IR 05000382/2019003
| ML19310G722 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/05/2019 |
| From: | John Dixon NRC/RGN-IV/DRP |
| To: | Vazquez S Entergy Operations |
| References | |
| IR 2019003 | |
| Preceding documents: |
|
| Download: ML19310G722 (37) | |
Text
November 5, 2019
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - INTEGRATED INSPECTION REPORT 05000382/2019003
Dear Mr. Vazquez:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Waterford Steam Electric Station, Unit 3. On October 10, 2019, 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.
Two findings of very low safety significance (Green) are documented in this report. One of these findings involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
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 an NCV consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Waterford.
If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Waterford Steam Electric Station. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects
Docket No. 05000382 License No. NPF-38
Enclosure:
As stated
Inspection Report
Docket Number:
05000382
License Number:
Report Number:
Enterprise Identifier: I-2019-003-0002
Licensee:
Entergy Operations, Inc.
Facility:
Waterford Steam Electric Station, Unit 3
Location:
Killona, LA 70057
Inspection Dates:
July 1, 2019 to September 30, 2019
Inspectors:
B. Baca, Health Physicist
L. Carson, Senior Health Physicist
K. Clayton, Senior Operations Engineer
M. Doyle, Operations Engineer
N. Greene, Senior Health Physicist
S. Makor, Reactor Inspector
J. O'Donnell, Health Physicist
F. Ramirez Munoz, Senior Resident Inspector
C. Speer, Resident Inspector
J. Vera, Resident Inspector
Approved By:
John L. Dixon, Jr., Chief
Reactor Projects Branch D
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Waterford Steam Electric Station, Unit 3, 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
Failure to Periodically Calibrate Radiation Monitoring Equipment Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000382/2019003-01 Open/Closed
[H.3] - Change Management 71124.05 The inspectors identified a Green non-cited violation (NCV) of 10 CFR 20.1501(c) for failure to periodically calibrate area radiation monitoring equipment used to perform dose rate measurements. Specifically, on or around January 18, 2012, the licensee began changing the periodic calibrations of area radiation monitors without verifying the instruments were in calibration.
Failure to Implement Procedures for Main Generator Exciter Maintenance Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000382/2019003-03 Open
[H.5] - Work Management 71153 The inspectors reviewed a self-revealed Green finding because the licensee did not follow procedure requirements when performing periodic maintenance on the main generator exciter. Specifically, the licensee did not implement the preventative maintenance steps required by Procedure ME-004-003, Main Exciter, Revisions 300 through 303, to perform inspection, cleaning, and testing of the main exciter during refueling outages.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000382/2019003-02 Quantity of Radioactive Material Shipment Error 71124.08 Open LER 05000382/2019-004-00 Boron Dilution Alarm (Startup Channel High Neutron Flux) Inoperable Resulting in Operation or Condition Prohibited by Technical Specifications.
71153 Closed LER 05000382/2019-005-00 Automatic Reactor SCRAM due to Steam Generator 1 High Level Resulting from a 71153 Discussed
Main Turbine Trip and Subsequent Reactor Power Cutback due to Failed Diode Modules within the Main Exciter
PLANT STATUS
The Waterford Steam Electric Station, Unit 3, began the inspection period at 100 percent power.
On July 31, 2019, operators shutdown the reactor in accordance with Technical Specification 3.0.3 due to excessive leakage in the chemical and volume control system, due to a crack in a drain line weld. On August 7, 2019, operators restarted the reactor. The unit achieved full power on August 8, 2019, and maintained full 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
External Flooding Sample (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated readiness to cope with external flooding for the following areas on July 11, 2019:
- Dry cooling towers
- Reactor auxiliary building
- Turbine building
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Auxiliary feedwater during a period of increased risk significance due to plant shutdown lineup on August 2, 2019
- (2) Emergency feedwater train B with train A inoperable for maintenance on August 3, 2019
- (3) Auxiliary component cooling water train A with train B inoperable for maintenance on August 22, 2019
- (4) Emergency diesel generator train A with train B inoperable for maintenance on September 16, 2019
71111.05A - Fire Protection (Annual)
Annual Inspection (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated fire brigade performance during an unannounced drill on September 4, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (2) Fire area ROOF W, main steam isolation valve A room, on July 30, 2019
- (3) Fire area RAB 8B, switchgear room B, on August 23, 2019
- (4) Fire area RAB 13, battery room 3A, on September 3, 2019
- (5) Fire area RAB 1A, B, C, D, control room, on September 30, 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) Flood zone 14, +46 heating, ventilation and air conditioning (HVAC) and chiller room, on July 25, 2019
71111.07A - Heat Sink Performance
Annual Review (IP Section 02.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Component cooling water heat exchanger A on September 9, 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 examinations.
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 licensed operator performance in the control room during a period of heightened activity due to an unplanned plant shutdown and cooldown in accordance with Technical Specification 3.0.3 due to excessive leakage in the chemical and volume control system, due to a crack in a drain line weld on July 31, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the simulator during an evaluated examination on August 20, 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) Main generator and 25 kV distribution system on September 18, 2019
- (2) Essential chillers on September 30, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Emergent work review associated with control element assembly 43 control system failure on July 17, 2019
- (2) Risk assessment associated with planned yellow risk due to emergency feedwater pump B maintenance on July 29, 2019
- (3) Emergent work review associated with elevated leakage in the chemical and volume control system on July 31, 2019
- (4) Risk assessment and emergent work review associated with control element drive motor control system undervoltage relay failure on August 21, 2019
- (5) Emergent work review associated with the failure of the auxiliary component cooling water header A component cooling water heat exchanger outlet temperature control valve on September 6, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (3 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Operability determination associated with the flow path to the charging pump suction header due to a leak near the volume control tank outlet header drain to the equipment drain tank sump valve on July 10, 2019
- (2) Operability determination associated with main generator lockout relays not actuating following a manual turbine trip on August 6, 2019
- (3) Operability determination associated with the essential chiller B hot gas bypass valve failing to open on September 27, 2019
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 temporary or permanent modifications:
- (1) Auxiliary component cooling water wet tower basin level setpoint change on July 17, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Control element assembly subgroup 10 following the replacement of associated control element drive system electrical components on July 22, 2019
- (2) Emergency feedwater header A to steam generator 1 backup flow control valve, following valve repacking, on August 4, 2019
- (3) Control element drive mechanism control system cabinet 3 undervoltage relay following relay replacement on August 22, 2019
- (4) Safety related switchgear 31A following undervoltage relay calibration on September 11, 2019
- (5) Emergency diesel generator B following a system maintenance outage on September 23, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the licensee's performance during a forced outage to repair failed piping in the chemical and volume control system from July 31 to August 8, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Auxiliary component cooling water pump A Baker test on July 11, 2019
- (2) Shutdown cooling heat exchanger A temperature loop calibration on July 18, 2019
- (3) Essential chillers A and B component cooling water common header inlet and outlet isolation valves on August 19, 2019
- (4) High pressure safety injection pump AB testing on September 17, 2019
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Condensate makeup train A quarterly valve testing on July 16, 2019
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated an emergency preparedness drill on September 25,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walk Downs and Observations (IP Section 02.01) (1 Sample)
The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.
- (1) The inspectors reviewed the following:
Portable Survey Instruments
- AMP 100 (CHP-ARM014)
- AMS-4 (CHP-RD-261)
- LM-177 (CHP-CR-148, CHP-CR-186, CHP-CR-195)
- Ludlum 9-3 (CHP-DR-286, HP-DR-562, CHP-DR-661)
- RO-20 (CHP-DR-119)
- SAC-4 (HP-DS-066)
- Wide range telepole (CHP-TEL034, CHP-TEL039, CHP-TEL138)
Source Check Demonstration
- AMS4 (CHP-AMSD-0214)
- ARGOS 5AB (1410-186)
- Cronos 4 (1011-061)
- MGP Small Tool Monitor (89-0527)
- PM7 (394, 395)
Area Radiation Monitors and Continuous Air Monitors
- Area Radiation Monitors: ARMIR5103, ARMIR5014, ARMIR5015, ARMIR5018, ARMIR5208
- Fuel Handling Building Normal Ventilation Radiation Monitor Loop
- Containment Particulate, Iodine, and Gaseous Monitor
Personnel Contamination Monitors, Portal Monitors and Small Article Monitors
- ARGOS 5AB (1410-86, 1412-364)
- Cronos 4 (1011-061, 1412-364)
- Fastscan (Dosimetry Office, West Side Access)
- GEM 5 (HP-DS-080, HP-DS-095)
- PM7 (394, 395)
Calibration and Testing Program (IP Section 02.02) (1 Sample)
The inspectors evaluated the calibration and testing program implementation.
- (1) The inspectors reviewed the following:
Alarm Setpoint and Calibration Method Check of Personnel Contamination Monitors, Portal Monitors and Small Article Monitors
- ARGOS 5AB (1410-186)
- Cronos4 (1011-061)
- MGP Small Tool Monitor (89-0527)
- PM7 (394, 395)
Failure to Meet Calibration or Source Check Acceptance Criteria
- GEM 5 (1410-190)
- Ludlum 9-3 (HP-DR-559, HP-DR-562)
- RO20 (CHP-DR-163)
- Telepole (CHP-TEL126, CHP-TEL135, CHP-TEL137)
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)
- Fuel Handling Building Exhaust Gaseous Radiation Monitor (RE-5107)
- Plant Stack RAB Ventilation Gaseous Radiation Monitor (RE-0100)
- Dry Cooling Tower Sump 1 Liquid Radiation Monitor (RE-6665)
- Turbine Building Industrial Waste Tank Liquid Radiation Monitor (RE-6778)
- Component Cooling Water Liquid Radiation Monitor (RE-7050)
- Circwater Discharge Liquid Radiation Monitor (RE-1900)
- Control Room Emergency Filtration Unit
- Controlled Ventilation Areas Filter Unit
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) Gaseous Effluent Radiation Monitors
- WO 52776602, RE-0002, Main Condenser Evacuation System (MCES),
March 19, 2019
- WO 52798848, RE-0100.1, RAB Ventilation System / Plant Stack A, June 3, 2019
- WO 52730813, RE-0648, Gaseous Waste Management System (GWMS),
July 7, 2018
- WO 52748891, RE-5107A, Fuel Handling Building Ventilation System A, December 3, 2018
- WO 52719287, RE-5107B, Fuel Handling Building Ventilation System B, March 20, 2018
Liquid Effluent Radiation Monitors
- WO 52717425, RE-7050B, Component Cooling Water Blowdown, March 12, 2018
- WO 52734471, RE-6776, Dry Cooling Tower Sump B, June 21, 2018
- WO 52773476, RE-6778, Turbine Building Industrial Waste Sump, May 6, 2019
- WO 52721495, RE-1900, Circulating Water Discharge, April 2, 2018
Sampling and Analysis (IP Section 02.03) (1 Sample)
The inspectors reviewed the following sampling and analysis:
- (1) Radioactive Effluent Sampling and Analysis Activities
- Fuel Handling Building Radiation Monitor A and B Filter Changeout, September 17, 2019
- Fuel Handling Building Radiation Monitor B Tritium Sample, September 17, 2019
- Plant Stack RAB Ventilation Filter Changeout, September 17, 2019
- Dry Cooling Tower Sump 2 Liquid Sample, September 18, 2019
Effluent Discharges
- The inspectors were unable to observe any active liquid or gaseous discharge activities, but reviewed numerous permits.
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
The inspectors reviewed the following radioactive effluent discharge system surveillance test results:
(1)
- WO 52716247, HVC B - Control Room Emergency Filtration Unit Charcoal Sampling, February 14, 2018
- WO 52716248, HVC B - Control Room Emergency Filtration Unit In-Place Charcoal Testing, February 14, 2018
- WO 52714811, CVAS B - Controlled Ventilation Areas Filtration Unit In-Place Charcoal Testing, March 15, 2018
- WO 52728264, SBV A - Shield Building Ventilation Unit Charcoal Sampling, June 4, 2018
- WO 52767953, CVAS A - Controlled Ventilation Areas Filtration Unit In-Place Charcoal Testing, January 11, 2019
- WO 52795776, HVC A - Control Room Emergency Filtration Unit In-Place Charcoal Testing, July 9, 2019
Dose Calculations (IP Section 02.05) (1 Sample)
The inspectors reviewed the following to asses public dose:
- (1) Gaseous Discharge Permits
- W3GB2017-151
- W3GB2018-038
- W3GB2019-017
- W3GC2018-063
- W3GC2018-150
- W3GC2019-020
Liquid Discharge Permits
- W3LB2017-269
- W3LB2018-078
- W3LB2019-023
- W3LC2017-267
- W3LC2018-242
- W3LC2019-016
Annual Radiological Effluent Release Reports
Abnormal Gaseous or Liquid Tank Discharges
- None occurred
71124.07 - Radiological Environmental Monitoring Program
Site Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the radiological environmental monitoring program implementation.
- (1) The inspectors reviewed the following:
Walkdowns, Calibrations, and Maintenance Record Review
Air Samplers
- APP-1
- APQ-1
- APF-1
- APE-26/30
- P-1
- Q-1
- R-1
- E-1
- M-1
Environmental Sample Collections and Preparation Observation
- SWK-1
- SWE-5
- SWP-7
Licensee Actions in Response to Missed Sample, Inoperable Sampler, Lost TLD or Anomalous Measurement
- For both 2017 and 2018, milk was unavailable at the indicator locations, so broadleaf vegetation was collected as a surrogate.
- In July 2019, air sample pump not running at full capacity, so pump was replaced.
- In July 2019, the G-8 and K1 thermoluminescent dosimeters (TLD) were missing and replaced with new TLDs.
Sampling Program for the Potential of Licensed Material Entering Groundwater
- Condensate Storage Tank
- Old Steam Generator Storage Facility
- Spent Fuel Pool
Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)
- (1) The inspectors evaluated the licensees voluntary groundwater protection initiative.
No additional observations were identified.
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
and Transportation
Radioactive Material Storage (IP Section 02.01)
The inspectors evaluated radioactive material storage.
- (1) The inspectors toured the following areas:
- Spent Fuel Pool
- Cask Storage Pit
- Low Level Waste Storage Facility
- Old Steam Generator Mausoleum
The inspectors performed a container check (e.g., swelling, leakage and deformation)on the following containers:
- Radwaste and Radioactive Material Containers in the Low Level Waste Storage Facility
- Spent Fuel Pool Container Inventory
- Cask Storage Pit Container Inventory
Radioactive Waste System Walkdown (IP Section 02.02) (1 Sample)
The inspectors evaluated the following radioactive waste processing systems [and processes] during plant walkdowns:
- (1) Liquid or Solid Radioactive Waste Processing Systems
- Spent Fuel Pool
- Cask Storage Pit
- Low Level Waste Storage Facility
- Old Steam Generator Mausoleum
Radioactive Waste Resin and/or Sludge Discharges Processes
- There were no current or resin and sludge discharge processes being conducted this inspection.
Waste Characterization and Classification (IP Section 02.03) (1 Sample)
The inspectors evaluated the radioactive waste characterization and classification for the following waste streams:
(1)
- Spent Fuel Pool Operations
- Storage of Spent Tri-Nuclear Filters
- Dry Active Waste
- Spent Resin Transfers
Shipment Preparation (IP Section 02.04) (2 Samples)
The inspectors evaluated [and observed] the following radioactive material shipment preparation processes:
- (1) There were no shipments being prepared for transit during this inspection period. However, the details and content of the following spent resin shipment to the licensees waste processor were reviewed:
- 18-1013, Rx Drain Tank Sludge to Bear Creek
- 18-1020, RWM Resin to Bear Creek
- 19-1019, LWM Resin LSA to Bear Creek
Shipping Records (IP Section 02.05) (1 Sample)
The inspectors evaluated the following non-excepted package shipment records:
(1)
- ACME Shipment to UniTech Services ORSC
- 18-3002, Detector ARM RD
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) July 1, 2018, through June 30, 2019
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) July 1, 2018, through June 30, 2019
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) July 1, 2018, through June 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 that might be indicative of a more significant safety issue. The inspectors identified an observation and associated minor violation related to the licensees treatment of repetitive issues with subgroup 10 of the control element drive mechanism control system documented in the Inspection Results section of this report.
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000382/2019-004-00, Boron Dilution Alarm (Startup Channel High Neutron Flux) Inoperable Resulting in Operation or Condition Prohibited by Technical Specifications (ADAMS Accession: ML19129A439). The inspectors documented a licensee identified violation associated with this LER in the inspection results section of this report.
- (2) LER 05000382/2019-005-00, Automatic Reactor Scram due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback due to Failed Diode Modules within the Main Exciter (ADAMS Accession:
ML19196A346). The circumstances surrounding this LER are documented in the Inspection Results section of this report.
INSPECTION RESULTS
Failure to Periodically Calibrate Radiation Monitoring Equipment Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety
Green NCV 05000382/2019003-01 Open/Closed
[H.3] - Change Management 71124.05 The inspectors identified a Green NCV of 10 CFR 20.1501(c) for failure to periodically calibrate area radiation monitoring equipment used to perform dose rate measurements.
Specifically, on or around January 18, 2012, the licensee began changing the periodic calibrations of area radiation monitors without verifying the instruments were in calibration.
Description:
During a review of calibration records for four area radiation monitors (ARMIR5013, ARMIR5014, ARMIR5015 and ARMIR5018), the inspectors identified the monitors last had a detector calibration on November 18, 2009, November 13, 2009, October 28, 2009, and November 19, 2009, respectively. Upon further review, the inspectors identified that on January 18, 2012, the licensee initiated an Action Request (AR 133414133414 to increase the radiation detector calibration frequency for these area radiation monitors from 2R (three years) to 4R (six years), where R represents a refueling cycle of 18 months. The licensee again extended the calibration frequency of the radiation detectors another time from 4R to 6R (nine years): AR 195165195165dated November 18, 2014, for ARMIR5013 and ARMIR5014; AR 213067213067 dated March 24, 2015, for ARMIR5015; and AR 267979267979 dated February 6, 2017, for ARMIR5018. For each of the frequency extensions, the licensee did not calibrate nor verify the calibration was acceptable before extending the calibration frequency.
These four area radiation monitors are listed in the licensees Final Safety Analysis Report (FSAR), Chapter 12, Table 12.3-2, and are used, in part, to
- (1) measure ambient gamma radiation and to indicate to operations personnel the ambient gamma radiation in specific areas of the plant;
- (2) annunciate and warn of abnormal radiation levels in specific areas of the plant;
- (3) provide base data in controlling access of personnel to radiation areas;
- (4) warn of uncontrolled or inadvertent movement of radioactive material in the plant;
- (5) provide local indication and alarms at key points where a substantial change in radiation levels might be of immediate importance to personnel frequenting the area; and
- (6) furnish information for making radiation surveys. Additionally, a specific note for these monitors in Table 12.3-2 of the FSAR points out these monitors are used by Radiation Protection during shutdown for personnel protection.
The inspectors determined the preventative maintenance program, as described in licensee Procedure EN-DC-324, Preventative Maintenance Program, Revision 22, does not prescriptively include the involvement of radiation protection within its program or process. By not including a member from the Radiation Protection organization during the calibration frequency change process for these four area radiation monitors, the licensee personnel implementing the changes failed to fully understand the area radiation monitor functions, as described in the FSAR, and how they related to Title 10 of the Code of Federal Regulations (10 CFR) Part 20, Standards for Protection Against Radiation, Subpart F, Surveys and Monitoring.
Corrective Actions: The licensee entered the issue in the corrective action program to re-evaluate and document an adequate basis for the calibration frequency change of monitors ARMIR5013, ARMIR5014, ARMIR5015, and ARMIR5018.
Corrective Action References: Condition Report CR-WF3-2019-07366
Performance Assessment:
Performance Deficiency: The failure to periodically calibrate area radiation monitoring instruments used to evaluate dose rate measurements as required by 10 CFR Part 20 was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the plant facilities/equipment and instrumentation attribute of the Occupational Radiation Safety Cornerstone and adversely affected the cornerstone objective to ensure the adequate protection of the worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation.
Specifically, the licensee failed to calibrate or verify the calibration of four area radiation monitors prior to extending their calibration frequency. As a result, the failure to calibrate or verify the calibration of the four area radiation monitors impacts the licensees ability to ensure accurate radiation measurements.
Significance: The inspectors assessed the significance of the finding using Appendix C, Occupational Radiation Safety SDP. The finding was:
- (1) not related to as low as is reasonably achievable planning,
- (2) did not involve an overexposure or
- (3) did not involve a substantial potential for overexposure, and
- (4) the ability to assess dose was not compromised. Therefore, the inspectors determined the finding to be of very low safety significance (Green).
Cross-Cutting Aspect: H.3 - Change Management: Leaders use a systematic process for evaluating and implementing change so that nuclear safety remains the overriding priority.
The finding had a cross-cutting aspect in the area of human performance associated with change management because the licensees change process did not identify that the instrument calibration requirements of 10 CFR Part 20 were applicable to area radiation monitors. Specifically, the change process did not involve an adequate systematic process to include members of the radiation protection organization to ensure compliance of 10 CFR Part 20 were maintained. Although these changes were made effective in 2012, there were recent opportunities for the licensee to evaluate the changes and/or ensure the affected monitors were appropriately calibrated due to multiple condition reports reviewed relative to the performance of these monitors.
Enforcement:
Violation: Title 10 CFR 20.1501(c) requires, in part, the licensee ensure that instruments used for quantitative radiation measurements (e.g., dose rate and effluent monitoring) are calibrated periodically for the radiation measured.
Contrary to the above, on or around January 18, 2012, the licensee failed to ensure that instruments used for quantitative radiation measurements (e.g., dose rate and effluent monitoring) are calibrated periodically for the radiation measured. Specifically, the licensee began changing the periodic calibrations of area radiation monitors without verifying the instruments were currently calibrated and may be adequately used for dose rate measurements of plant areas.
Enforcement Action: This violation is being treated as an NCV, consistent with Section 2.3.2 of the Enforcement Policy.
Quantity of Radioactive Material Shipment Error Unresolved Item (Open)
Unresolved Item URI 05000382/2019003-02 71124.08
Description:
While reviewing the circumstances associated with a solid radwaste/radioactive material (SRW/RAM) transportation event that was identified on May 1, 2019, the inspectors identified several issues of concern related to compliance with certain regulatory requirements, such as, 10 CFR Part 37 and 10 CFR 71.5. The inspectors identified that during a period from April 2-17, 2019, the licensee unknowingly mischaracterized, relocated, prepared, and shipped offsite Category 2 radioactive material quantities of concern (RAMQC). On April 17, 2019, the licensee sent a radioactive waste shipment (19-1015) to a waste processor in Tennessee. The shipment left the site with inaccurate information relative to the total weight and radioactivity amounts on the waste manifest shipping papers. The waste manifest (NRC Forms 540 and 541) accompanying the shipment indicated that shipment 19-1015 contained a total of 8.32 Curies; however, it actually contained 79.2 Curies.
The licensee became aware of the problem with this shipment because their waste processor questioned the net weight of the shipment upon its arrival at their facility. On May 1, 2019, Energy Solutions, located in Oak Ridge, Tennessee, received a shipment of spent resin from Waterford, Unit 3, for processing. The weight of the container was determined to be significantly different from the weight listed on the manifest. Specifically, the manifest indicated the container weighed approximately 742 lbs. When Energy Solutions weighed the container upon receipt, it weighed 6,550 lbs. Waterford, Unit 3, was notified of the inaccuracy of the weight in the manifest, and after revising the weight-based calculated activities for the radionuclides, the licensee provided a revised manifest to Energy Solutions. The original manifest indicated a total package activity of 8.2 Ci, of which 2.1 Ci was Co-60. The revised and corrected manifest specified a total package activity of 72.9 Ci, including 18.7 Ci of Co-60. This radioactivity amount exceeded the Category 2 limits (8.2 Ci) for security concerns under 10 CFR Part 37. Additionally, the licensee had stored, prepared, and shipped offsite RAMQC into the public domain which appeared to be in non-compliance with 10 CFR 71.5 in the implementation of DOT regulations 49 CFR 172.203(d)(3), Subpart C and 49 CFR 172.800 and 802, Subpart I.
These issues of concern require additional information and review to determine whether the preparation and shipment of RAMQC constituted violations of NRC requirements.
Consequently, we are considering this matter as an Unresolved Item (URI).
Planned Closure Actions: The NRC inspectors plan to continue their review of documents provided by the licensee, as they are made available. This review will be a comprehensive assessment of all associated violations and/or findings related to this shipping occurrence of incorrectly calculating the weighted-activities of radionuclides and improperly characterizing the shipment.
Licensee Actions: The licensee placed this matter into their corrective action program for review. The inspectors did not perceive any immediate safety or security concerns.
Corrective Action References: CR-WF3-2019-04477, CR-WF3-2019-07307, CR-WF3-2019-07312
Observation: Semi-Annual Trend Review Associated with the Control Element Drive Mechanism Control System 71152 The inspectors identified an adverse trend involving operability reviews for repetitive failures involving subgroup 10 of the control element drive mechanism control system. From April 29, 2019, through September 9, 2019, the licensee initiated 18 condition reports involving apparent repetitive failures of control element assemblies in subgroup 10 that caused the assemblies to become immovable, but remain trippable. Each condition report affected at least one of the four control element assemblies in subgroup 10. In each instance, the licensee declared the affected rods inoperable and took the actions required by Technical Specification 3.1.3.1, Moveable Control Assemblies.
After six of the condition reports were generated, the inspectors noted that for each identified condition, the licensee reviewed the impact of the condition on the individually affected control element assemblies and made the appropriate operability determination, but the licensee did not review the impact of the aggregate conditions on the operability of subgroup 10 overall.
The licensee addressed the operability of equipment using licensee procedure EN-OP-104, Operability Determination Process, Revision 16. Section 8.10.11 of EN-OP-104 specifically addresses reduced reliability as a degraded or nonconforming condition. Section 8.10.11 requires that the licensee review repetitive failures and, if reliability has been reduced, to consider the equipment degraded or non-conforming and assess its operability.
The inspectors questioned the licensee regarding the operability of subgroup 10 given the guidance in Section 8.10.11 of EN-OP-104. Due to inspector questioning, the licensee reclassified subgroup 10 as operable but degraded or non-conforming due to reduced reliability in condition report CR-WF3-2019-05729. The licensee concluded that subgroup 10 was still capable of performing its safety function to insert control element assemblies into the reactor core.
The inspectors determined that the licensees failure to address the impact of reduced reliability on the operability of subgroup 10 as required by EN-OP-104 was a minor violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings. The licensees cause evaluation for the underlying conditions leading to the repetitive failures of subgroup 10 is still ongoing. The inspectors will document any findings related to the underlying condition in a future inspection report.
Failure to Implement Procedures for Main Generator Exciter Maintenance Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events
Green FIN 05000382/2019003-03 Open
[H.5] - Work Management 71153 The inspectors reviewed a self-revealed Green finding because the licensee did not follow procedure requirements when performing periodic maintenance on the main generator exciter. Specifically, the licensee did not implement the preventative maintenance steps required by procedure ME-004-003, Main Exciter, Revisions 300 through 303, to perform inspection, cleaning, and testing of the main exciter during refueling outages.
Description:
On May 16, 2019, the Waterford, Unit 3, main generator automatically tripped as designed following a loss of excitation field. As part of their troubleshooting, the licensee disassembled the main exciter and discovered that the rotating rectifier had 13 of the 72 outboard fuses failed, 12 of the 36 outboard diodes failed, 2 additional outboard diodes arced and shorted between phases, and one of the 36 inboard diodes failed. The design of the rotating rectifier is to operate at full capacity with up to two diodes per phase out of service. In addition to the component failures, the licensee discovered excessive dirt and debris buildup in the interior of the rotating rectifier.
The licensee established a preventative maintenance program for the main exciter that required the main exciter to be sent offsite to a specialist vendor for major refurbishment every 8 years. This was last performed as part of the refueling outage in 2012. The licensees preventative maintenance program also required minor refurbishment be performed on the main exciter during refueling outages where major refurbishment was not performed. The licensee accomplished this minor refurbishment using licensee Procedure ME-004-003, Main Exciter. Procedure ME-004-003 provides instructions for maintenance and testing of the main exciter, including instructions to ensure electrical and mechanical integrity of the rotating rectifier and its components. The licensee scheduled the minor refurbishment tasks using procedure ME-004-003 during refueling outages in 2014, 2015, 2017, and 2019.
In their review of the past maintenance on the main generator exciter, the licensee found that large portions of procedure ME-004-003 were not performed. During refueling outages 19, 20, 21, and 22, electrical maintenance personnel only inspected the rectifier wheel fuses and cleaned accessible portions of the exciter. Since the main generator exciter was not fully disassembled when Procedure ME-004-003 was performed during those refueling outages, the steps to clean, inspect, and test the internal components of the main exciter were marked as not applicable and not performed. In each instance, electrical maintenance personnel documented the concurrence of systems engineering personnel to not perform the applicable portions of Procedure ME-004-003.
Licensee Procedure EN-HU-106, Procedure and Work Instruction Use and Adherence, Revisions 3 through 7, is used to control when personnel may mark procedural steps as not applicable. Section 7.1.3 of Procedure EN-HU-106 only allows the use of not applicable when doing so does not change the intent of the steps or sections.
Prior to performing Procedure ME-004-003, electrical maintenance personnel requested guidance from systems engineering personnel for which portions were required. Systems engineering personnel advised that the scope of work should be based off the previous refueling outages. System engineering personnel did not confirm the adequacy of the scope of maintenance performed during previous outages. Additionally, electrical maintenance personnel did not ensure that marking sections of Procedure ME-004-003 as not applicable did not change the intent of the steps or sections.
Corrective Actions: The licensees immediate corrective action was to disassemble and clean the main generator exciter, and to either repair or replace the failed components associated with the rotating rectifier. Long term corrective actions include revising the preventative maintenance strategy and procedures to ensure the correct scope of maintenance is included in both the 8-year major and every refueling cycle minor refurbishments.
Corrective Action References: CR-WF3-2019-04788
Performance Assessment:
Performance Deficiency: The failure to implement the requirements of Procedure ME-004-003 when required by the preventative maintenance program was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the equipment performance attribute of the Initiating Events Cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, the failure to perform maintenance in accordance with Procedure ME-004-003 to ensure the integrity and cleanliness of internal components of the main generator exciter resulted in an electrical fault that caused an automatic trip of the main turbine and generator.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using IMC 0609, Appendix A, Exhibit 1, Initiating Events Screening Questions, the inspectors determined the finding to be of very low safety significance (Green) because the finding did not cause a reactor trip and the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition.
Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities. Specifically, the licensee did not implement the process of controlling and executing work activities controlled by Procedure EN-HU-104 when personnel implementing Procedure ME-004-003 regularly marked large sections as not applicable which changed the intent of the sections.
Enforcement:
Inspectors did not identify a violation of regulatory requirements associated with this finding.
LER (Discussed)
Automatic Reactor SCRAM due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback due to Failed Diode Modules within the Main Exciter LER 05000382/2019-005-00 71153
Description:
On May 16, 2019, the Waterford main generator automatically tripped as designed following a loss of excitation field. Following the trip, the reactor power cutback system actuated as designed to reduce reactor power. Following the reactor power cutback, the reactor automatically tripped due to high feedwater level in steam generator 1. The inspectors documented a Green finding in this report related to the cause of the automatic main generator trip. The cause evaluation of the subsequent automatic reactor trip due to high steam generator level is still ongoing and will be documented in a later inspection report.
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 an NCV, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Technical Specification 3.1.2.9, Boron Dilution, requires, in part, that with one boron dilution alarm inoperable and the primary makeup water flow path to the reactor coolant system not isolated, determine reactor coolant system boron concentration within one hour. Contrary to the above, on March 10, 2019, with one boron dilution alarm inoperable and the primary makeup water flow path to the reactor coolant system not isolated, the licensee did not determine reactor coolant system boron concentration within one hour.
On March 10, 2019, startup channel 1, one of the boron dilution alarms, was de-energized and rendered inoperable during the performance of surveillance testing at approximately 3:30 p.m. on March 10, 2019. The licensee identified that startup channel 1 was de-energized while taking Technical Specification logs and re-energized startup channel 1 on March 10, 2019, at 11:18 p.m., exceeding the Technical Specification 3.1.2.9 allowed outage time by approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
Significance/Severity: The finding was of very low safety significance, Green, in accordance with Inspection Manual Chapter 0609, Appendix G, Attachment 1, Exhibit 3, Mitigating Systems Screening Questions because the loss of the boron dilution alarms did not represent the actual loss of a safety function.
Corrective Action References: CR-WF3-2019-03161
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On September 19, 2019, the inspectors presented the Public Radiation Safety exit meeting inspection results to Mr. B. Lanka, Acting Site Vice President, and other members of the licensee staff.
- On September 24, 2019, the inspectors presented the 2019003 Biennial Requalification telephonic exit debrief inspection results to Mr. V. Ford, Operations Training Superintendent, and other members of the licensee staff.
- On October 10, 2019, the inspectors presented the integrated inspection results to Mr. S. Vazquez, Site Vice President, and other members of the licensee staff.
- On October 17, 2019, the inspectors presented the Final Exit Meeting for Radiation Safety Inspection results to Mr. S. Vazquez, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
ECM15-004
Waterford FLEX Internal Flooding Calculation
MNQ3-5
Flooding Analysis Outside Containment
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2018-06958, 2019-03900, 2019-05201
Procedures
OP-901-521
Severe Weather and Flooding
71111.04Q Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-04798, 2019-03258
Procedures
OP-002-001
Auxiliary Component Cooling Water
315
OP-003-035
310
OP-009-002
351
OP-009-003
Emergency Feedwater
309
71111.05Q Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-03742, 2019-05956
Miscellaneous
NS-TB-002
Turbine Building +15.00' West including Feedwater Pump
"A" Auxiliary Feedwater Pump, Main Lube Oil Storage Tank
and Condensate Pump
Procedures
Fire Brigade Drills
Fire Brigade Equipment
310
Fire Emergency/Fire Report
2
RAB 13-001
Battery Room 3A
RAB 1A, B, C, D-
001
Control Room, H&V Room, Emergency Living Quarters and
Computer Room
RAB 8B,E,F-001
Switchgear Room B
Switchgear Room A/B
ROOF W-001
Roof W (MSIV A)
UNT-005-013
Calculations
ECM05-004
Required Isolation Time to Prevent Depletion of CCW Surge
Tank due to SSE
ECM15-004
Waterford FLEX Internal Flooding Calculation
MNQ3-5
Flooding Analysis Outside Containment
PRA-W3-01-002
W3 Internal Flooding Analysis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-01724, 2019-01719
Procedures
OP-002-004
Chilled Water System
317
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2018-05404, 2018-06396, 2018-07109, 2019-2164
Procedures
CE-002-003
Maintaining Auxiliary Component Cooling Water Chemistry
306
CE-002-007
Maintaining Component Cooling Water Chemistry
309
Corrective Action
Documents
Control Room
Condition Report
Summary for
2018-2019
Control Room Condition Report Summary for 2018-2019
06/25/2019
Miscellaneous
Simulator
Differences List
Simulator Differences List
June 26,
2019
Simulator
Discrepancy
Report July 2017
to July 2019
Simulator Discrepancy Report July 2017 to July 2019
07/02/2019
Waterford 2019
Requalification
Exam Week 1 - 3
Operations Exam
07/29/2019
Waterford 2019
Requalification
Exam Week 1 - 3
Written Exam
07/29/2019
Procedures
Licensed Operator Requalification Training Program
Description
Systematic Approach to Training Process
Revision 23
Simulator Configuration Control
Revision 10
Conduct of Simulator Training
Revision 15
Examination Security
Revision 8
OI-024-000
Maintaining Active SRO-RO Status
314
TQF-202-SBT
Scenario Based Testing Checklist
Revision 1
TQF-210-DD03
LOR Simulator Crew performance Evaluation Grading
Criteria
Revision 5
WSIM-DIR-002
Simulator Core Reload Acceptance Test
Revision 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.11Q Miscellaneous
WSXM-LOR-
194EXM
2019 Cycle 4 Biennial Simulator Exam Week 5
Procedures
OP-010-005
Plant Shutdown
336
OP-010-006
Outage Operations
333
OP-901-113
Volume Control Tank Makeup Control Malfunction
305
OP-901-311
Loss of Train B Safety Bus
2
OP-902-000
Standard Post Trip Actions
OP-902-003
Loss of Offsite Power/Loss of Forced Circulation Recovery
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2017-05763, 2017-05844, 2019-04788, 2019-04813, 2019-
04848, 2019-07376
Procedures
Maintenance Rule Scope and Basis
Maintenance Rule Monitoring
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-06375
Procedures
Shutdown Safety Management Program (SSMP)
On Line Risk Assessment
OI-37-000
Operations Risk Assessment Guideline
313
Work Orders
2790245
Calculations
SI Calculation
1900769.301
Evaluation of Leaking 1-inch Line Upstream of Valve CVC-
186
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-05704, 2019-05755, 2019-06307, 2019-07242, 2019-
07462
Miscellaneous
BOP-RT-19-001
Digital Radiographic Examination
07/09/2019
BOP-VT-19-019
Visual Examination of Welds
07/09/2019
Procedures
Operability Determination Process
Calculations
EC 102-001
Ultimate Heat Sink Margin Restoration - WCT Basin Level
Setpoint Change - Train A
COLSS Analysis/Station Interface Calculation
ECI91-005
Wet Cooling Tower Basin Water Level Instrumentation
Loops Uncertainty Calculation
MN(Q)-9-38
Capacity of Wet Cooling Tower Basins
Drawings
B425 L7079A
ACC - WET COOLING TOWER A BASIN WATER LEVEL
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
DEIC-I-502
Setpoint and Uncertainty Determination
Ultimate Heat Sink Margin Restoration
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-06374
Procedures
Operability Determination Process
ME-003-318
G.E. Undervoltage Relay Model 12IAV55C
306
ME-007-036
G.E. Auxiliary Relays 12HFA51B and 12HFA151B7F
306
OP-903-005
Control Element Assembly Operability Check
OP-903-121
Safety Systems Quarterly IT Valve Tests
Work Orders
00528219, 00529055, 52811969, 530144
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-06358, 2019-06379, 2019-06384
Procedures
On-Site Safety Review Committee
Shutdown Safety Management Program (SSMP)
OP-003-033
Main Feedwater
25
OP-003-035
310
OP-010-003
Plant Startup
349
OP-010-006
Outage Operations
333
Calculations
ECP96-007
Auxiliary Component Cooling Water Supply and Return
Piping
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-06518, 2018-01724, 2018-01719
Procedures
Online Motor Electrical Testing
MI-005-219
Calibration Check and Verification of Thermocouples and
304
OP-903-119
Secondary Auxiliaries Quarterly IST Valve Test
Work Orders
2798924, 52877149, 52814428
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-07397, 2019-07422, 2019-07424, 2019-07445, 2019-
07449, 2019-07450, 2019-07451, 2019-07467
Procedures
Recognition & Classification of Emergency Conditions
Alert
310
Site Area Emergency
309
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
General Emergency
310
OP-010-005
Plant Shutdown
337
OP-901-102
305
OP-901-212
Rapid Plant Power Reduction
OP-901-402
High Airborne Radioactivity in Reactor Auxiliary Building
OP-901-410
High Activity in Reactor Coolant System
OP-901-512
Loss of Turbine Cooling Water
OP-902-000
Standard Post Trip Actions
OP-902-001
Reactor Trip Recovery
OP-902-007
Steam Generator Tube Rupture Recovery Procedure
Calibration
Records
2018-B2.28-
CALDAT-04015
Portable Instrumentation Calibration Data Sheet: Ludlum
LM-177 (CHP-CR-186)
10/01/2018
2018-B2.28-
CALDAT-05747
Portable Instrumentation Calibration Data Sheet: AMP100
(CHP-ARM014)
09/06/2018
2018-B2.28-
CALDAT-06937
Portable Instrumentation Calibration Data Sheet: Wide
Range Telepole (CHP-TEL034)
10/10/2018
2018-B2.28-
CALDAT-06939
Portable Instrumentation Calibration Data Sheet: Wide
Range Telepole (CHP-TEL039)
10/10/2018
2018-B2.28-
CALDAT-07490
Portable Instrumentation Calibration Data Sheet: RO-20
(CHP-DR-119)
11/14/2018
2018-B2.28-
CALDAT-08281
Portable Instrumentation Calibration Data Sheet: Ludlum
LM-177 (CHP-CR-195)
2/18/2018
2018-B2.28-
CALDAT-08396
Portable Instrumentation Calibration Data Sheet: AMS-4
Particulate Detector (HP-RD-261)
2/27/2018
2019-B2.28-
CALDAT-00247
Portable Instrumentation Calibration Data Sheet: SAC-4
(HP-DS-066)
01/08/2019
2019-B2.28-
CALDAT-03118
Portable Instrumentation Calibration Data Sheet: Ludlum
LM-177 (CHP-CR-148)
04/11/2019
2019-B2.28-
CALDAT-03128
Portable Instrumentation Calibration Data Sheet: Wide
Range Telepole (CHP-TEL138)
04/15/2019
2019-B2.28-
CALDAT-03199
Portable Instrumentation Calibration Data Sheet: Ludlum 9-3
(CHP-DR-286)
04/16/2019
2019-B2.28-
CALDAT-03211
Portable Instrumentation Calibration Data Sheet: Ludlum 9-3
(HP-DR-562)
04/17/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2019-B2.28-
CALDAT-04802
Portable Instrumentation Calibration Data Sheet: Ludlum 9-3
(CHP-DR-661)
08/20/2019
ARGOS
Calibration Data
Sheet HP-DS-077
ARGOS Calibration Data Sheet: HP-DS-077, Westside
Access
5/8/2019
ARGOS
Calibration Data
Sheet HP-DS-098
ARGOS Calibration Data Sheet: HP-DS-098, Westside
Access
05/07/2019
Canberra GEM-5
Calibration Sheet
HP-DS-080
Canberra GEM-5 Calibration Sheet HP-DS-080, Westside
Access
07/10/2019
Canberra GEM-5
Calibration Sheet
HP-DS-095
Canberra GEM-5 Calibration Sheet HP-DS-095, PAP
10/30/2018
CRONOS
Calibration Data
Sheet HP-DS-090
CRONOS Calibration Data Sheet: HP-DS-090, Westside
Access
3/26/2019
CRONOS
Calibration Data
Sheet HP-DS-091
CRONOS Calibration Data Sheet: HP-DS-091, Westside
Access
08/12/2019
Fastscan
2019 Fastscan Recalibration Waterford 3 West Side Access
07/14/2019
Fastscan
2019 Fastscan Recalibration Waterford 3 Dosimetry Office
07/14/2019
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2017-09300; 2017-09392; 2017-09662; 2018-00104; 2018-
239; 2018-00362; 2018-00547; 2018-00983; 2018-01348;
2018-01371; 2018-02007; 2018-02085; 2018-02917; 2018-
03146; 2018-03680; 2018-03868; 2018-05670; 2018-05842;
2018-06684; 2019-00461; 2019-00780; 2019-01532; 2019-
03504; 2019-03529; 2019-03899; 2019-04105; 2019-04407;
2019-04624
Miscellaneous
Results of the Radiochemistry Cross Check Program -
Entergy Waterford 4 - 2nd Quarter 2019
07/24/2019
Results of the Radiochemistry Cross Check Program -
Entergy Waterford 4 - 3rd Quarter 2018
11/27/2018
Results of the Radiochemistry Cross Check Program -
10/04/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Entergy Waterford 4 - 2nd Quarter 2017
Instrument Source Checking Source Inventory
09/11/2019
2018-B2.28-
LABSTN-0004
Laboratory Standard - Calibration/verification Data: V-570
Meter
06/12/2018
2018-B2.28-
SRCVER-0006
Source Verification: MODEL-89 (400) Serial Number: 2414-
SRC1993001
2/18/2018
TD-G063.0115
General Atomic Area Radiation Monitoring Systems
Equipment Manual E-115-930
2/10/1987
Procedures
Laboratory Analytical Quality Control
EN-CY-102-01
Quality Control for Analytical Laboratory Interlab and Intralab
Cross-Check Programs
EN-CY-102-02
Analytical Method Development Quality Assurance
EN-CY-102-03
Calculation Guide for Laboratory QAQC
Preventive Maintenance Component Classification
Maintenance Rule Scope and Basis
Preventive Maintenance Program
MI-005-906
RADIATION MONITORING SYSTEM DESK GUIDE
MI-005-923
Calibration Procedure - General Atomic Area Radiation
Monitor Assemblies 0359-360: ARMIR5013, 5014, 5015,
5018
Self-Assessments LO-WLO-2017-
0032
Pre-NRC Self-Assessment IP 71124.05 Radiation Monitoring
Instrumentation
09/20/2017
LO-WLO-2019-
0015
Pre-NRC Self-Assessment, IP71124.05 Radiation Monitoring
Instrumentation
07/18/2019
Work Orders
WO-WF3-
180572; 180573; 425005; 470721; 485439; 495141;
519720; 51693877; 52329961; 52668978; 52675543;
2739065; 52743583; 52745414; 52759169; 52780184;
2780545; 52780748; 52781284; 52782394;
2782394; 52878443
Calibration
Records
Component Cooling Water Blowdown (RE-7050B)
03/12/2018
Fuel Handling Building Ventilation System B (RE-5107B)
03/20/2018
Circulating Water Discharge (RE-1900)
04/02/2018
Gaseous Waste Management System (GWMS) (RE-0648)
07/16/2018
Dry Cooling Tower Sump B (RE-6776)
06/21/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Fuel Handling Building Ventilation System A (RE-5107A)
2/03/2018
Turbine Building Industrial Waste Sump (RE-6778)
05/06/2019
Main Condenser Evacuation System (MCES) (RE-002)
03/19/2019
RAB Ventilation System/Plant Stack A (RE-0100.1)
06/03/2019
Corrective Action
Documents
CR-HQN-YYYY-
NNNNN
2017-00319
CR-WF3-YYYY-
NNNNN
2017-08186; 2017-09325; 2017-09736; 2018-00983; 2018-
2000; 2018-02007; 2018-03972; 2019-04516; 2019-04712;
2019-06735; 2019-006736; 2019-06737; 2019-06748
Miscellaneous
2018 Annual Radioactive Effluent Release Report
2018
Results of Radiochemistry Cross Check Program - 4th
Quarter 2018
05/13/2019
Results of Radiochemistry Cross Check Program - 3rd
Quarter 2018
11/27/2018
Results of Radiochemistry Cross Check Program - 2nd
Quarter 2019
08/12/2019
2017 Annual Radioactive Effluent Release Report
2017
Results of Radiochemistry Cross Check Program - 4th
Quarter 2017
07/11/2018
W3GB2017-151
Containment Gas Effluent Release Report - Batch
2/20/2017
W3GB2018-038
Containment Gas Effluent Release Report - Batch
03/22/2018
W3GB2019-017
Miscellaneous Gas Effluent Release Report - Batch
2/22/2019
W3GC2018-063
Plant Stack Gas Effluent Release Report - Continuous
05/17/2018
W3GC2018-150
Main Condenser Evacuation System (MCES) Gas Effluent
Release Report - Continuous
11/29/2018
W3GC2019-020
Fuel Handling Building (FHB) Gas Effluent Release Report -
Continuous
2/19/2019
W3LB2017-269
Boric Acid Condenser Tank C Liquid Effluent Release
Report - Batch
2/01/2017
W3LB2018-078
Liquid Waste Management Liquid Effluent Release Report -
Batch
05/12/2018
W3LB2019-023
Steam Generator Blowdown Liquid Effluent Release Report -
Batch
01/29/2019
W3LC2017-267
Turbine Building Industrial Waste System (TBIWS) Liquid
2/04/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Effluent Release Report - Continuous
W3LC2018-242
Turbine Building Industrial Waste System (TBIWS) Liquid
Effluent Release Report - Continuous
01/01/2019
W3LC2019-016
Dry Cooling Tower Sump 1 (DCTS1) Liquid Effluent Release
Report - Continuous
01/01/2019
Procedures
CE-001-004
Periodic Analysis Scheduling Program
318
CE-003-509
Routine Filter Replacement and Grab Sampling on
Particulate Iodine Gas (PIG) Monitors and Wide Range Gas
Monitors (WRGMs)
308
CE-003-512
Liquid Radioactive Waste Release Permit (Manual)
2
CE-003-513
Gaseous Radioactive Waste Release Permit (Manual)
304
CE-003-514
Liquid Radioactive Waste Release Permit (Computer)
303
CE-003-515
Gaseous Radioactive Waste Release Permit (Computer)
304
CE-003-516
Calculation and Adjustment of Radiation Monitoring
Setpoints
2
CE-003-700
General Grab Sampling Techniques
316
MI-003-368
Fuel Handling Building Ventilation System Normal Effluent
Exhaust A or B Particulate and Gaseous Radiation Monitor
Calibration PRMIR5107.A or PRMIR5107.B
016
MI-003-380
Plant Vent Stack Safety Channel A or B Particulate and
Gaseous Radiation Monitor Calibration PRMIR0100.1 or
PRMIR0100.2
309
MI-003-466
Dry Cooling Tower Sumps Liquid Effluent Radiation Monitor
Channel Calibration PRMIR6775 or PRMIR6776
308
MI-003-469
Turbine Building Industrial Waste Sumps Combined
Discharge Liquid Effluent Radiation Monitor Channel
Calibration PRMIR6778
013
MI-003-471
Circulating Water Discharge Liquid Effluent Radiation
Monitor Channel Calibration PRMIR1900
011
MI-003-473
Gaseous Waste Management Discharge Noble Gas
Radiation Monitor Channel Calibration PRMIR0648
305
UNT-005-014
Offsite Dose Calculation Manual
307
Self-Assessments LO-WLO-2019-
0016
Pre-NRC Assessment of Radiation Safety Inspection Criteria
08/07/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
CVAS B - Controlled Ventilation Areas Filtration Unit In-
Place Charcoal Testing
03/15/2018
HVC B - Control Room Emergency Filtration Unit Charcoal
Sampling
2/14/2018
HVC B - Control Room Emergency Filtration Unit In-Place
Charcoal Testing
2/14/2018
SBV A - Shield Building Ventilation Unit Charcoal Sampling
06/04/2018
CVAS A - Controlled Ventilation Areas Filtration Unit In-
Place Charcoal Testing
01/11/2019
HVC A - Control Room Emergency Filtration Unit In-Place
Charcoal Testing
07/09/2019
Calibration
Records
ENV-FT-016
Flow Totalizer for APQ-1
03/13/2019
EM IM0110, Calibrate Backup Met Tower IAW MI-003-396
09/19/2019
EM IM0100, Calibrate Primary Met Tower IAW MI-003-395
2/20/2018
EM IM0110, Calibrate Backup Met Tower MI-003-396
03/20/2019
EM IM0100, Calibrate Primary Met Tower IAW MI-003-395
07/05/2019
Corrective Action
Documents
CR-HQN-YYYY-
NNNNN
2017-01911; 2018-02412
CR-WF3-YYYY-
NNNNN
2017-09465; 2017-09810; 2018-00539; 2018-01625; 2018-
01749; 2018-02620; 2018-04363; 2018-05354; 2018-06463;
2018-07201; 2018-07297; 2019-02608; 2019-03611; 2019-
03804; 2019-04264; 2019-04329; 2019-04412; 2019-05720;
2019-05762; 2019-05882; 2019-06851
Miscellaneous
Ground Water Monitoring Plan
2/10/2014
2017
Annual Radioactive Effluent Release Report
2018
2017
Annual Radiological Environmental Operating Report
2018
2018
Annual Radioactive Effluent Release Report
2019
2018
Annual Radiological Environmental Operating Report
2019
CR-WF3-2019-
07315
CR with attached Inspections of Met Towers
09/19/2019
PR-PRHQN-
2018-00908
Procedure Revision Tracker associated with CR-HQN-2018-
2412 for EN-FAP-OM-012
11/06/2018
Primary
Guyed Tower Inspection Report
6/3/2019
Secondary
Guyed Tower Inspection Report
6/3/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
WF3-CR-2017-
09001
Response to Contaminated Spills/Leaks
11/10/2017
WF3-CR-2018-
03420
Response to Contaminated Spills/Leaks
06/16/2018
Procedures
CE-001-004
Periodic Analysis Scheduling
318
CE-003-522
Meteorological Data Collection and Processing
CE-003-523
Meteorological Monitoring Program
Monitoring of Nonradioactive Systems
Radiological Ground Water Monitoring Program
Radiological Environmental Monitoring Program
Response to Contaminated Spills/Leaks
MI-003-395
Primary Meteorological Tower Instrument Calibration EM
IM0110
2
MI-003-396
Secondary Meteorological Tower Instrument Calibration EM
IM0110
UNT-005-014
Offsite Dose Calculation Manual
307
Self-Assessments
Teledyne Brown Engineering Knoxville Laboratory Internal
QA Audit 2018
11/13/2018
Internal Assessment - Stanford Dosimetry
01/29/2019
NUPIC Joint Utility Audit No. 24791
05/09/2019
LO-WLO-2019-
0016
Pre-NRC Assessment of Radiation Safety Inspection Criteria
08/07/2019
Work Orders
Primary Met Tower Reading Suspect
2/19/2017
Troubleshoot/Repair Secondary Met Tower
From WR 437511
08/22/2018
Troubleshoot/Repair BU Met Tower 33 ft. Wind Direction
CR-19-4329
05/01/2019
Corrective Action
Documents
CR-HQN-YYYY-
NNNNN
2017-01400; 2017-01543
CR-WF3-YYYY-
NNNNN
2017-03321; 2017-07899; 2017-07903; 2019-4177
Procedures
Integrated Transportation Security Plan
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Self-Assessments WLO-2019-
000015
Pre-Assessment of NRC IP71124.08
8/21/2019
Shipping Records 17-1009
Unitech ORSC: Blowdown Resin
4/20/17
17-1017
Unitech-ORSC: Wood waste
6/19/17
17-1018
Unitech-ORSC: Wood waste
7/28/17
18-1013
ESM: Scaffolding
18-1014
ESBS: Cask Liner with Resin and Sludge
5/24/18
18-3002
Radiation Instruments: GA
1/18/18
19-1015
ESBC: Resin in a Shielded Cask
19-1019
ESBC: Resin in a Shielded Cask
8/15/19
71151
Miscellaneous
NRC Performance Indicator (PI) Data - 3rd Quarter 2018
ROP Data
10/21/2018
NRC Performance Indicator (PI) Data - 4th Quarter 2018
ROP Data
01/10/2019
NRC Performance Indicator (PI) Data - 1st Quarter ROP
Data
04/11/2019
NRC Performance Indicator (PI) Data - 2nd Quarter ROP
Data
07/15/2019
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2019-03572, 2019-04410, 2019-04628, 2019-04654,
2019-04988, 2019-05014, 2019-05026, 2019-05279,
2019-05488, 2019-05489, 2019-05662, 2019-05729,
2019-06000, 2019-07075, 2019-07529
Procedures
Operability Determination Process
OP-004-004
Control Element Drive
24