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| issue date = 10/30/2018 | | issue date = 10/30/2018 | ||
| title = NRC Integrated Inspection Report 05000382/2018003 | | title = NRC Integrated Inspection Report 05000382/2018003 | ||
| author name = O'Keefe N | | author name = O'Keefe N | ||
| author affiliation = NRC/RGN-IV/DRP/RPB-D | | author affiliation = NRC/RGN-IV/DRP/RPB-D | ||
| addressee name = Dinelli J | | addressee name = Dinelli J | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:ber 30, 2018 | ||
==SUBJECT:== | |||
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NRC INTEGRATED INSPECTION REPORT 05000382/2018003 | |||
ims.certrec.com | ==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 | |||
U.S. NUCLEAR REGULATORY COMMISSION | |||
==Inspection Report== | |||
Docket Number(s): 05000382 License Number(s): NPF-38 Report Number(s): 05000382/2018003 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 Enclosure | |||
=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 Status Section URI 05000382/2017008-04 Potential Failure to Obtain a 71111.21M Closed License Amendment for Changes to Diesel Generator Surveillance Test Interval | |||
=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 === | |||
{{IP sample|IP=IP 71111.01|count=1}} | |||
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 === | |||
{{IP sample|IP=IP 71111.04|count=4}} | |||
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 === | |||
{{IP sample|IP=IP 71111.05|count=5}} | |||
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 === | |||
{{IP sample|IP=IP 71111.11|count=1}} | |||
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 === | |||
{{IP sample|IP=IP 71111.12|count=2}} | |||
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 === | |||
{{IP sample|IP=IP 71111.13|count=5}} | |||
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 === | |||
{{IP sample|IP=IP 71111.15|count=4}} | |||
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 === | |||
{{IP sample|IP=IP 71111.18|count=2}} | |||
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 === | |||
{{IP sample|IP=IP 71111.19|count=6}} | |||
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 === | |||
{{IP sample|IP=IP 71111.22|count=5}} | |||
: (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 === | |||
{{IP sample|IP=IP 71114.02|count=1}} | |||
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 === | |||
{{IP sample|IP=IP 71114.03|count=1}} | |||
The inspector evaluated the readiness Emergency Preparedness Organization on August 2, 2018. | |||
===71114.04Emergency Action Level and Emergency Plan Changes === | |||
{{IP sample|IP=IP 71114.04|count=2}} | |||
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 === | |||
{{IP sample|IP=IP 71114.05|count=1}} | |||
The inspector evaluated the maintenance of the emergency preparedness program on August 6 and 7, 2018. | |||
===71114.06Drill Evaluation Emergency Planning Drill === | |||
{{IP sample|IP=IP 71114.06|count=1}} | |||
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 === | |||
{{IP sample|IP=IP 71124.02|count=1}} | |||
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 | |||
: (4) RWP 2017-0515, RCP 1B Motor Replacement, 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 === | |||
{{IP sample|IP=IP 71124.04|count=1}} | |||
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 === | |||
{{IP sample|IP=IP 71151|count=6}} | |||
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 === | |||
{{IP sample|IP=IP 71152|count=2}} | |||
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 === | |||
{{IP sample|IP=IP 71153|count=2}} | |||
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 Potential Failure to Obtain a License Amendment for 7111.21M (Closed) Changes to Diesel Generator Surveillance Test Interval URI 05000382/2017008-04 | |||
=====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 | |||
CR-WF3-2018-04408 | |||
Procedures | |||
Number Title Revision | |||
EN-LI-100 Process Applicability Determination 10 | |||
OP-901-521 Severe Weather and Flooding 326 | |||
Drawings | |||
Number Title Date | |||
G-580 Nuclear Plant Island Structure Flood Wall July 10, 2018 | |||
Penetrations, Sheet 1 | |||
G-580 Nuclear Plant Island Structure Flood Wall April 3, 2011 | |||
Penetrations, Sheet 2 | |||
G-580 Nuclear Plant Island Structure Flood Wall April 25, 1991 | |||
Penetrations, Sheet 3 | |||
71111.04 - Equipment Alignment | |||
Condition Reports | |||
CR-WF3-2017-01509 CR-WF3-2017-04445 CR-WF3-2018-04638 CR-WF3-2017-07561 | |||
CR-WF3-2017-07550 | |||
Work Orders | |||
00475847 00476848 00433888 00397848 | |||
00427894 00468224 00467879 00435999 | |||
Procedures | |||
Number Title Revision | |||
OP-008-008 Shield Building Ventilation 10 | |||
OP-003-035 Auxiliary Feedwater 309 | |||
OP-009-003 Emergency Feedwater 309 | |||
OP-009-002 Emergency Diesel Generator 346 | |||
OP-002-010 Reactor Auxiliary Building HVAC and Containment 312 | |||
Purge | |||
71111.05 - Fire Protection | |||
Procedures | |||
Number Title Revision | |||
NS-TB-001 Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +15.00 4 | |||
East | |||
NS-TB-003 Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +40.00 1 | |||
East | |||
RAB 34-001 Waterford-3 S.E.S Pre-Fire Strategy Elev. -15.50 RAB (RCA) 8 | |||
NS-TB-004 Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +40.00 1 | |||
West | |||
RAB 2-001 Waterford-3 S.E.S Pre-Fire Strategy Elev. +46.00 RAB (RCA) 13 | |||
EN-TQ-125 Fire Brigade Drills 6 | |||
RAB 6-001 Waterford-3 S.E.S Pre-Fire Strategy Elev. +35.00 RAB 9 | |||
Miscellaneous | |||
Documents | |||
Number Title Date | |||
Waterford 3 Fire Brigade Drill 2018 Completion September | |||
Tracking Matrix 2018 | |||
Waterford 3 Fire Brigade Drill 2017 Completion September | |||
Tracking Matrix 2018 | |||
Waterford 3 Fire Brigade Drill 2016 Completion September | |||
Tracking Matrix 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 11 | |||
OP-901-220 Loss of Condenser Vacuum 303 | |||
OP-901-212 Rapid Plant Power Reduction 10 | |||
OP-902-000 Standard Post Trip Actions 16 | |||
OP-902-001 Reactor Trip Recovery 16 | |||
OP-902-008 Functional Recovery 27 | |||
OP-902-009 Standard Appendices 317 | |||
EP-001-001 Recognition & Classification of Emergency Conditions 33 | |||
OP-903-005 Control Element Assembly Operability Check 14 | |||
OP-903-094 ESFAS Subgroup Relay Test - Operating 31 | |||
Miscellaneous | |||
Documents Revision | |||
Number Title 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 1 | |||
EN-MA-125 Troubleshooting Control and Maintenance Activities 22 | |||
EN-WM-104 On Line Risk Management 17 | |||
OI-037-000 Operations Risk Assessment Guideline 313 | |||
EN-WM-104 On Line Risk Management 18 | |||
EN-OP-119 Protected Equipment Postings 9 | |||
Miscellaneous | |||
Documents | |||
Number Title Date | |||
EN-OP-119 Att. 9.1 Protected Equipment Postings List for Emergency September 23, | |||
Diesel Generator A work window 2018 | |||
EN-OP-119 Att. 9.1 Protected Equipment Postings List for Emergency August 20, | |||
Feedwater 228A and 224A 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 10 | |||
OP-903-068 Emergency Diesel Generator and Subgroup Relay 321 | |||
Operability Verification | |||
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 | |||
EN-DC-136 Temporary Modifications 17 | |||
OP-001-001 Reactor Coolant System Fill and Vent 35 | |||
OP-903-097 Pressurizer Heater Capacity Verification 12 | |||
OP-901-502 Evacuation of Control Room and Subsequent Plant 35 | |||
Cooldown | |||
Drawings | |||
Number Title Revision | |||
5817-14492 UHS Air Deflector Structure Details Sheets 1 - 41 | |||
B424 Sheet 291 Pressurizer Proportional Heater Bank-1 18 | |||
B424 Sheet 286 Pressurizer Backup Heaters Bank 2 20 | |||
B424 Sheet 287 Pressurizer Backup Heaters Bank 3 18 | |||
B289 Sheet 23A1 480V Switchgear 3A32 Programmer Settings 8 | |||
B289 Sheet 23 Power Distribution and Motor Data 480V Switchgear 3A32 17 | |||
One Line Diagram | |||
B289 Sheet 101 Power Distribution and Motor Data 480V Distribution Panels 6 | |||
B289 Sheet 158 Power Distribution and Motor Data 480V Switchgear Front 13 | |||
View | |||
Miscellaneous | |||
Documents | |||
Number Title Revision | |||
EC-71594 Temporary Replace Failed Proportional Heater Bank 1 0 | |||
Heaters 3 (position F2) and 4 (position H2) with heaters from | |||
Backup Bank 2and 3 (positions E1 and C2) | |||
EC-54532 Ultimate Heat Sink Margin Restoration - Phase 3 0 | |||
EC-52043 Ultimate Heat Sink Margin Restoration 0 | |||
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 52735553 | |||
00450472 52756221 52713822 52746212 | |||
2745254 52735551 00477067 50551501 | |||
2805322 00496405 | |||
Procedures | |||
Number Title Revision | |||
OP-903-068 Emergency Diesel Generator and Subgroup Relay Operability 321 | |||
Verification | |||
OP-009-002 Emergency Diesel Generator 346 | |||
OP-903-003 Charging Pump Operability Check 312 | |||
OP-904-007 Charging Pump Pulsation Dampener Pressure Check 016 | |||
OP-903-131 AFW High Discharge Pressure Trip Test 002 | |||
MM-006-161 AFW Pump Disassembly, Inspection and Reassembly 9 | |||
MM-006-162 Diesel Generator Cylinder Head Removal, Inspection and 7 | |||
Installation | |||
EN-HU-106 Procedure and Work Instruction Use and Adherence 6 | |||
EN-MA-118 Foreign Material Exclusion 13 | |||
UNT-005-007 Plant Lubrication Procedure 304 | |||
OP-002-010 Reactor Auxiliary Building HVAC and Containment Purge 312 | |||
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 55 | |||
Miscellaneous | |||
Documents | |||
Number Title Revision | |||
WLP-OPS-CVC00 CVCS training document 27 | |||
WF3-ME-18-00001 Charging Pump Pulsation Dampener Vibration Evaluation 0 | |||
EC-75478 Evaluation of Charging Pump Pulsation Dampener Impact on 0 | |||
Operability | |||
PE Eval 153315 Head, Cylinder, Emergency Diesel Generator 0 | |||
71111.22 - Surveillance Testing | |||
Condition Reports | |||
CR-WF3-2018-04236 CR-WF3-2018-04214 CR-WF3-2018-04202 CR-WF3-2018-04314 | |||
CR-WF3-2018-04365 | |||
Work Orders | |||
2645246 52819598 | |||
Procedures | |||
Number Title Revision | |||
OP-903-030 Safety Injection Pump Operability Verification 36 | |||
MI-005-214 Calibration of Flow Instruments 6 | |||
OP-903-006 Reactor Trip Circuit Breaker Test 13 | |||
MI-003-126 Core Protection Calculator Functional Test 20 | |||
OP-903-100 MOV Overload Bypass Test 310 | |||
OP-903-046 Emergency Feed Pump Operability Check 322 | |||
Drawings | |||
Number Title Revision | |||
B-424 Sheet 1153 Control Room Emergency Filtration Unit North Intake 20 | |||
Miscellaneous | |||
Documents | |||
Number Title Revision | |||
SEP-WF3-IST-2 WF3 IST Plan 7 | |||
71114.02 - Alert and Notification System Testing | |||
Condition Reports | |||
2017-03818 2017-06905 | |||
Work Orders | |||
2710344 52735556 52735558 | |||
Procedures Revision | |||
Number Title or Date | |||
Updated Alert and Notification System Design Report, December 8 | |||
2014 | |||
FEMA REP-10 Design Report Addendum July 14, | |||
2015 | |||
EPP-422 Siren and Helicopter Warning System Maintenance, 11 | |||
EPP-424 Siren Testing and Siren System Administrative Controls, 19 | |||
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 | |||
EN-EP-310 Emergency Response Organization Notification System 5 | |||
EN-EP-801 Emergency Response Organization 15 | |||
EP-002-015 Emergency Responder Activation 303 | |||
EPP-462 Evaluation of Pager Tests 4 | |||
71117.04 - Emergency Action Level and Emergency Plan Changes | |||
Procedures | |||
Number Title Revision | |||
EN-EP-305 Emergency Planning 10CFR50.54(q) Review Program 6 | |||
Miscellaneous | |||
Documents | |||
Number Title Revision | |||
10CFR50.54(q)(3) Screening Evaluation for EP-002-100 45 | |||
10CFR50.54(q)(3) Screening Evaluation for EN-EP-801 14 | |||
10CFR50.54(q)(3) Screening Evaluation for Emergency Plan 47 | |||
10CFR50.54(q)(3) Screening Evaluation for Emergency Plan 48 | |||
10CFR50.54(q)(3) Screening Evaluation for On-Shift Staffing 1 | |||
Analysis | |||
10CFR50.54(q)(3) Screening for Emergency Plan 49 | |||
10CFR50.54(q)(3) Screening Evaluation for EP-001-001 33 | |||
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-2016-00050 LO-HQNLO-2016-00056 | |||
CRHQN-2018-01704 | |||
Work Orders | |||
00422707 00422708 00448915 00450676 | |||
00451436 00451985 00461103 00476211 | |||
00488788 00489973 00492462 00495965 | |||
2580909 52702861 52707267 52772677 | |||
2728394 | |||
Procedures | |||
Number Title Revision | |||
EN-EP-306 Drills and Exercises 9 | |||
EN-EP-308 Emergency Planning Critiques 5 | |||
EN-EP-801 Emergency Response Organization 15 | |||
EN-LI-102 Corrective Action Program 32, 33 | |||
EN-LI-104 Self-Assessment and Benchmark Process 13 | |||
EN-QV-109 Audit Process 34 | |||
EP-001-010 Unusual Event 303 | |||
EP-002-015 Emergency Responder Activation 301 | |||
EP-003-020 Emergency Preparedness Drills and Exercises, 304 | |||
EP-003-030 Emergency Program Review, Updating, and Modification, 303 | |||
EP-003-040 Emergency Equipment Inventory, 308 | |||
EP-003-070 Emergency Communications Systems Routine Testing, 304 | |||
EPP-401 Review, Publication and Distribution of Public Information 2 | |||
Materials, | |||
EPP-428 Emergency Facilities and Equipment Readiness, 306 | |||
Miscellaneous | |||
Documents Revision | |||
Number Title or Date | |||
Waterford3 Emergency Plan 47, 48, 49 | |||
LO-WLO-2017-0048 2017 Pre NRC Evaluation Exercise Assessment October 16, | |||
2017 | |||
LO-WLO-2017-00077 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 September 29, | |||
Facility 2016 | |||
Readiness Condition - Emergency Operations July 6, 2017 | |||
Facility (March) | |||
Readiness Condition - Emergency Operations July 6, 2017 | |||
Facility (June) | |||
Readiness Condition - Emergency Operations April 3, 2018 | |||
Facility | |||
Readiness Condition - Emergency Operations June 19, 2018 | |||
Facility | |||
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 18, | |||
February 12, 2016 2016 | |||
W3D3-2016-0003 Evaluation Report for the Exercise Conducted May 3, 2016 | |||
April 6, 2016 | |||
Evaluation Report for the Health Physics Drill July 13, 2016 | |||
Conducted June 22, 2016 | |||
W3D3-2016-0006 Evaluation Report for the Exercise Conducted July 15, 2016 | |||
June 15, 2016 | |||
W3E3-2016-0008 Evaluation Report for the Exercise Conducted September 27, | |||
August 31, 2016 2016 | |||
W3D3-2016-0009 Evaluation Report for the Drill Conducted October 7, 2016 | |||
October 7, 2016 | |||
W3D3-2016-0008 Evaluation Report for the Drill Exercise Conducted | |||
December 7, 2016 | |||
Evaluation Report for the Medical Drill Conducted February 22, | |||
January 23, 2017 2017 | |||
W3D3-2017-0004 Evaluation Report for the Control Room Breathing March 24, 2017 | |||
Air Drill Conducted March 24, 2017 | |||
Evaluation Report for the Exercise Conducted | |||
June 28, 2017 | |||
W3D3-2017-0007 Evaluation Report for the Control Room Breathing September 19, | |||
Air Drill Conducted September 15, 2017 2017 | |||
2017-05 Evaluation Report for the Drill Exercise Conducted October 19, | |||
July 12, 2017, Revision 1 2017 | |||
Evaluation Report for the Exercise Conducted | |||
October 26, 2017 | |||
2017-017 Evaluation Report for the Focused Drill for Site November 29, | |||
Accountability 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 June 15, 2018 | |||
Air Drill Conducted June 15, 2018 | |||
Evaluation Report for the Exercise Conducted July 18, 2018 | |||
June 20, 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 WF3-2017-03771 WF3-2017-03778 WF3-2018-00831 | |||
Procedures | |||
Number Title Revision | |||
EN-RP-100 Radiation Worker Expectations 12 | |||
EN-RP-105 Radiological Work Permits 18 | |||
EN-RP-109 Hot Spot Program 05 | |||
EN-RP-110 ALARA Program 14 | |||
Procedures | |||
Number Title Revision | |||
EN-RP-110-03 Collective Radiation Exposure (CRE) Reduction 04 | |||
Guidelines | |||
EN-RP-110-04 Radiation Protection Risk Assessment Process 07 | |||
EN-RP-152 Conduct of Radiation Protection 04 | |||
Audits and Self-Assessments | |||
Number Title Date | |||
Self-Assessment: Occupational ALARA Planning | |||
LO-WLO-2017-00069 July 24, 2018 | |||
and Controls | |||
Radiation Work Permits | |||
Number Title Revision | |||
2016-0118 Loading of Dry Fuel Storage Cask #18 with Spent Fuel and 02 | |||
Transport including all DFS Support Activities to include Set | |||
Up/Demob | |||
2016-0119 Loading of Dry Fuel Storage Cask #19 with Spent Fuel and 01 | |||
Transport including all DFS Support Activities to include Set | |||
Up/Demob | |||
2016-0123 Loading of Dry Fuel Storage Cask #23 with Spent Fuel and 00 | |||
Transport including all DFS Support Activities to include Set | |||
Up/Demob | |||
2017-0515 RCP 1B Motor Replacement 00 | |||
2017-0610 Erect/Dismantle Scaffolding in the Reactor Containment 00 | |||
Building | |||
2017-0702 Reactor Disassembly Activities 00 | |||
2017-0705 Reactor Reassembly Activities 00 | |||
2018-0001 Radiation Protection to Perform Job Coverage, Routine 00 | |||
Surveys, Inspections and Walkdowns | |||
2018-0006 Radwaste Processing/Shipping in all Radiologically Controlled 00 | |||
Areas | |||
ALARA Planning, In-Progress Reviews, and Post-Job Reviews | |||
Number Title Revision | |||
EN-RP-105, Att.9.5 Refuel 20 Outage ALARA Report 01 | |||
EN-RP-105, Att.9.5 Refuel 21 Outage ALARA Report 00 | |||
Miscellaneous | |||
Documents Revision | |||
Number Title or Date | |||
EC 0000042470 Evaluate TSR 2008-24, 2010-01, 2011-30, 2012-24, February 20, | |||
2012-33, 2012-36, 2011-79 as Long-Term Shielding 2013 | |||
2017 Annual Radiation Protection Program Report 06 | |||
Waterford-3 Abbreviated 5-Year Exposure Reduction Plan December 4, | |||
2018-2022 2017 | |||
71124.04 - Occupational Dose Assessment | |||
Condition Reports | |||
HQN-2016-1136 WF3-2016-07300 WF3-2017-01829 WF3-2017-02024 WF3-2017-06719 | |||
WF3-2017-06758 WF3-2017-07702 WF3-2018-01726 WF3-2017-03148 | |||
Procedures | |||
Number Title Revision | |||
EN-RP-131 Air Sampling 16 | |||
EN-RP-201 Dosimetry Administration 05 | |||
EN-RP-204 Special Monitoring Requirements 11 | |||
EN-RP-205 Prenatal Monitoring 03 | |||
EN-RP-208 Whole Body Counting/In-Vitro Bioassay 07 | |||
EN-RP-312 Operation and Calibration of the Canberra GEM-5 01 | |||
EN-RP-314 Passive Monitor Sensitivity Testing 00 | |||
Audits and Self-Assessments | |||
Number Title Date | |||
January 16, | |||
LO-WLO-2016-00037 Self-Assessment: Bioassay Program | |||
2017 | |||
LO-WLO-2017-00069 Self-Assessment: Occupational Dose Assessment July 23, 2018 | |||
Calibration Records | |||
Number Title Date | |||
017027353 Canberra GEM-5 Calibration Data Sheet April 25, 2018 | |||
Miscellaneous | |||
Documents | |||
Number Title Date | |||
Entergy Waterford-3 Radiation Protection Department | |||
2017-2018 September 4, 2018 | |||
Respiratory Improvement Plan | |||
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 | |||
October 4, 2017 | |||
Program to Detect Intakes at Waterford-3 | |||
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 | |||
EP-001-001 Recognition and Classification of Emergencies 32, 33 | |||
EP-002-010 Notifications and Communications 313, 314, 315 | |||
EP-002-052 Protective Action Guidelines 25 | |||
EPP-424 Siren Testing and Siren System Administrative Controls, 19 | |||
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 10 CFR 21 Discovery Determination & Reportability 9 | |||
Evaluation Sheet for CR-WF3-2018-1994 | |||
EN-DC-205 Maintenance Rule Monitoring 6 | |||
Drawings | |||
Number Title Revision | |||
B425 T7075B1 Control Loop Diagram CC-Dry Cooling tower B Fan 4 | |||
Cooling | |||
B425 T7070BD Control Loop Diagram CC-Dry Cooling tower B Outlet 4 | |||
Temp | |||
B425 T5009A Control Loop Diagram HVR-CCW Pump Heat Exchanger 5 | |||
A Room Temp | |||
71153 - Event Followup | |||
Miscellaneous | |||
Documents | |||
Number Title Date | |||
W3F1-2017-0076 NRC Performance Indicator (PI) Data - 3rd Quarter 2017 October 6, | |||
ROP Data 2017 | |||
W3F1-2018-0004 NRC Performance Indicator (PI) Data - 4th Quarter 2017 January 9, | |||
ROP Data 2018 | |||
W3F1-2018-0024 NRC Performance Indicator (PI) Data - 1st Quarter 2018 April 12, | |||
ROP Data 2018 | |||
W3F1-2018-0042 NRC Performance Indicator (PI) Data - 2nd Quarter 2018 July 13, 2018 | |||
ROP Data | |||
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.) | |||
: [[contact::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. | |||
: [[contact::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. | |||
: [[contact::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. | |||
: [[contact::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). | |||
: [[contact::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.) | |||
: [[contact::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. | |||
: [[contact::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 | |||
: [[contact::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. | |||
: [[contact::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. | |||
: [[contact::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.). | |||
: [[contact::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. | |||
: [[contact::Q. A list of EDEX or multi-badge dosimetry uses since the last inspection]], include the | |||
associated RWP and dose accrued. | |||
ML18304A163 | |||
SUNSI Review ADAMS: Non-Publicly Available Non-Sensitive Keyword: | |||
By: NFO Yes No Publicly Available Sensitive NRC-002 | |||
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 CAS 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 NFO | |||
DATE 10/25/2018 10/29/2018 | |||
}} | }} |
Latest revision as of 17:21, 18 December 2019
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
ber 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
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number(s): 05000382 License Number(s): NPF-38 Report Number(s): 05000382/2018003 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 Enclosure
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 Status Section URI 05000382/2017008-04 Potential Failure to Obtain a 71111.21M Closed License Amendment for Changes to Diesel Generator Surveillance Test Interval
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 Potential Failure to Obtain a License Amendment for 7111.21M (Closed) Changes to Diesel Generator Surveillance Test Interval URI 05000382/2017008-04
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
EN-LI-100 Process Applicability Determination 10
OP-901-521 Severe Weather and Flooding 326
Drawings
Number Title Date
G-580 Nuclear Plant Island Structure Flood Wall July 10, 2018
Penetrations, Sheet 1
G-580 Nuclear Plant Island Structure Flood Wall April 3, 2011
Penetrations, Sheet 2
G-580 Nuclear Plant Island Structure Flood Wall April 25, 1991
Penetrations, Sheet 3
71111.04 - Equipment Alignment
Condition Reports
CR-WF3-2017-01509 CR-WF3-2017-04445 CR-WF3-2018-04638 CR-WF3-2017-07561
CR-WF3-2017-07550
Work Orders
00475847 00476848 00433888 00397848
00427894 00468224 00467879 00435999
Procedures
Number Title Revision
OP-008-008 Shield Building Ventilation 10
OP-003-035 Auxiliary Feedwater 309
OP-009-003 Emergency Feedwater 309
OP-009-002 Emergency Diesel Generator 346
OP-002-010 Reactor Auxiliary Building HVAC and Containment 312
Purge
71111.05 - Fire Protection
Procedures
Number Title Revision
NS-TB-001 Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +15.00 4
East
NS-TB-003 Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +40.00 1
East
RAB 34-001 Waterford-3 S.E.S Pre-Fire Strategy Elev. -15.50 RAB (RCA) 8
NS-TB-004 Waterford-3 S.E.S Pre-Fire Strategy Turbine Building +40.00 1
West
RAB 2-001 Waterford-3 S.E.S Pre-Fire Strategy Elev. +46.00 RAB (RCA) 13
EN-TQ-125 Fire Brigade Drills 6
RAB 6-001 Waterford-3 S.E.S Pre-Fire Strategy Elev. +35.00 RAB 9
Miscellaneous
Documents
Number Title Date
Waterford 3 Fire Brigade Drill 2018 Completion September
Tracking Matrix 2018
Waterford 3 Fire Brigade Drill 2017 Completion September
Tracking Matrix 2018
Waterford 3 Fire Brigade Drill 2016 Completion September
Tracking Matrix 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 11
OP-901-220 Loss of Condenser Vacuum 303
OP-901-212 Rapid Plant Power Reduction 10
OP-902-000 Standard Post Trip Actions 16
OP-902-001 Reactor Trip Recovery 16
OP-902-008 Functional Recovery 27
OP-902-009 Standard Appendices 317
EP-001-001 Recognition & Classification of Emergency Conditions 33
OP-903-005 Control Element Assembly Operability Check 14
OP-903-094 ESFAS Subgroup Relay Test - Operating 31
Miscellaneous
Documents Revision
Number Title 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 1
EN-MA-125 Troubleshooting Control and Maintenance Activities 22
EN-WM-104 On Line Risk Management 17
OI-037-000 Operations Risk Assessment Guideline 313
EN-WM-104 On Line Risk Management 18
EN-OP-119 Protected Equipment Postings 9
Miscellaneous
Documents
Number Title Date
EN-OP-119 Att. 9.1 Protected Equipment Postings List for Emergency September 23,
Diesel Generator A work window 2018
EN-OP-119 Att. 9.1 Protected Equipment Postings List for Emergency August 20,
Feedwater 228A and 224A 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 10
OP-903-068 Emergency Diesel Generator and Subgroup Relay 321
Operability Verification
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
EN-DC-136 Temporary Modifications 17
OP-001-001 Reactor Coolant System Fill and Vent 35
OP-903-097 Pressurizer Heater Capacity Verification 12
OP-901-502 Evacuation of Control Room and Subsequent Plant 35
Cooldown
Drawings
Number Title Revision
5817-14492 UHS Air Deflector Structure Details Sheets 1 - 41
B424 Sheet 291 Pressurizer Proportional Heater Bank-1 18
B424 Sheet 286 Pressurizer Backup Heaters Bank 2 20
B424 Sheet 287 Pressurizer Backup Heaters Bank 3 18
B289 Sheet 23A1 480V Switchgear 3A32 Programmer Settings 8
B289 Sheet 23 Power Distribution and Motor Data 480V Switchgear 3A32 17
One Line Diagram
B289 Sheet 101 Power Distribution and Motor Data 480V Distribution Panels 6
B289 Sheet 158 Power Distribution and Motor Data 480V Switchgear Front 13
View
Miscellaneous
Documents
Number Title Revision
EC-71594 Temporary Replace Failed Proportional Heater Bank 1 0
Heaters 3 (position F2) and 4 (position H2) with heaters from
Backup Bank 2and 3 (positions E1 and C2)
EC-54532 Ultimate Heat Sink Margin Restoration - Phase 3 0
EC-52043 Ultimate Heat Sink Margin Restoration 0
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 52735553
00450472 52756221 52713822 52746212
2745254 52735551 00477067 50551501
2805322 00496405
Procedures
Number Title Revision
OP-903-068 Emergency Diesel Generator and Subgroup Relay Operability 321
Verification
OP-009-002 Emergency Diesel Generator 346
OP-903-003 Charging Pump Operability Check 312
OP-904-007 Charging Pump Pulsation Dampener Pressure Check 016
OP-903-131 AFW High Discharge Pressure Trip Test 002
MM-006-161 AFW Pump Disassembly, Inspection and Reassembly 9
MM-006-162 Diesel Generator Cylinder Head Removal, Inspection and 7
Installation
EN-HU-106 Procedure and Work Instruction Use and Adherence 6
EN-MA-118 Foreign Material Exclusion 13
UNT-005-007 Plant Lubrication Procedure 304
OP-002-010 Reactor Auxiliary Building HVAC and Containment Purge 312
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 55
Miscellaneous
Documents
Number Title Revision
WLP-OPS-CVC00 CVCS training document 27
WF3-ME-18-00001 Charging Pump Pulsation Dampener Vibration Evaluation 0
EC-75478 Evaluation of Charging Pump Pulsation Dampener Impact on 0
Operability
PE Eval 153315 Head, Cylinder, Emergency Diesel Generator 0
71111.22 - Surveillance Testing
Condition Reports
CR-WF3-2018-04236 CR-WF3-2018-04214 CR-WF3-2018-04202 CR-WF3-2018-04314
CR-WF3-2018-04365
Work Orders
2645246 52819598
Procedures
Number Title Revision
OP-903-030 Safety Injection Pump Operability Verification 36
MI-005-214 Calibration of Flow Instruments 6
OP-903-006 Reactor Trip Circuit Breaker Test 13
MI-003-126 Core Protection Calculator Functional Test 20
OP-903-100 MOV Overload Bypass Test 310
OP-903-046 Emergency Feed Pump Operability Check 322
Drawings
Number Title Revision
B-424 Sheet 1153 Control Room Emergency Filtration Unit North Intake 20
Miscellaneous
Documents
Number Title Revision
71114.02 - Alert and Notification System Testing
Condition Reports
2017-03818 2017-06905
Work Orders
2710344 52735556 52735558
Procedures Revision
Number Title or Date
Updated Alert and Notification System Design Report, December 8
2014
FEMA REP-10 Design Report Addendum July 14,
2015
EPP-422 Siren and Helicopter Warning System Maintenance, 11
EPP-424 Siren Testing and Siren System Administrative Controls, 19
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
EN-EP-310 Emergency Response Organization Notification System 5
EN-EP-801 Emergency Response Organization 15
EP-002-015 Emergency Responder Activation 303
EPP-462 Evaluation of Pager Tests 4
71117.04 - Emergency Action Level and Emergency Plan Changes
Procedures
Number Title Revision
EN-EP-305 Emergency Planning 10CFR50.54(q) Review Program 6
Miscellaneous
Documents
Number Title Revision
10CFR50.54(q)(3) Screening Evaluation for EP-002-100 45
10CFR50.54(q)(3) Screening Evaluation for EN-EP-801 14
10CFR50.54(q)(3) Screening Evaluation for Emergency Plan 47
10CFR50.54(q)(3) Screening Evaluation for Emergency Plan 48
10CFR50.54(q)(3) Screening Evaluation for On-Shift Staffing 1
Analysis
10CFR50.54(q)(3) Screening for Emergency Plan 49
10CFR50.54(q)(3) Screening Evaluation for EP-001-001 33
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-2016-00050 LO-HQNLO-2016-00056
Work Orders
00422707 00422708 00448915 00450676
00451436 00451985 00461103 00476211
00488788 00489973 00492462 00495965
2580909 52702861 52707267 52772677
2728394
Procedures
Number Title Revision
EN-EP-306 Drills and Exercises 9
EN-EP-308 Emergency Planning Critiques 5
EN-EP-801 Emergency Response Organization 15
EN-LI-102 Corrective Action Program 32, 33
EN-LI-104 Self-Assessment and Benchmark Process 13
EN-QV-109 Audit Process 34
EP-001-010 Unusual Event 303
EP-002-015 Emergency Responder Activation 301
EP-003-020 Emergency Preparedness Drills and Exercises, 304
EP-003-030 Emergency Program Review, Updating, and Modification, 303
EP-003-040 Emergency Equipment Inventory, 308
EP-003-070 Emergency Communications Systems Routine Testing, 304
EPP-401 Review, Publication and Distribution of Public Information 2
Materials,
EPP-428 Emergency Facilities and Equipment Readiness, 306
Miscellaneous
Documents Revision
Number Title or Date
Waterford3 Emergency Plan 47, 48, 49
LO-WLO-2017-0048 2017 Pre NRC Evaluation Exercise Assessment October 16,
2017
LO-WLO-2017-00077 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 September 29,
Facility 2016
Readiness Condition - Emergency Operations July 6, 2017
Facility (March)
Readiness Condition - Emergency Operations July 6, 2017
Facility (June)
Readiness Condition - Emergency Operations April 3, 2018
Facility
Readiness Condition - Emergency Operations June 19, 2018
Facility
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 18,
February 12, 2016 2016
W3D3-2016-0003 Evaluation Report for the Exercise Conducted May 3, 2016
April 6, 2016
Evaluation Report for the Health Physics Drill July 13, 2016
Conducted June 22, 2016
W3D3-2016-0006 Evaluation Report for the Exercise Conducted July 15, 2016
June 15, 2016
W3E3-2016-0008 Evaluation Report for the Exercise Conducted September 27,
August 31, 2016 2016
W3D3-2016-0009 Evaluation Report for the Drill Conducted October 7, 2016
October 7, 2016
W3D3-2016-0008 Evaluation Report for the Drill Exercise Conducted
December 7, 2016
Evaluation Report for the Medical Drill Conducted February 22,
January 23, 2017 2017
W3D3-2017-0004 Evaluation Report for the Control Room Breathing March 24, 2017
Air Drill Conducted March 24, 2017
Evaluation Report for the Exercise Conducted
June 28, 2017
W3D3-2017-0007 Evaluation Report for the Control Room Breathing September 19,
Air Drill Conducted September 15, 2017 2017
2017-05 Evaluation Report for the Drill Exercise Conducted October 19,
July 12, 2017, Revision 1 2017
Evaluation Report for the Exercise Conducted
October 26, 2017
2017-017 Evaluation Report for the Focused Drill for Site November 29,
Accountability 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 June 15, 2018
Air Drill Conducted June 15, 2018
Evaluation Report for the Exercise Conducted July 18, 2018
June 20, 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 WF3-2017-03771 WF3-2017-03778 WF3-2018-00831
Procedures
Number Title Revision
EN-RP-100 Radiation Worker Expectations 12
EN-RP-105 Radiological Work Permits 18
EN-RP-109 Hot Spot Program 05
Procedures
Number Title Revision
EN-RP-110-03 Collective Radiation Exposure (CRE) Reduction 04
Guidelines
EN-RP-110-04 Radiation Protection Risk Assessment Process 07
EN-RP-152 Conduct of Radiation Protection 04
Audits and Self-Assessments
Number Title Date
Self-Assessment: Occupational ALARA Planning
LO-WLO-2017-00069 July 24, 2018
and Controls
Radiation Work Permits
Number Title Revision
2016-0118 Loading of Dry Fuel Storage Cask #18 with Spent Fuel and 02
Transport including all DFS Support Activities to include Set
Up/Demob
2016-0119 Loading of Dry Fuel Storage Cask #19 with Spent Fuel and 01
Transport including all DFS Support Activities to include Set
Up/Demob
2016-0123 Loading of Dry Fuel Storage Cask #23 with Spent Fuel and 00
Transport including all DFS Support Activities to include Set
Up/Demob
2017-0515 RCP 1B Motor Replacement 00
2017-0610 Erect/Dismantle Scaffolding in the Reactor Containment 00
Building
2017-0702 Reactor Disassembly Activities 00
2017-0705 Reactor Reassembly Activities 00
2018-0001 Radiation Protection to Perform Job Coverage, Routine 00
Surveys, Inspections and Walkdowns
2018-0006 Radwaste Processing/Shipping in all Radiologically Controlled 00
Areas
ALARA Planning, In-Progress Reviews, and Post-Job Reviews
Number Title Revision
EN-RP-105, Att.9.5 Refuel 20 Outage ALARA Report 01
EN-RP-105, Att.9.5 Refuel 21 Outage ALARA Report 00
Miscellaneous
Documents Revision
Number Title or Date
EC 0000042470 Evaluate TSR 2008-24, 2010-01, 2011-30, 2012-24, February 20,
2012-33, 2012-36, 2011-79 as Long-Term Shielding 2013
2017 Annual Radiation Protection Program Report 06
Waterford-3 Abbreviated 5-Year Exposure Reduction Plan December 4,
2018-2022 2017
71124.04 - Occupational Dose Assessment
Condition Reports
HQN-2016-1136 WF3-2016-07300 WF3-2017-01829 WF3-2017-02024 WF3-2017-06719
WF3-2017-06758 WF3-2017-07702 WF3-2018-01726 WF3-2017-03148
Procedures
Number Title Revision
EN-RP-131 Air Sampling 16
EN-RP-201 Dosimetry Administration 05
EN-RP-204 Special Monitoring Requirements 11
EN-RP-205 Prenatal Monitoring 03
EN-RP-208 Whole Body Counting/In-Vitro Bioassay 07
EN-RP-312 Operation and Calibration of the Canberra GEM-5 01
EN-RP-314 Passive Monitor Sensitivity Testing 00
Audits and Self-Assessments
Number Title Date
January 16,
LO-WLO-2016-00037 Self-Assessment: Bioassay Program
2017
LO-WLO-2017-00069 Self-Assessment: Occupational Dose Assessment July 23, 2018
Calibration Records
Number Title Date
017027353 Canberra GEM-5 Calibration Data Sheet April 25, 2018
Miscellaneous
Documents
Number Title Date
Entergy Waterford-3 Radiation Protection Department
2017-2018 September 4, 2018
Respiratory Improvement Plan
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
October 4, 2017
Program to Detect Intakes at Waterford-3
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
EP-001-001 Recognition and Classification of Emergencies 32, 33
EP-002-010 Notifications and Communications 313, 314, 315
EP-002-052 Protective Action Guidelines 25
EPP-424 Siren Testing and Siren System Administrative Controls, 19
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 10 CFR 21 Discovery Determination & Reportability 9
Evaluation Sheet for CR-WF3-2018-1994
EN-DC-205 Maintenance Rule Monitoring 6
Drawings
Number Title Revision
B425 T7075B1 Control Loop Diagram CC-Dry Cooling tower B Fan 4
Cooling
B425 T7070BD Control Loop Diagram CC-Dry Cooling tower B Outlet 4
Temp
B425 T5009A Control Loop Diagram HVR-CCW Pump Heat Exchanger 5
A Room Temp
71153 - Event Followup
Miscellaneous
Documents
Number Title Date
W3F1-2017-0076 NRC Performance Indicator (PI) Data - 3rd Quarter 2017 October 6,
ROP Data 2017
W3F1-2018-0004 NRC Performance Indicator (PI) Data - 4th Quarter 2017 January 9,
ROP Data 2018
W3F1-2018-0024 NRC Performance Indicator (PI) Data - 1st Quarter 2018 April 12,
ROP Data 2018
W3F1-2018-0042 NRC Performance Indicator (PI) Data - 2nd Quarter 2018 July 13, 2018
ROP Data
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.
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.
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.
associated RWP and dose accrued.
SUNSI Review ADAMS: Non-Publicly Available Non-Sensitive Keyword:
By: NFO Yes No Publicly Available Sensitive NRC-002
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 CAS 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 NFO
DATE 10/25/2018 10/29/2018