IR 05000382/2018003
| ML18304A163 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/30/2018 |
| From: | O'Keefe N NRC/RGN-IV/DRP/RPB-D |
| To: | Dinelli J Entergy Operations |
| References | |
| IR 2018003 | |
| Download: ML18304A163 (33) | |
Text
October 30, 2018
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NRC INTEGRATED INSPECTION REPORT 05000382/2018003
Dear Mr. Dinelli:
On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Waterford Steam Electric Station, Unit 3. On October 11, 2018, 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.
The NRC inspectors did not identify any finding or violation of more than minor significance.
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/
Neil OKeefe, Chief Branch D Division of Reactor Projects
Docket No. 50-382 License No. NPF-38
Enclosure:
Inspection Report 05000382/2018003 w/ Attachments:
1. Documents Reviewed 2. NRC Request for Information
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number(s):
05000382
License Number(s):
Report Number(s):
Enterprise Identifier: 1-2018-003-0002
Licensee:
Entergy Operations, Inc.
Facility:
Waterford Steam Electric Station, Unit 3
Location:
Killona, Louisiana
Inspection Dates:
July 1, 2018 to September 30, 2018
Inspectors:
F. Ramírez, Senior Resident Inspector
C. Speer, Resident Inspector
J. Dixon, Senior Project Engineer
T. Farina, Senior Operations Engineer
P. Elkmann, Senior Emergency Preparedness Inspector
N. Greene, PhD, Senior Health Physicist
I. Anchondo, Reactor Inspector, Engineering Branch 2
G. George, Senior Reactor Inspector, Engineering Branch 1
Approved By:
Neil OKeefe
Branch Chief
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.
List of Findings and Violations
No findings or violations of more than minor significance were identified during the inspection.
Additional Tracking Items
Type Issue number Title Report Section Status URI 05000382/2017008-04 Potential Failure to Obtain a License Amendment for Changes to Diesel Generator Surveillance Test Interval 71111.21M Closed
PLANT STATUS
The plant operated at or near rated thermal power for the entire 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
71111.01Adverse Weather Protection External Flooding
The inspectors evaluated readiness to cope with external flooding in the safety-related switchgear room A on August 1, 2018.
71111.04Equipment Alignment Partial Walkdown
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Shield building ventilation train A with train B out of service for maintenance on July 17, 2018
- (2) Auxiliary feedwater system following an extended system outage on August 19, 2018
- (3) Emergency feedwater train A with train B out of service for maintenance on August 21, 2018
- (4) Emergency diesel generator A with emergency diesel generator B out of service for maintenance on September 11, 2018
Completed Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the reactor auxiliary building controlled ventilation area system on September 12, 2018.
===71111.05AQFire Protection Annual/Quarterly
Quarterly Inspection===
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Fire area NS-TB-001, turbine building +15.00 east on July 18,2018
- (2) Fire area NS-TB-003, turbine building mezzanine +40.00 east on August 19, 2018
- (3) Fire area RAB 34-001, safeguards valve gallery rooms A and B on August 21, 2018
- (4) Fire area NS-TB-004, turbine building +40.00 west on August 22, 2018
- (5) Fire area RAB2-001, heating and ventilation mechanical room on September 11, 2018
Annual Inspection (1 Sample)
The inspectors evaluated fire brigade performance during an unannounced fire drill in the +35 reactor auxiliary building electrical penetration B area on September 21, 2018.
===71111.11Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification===
The inspectors observed and evaluated requalification scenario in the simulator on July 23, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated control room performance during control element assembly testing on August 3, 2018.
Operator Exams (1 Sample)
The inspector reviewed and evaluated requalification examination results on August 27, 2018.
===71111.12QMaintenance Rule Implementation
Routine Maintenance Effectiveness===
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Dry cooling tower sump pump failures on July 24, 2018
- (2) Controlled ventilation area system routine assessment of maintenance on August 8, 2018
71111.13Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Emergent work related to electrical bus 31AB on July 25, 2018
- (2) Risk assessment associated with work in the transformer yard on August 13, 2018
- (3) Planned yellow risk due to emergency feedwater system train B work window on August 21, 2018
- (4) Planned yellow risk due to emergency diesel generator B work window on September 10, 2018
- (5) Planned yellow risk due to emergency diesel generator A work window on September 27, 2018
71111.15Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Operability determination for charging pump B due to relay calibration values found out of tolerance on July 19, 2018
- (2) Functionality assessment for motor generator set B due to high vibrations on July 31, 2018
- (3) Operability determination for emergency diesel generator B due to low field voltage and current during testing on August 6, 2018
- (4) Operability determination for emergency diesel generator B subgroup relays due to the failure of the safety injection actuation signal relay on August 21, 2018
71111.18Plant Modifications
The inspectors evaluated the following temporary modification:
- (1) Temporary replacement of failed pressurizer proportional heater bank 1 heaters 3 and 4 with heaters from backup bank 2 and 3 on August 1, 2018
- (2) Ultimate heat sink margin restoration Phase 3 permanent modification on August 15, 2018
71111.19Post Maintenance Testing
The inspectors evaluated the following post maintenance tests:
- (1) Train A sequencer following relay replacement on August 6, 2018
- (2) Charging pump A after seal pump/motor and gearbox replacement on August 9, 2018
- (3) Auxiliary feedwater pump to motor coupling removal/reinstallation and pump outboard bearing gasket replacement on August 14, 2018
- (4) Reactor auxiliary building +46 HVAC air handling unit following planned maintenance on September 5, 2018
- (5) Auxiliary component cooling water pump B following emergent bearing oil replacement on September 18, 2018
- (6) Emergency diesel generator A following planned relay replacement on September 27, 2018
===71111.22Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine===
- (1) Emergency feedwater pump A operability run on July 10, 2018
- (2) High pressure safety injection pump B operability run on July 25, 2018
- (3) Reactor trip circuit breaker #5 test on August 1, 2018
- (4) Core protection calculator A test on August 2, 2018
- (5) Control room emergency filtration unit outside air intake upstream isolation valve test on August 14, 2018
71114.02Alert and Notification System Testing
The inspector evaluated the maintenance and testing of the alert and notification system on August 1, 2018.
71114.03Emergency Response Organization Staffing and Augmentation System
The inspector evaluated the readiness Emergency Preparedness Organization on August 2, 2018.
71114.04Emergency Action Level and Emergency Plan Changes
The inspector evaluated submitted changes to the Waterford 3 Steam Electric Station Emergency Plan, Revision 49, and Procedure EP-001-001, Recognition and Classification of Emergency Conditions, Revision 33, between July 9 and 12, 2018. This evaluation does not constitute NRC approval.
71114.05Maintenance of Emergency Preparedness
The inspector evaluated the maintenance of the emergency preparedness program on August 6 and 7, 2018.
71114.06Drill Evaluation Emergency Planning Drill
The inspectors evaluated an emergency planning drill on August 29,
RADIATION SAFETY
71124.02Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Radiological Work Planning
The inspector evaluated the licensees radiological work planning by reviewing the following activities:
- (1) RWP 2016-0118, Loading of Dry Fuel Storage Cask #18, with Spent Fuel and Transport including all DFS Support Activities to include Set Up/Demobilization, Revision 02
- (2) RWP 2016-0119, Loading of Dry Fuel Storage Cask #19, with Spent Fuel and Transport including all DFS Support Activities to include Set Up/Demobilization, Revision 01
- (3) RWP 2016-0123, Loading of Dry Fuel Storage Cask #23, with Spent Fuel and Transport including all DFS Support Activities to include Set Up/Demobilization, Revision 00
- (5) RWP 2017-0610, Erect/Dismantle Scaffolding in the Reactor Containment Building, Revision 00
- (6) RWP 2017-0702, Reactor Disassembly Activities, Revision 00
- (7) RWP 2017-0705, Reactor Reassembly Activities, Revision 00
- (8) RWP 2018-0001, Radiation Protection to Perform Job Coverage, Routine Surveys, Inspections and Walkdowns, Revision 00
- (9) RWP 2018-0006, Radwaste Processing/Shipping in all Radiologically Controlled Areas, Revision 00
Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)
The inspectors evaluated dose estimates and exposure tracking.
71124.04Occupational Dose Assessment Source Term Characterization
The inspectors evaluated the licensees source term characterization.
External Dosimetry (1 Sample)
The inspectors evaluated the licensees external dosimetry program.
Internal Dosimetry (1 Sample)
The inspectors evaluated the licensees internal dosimetry program.
Special Dosimetric Situations (1 Sample)
The inspectors evaluated the licensees performance for special dosimetric situations.
OTHER ACTIVITIES - BASELINE
71151Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
- (1) MS08: Heat Removal Systems (07/01/2017-06/30/2018)
- (2) MS09: Residual Heat Removal Systems (07/01/2017-06/30/2018)
- (3) MS10: Cooling Water Support Systems (07/01/2017-06/30/2018)
- (4) EP01: Drill/Exercise Performance Sample (10/01/2017-06/30/2018)
- (5) EP02: Emergency Response Organization Drill Participation Sample (10/01/2017-06/30/2018)
- (6) EP03: Alert And Notification System Reliability Sample (10/01/2017-06/30/2018)
71152Problem Identification and Resolution Annual Follow-up of Selected Issues
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Process analog control card failures that resulted in a Part 21 report to the NRC on September 6, 2018
- (2) Maintenance rule failure classification of the fast bus transfer failure during the Notification of Unusual Event in June 2017 on September 13, 2018
71153Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports
The inspectors evaluated the following licensee event reports which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
- (1) Licensee Event Reports 05000382/2018-002-00 and 05000382/2018-002-01, Unplanned Loss of a Train of Control Room Outside Air Intake Radiation Monitors Results in a Condition Prohibited by Technical Specifications, on August 16, 2018.
- (2) Licensee Event Report 05000382/2017-002-01, Automatic Reactor Scram due to the Failure of Fast Dead Bus Transfer Relays to Automatically Transfer Station Load to Off-Site Power on a Main Generator Trip, on August 16,
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
INSPECTION RESULTS
Unresolved Item (Closed)
Potential Failure to Obtain a License Amendment for Changes to Diesel Generator Surveillance Test Interval URI 05000382/2017008-04 7111.21M
Description:
U.S. Nuclear Regulatory Commission (NRC) Design Bases Assurance Inspection Report 05000382/2017008 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML17362A424), dated December 28, 2017, documents Unresolved Item 05000382/2017008-04, Potential Failure to Obtain a License Amendment for Changes to Diesel Generator Surveillance Test Interval. During that inspection, the team reviewed the licensees change to the surveillance test intervals for the train A and B emergency diesel generators, which was completed in accordance with the Waterford surveillance frequency control program. As a result, both emergency diesel generators went from being tested every 18 months to each emergency diesel generator being tested every 36 months. The team concluded that the license had failed to correctly evaluate the change in accordance with the surveillance frequency control program change process per NEI 04-10, Risk Informed Method for Control of Surveillance Frequencies, Revision 1. Specifically, the licensee had not correctly evaluated NEI 04-10, step 1, Check for Prohibitive Commitments, and step 2, Can Commitments be Changed? of the change process. During the inspection, the team determined that this change would have necessitated a 10 CFR 50.59 safety evaluation and subsequent license amendment because it would have resulted in more than a minimal increase in likelihood of a malfunction of a component important to safety as previously described in the final safety analysis report. At the conclusion of the inspection, the team decided to address this item pending the review of the licensees previously documented corrective actions associated with the potential issue.
Since the conclusion of the inspection, the regulatory applicability of this unresolved item was addressed in NRC letter to Byron Generating Station, dated July 23, 2018, (ADAMS Accession Number ML18204A144). The letter documents the withdrawal of a non-cited violation associated with 10 CFR 50.59 requirements applicable to changes in surveillance test intervals of emergency diesel generators. The review was conducted by an independent NRC panel and the outcome was documented, in part, as follow;
In NEI 04-10 Step 2, a check is made to determine if the applicable regulatory commitments to the NRC can be changed. Evaluating changes to regulatory commitments is a separate activity based on a method acceptable to the NRC for managing and changing regulatory commitments (e.g., NEI 99-04). NEI 99-04 Section 3.1, Definitions, defines a regulatory commitment as an explicit statement to take a specific action agreed to, or volunteered by, a licensee and submitted in writing on the docket to the NRC. A regulatory commitment is an intentional undertaking by the licensee to
- (1) restore compliance with regulatory requirements, or
- (2) complete a specific action to address an NRC issue or concern (e.g., generic letter, bulletin, order, etc.)...Thus, there was no associated regulatory commitment to change under NEI 04-10 Step 2, and it was appropriate for the licensee to continue to step through the NDE 04-10 process to evaluate an EDG surveillance frequency change.
Therefore, given the circumstances for the non-cited violation withdrawal and its applicability to this unresolved item, the NRC has concluded that there is no violation and no license amendment was required. This item is closed.
Corrective Action Reference(s): N/A
EXIT MEETINGS AND DEBRIEFS
On August 9, 2018, the inspector presented the emergency preparedness inspection results to Mr. J. Dinelli, Site Vice President, and other members of the licensee staff. The inspector verified that no proprietary information was retained or documented in this report.
On August 27, 2018, the inspector presented the annual requalification inspection results to Mr. D. Constance, Operations Training Superintendent. The inspector verified no proprietary information was retained or documented for this inspection report.
On September 13, 2018, the inspector presented the baseline radiation safety inspection results to Mr. S. Vazquez, General Manager of Plant Operations, and other members of the licensee staff. The inspector verified no proprietary information was retained or documented in this report.
On October 11, 2018, the inspector presented the quarterly resident inspector inspection results to Mr. J. Dinelli, Site Vice President, and other members of the licensee staff. The inspectors verified no proprietary information was retained or documented in this report.
DOCUMENTS REVIEWED
71111.01 - Adverse Weather Protection
Condition Reports
Procedures
Number
Title
Revision
Process Applicability Determination
OP-901-521
Severe Weather and Flooding
26
Drawings
Number
Title
Date
G-580
Nuclear Plant Island Structure Flood Wall
Penetrations, Sheet 1
July 10, 2018
G-580
Nuclear Plant Island Structure Flood Wall
Penetrations, Sheet 2
April 3, 2011
G-580
Nuclear Plant Island Structure Flood Wall
Penetrations, Sheet 3
April 25, 1991
71111.04 - Equipment Alignment
Condition Reports
CR-WF3-2017-01509 CR-WF3-2017-04445 CR-WF3-2018-04638 CR-WF3-2017-07561
Work Orders
00475847
00476848
00433888
00397848
00427894
00468224
00467879
00435999
Procedures
Number
Title
Revision
OP-008-008
Shield Building Ventilation
OP-003-035
309
OP-009-003
Emergency Feedwater
309
OP-009-002
346
OP-002-010
Reactor Auxiliary Building HVAC and Containment
Purge
2
71111.05 - Fire Protection
Procedures
Number
Title
Revision
NS-TB-001
Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +15.00
East
NS-TB-003
Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +40.00
East
RAB 34-001
Waterford-3 S.E.S Pre-Fire Strategy Elev. -15.50 RAB (RCA)
NS-TB-004
Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +40.00
West
RAB 2-001
Waterford-3 S.E.S Pre-Fire Strategy Elev. +46.00 RAB (RCA)
Fire Brigade Drills
RAB 6-001
Waterford-3 S.E.S Pre-Fire Strategy Elev. +35.00 RAB
Miscellaneous
Documents
Number
Title
Date
Waterford 3 Fire Brigade Drill 2018 Completion
Tracking Matrix
September
2018
Waterford 3 Fire Brigade Drill 2017 Completion
Tracking Matrix
September
2018
Waterford 3 Fire Brigade Drill 2016 Completion
Tracking Matrix
September
2018
71111.11 - Licensed Operator Requalification
Condition Reports
CR-WF3-2018-03123 CR-WF3-2018-03213 CR-WF3-2018-03085 CR-WF3-2017-06573
CR-WF3-2016-05408 CR-WF3-2016-07255 CR-WF3-2018-02492 CR-WF3-2017-00464
CR-WF3-2017-02044 CR-WF3-2017-01218 CR-WF3-2017-01623 CR-WF3-2017-03600
Procedures
Number
Title
Revision
OP-100-010
Equipment Out of Service
316
OP-901-110
Pressurizer Level Control Malfunction
OP-901-220
303
OP-901-212
Rapid Plant Power Reduction
OP-902-000
Standard Post Trip Actions
OP-902-001
Reactor Trip Recovery
OP-902-008
Functional Recovery
OP-902-009
Standard Appendices
317
Recognition & Classification of Emergency Conditions
OP-903-005
Control Element Assembly Operability Check
OP-903-094
ESFAS Subgroup Relay Test - Operating
Miscellaneous
Documents
Number
Title
Revision
or Date
WSXM-LOR-184EXM 2018 Cycle 4 Annual Simulator Exam - Week 3
E-214
Annual Requalification Results Summary
August 20,
2018
71111.13 - Maintenance Risk Assessment and Emergent Work Review
Condition Reports
CR-WF3-2018-04154 CR-WF3-2018-04156 CR-WF3-2018-04180 CR-WF3-2018-05046
Work Orders
00432117
00427084
00432121
Procedures
Number
Title
Revision
EN-FAP-WM-107
Emergent Issues Process
Troubleshooting Control and Maintenance Activities
On Line Risk Management
OI-037-000
Operations Risk Assessment Guideline
313
On Line Risk Management
Protected Equipment Postings
Miscellaneous
Documents
Number
Title
Date
EN-OP-119 Att. 9.1
Protected Equipment Postings List for Emergency
Diesel Generator A work window
September 23,
2018
EN-OP-119 Att. 9.1
Protected Equipment Postings List for Emergency
Feedwater 228A and 224A
August 20,
2018
71111.15 - Operability Evaluations
Condition Reports
CR-WF3-2018-04025 CR-WF3-2018-04021 CR-WF3-2018-04114 CR-WF3-2018-04709
Procedures
Number
Title
Revision
OP-008-008
Shield Building Ventilation
OP-903-068
Emergency Diesel Generator and Subgroup Relay
Operability Verification
21
71111.18 - Plant Modifications
Condition Reports
CR-WF3-2017-02774 CR-WF3-2018-04367 CR-WF3-2018-04296 CR-WF3-2018-04677
Procedures
Number
Title
Revision
OP-001-001
Reactor Coolant System Fill and Vent
OP-903-097
Pressurizer Heater Capacity Verification
OP-901-502
Evacuation of Control Room and Subsequent Plant
Cooldown
Drawings
Number
Title
Revision
5817-14492
UHS Air Deflector Structure Details Sheets 1 - 41
B424 Sheet 291
Pressurizer Proportional Heater Bank-1
B424 Sheet 286
Pressurizer Backup Heaters Bank 2
B424 Sheet 287
Pressurizer Backup Heaters Bank 3
B289 Sheet 23A1
480V Switchgear 3A32 Programmer Settings
B289 Sheet 23
Power Distribution and Motor Data 480V Switchgear 3A32
One Line Diagram
B289 Sheet 101
Power Distribution and Motor Data 480V Distribution Panels
B289 Sheet 158
Power Distribution and Motor Data 480V Switchgear Front
View
Miscellaneous
Documents
Number
Title
Revision
Temporary Replace Failed Proportional Heater Bank 1
Heaters 3 (position F2) and 4 (position H2) with heaters from
Backup Bank 2and 3 (positions E1 and C2)
Ultimate Heat Sink Margin Restoration - Phase 3
Ultimate Heat Sink Margin Restoration
71111.19 - Post-Maintenance Testing
Condition Reports
CR-WF3-2018-04419 CR-WF3-2018-07223 CR-WF3-2018-04415 CR-WF3-2018-01508
CR-WF3-2018-01004 CR-WF3-2018-00589 CR-WF3-2017-05397 CR-WF3-2018-04463
CR-WF3-2017-01483 CR-WF3-2017-05329 CR-WF3-2018-04444 CR-WF3-2017-04606
CR-WF3-2018-04632 CR-WF3-2018-05448
Work Orders
00496628
00434744
00364478
2735553
00450472
2756221
2713822
2746212
2745254
2735551
00477067
50551501
2805322
00496405
Procedures
Number
Title
Revision
OP-903-068
Emergency Diesel Generator and Subgroup Relay Operability
Verification
21
OP-009-002
346
OP-903-003
Charging Pump Operability Check
2
OP-904-007
Charging Pump Pulsation Dampener Pressure Check
016
OP-903-131
AFW High Discharge Pressure Trip Test
2
MM-006-161
AFW Pump Disassembly, Inspection and Reassembly
MM-006-162
Diesel Generator Cylinder Head Removal, Inspection and
Installation
Procedure and Work Instruction Use and Adherence
UNT-005-007
Plant Lubrication Procedure
304
OP-002-010
Reactor Auxiliary Building HVAC and Containment Purge
2
OP-903-050
Component Cooling Water and Auxiliary Component Cooling
Water Pump and Valve Operability Test
Drawings
Number
Title
Revision
G-168 Sheet 2
CVCS Flow Diagram
Miscellaneous
Documents
Number
Title
Revision
WLP-OPS-CVC00
CVCS training document
WF3-ME-18-00001
Charging Pump Pulsation Dampener Vibration Evaluation
Evaluation of Charging Pump Pulsation Dampener Impact on
Operability
PE Eval 153315
Head, Cylinder, Emergency Diesel Generator
71111.22 - Surveillance Testing
Condition Reports
CR-WF3-2018-04236 CR-WF3-2018-04214 CR-WF3-2018-04202 CR-WF3-2018-04314
Work Orders
2645246
2819598
Procedures
Number
Title
Revision
OP-903-030
Safety Injection Pump Operability Verification
MI-005-214
Calibration of Flow Instruments
OP-903-006
Reactor Trip Circuit Breaker Test
MI-003-126
Core Protection Calculator Functional Test
OP-903-100
MOV Overload Bypass Test
310
OP-903-046
Emergency Feed Pump Operability Check
2
Drawings
Number
Title
Revision
B-424 Sheet 1153
Control Room Emergency Filtration Unit North Intake
Miscellaneous
Documents
Number
Title
Revision
SEP-WF3-IST-2
71114.02 - Alert and Notification System Testing
Condition Reports
2017-03818
2017-06905
Work Orders
2710344
2735556
2735558
Procedures
Number
Title
Revision
or Date
Updated Alert and Notification System Design Report, December
2014
FEMA REP-10 Design Report Addendum
July 14,
2015
EPP-422
Siren and Helicopter Warning System Maintenance,
EPP-424
Siren Testing and Siren System Administrative Controls,
71114.03 - Emergency Response Organization Staffing and Augmentation Systems
Condition Reports
2016-04434
2016-04435
2016-04436
2016-04437
2016-04438
2016-06548
2016-06547
2016-06549
2016-06949
2017-01152
2017-01154
2017-05394
2017-05396
2017-07826
2017-09090
Procedures
Number
Title
Revision
Emergency Response Organization Notification System
Emergency Response Organization
Emergency Responder Activation
303
EPP-462
Evaluation of Pager Tests
71117.04 - Emergency Action Level and Emergency Plan Changes
Procedures
Number
Title
Revision
Emergency Planning 10CFR50.54(q) Review Program
Miscellaneous
Documents
Number
Title
Revision
10CFR50.54(q)(3) Screening Evaluation for EP-002-100
10CFR50.54(q)(3) Screening Evaluation for EN-EP-801
10CFR50.54(q)(3) Screening Evaluation for Emergency Plan
10CFR50.54(q)(3) Screening Evaluation for Emergency Plan
10CFR50.54(q)(3) Screening Evaluation for On-Shift Staffing
Analysis
10CFR50.54(q)(3) Screening for Emergency Plan
10CFR50.54(q)(3) Screening Evaluation for EP-001-001
71114.05 - Maintenance of Emergency Preparedness
Condition Reports
2016-04573
2016-04891
2016-05315
2016-05563
2016-05572
2016-06017
2016-06404
2016-07104
2016-07597
2017-00008
2017-01627
2017-01826
2017-02502
2017-03304
2017-04233
2017-05494
2017-05535
2017-05662
2017-05875
2017-06905
2017-06978
2017-07707
2017-08244
2017-08367
2017-08388
2017-09328
2017-09512
2017-09772
2017-09804
2017-09833
2018-00047
2018-00104
2018-00539
2018-00980
2018-01009
2018-02867
2018-02988
2018-03489
2018-04476
2018-04479
LO-HQNLO-2016-00056
Work Orders
00422707
00422708
00448915
00450676
00451436
00451985
00461103
00476211
00488788
00489973
00492462
00495965
2580909
2702861
2707267
2772677
2728394
Procedures
Number
Title
Revision
Drills and Exercises
Emergency Planning Critiques
Emergency Response Organization
Corrective Action Program
2, 33
Self-Assessment and Benchmark Process
Audit Process
Unusual Event
303
Emergency Responder Activation
301
Emergency Preparedness Drills and Exercises,
304
Emergency Program Review, Updating, and Modification,
303
Emergency Equipment Inventory,
308
Emergency Communications Systems Routine Testing,
304
EPP-401
Review, Publication and Distribution of Public Information
Materials,
EPP-428
Emergency Facilities and Equipment Readiness,
306
Miscellaneous
Documents
Number
Title
Revision
or Date
Waterford3 Emergency Plan
47, 48, 49
2017 Pre NRC Evaluation Exercise Assessment
October 16,
2017
Pre NRC Program Inspection Assessment
QA-7-2017-W3-1
Emergency Preparedness Audit
May 26, 2017
QA-7-2018-W3-1
Emergency Preparedness Audit
May 10, 2018
Monthly Communications Drill
September 13,
2016
Monthly Communications Drill
January 31,
2017
Monthly Communications Drill
November 21,
2017
Monthly Communications Drill
April 3, 2018
Inspection of Emergency Diesel Generator
September 12,
2016
Inspection of Emergency Diesel Generator
July 6, 2017
Inspection of Emergency Diesel Generator
May 3, 2018
Emergency Communications Test Sheet
August 30, 2016
Emergency Communications Test Sheet
December 20,
2016
Emergency Communications Test Sheet
April 30, 2017
Emergency Communications Test Sheet
November 6,
2017
Emergency Communications Test Sheet
December 13,
2017
Emergency Communications Test Sheet
February 20,
2018
Readiness Condition - Control Room
December 12,
2016
Readiness Condition - Control Room
November 1,
2017
Readiness Condition - Control Room
April 3, 2018
Readiness Condition - Technical Support Center
July 6, 2017
Readiness Condition - Technical Support Center
December 4,
2017
Readiness Condition - Technical Support Center
June 19, 2018
Readiness Condition - Operational Support Center July 6, 2017
Readiness Condition - Operational Support Center April 3, 2018
Readiness Condition - Emergency Operations
Facility
September 29,
2016
Readiness Condition - Emergency Operations
Facility (March)
July 6, 2017
Readiness Condition - Emergency Operations
Facility (June)
July 6, 2017
Readiness Condition - Emergency Operations
Facility
April 3, 2018
Readiness Condition - Emergency Operations
Facility
June 19, 2018
Readiness Condition - Joint Information Center
December 4,
2017
Readiness Condition - Joint Information Center
April 3, 2018
Assembly Area Supervisors Kit Inventory
July 6, 2017
Assembly Area Supervisors Kit Inventory
June 19, 2018
After-Action Report for the Notification of Unusual
Event declared on July 17, 2017
Evaluation Report for the Medical Drill Conducted
February 12, 2016
February 18,
2016
Evaluation Report for the Exercise Conducted
April 6, 2016
May 3, 2016
Evaluation Report for the Health Physics Drill
Conducted June 22, 2016
July 13, 2016
Evaluation Report for the Exercise Conducted
June 15, 2016
July 15, 2016
Evaluation Report for the Exercise Conducted
August 31, 2016
September 27,
2016
Evaluation Report for the Drill Conducted
October 7, 2016
October 7, 2016
Evaluation Report for the Drill Exercise Conducted
December 7, 2016
Evaluation Report for the Medical Drill Conducted
January 23, 2017
February 22,
2017
Evaluation Report for the Control Room Breathing
Air Drill Conducted March 24, 2017
March 24, 2017
Evaluation Report for the Exercise Conducted
June 28, 2017
Evaluation Report for the Control Room Breathing
Air Drill Conducted September 15, 2017
September 19,
2017
2017-05
Evaluation Report for the Drill Exercise Conducted
July 12, 2017, Revision 1
October 19,
2017
Evaluation Report for the Exercise Conducted
October 26, 2017
2017-017
Evaluation Report for the Focused Drill for Site
Accountability
November 29,
2017
Evaluation Report for the Exercise Conducted
December 13, 2017
Evaluation Report for the Exercise Conducted
February 21, 2018
Evaluation Report for the Control Room Breathing
Air Drill Conducted June 15, 2018
June 15, 2018
Evaluation Report for the Exercise Conducted
June 20, 2018
July 18, 2018
WF3-IC-17-00002
Engineering Report: Plant Paging System
Reliability Study
71114.06 - Drill Evaluation
Miscellaneous
Documents
Number
Title
Date
Red Team Site Drill Scenario Description
August 29,
2018
Notification Forms for Red Team Site Drill
August 29,
2018
71124.02 - Occupational ALARA Planning and Controls
Condition Reports
WF3-2017-03249 WF3-2017-03344
WF3-2017-03778 WF3-2018-00831
Procedures
Number
Title
Revision
Radiation Worker Expectations
Radiological Work Permits
Hot Spot Program
ALARA Program
Procedures
Number
Title
Revision
EN-RP-110-03
Collective Radiation Exposure (CRE) Reduction
Guidelines
EN-RP-110-04
Radiation Protection Risk Assessment Process
Conduct of Radiation Protection
Audits and Self-Assessments
Number
Title
Date
Self-Assessment: Occupational ALARA Planning
and Controls
July 24, 2018
Radiation Work Permits
Number
Title
Revision
2016-0118
Loading of Dry Fuel Storage Cask #18 with Spent Fuel and
Transport including all DFS Support Activities to include Set
Up/Demob
2016-0119
Loading of Dry Fuel Storage Cask #19 with Spent Fuel and
Transport including all DFS Support Activities to include Set
Up/Demob
2016-0123
Loading of Dry Fuel Storage Cask #23 with Spent Fuel and
Transport including all DFS Support Activities to include Set
Up/Demob
2017-0515
RCP 1B Motor Replacement
2017-0610
Erect/Dismantle Scaffolding in the Reactor Containment
Building
2017-0702
Reactor Disassembly Activities
2017-0705
Reactor Reassembly Activities
2018-0001
Radiation Protection to Perform Job Coverage, Routine
Surveys, Inspections and Walkdowns
2018-0006
Radwaste Processing/Shipping in all Radiologically Controlled
Areas
ALARA Planning, In-Progress Reviews, and Post-Job Reviews
Number
Title
Revision
EN-RP-105, Att.9.5
Refuel 20 Outage ALARA Report
EN-RP-105, Att.9.5
Refuel 21 Outage ALARA Report
Miscellaneous
Documents
Number
Title
Revision
or Date
Evaluate TSR 2008-24, 2010-01, 2011-30, 2012-24,
2012-33, 2012-36, 2011-79 as Long-Term Shielding
February 20,
2013
2017 Annual Radiation Protection Program Report
Waterford-3 Abbreviated 5-Year Exposure Reduction Plan
2018-2022
December 4,
2017
71124.04 - Occupational Dose Assessment
Condition Reports
WF3-2017-01829
WF3-2017-06719
WF3-2017-07702
WF3-2017-03148
Audits and Self-Assessments
Number
Title
Date
Self-Assessment: Bioassay Program
January 16,
2017
Self-Assessment: Occupational Dose Assessment
July 23, 2018
Calibration Records
Number
Title
Date
017027353
Canberra GEM-5 Calibration Data Sheet
April 25, 2018
Procedures
Number
Title
Revision
Air Sampling
Dosimetry Administration
Special Monitoring Requirements
Prenatal Monitoring
Whole Body Counting/In-Vitro Bioassay
Operation and Calibration of the Canberra GEM-5
Passive Monitor Sensitivity Testing
Miscellaneous
Documents
Number
Title
Date
2017-2018
Entergy Waterford-3 Radiation Protection Department
Respiratory Improvement Plan
September 4, 2018
Review of Neutron Dose Estimates 2016
July 25, 2017
Field Trials with the Use of the REM-500 at Waterford-3
July 28, 2017
Review of the Capabilities of the Passive Monitoring
Program to Detect Intakes at Waterford-3
October 4, 2017
71151 - Performance Indicator Verification
Condition Reports
2017-07707
2017-08036
2017-08367
2017-08790
2017-09261
2017-09507
2017-09512
2017-09637
2018-00678
2018-02077
2018-02656
2018-02870
Procedures
Number
Title
Revision
Recognition and Classification of Emergencies
2, 33
Notifications and Communications
313, 314, 315
Protective Action Guidelines
EPP-424
Siren Testing and Siren System Administrative Controls,
71152 - Identification and Resolution of Problems
Condition Reports
CR-WF3-2018-01054 CR-WF3-2018-01849 CR-WF3-2017-07486 CR-WF3-2018-01981
CR-WF3-2017-09887 CR-WF3-2018-01049 CR-WF3-2018-01978 CR-WF3-2018-01994
CR-WF3-2018-06078 CR-WF3-2018-05252
Procedures
Number
Title
Revision
EN-LI-108 Att. 9.1
CFR 21 Discovery Determination & Reportability
Evaluation Sheet for CR-WF3-2018-1994
Maintenance Rule Monitoring
Drawings
Number
Title
Revision
B425 T7075B1
Control Loop Diagram CC-Dry Cooling tower B Fan
Cooling
B425 T7070BD
Control Loop Diagram CC-Dry Cooling tower B Outlet
Temp
B425 T5009A
Control Loop Diagram HVR-CCW Pump Heat Exchanger
A Room Temp
71153 - Event Followup
Miscellaneous
Documents
Number
Title
Date
NRC Performance Indicator (PI) Data - 3rd Quarter 2017
ROP Data
October 6,
2017
NRC Performance Indicator (PI) Data - 4th Quarter 2017
ROP Data
January 9,
2018
NRC Performance Indicator (PI) Data - 1st Quarter 2018
ROP Data
April 12,
2018
NRC Performance Indicator (PI) Data - 2nd Quarter 2018
ROP Data
July 13, 2018
The following items are requested for the
Occupational Radiation Safety Inspection
at Waterford-3
Dates of Inspection: 09/10/2018 to 09/14/2018
Integrated Report 2018003
Inspection areas are listed in the attachments below.
Please provide the requested information on or before Monday, August 13, 2018.
Please submit this information using the same lettering system as below. For example, all
contacts and phone numbers for Inspection Procedure 71124.02 should be in a file/folder titled
2-A, applicable organization charts in file/folder 2-B, etc.
If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at
least 30 days later than the onsite inspection dates, so the inspector will have access to the
information while writing the report.
In addition to the corrective action document lists provided for each inspection procedure listed
below, please provide updated lists of corrective action documents at the entrance meeting.
The dates for these lists should range from the end dates of the original lists to the day of the
entrance meeting.
If more than one inspection procedure is to be conducted and the information requests appear
to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which
file the information can be found.
If you have any questions or comments, please contact Natasha Greene at 817-200-1154 or via
e-mail at Natasha.Greene@nrc.gov.
PAPERWORK REDUCTION ACT STATEMENT
This letter does not contain new or amended information collection requirements subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
collection requirements were approved by the Office of Management and Budget,
control number 3150-0011.
2.
Occupational ALARA Planning and Controls (71124.02)
Date of Last Inspection:
April 24, 2017
A.
List of contacts and telephone numbers for ALARA program personnel. Please include
area code and prefix. If work cell numbers are appropriate, then please include them as
well.
B.
Applicable organization charts including position or job titles. Please include as
appropriate for your site, Site Management, RP, Chemistry, Maintenance (I&C),
Engineering, and Emergency Protection. (Recent pictures are appreciated.)
C.
Copies of audits, self-assessments, LARs, and LERs, written since the date of last
inspection, focusing on ALARA
D.
Procedure index for ALARA Program procedures and other related disciplines.
E.
Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures may be requested by number after the inspector reviews
the procedure indexes.
1. ALARA Program
2. ALARA Planning
3. ALARA Reviews
4. ALARA Committee
5. Radiation Work Permit Preparation
F.
Please provide a list of NRC Regulatory Guides and NUREGs that you are currently
committed to relative to this program. Please include the revision and/or date for the
commitment and where this may be located in your current licensing basis documents.
G.
Please provide a summary list of corrective action documents (including corporate and
sub-tiered systems) written since the date of last inspection, related to the ALARA
program, including exceeding RWP Dose Estimates.
NOTE: These lists should include a description of the condition that provides
sufficient detail that the inspector can ascertain the regulatory impact, the
significance level assigned to the condition, the status of the action (e.g., open,
working, closed, etc.) and the search criteria used. Please provide in document
formats which are sortable and searchable so that inspector can quickly and
efficiently determine appropriate sampling and perform word searches, as
needed. (Excel spreadsheets are the preferred format.) If codes are used,
please provide a legend for each column where a code is used.
H.
List of work activities (RWPs) greater than 1 rem, since date of last inspection,
including the original dose estimates and actual doses accrued. (Excel format
preferred). Please provide all revisions/changes, as well as any related RWPs that
support the work activity.
Provide any post evaluations, lessons learned, and/or corrective action documents
generated as a result of this work activity. If available, provide any justifications/reasons
for actual dose exceedances of the initial dose estimate.
I.
List of active work activities (RWPs) that will be in use while we are onsite, including the
dose and dose rate settings, and if available, the planned dose.
J.
Site dose totals for the past 3 years (based on dose of record). Also provide the current
year-to-date (YTD) collective radiation exposure (CRE). In addition, please provide
another document that separates the online and outage doses for the past 3 years.
K.
Most recent assessment of your isotopic mix, including the hard-to-detect radionuclides
and alpha hazards. Include a list of new and historical exposure issues (radiological
source term or high exposure areas/activities).
L.
If available, provide a copy of the ALARA outage report or evaluation for the two most
recently completed outages for each unit
M.
Please provide the methods/reports that are in your process to meet the requirements of
CFR 20.1101(c) for periodic review of your RP program.
N.
Current exposure trends (BRAC dose rates and/or source term information)
4.
Occupational Dose Assessment (Inspection Procedure 71124.04)
Date of Last Inspection:
September 12, 2016
A.
List of contacts and telephone numbers for the Dose Assessment personnel. Please
include area code and prefix. If work cell numbers are appropriate, then please include
them as well.
B.
Applicable organization charts including position or job titles. Please include as
appropriate for your site, Site Management, RP, Chemistry, Maintenance (I&C),
Engineering, and Emergency Protection. (Recent pictures are appreciated.)
C.
Copies of audits, self-assessments, vendor or NUPIC audits of contractor support, and
LERs written since date of last inspection, related to Occupational Dose Assessment
D.
Procedure indexes for Occupational Dose Assessment procedures and other related
disciplines.
E.
Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures will be requested by number after the inspector reviews
the procedure indexes.
1. Radiation Protection Program
2. Radiation Protection Conduct of Operations
3. Personnel Dosimetry Program
4. Electronic Dosimeters
5. Air Sample Analysis
6. Performance of High or Special Exposure Work
7. Declared Pregnant Worker
8. Bioassay Program (Internal Dose Assessment)
F.
Please provide a list of NRC Regulatory Guides and NUREGs that you are currently
committed to relative to this program. Please include the revision and/or date for the
commitment and where this may be located in your current licensing basis documents.
G.
Please provide a summary list of corrective action documents (including corporate and
sub-tiered systems) written since date of last inspection, associated with:
1. National Voluntary Laboratory Accreditation Program (NVLAP)
2. Dosimetry (TLD/OSL, etc.) problems
3. Electronic alarming dosimeters
4. Bioassays or internally deposited radionuclides or internal dose
5. Neutron dose
NOTE: These lists should include a description of the condition that provides
sufficient detail that the inspector can ascertain the regulatory impact, the
significance level assigned to the condition, the status of the action (e.g., open,
working, closed, etc.) and the search criteria used. Please provide in document
formats which are sortable and searchable so that inspector can quickly and
efficiently determine appropriate sampling and perform word searches, as
needed. (Excel spreadsheets are the preferred format) If codes are used,
please provide a legend for each column where a code is used.
H.
List of positive whole body counts (excluding K-40) since date of last inspection, include
date(s), reason(s), activity assessed, and doses calculated and assigned. Names and
personal information can be redacted, if desired
I.
Part 61 analyses or other analyses of plant isotopic mixture (alpha, beta, gamma, and
neutron) for appropriate instrumentation calibration sources and dosimetry selection and
hard-to-detect plant nuclide scaling factors for intakes/uptakes.
J.
The most recent National Voluntary Laboratory Accreditation Program (NVLAP)
accreditation report or, if dosimetry is provided by a vendor, the vendors most recent
results and which dosimeter(s) is (are) use at the site and for what purpose(s) (DLR,
neutron, environmental, etc.).
K.
Please provide the latest assessment of your radiological source term as it relates to the
internal/external exposure of workers.
L.
If available, please provide your latest source term reduction strategy.
M.
Have available for on-site review the LLDs or MDAs for each onsite WBC or other
internal dose assessment instrumentation.
N.
If available, please provide the latest neutron source term characterization.
Describe why the neutron dosimetry used is appropriate for these locations.
O.
A list of airborne radioactivity areas (and associate RWPs) where DAC-hr monitoring
was used with air sampling to track and assign dose (BZ lapel air samples, etc.).
P.
Please have available for on-site review, a list of workers that declared a pregnancy
since the last inspection. Declared Pregnant Worker monitoring of worker and fetus.
Please provide the most recent NRC Form 5 for these individuals. No more than three
are requested. Please redact any sensitive information.
Q.
A list of EDEX or multi-badge dosimetry uses since the last inspection, include the
associated RWP and dose accrued.
SUNSI Review
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By: NFO
Yes No
Publicly Available
Sensitive
OFFICE
SRI:DRP/D
RI:DRP/D
Tl:DRS/IPAT
BC:DRS/EB1
Bc:DRS/EB2
BC:DRS/PSB2
NAME
FRamirez
CSpeer
GMiller
TFarnholtz
GWerner
HGepford
SIGNATURE
FCR
GBM
TRF
GEW
hjg
DATE
10/16/2018
10/17/18
10/25/18
10/25/2018
10/24/2018
10/25/18
OFFICE
BC:DRS/OB
BC:DRP/D
NAME
VGaddy
NOKeefe
SIGNATURE
TJF for
DATE
10/25/2018
10/29/2018