water System
OI 416A6
Residual Heat Removal Service Water System Control Panel
Lineup
OI 454
Emergency Service Water System
STP 3.5.1-05
HPCI System Operability Test
STP NS540002-A 'A' Emergency Service Water Operability Test
STP NS550003
Surveillance Test Procedure (STP) ASME CDR Accumulator
Check Valve test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
40637955-01
GWPP Mitigation System / 'A' Emergency Service Water
Operability test
09/26/2019
Drawings
GMP-ELEC-39
Electrical Man-Hole Inspection
Corrective Action
Documents
CR 2263827
PDA Interim Report - Operations
05/11/2018
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
2/23/2019
CR 2305415
Near Miss - Exam Validation Session on Simulator Printer
03/12/2019
Engineering
Changes
278899
Replace River Water Make-up System Controllers
284591
Replacing Transverse Incore Probe Drawers and Removing
XY Plotters from Panel 1C13
288619
Replacing and Removing Switchyard Breaker Handswitches
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
Annual Operating
Exam Report
Examination Summary
08/08/2018
2018 Operability
and Steady State
Test Data
21.4% Power Test
10/01/2018
2018 Operability
and Steady State
Test Data
53.7% Power Test
10/01/2018
2018 Operability
and Steady State
Test Data
78.9% Power Test
10/02/2018
2018 Operability
and Steady State
Test Data
99.1% Power Test
10/02/2018
2018 Operability
and Steady State
Test Data
Stability Test @ 100% Power
10/02/2018
2019 Written
Written Examination Sample Plan
2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Sample Plan
DAEC 2017
LOCT Biennial
Exam
Examination Summary
2/15/2017
Written Exam Development Methodology Matrix
2017
DAEC LOCT Two
Year Plan
Training Plan
2018-2019
ESG and JPM
Sample Plan
Operating Test Sample Plan
2019
JPM 2.4.35-01
JPM 2.4.41-23
JPM 201003-03
JPM 215001-01
JPM 217000-01
JPM 259001-12
JPM 264000-10
JPM 295004-02
JPM 304.2-07.02-
JPM 304.2-07.02-
Normal Evolution
3.4.3.3
Reactor Core Reload and Core Performance Testing
11/12/2018
Normal Evolution
STP 3.5.1-01
Core Spray System Operability Test
04/12/2018
ODI-009
Individual Status Change Letter (Active)
08/13/2018
ODI-009
Individual Status Change Letter (Active)
08/28/2018
Quarterly Personnel Watchstanding Verifications, Various
2017-2019
PDA OPS 50008
2019 LOCT Biennial Comprehensive Written Exam (RO)
Week 1
PDA OPS 50008
2019 LOCT Biennial Comprehensive Written Exam (RO)
Week 3
PDA OPS 50008
2019 LOCT Biennial Comprehensive Written Exam (SRO)
Week 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PDA OPS ESG
350
Simulator Exercise Guide
PDA OPS ESG
351
Simulator Exercise Guide
PDA OPS ESG
354
Simulator Exercise Guide
PDA OPS ESG
356
Simulator Exercise Guide
Post Event
Simulator Testing
01/18/2019
Post Event
Simulator Testing
Feedwater Pumps Suction Pressure Trip and Manual Scram
06/18/2019
Scenario Based
Testing
OPS 19-1 NRC Scenario 1
04/19/2019
Scenario Based
Testing
OPS 19-1 NRC Scenario 2
04/19/2019
Scenario Based
Testing
OPS 19-1 NRC Scenario 3
04/19/2019
Simulator Testing
2018 Real Time and Repeatability Test
09/24/2018
Simulator
Transient Test
Loss of All Feedwater
10/17/2018
Simulator
Transient Test
Trip of One Recirculation Pump
10/17/2018
Simulator
Transient Test
Unisolable Main Steam Line Break
10/17/2018
TR-AA-220-1004-
F01
LOCT Annual/Biennial Exam Results Summaries, Various
11/20/2019
TR-AA-230-1000-
F10
Remediation
11/16/2017
TR-AA-230-1007-
F01
Crew Simulator Evaluation Form
11/19/2019
TR-AA-230-1007-
F02
Individual Simulator Evaluation Forms, Various
11/19/2019
TR-AA-230-1007-
STA Simulator Evaluation Forms, Various
11/19/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
F03
TR-AA-230-1007-
F13
Crew Grading Attachments, Various
11/19/2019
TR-AA-230-J405
Training Review Board
11/13/2017
Training
Attendance
Records
Curricula Item Status Matrices, 2017-2019
11/18/2019
Procedures
1801.4
Simulator Configuration Management
OI 152
High Pressure Coolant Injection System
20
License Maintenance and Activation
NRC Operator License Application and Renewal
Requirements
TR-AA-201-1000-
F01
Licensed Operator Continuing Training 2018-2019 Training
Plan
06/29/2018
TR-AA-201-1000-
F02
DAEC Licensed Operator Continuing Training Program
Description
10/13/2019
TR-AA-201-1000-
F02
Training Program Description
NRC Licensed Operator Exam Security
Licensed Operator Continuing Training Annual Operating
and Biennial Written Exams
Simulator Change Control
Conduct of Simulator Training and Evaluation
Training Examination Security
Self-Assessments
2019 DAEC Simulator Annual Report
11/13/2019
AR - L2A #:
NAMS 2287755 /
276322
Pre-NRC Licensed Operator Requalification Program
Assessment
08/30/2019
NG-18-0141
2018 DAEC Simulator Annual Report
11/27/2018
Work Orders
PEST Issue: Total Core Flow, Core Plate DP, Jet Pump DP
01/17/2019
PEST Issue: B024 RWCU System Cooldown Issue
01/17/2019
PEST Issue: Main Steamline Flowrates Issue
01/17/2019
PEST Issue: Containment Pressure/Temperature Response
01/17/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
to Scram/ Recirc Trips
PEST Issue: Torus Water Level Response to HPCI, RCIC
Running Issues
01/17/2019
Meteorological Recorder YR-9400 Multiple Issues
Turbine Vibes too Elevated at Critical Turbine RPMs After
Trip
HPCI Auxiliary Oil Pump Handswitch Wobbly
Hardened Containment Vent System Radiation Monitor
Display Inoperable
Primary Containment Isolation System Valve Closing Time
not within Specification
71111.11Q Corrective Action
Documents
CR 02334071
RPS Relays did not Cycle as Expected for 'B' Inboard Main
Steam Isolation Valve
11/03/2019
Miscellaneous
Evaluated
Scenario
Scenario ESG 2019D-01E
Procedures
NS930002
Main Turbine Stop and Combined Intermediate Valves Test
STP 3.3.1.1-13
Turbine Control Valve Recirculation Pump Trip Logic and
Reactor Protection System Instruments Functional Test
STP 3.3.1.1-17
Main Steam Line Isolation Valve Functional Test
STP 3.3.1.1-19
Functional Test of Turbine Stop Valve Closure Input to
Reactor Protection System Recirculation Pump Trip
Corrective Action
Documents
CR 02331615
PSV3302 Internal Parts Degradation
10/15/2019
Miscellaneous
Roy Hanson Email: Electric Fire Pump Unavailability
10/17/2019
Operations Shift Log
10/22/2019
NG-006M
Electrical Termination Sheet
NG-006M
Electrical Termination Sheet
NG-015K
Shift Manager, CRS, WCCS, and STA Turnover Form dated
October 22, 2019
Work Orders
40478652-01
Replace and Calibrate Stilling Basin Differential Pressure
Indicator LIS4935A
11/07/2019
4068329-01
PSV3301; Rebuild and Repack
10/15/2019
Corrective Action
Documents
Shift Operations Log
2/03/2019
CR 02327515
Observed Step Rise in Reactor Power
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Shift Operations Logs
2/03/2019
Risk Analysis
White Paper on 'A' Control Building Chiller Risk
Work Plan
40644666
Calibrate I/I 6924A, as part of 'A' CB Chiller AC to DC
Converter Issue
2/05/2019
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
40644666
'A' CB Chiller AC to DC Converter Card
2/05/2019
Corrective Action
Documents
CR 02329060
Emergency Service Water Abnormal Indication
09/24/2019
Corrective Action
Documents
CR 02329584
Rod Block Monitor (RBM) Issues when Selecting a Rod
09/28/2019
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
Per STP
10/31/2019
Drawings
BECH-M132<1>
Diesel Generator Systems
Miscellaneous
Work Plan
40682200-01
Air Receiver 1T-115A Outlet Check Valve
09/17/2019
Work Plan
40682200-01
Air Receiver 1T-115A Outlet Check Valve
09/18/2019
Work Plan
40682200-01
Air Receiver 1T-115A Outlet Check Valve
11/08/2019
Work Plan
40682200-05
Air Receiver 1T-115A Outlet Check Valve
11/19/2019
Work Plan
40682200-05
Air Receiver 1T-115A Outlet Check Valve
11/20/2019
Procedures
CAL-M01-071
Valve Number CV1956A
Printed Circuit Board Life Cycle Management Plan
Printed Circuit Board Life Cycle Management Plan
GMP-Test-58
Air Operated Valve Diagnostic Testing
OI 878.5
Rod Block Monitoring System
STP 3.1.3-01
Control Rod Exercises
STP 3.3.2.1-01
Rod Block Monitor Functional Check
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
STP 3.3.2.1-01
Rod Block Monitor Functional Check
STP 3.3.2.1-02
Rod Block Monitor Calibration
STP 3.3.2.1-02
Rod Block Monitor Calibration
STP 3.3.5.1-29A
'A' Containment Spray Logic System Functional Test and
RHR Timer Calibration
STP 3.3.6.3-03
Low-Low Set Pressure Set Point Channels Functional Test
STP 3.8.1-11A
Standby Diesel Generator Air Compressor and Air Start
Check Valve Test
STP NS540002A
'A' Emergency Service Water
Work Orders
40609798-01
CV-1959A-0 Perform AOV Diagnostic Testing
10/28/2019
40619490-01
'A' Containment Spray Logic System Functional Test and
RHR Timer Calibration
10/29/2019
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
Maintenance Test
11/07/2019
Work Request for V-32-043, 'A' Emergency Diesel Starting
Air Check Valve, Failed Surveillance Test
09/03/2019
Miscellaneous
Forced Outage Scope List
05/08/2019
Procedures
NS500001
Reactor Core Isolation Cooling System Leakage Inspection
Walkdown
NS530001
Standby Liquid Control System Leakage Inspection
Walkdown
STP 3.1.7-01
Standby Liquid Control Pump Operability Test
STP 3.5.1-05
HPCI System Operability Test
STP 3.5.3-02
Reactor Core Isolation Cooling Operability Test
Miscellaneous
CFR 50.54(q) Screening and Evaluation Personnel
Training and Qualification Records
07/03/2019
PCR 2269673
CFR 50.54(q) Screening and Evaluation Forms, Joint
Information Center (JIC) Relocation and Staff
Reorganization Screen and Evaluation
07/17/2018
PCR 2277166
CFR 50.54(q) Screening Form, Emergency Plan,
Appendix 6 - Correct Typo"
04/22/2019
PCR 2290125
CFR 50.54(q) Screening Form, Emergency Procedures
2/19/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Update due to NRC Approval of LAR 308 - EAL Scheme
Revision - Editorial Changes
PCR 2299716
CFR 50.54(q) Screening and Evaluation Forms,
Emergency Plan, Section G Revision - Public Information
Requirements and Education Screen and Evaluation
2/05/2019
PCR 2302439
CFR 50.54(q) Screening and Evaluation Forms,
Emergency Plan, Section B Revision to Reflect
Reorganization of EOF and JIC Screen and Evaluation
04/02/2019
PCR 2310522
CFR 50.54(q) Screening and Evaluation Forms,
Emergency Plan, Section B Revision - TSC Staff
Reorganization Screen and Evaluation
05/14/2019
PCR 2313357
CFR 50.54(q) Screening and Evaluation Forms, EAL
Matrix and EAL Technical Bases Document Revisions
Screen and Evaluation
05/14/2019
Procedures
DAEC Emergency Plan, Section B - Emergency Response
Organization
DAEC Emergency Plan, Section B - Emergency Response
Organization
DAEC Emergency Plan, Appendix 6 - Definitions
DAEC Emergency Plan, Appendix 6 - Definitions
DAEC Emergency Plan, Section G - Public Education and
Information
DAEC Emergency Plan, Section G - Public Education and
Information
2310525
CFR 50.54(q) Screening and Evaluation Forms,
Emergency Plan, Section B Revision - TSC Staff
Reorganization Screen and Evaluation
05/14/2019
Evaluation of Changes to the Emergency Plan, Supporting
Documents and Equipment [10 CFR 50.54(Q)]
PCR 2299718
CFR 50.54(q) Screening and Evaluation Forms,
Emergency Plan, Section G Revision - Public Information
Requirements and Education Screen and Evaluation
Miscellaneous
Radiation Protection Work Plan For HPCI/RCIC Runs
01/10/2019
Procedures
HPP 3104.03
Radiological Air Sample Collection and Analysis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
Form HP-48
Air Sample Record For Tri-Nuke Filter Removal
10/15/2019
Form HP-48
Air Sample Record For Reactor Water Clean Up Pump Work
2/18/2019
Form HP-48
Air Sample Record For High Pressure Coolant Injection
Surveillance
10/23/2019
PDA-M-
20170112-2
Surveys For High Pressure Coolant Injection and Torus
Rooms
01/12/2017
PDA-M-
20190218-2
Reactor Water Clean Up Pump Removal Surveys
2/18/2019
PDA-M-
20190219-1
Reactor Water Clean Up Pump Removal Surveys
2/19/2019
PDA-M-
20190530-2
Heater Bay Surveys For Camera Installation
05/30/2019
PDA-M-
20190603-7
Heater Bay Surveys For Steam Leak Isolation
06/03/2019
PDA-M-
20191015-1
Refuel Floor Tri-Nuke Filter Removal Surveys
10/15/2019
PDA-M-
20191016-2
Refuel Floor Tri-Nuke Filter Removal Surveys
10/16/2019
PDA-M-
20191023-2
Surveys For Torus Rooms
10/23/2019
PDA-M-
20191023-3
Surveys For High Pressure Coolant Injection Rooms
10/23/2019
Radiation Work
Permits (RWPs)
19-0051
Routine Work and Inspections
19-0112
Refuel Floor Pool Work
19-0600
High Steam Areas At Power
Work Orders
40624340
Sealed Source Leakage Test
07/17/2019
Corrective Action
Documents
298709
Kaman 5 Mid-Range Conversion Factor Incorrectly
Calculated
01/21/2019
Procedures
NS790601
Effluent Particulate and Iodine Sampling and Analysis
NS790708
Offsite Effluent Dose Calculations
NS790709
Ground Water Protection Program Mitigation System
PCP 10.1
MIDAS - Offsite Radiation Dose Assessment
Work Orders
40562421
Kaman 5 Calibration
01/03/2019
40608222
Standby Gas Treatment System Filter Efficiency
2/04/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40617861
RE 1997: Replacement Detector
08/31/2018
40626760
Kaman 6 Calibration
10/17/2019
71151
Miscellaneous
Reactor
Oversight
Process
Radiological Effluent Technical Specifications/Offsite Dose
Calculation Manual NRC PI Data Calculation, Review and
Approval, 3rd Quarter 2019
Reactor
Oversight
Process
Residual Heat Removal NRC PI Data Calculation, Review
and Approval, 2nd Quarter 2019
Reactor
Oversight
Process
Cooling Water Support Systems NRC PI Data Calculation,
Review and Approval, 1st Quarter 2019
Reactor
Oversight
Process
Reactor Coolant Systems Specific Activity Samples NRC PI
Data Calculation, Review and Approval, 4th Quarter 2018
Corrective Action
Documents
CR 02308485
Received Multiple Momentary Reactor Building Kaman
Alarms
04/02/2019
CR 02310749
RIM6101B Control Building Radiation Monitor Trouble and
'B' Standby Filter Unit Auto-Start
04/16/2019
Procedures
PSAP 6.1
Emergency Procedures for Effluent Sample Retrieval
6