IR 05000482/2019001
| ML19128A369 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/08/2019 |
| From: | Nick Taylor NRC/RGN-IV/DRP/RPB-B |
| To: | Heflin A Wolf Creek |
| References | |
| EA-19-023 IR 2019001 | |
| Download: ML19128A369 (31) | |
Text
May 8, 2019
SUBJECT:
WOLF CREEK GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000482/2019001
Dear Mr. Heflin:
On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Wolf Creek Generating Station. On April 10, 2019, the NRC inspectors discussed the results of this inspection with Mr. J. McCoy, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
NRC inspectors documented one Severity Level IV violation with no associated finding. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
Further, inspectors documented a licensee-identified violation which was determined to be of very low safety significance in this report. The NRC is treating this violation as an NCV consistent with Section 2.3.2 of the Enforcement Policy.
Additionally, in the preceding twelve months the NRC issued three Severity Level IV traditional enforcement violations associated with impeding the regulatory process, as described in NRC Inspection Reports 05000482/2018002, dated August 12, 2018; 05000482/2018003, dated November 7, 2018; and in this report. Therefore, the NRC plans to conduct an inspection using Inspection Procedure 92723, Follow up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12-Month Period, to follow-up on these violations. This inspection will be scheduled and completed once you provide written notification of your readiness for the inspection.
If you contest the violation or significance of this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC resident inspector at the Wolf Creek Generating Station. If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC resident inspector at the Wolf Creek Generating Station.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Nicholas H. Taylor, Chief Project Branch B Division of Reactor Projects
Docket No. 05000482 License No. NPF-42
Enclosure:
Inspection Report 05000482/2019001 w/Attachment: Request for Information
Enclosure U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
Enterprise Identifier: I-2019-001-0012
Licensee:
Wolf Creek Nuclear Operating Corporation
Facility:
Wolf Creek Generating Station
Location:
Burlington, Kansas 66839
Inspection Dates:
January 1, 2019, to March 31, 2019
Inspectors:
D. Dodson, Senior Resident Inspector
F. Thomas, Resident Inspector
L. Carson II, Senior Health Physicist
B. Correll, Reactor Inspector
S. Hedger, Emergency Preparedness Inspector
Approved By:
Nicholas H. Taylor
Chief, Project Branch B
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a quarterly inspection at Wolf Creek Unit 1 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. NRC-identified and self-revealed findings, violations, and additional items are summarized in the table below.
Licensee-identified non-cited violations are documented in report sections: 7115
List of Findings and Violations
Failure to Provide Unfettered Access to an NRC Resident Inspector Cornerstone Severity Cross-cutting Aspect Inspection Procedure Not Applicable Severity Level IV NCV 05000482/2019001-01 Closed Not Applicable 71111.22 -
Surveillance Testing The inspectors identified a Severity Level IV non-cited violation of 10 CFR 50.70(b)(3), associated with the licensees failure to provide unfettered access to an NRC resident inspector. Specifically, while the NRC resident inspector was performing deep backshift observations and inspections, the resident inspector was removed from the site even though the resident inspector complied with applicable access control measures. As a result, the NRCs ability to regulate was adversely impacted.
Additional Tracking Items
None.
PLANT STATUS
Wolf Creek Generating Station operated at or near full 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
71111.01 - Adverse Weather Protection
Summer Readiness Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems.
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 02.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Component cooling water train B on February 15, 2019
- (2) Residual heat removal train B on March 20, 2019
- (3) Instrument air compressor A on March 21, 2109
- (4) Spent fuel pool cooling train A on March 22, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (4 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Auxiliary building, elevation 1,974 and 2,026 feet, fire area A-3 on March 13, 2019
- (2) Fuel building, elevation 2,000 feet, fire areas F-2 and F-3 on March 20, 2019
- (3) Fuel building, elevation 2,047 feet, fire areas F-6 and F-7 on March 20, 2019
- (4) Auxiliary building, elevation 2,000 feet, fire areas A-24 and A-25 on March 26, 2019 Annual Inspection (IP Section 03.02) (1 Partial Sample)
The inspectors evaluated fire brigade performance on February 8, 2019.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
The inspectors observed and evaluated licensed operator performance during reactivity manipulations by under instruction reactor operators on February 20, 2019; during performance of offsite power operability verification in accordance with STS NB-005, "Breaker Alignment Verification," during an extended emergency diesel generator maintenance window on March 5, 2019; and during performance of component cooling water pump B inservice testing in accordance with STS EG-100B, "Component Cooling Water Pumps B/D Inservice Pump Test," by under instruction reactor operators on March 11, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated licensed operator simulator requalification activities that included multiple instrument and component malfunctions and a steam generator tube rupture scenario on February 5, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with instrument air compressor A, which failed to maintain pressure on December 23, 2018.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Essential service water train B unplanned strainer piping replacement on January 8, 2019
- (2) Risk assessment associated with component cooling water train A planned maintenance on February 12, 2019
- (3) Risk assessment associated with emergency diesel generator and service water pump B planned maintenance during the week of March 4, 2019
- (4) Risk assessment associated with component cooling water train B planned maintenance on March 14, 2019
- (5) Risk assessment associated with auxiliary feedwater train A planned maintenance on March 28, 2019
71111.15 - Operability Determinations and Functionality Assessments
Sample Selection (IP Section 02.01) (4 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Steam generator secondary side un-reinforced penetration cover plate stress report error on January 3, 2019
- (2) Identification of new or previously unevaluated boric acid leaks on February 21, 2019
- (3) Pressurizer safety valve B increased tailpipe temperature indication on March 2, 2019
- (4) Emergency diesel generator train B phase C output cable strands found cut on March 18, 2019
71111.19 - Post Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Safety injection pump A following planned maintenance on January 15, 2019
- (2) Containment spray pump A following planned maintenance on January 16, 2019
- (3) Essential service water pump B following planned maintenance on January 29, 2019
- (4) Diesel driven fire pump following planned maintenance on February 19, 2019
- (5) Loss of voltage and degraded voltage testing of channel 2 bistable after replacement of associated power supply on February 20, 2019
- (6) Turbine driven auxiliary feedwater pump following planned maintenance on February 27, 2019
- (7) Turbine driven auxiliary feedwater pump discharge to steam generator C valve (ALHV0012) following planned maintenance on February 27, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Reactor Coolant System (RCS) Leak Detection (IP Section 03.01) (1 Sample)
- (1) STS BB-006, "[Reactor Coolant System] Water Inventory Balance Using the [Nuclear Plant Information System] Computer," on February 1, 2019
Surveillance Testing (IP Section 03.01) (5 Samples)
- (1) STS SF-001, "Control and Shutdown Rod Operability Verification," on January 17, 2019
- (2) STS IC-909B, "Accumulator Pressure Instrument Channel Calibration," on February 6, 2019
- (3) STS IC-217, "[Reactor Coolant Pump] Loss of Voltage and Underfrequency [Trip Actuation Device Operational Testing]," on February 28, 2019
- (4) STS KJ-005B, "Manual/Auto Start, [Synchronization] & Loading of [Emergency Diesel Generator] NE02," on March 6, 2019
- (5) STN KU-010, "Station Blackout Diesel and Non-Safety [Auxiliary Feedwater] Pump Test," on March 11, 2019
71114.06 - Drill Evaluation
Drill and/or Simulator-Based Licensed Operator Requalification Training (IP Section 02.01) (1 Sample)
The inspectors evaluated the emergency preparedness drill on January 30, 2019
Emergency Preparedness (EP) Drill (IP Section 02.01) (1 Sample)
The inspectors evaluated the emergency preparedness drill on February 20,
RADIATION SAFETY
71124.02 - Occupational ALARA Planning and Controls
Radiological Work Planning (IP Section 02.01) (1 Sample)
The inspectors evaluated the licensees radiological work planning by reviewing the following activities:
- RWP 183000, "Non-Destructive Testing/ISI"
- RWP 183220, "Primary Steam Generator Eddy Current"
- RWP 184420, "Maintenance Support/Scaffolding"
- RWP 186020, "Reactor Vessel Head Lift Activity"
Verification of Dose Estimates and Exposure Tracking Systems (IP Section 02.02) (1 Sample)
The inspectors evaluated dose estimates and exposure tracking. The inspectors reviewed the following ALARA planning documents:
- RWP 183000, "Non-Destructive Testing/ISI"
- RWP 183220, "Primary Steam Generator Eddy Current Testing"
Additionally, the inspectors reviewed the following radiological outcome evaluations:
- RWP 183220, "Primary Steam Generator Eddy Current Testing"
71124.04 - Occupational Dose Assessment
External Dosimetry (IP Section 02.02) (1 Sample)
The inspectors evaluated the external dosimetry program implementation.
Internal Dosimetry (IP Section 02.03) (1 Sample)
The inspectors evaluated the internal dosimetry program implementation.
Whole Body Counts:
- ACAD no. 7657
- ACAD no. 1174
- ACAD no. 7723
In-vitro internal monitoring:
There was no in-vitro internal monitoring at Wolf Creek from 2018 to 2019.
Dose assessments performed using air sampling and DAC-hr. monitoring:
- Air sample no. 18-0181
- ACAD no. 1356
- ACAD no. 3635
- ACAD no. 3933
- ACAD no. 2364
Source Term Categorization (IP Section 02.01) (1 Sample)
The inspectors evaluated the licensees characterization of the source term and use of scaling factors for the use of hard-to-detect radionuclide activity.
Special Dosimetric Situations (IP Section 02.04) (1 Sample)
The inspectors evaluated the licensees performance for special dosimetric situations.
Declared pregnant workers:
There were no declared pregnant workers at Wolf Creek in 2018 and 2019.
EDEX exposures:
- EDEX multi-package no. MP6042
- EDEX multi-package no. MP6051
Shallow Dose Equivalent:
- Skin dose ACAD no. 3933
- Skin dose ACAD no. 2364
Neutron Dose Assessment:
- 2017 - RWP 170036
- 2018 - RWP 180036
- 2019 - RWP
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
Unplanned Scrams per 7000 Critical Hours Sample (01/01/2018-12/31/2018)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
Unplanned Power Changes per 7000 Critical Hours Sample (01/01/2018-12/31/2018)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
Unplanned Scrams with Complications (USwC) Sample (01/01/2018-12/31/2018)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) On November 27, 2018, Condition Report 128267 documented that Administrative Controls page for Technical Specification Surveillance Requirement 3.3.5.3 was added to the technical specifications prematurely and needed to be removed.
- (2) On January 8, 2019, Condition Report 129197 documented that errors were found in documentation revised to implement a new emergency action level scheme.
INSPECTION RESULTS
Failure to Provide Unfettered Access to an NRC Resident Inspector Cornerstone Severity Cross-cutting Aspect Inspection Procedure Not Applicable Severity Level IV NCV 05000482/2019001-01 Closed Not Applicable
71111.22 - Surveillance
Testing The inspectors identified a Severity Level IV non-cited violation of 10 CFR 50.70(b)(3),associated with the licensees failure to provide unfettered access to an NRC resident inspector. Specifically, while the NRC resident inspector was performing deep backshift observations and inspections, the resident inspector was removed from the site even though the resident inspector complied with applicable access control measures. As a result, the NRCs ability to regulate was adversely impacted.
Description:
At approximately 10:00 p.m. on January 31, 2019, the resident inspector arrived at the Wolf Creek control room to observe reactor coolant system water inventory balance activities being performed by reactor operators. This observation was part of a baseline inspection sample required by Inspection Procedure 71111, Attachment 22, Surveillance Testing. At approximately 11:30 p.m., the control room operators reached a point in the testing procedure that required a 2-hour waiting period. During this time, the resident inspector performed plant status walk-downs of Class 1E electrical equipment and other control building equipment. At approximately 12:00 a.m. on February 1, 2019, an announcement was made over the plant announcement system requesting the resident inspector to answer. When the resident inspector responded, he was informed by a plant security officer that his plant access data system access had expired as a result of expired site access qualifications. The resident inspector was told that he would need to exit the protected area.
The resident inspector then attempted to exit the area, but discovered that his key card did not work. Almost immediately after having attempted to scan the key card, another security officer made an announcement and requested the resident inspector answer. The resident inspector notified the officer that the residents key card did not work and the security officer indicated that another security officer was on the way to escort the resident inspector out of the protected area. After a second check of the plant access training list, the security officer still did not see the resident inspectors name listed. Security then allowed the resident inspector to gather his personal belongings (while maintaining escort line of sight of the resident inspector), and then the resident inspector was escorted outside the protected area at approximately 12:30 a.m. After communicating with NRC management, the resident inspector left the Wolf Creek site at approximately 1:00 a.m. As a result, the resident inspector was neither able to observe all desired portions of the planned surveillance inspection activity, nor able to observe station conditions during the deep backshift, as planned.
After the NRC branch chief made licensee management aware of the resident inspectors access issues the following morning, the licensee conducted fact-finding and determined that the resident inspector had properly complied with applicable access control measures for security, radiological protection, and personal safety and had taken all actions necessary to ensure unfettered access. The resident inspectors site access was restored later on the morning of February 1, 2019.
Corrective Actions: The licensee performed fact-finding, reinstated the NRC inspectors site access, and briefed executive management. Additionally, the licensee conducted a basic cause evaluation to understand the causes of the issue. The licensee determined the probable cause to be that personnel in the licensing division had not communicated to the individual responsible for entering the training records into the learning management system (LMS) [an internal licensee training database], that the security division needed to be notified when an NRC inspectors site access training dates have been updated.
Corrective Action References: Condition Reports 129819, 129828, and 130158
Performance Assessment:
The inspectors determined this violation was associated with a minor performance deficiency.
Enforcement:
The ROPs significance determination process does not specifically consider the regulatory process impact in its assessment of licensee performance. Therefore, it is necessary to address this violation, which impedes the NRCs ability to regulate, using traditional enforcement to adequately deter non-compliance.
Severity: The finding was evaluated in accordance with the NRCs Enforcement Policy. The finding was reviewed by NRC management and because the violation was of very low safety significance, was not repetitive or willful, and was entered into the corrective action program, this violation is being treated as a Severity Level IV non-cited violation, consistent with the Enforcement Policy.
Violation: Title 10 CFR 50.70(b)(3), requires, in part, that the licensee shall afford any NRC resident inspector assigned to that site unfettered access, equivalent to access provided regular plant employees, following proper identification and compliance with applicable access control measures for security, radiological protection, and personal safety. Contrary to the above, on February 1, 2018, the licensee did not afford an NRC resident inspector assigned to the site unfettered access, equivalent to access provided regular plant employees, following proper identification and compliance with applicable access control measures for security, radiological protection, and personal safety. Specifically, while the NRC resident inspector was performing deep backshift observations and inspections, the resident inspector was removed from the site, even though the resident inspector complied with applicable access control measures. As a result, the NRCs ability to regulate was adversely impacted.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Licensee-Identified Non-Cited Violation
71152 - Problem
Identification and Resolution This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Title 10 CFR 50.54(q)(2) requires, in part, a holder of a license under this part shall maintain the effectiveness of an emergency plan that meets the requirements in Appendix E to this part and the planning standards of 50.47(b). Planning standard 10 CFR 50.47(b)(4)requires, in part, that a standard emergency classification and action level scheme is in use by the nuclear facility licensee. Contrary to the above, from September 26, 2018, to January 22, 2019, the licensee failed to maintain the effectiveness of an emergency plan which met the requirements in Appendix E to this part and the planning standards of 10 CFR 50.47(b). Specifically, the licensee failed to maintain a standard emergency classification scheme as required by 10 CFR 50.47(b)(4) because document APF 06-002-03, "EAL [elevated action level] Classification Matrix," Revision 0A, failed to include an elevated action level threshold associated with the potential loss of reactor coolant system barrier.
Significance: The finding was evaluated using Inspection Manual Chapter 0609, Appendix B, "Emergency Preparedness Significance Determination Process," issued September 22, 2015, and determined to be of very low safety significance (Green) because it was a failure to comply with NRC requirements, was associated with a risk-significant planning standard, and was not a lost or degraded planning standard function.
Corrective Action References: Condition Reports 129197, 129228, and
EXIT MEETINGS AND DEBRIEFS
On March 14, 2019, the inspector presented the baseline radiation safety inspection results to Mr. S. L. Smith, Vice President Engineering, and other members of the licensee staff.
On April 3, 2019, the inspector presented baseline problem identification and resolution inspection results to Mr. J. McCoy, Site Vice President, and other members of the licensee staff.
On April 10, 2019, the inspectors presented the quarterly resident inspection results to Mr. J. McCoy, 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
71111.01Adverse Weather Protection
Procedures
Number
Title
Revision
CKL ZL-009
Site Readings Sheets
111
Drawings
Number
Title
Revision
KD-7496
One Line Diagram
KD-7496A
Distribution System Equipment Lineup Limitations
71111.04Equipment Alignment
Procedures
Number
Title
Revision
CKL EC-120
Fuel Pool Cooling and Cleanup System Normal Valve
Lineup/Breaker Checklist
18A
CKL EG-120
Component Cooling Water System Valve, Switch and
Breaker Lineup
CKL EJ-120
RHR System Lineup
CKL KA-120
Compressed Air Valve, Breaker and Switch Lineup
36A
SYS EC-121
Recirc of the RWST Through The Fuel Pool Cleanup
System
SYS EC-201
Filling Spent Fuel Pool From Reactor Makeup Water
SYS KA-201
Instrument Air Dryer Operation
Drawings
Number
Title
Revision
M-12BN01
Piping & Instrumentation Diagram Borated Refueling
Water Storage System
M-12EC01
Piping & Instrumentation Diagram Fuel Pool Cooling and
Clean-Up System
M-12EC02
Piping & Instrumentation Diagram Fuel Pool Cooling and
Clean-Up System
M-12EJ01
Piping & Instrumentation Diagram Residual Heat
Removal System
M-12EG01
Piping & Instrumentation Diagram Component Cooling
Water System
M-12KA01
Piping & Instrumentation Diagram Compressed Air
System
M-12KA02
Piping & Instrumentation Diagram Compressed Air
System (Service Air)
Condition Reports
131029
Miscellaneous
Documents
Number
Title
Date
APF 21-001-02
Control Room Turnover Checklist - On-Coming
CRS/WC SRO/RO/BOP Review - Night Shift
03/22/2019
APF 22C-003-01
On-Line Nuclear Safety and Generation Risk
Assessment: Schedule Week 19-0112
03/18/2019 to
03/24/2019
71111.05AQFire Protection Annual/Quarterly
Procedures
Number
Title
Revision
AP 10-106
Fire Preplans
18A
Miscellaneous
Documents
Number
Title
Revision
or Date
APF 10-105-02
Fire Drill Scenario and Critique Report: 1974 Aux
Building PC Storage Area
2/08/2019
APF 10-105-02
Fire Drill Scenario and Critique Report: 1974 Aux
Building PC Storage Area: Backshift
2/08/2019
E-1F9905
Fire Hazard Analysis
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
Procedures
Number
Title
Revision
AI 30B-015
Licensed Operator Requalification Examination
Guidelines
Miscellaneous
Documents
Number
Title
Date
APF 30E-003-05
Lesson Plan Coversheet - Simulator Discovery
Scenario
01/29/2019
STS NB-005
Surveillance Test Routing Sheet (STRS) - Breaker
Alignment Verification
03/04/2019
71111.12Maintenance Effectiveness
Drawings
Number
Title
Revision
M-12KA01
Piping & Instrumentation Diagram Compressed Air
System
M-12KA04
Piping & Instrumentation Diagram Instrument Air System 21
Condition Reports
28929
28970
130277
130471
Miscellaneous
Documents
Number
Title
Revision
or Date
Final Scope Evaluation - Pending MREP Approval:
EF - Essential Service Water
03/26/2019
Functional Failure Determination Checklist for KA -
CR 126897
10/17/2018
Functional Failure Determination Checklist for KA -
CR 128929
01/23/2019
Maintenance Rule Expert Panel Meeting Agenda
2/19/2019
Maintenance Rule Expert Panel Meeting Agenda
03/26/2019
System Health Report for KA
01/01/2018 to
06/30/2018
APF 16C-006-03
Work Order Revision Sheet - WO 18-440917-000
71111.13Maintenance Risk Assessments and Emergent Work Control
Procedures
Number
Title
Revision
AI 22C-013
Protected Equipment Program
AP 10-103
Fire Protection Impairment Control
On-Line Nuclear Safety and Generation Risk
Assessment
Condition Reports
130240
Work Orders
17-431786-006
Miscellaneous
Documents
Number
Title
Revision
or Date
APF 22C-003-01
On-Line Nuclear Safety and Generation Risk
Assessment: Schedule Week 2019-0102
01/07/2019 to
01/13/2019
APF 22C-003-01
On-Line Nuclear Safety and Generation Risk
Assessment: Schedule Week 19-0105
2/11/2019 to
2/17/2019
APF 22C-003-01
On-Line Nuclear Safety and Generation Risk
Assessment: Schedule Week 19-0107
01/27/2019 to
2/02/2019
APF 22C-003-01
On-Line Nuclear Safety and Generation Risk
Assessment: Schedule Week 2019-0110
03/04/2019 to
03/10/2019
APF 22C-003-01
On-Line Nuclear Safety and Generation Risk
Assessment: Schedule Week 2019-0111
03/11/2019 to
03/17/2019
APF 22C-003-01
On-Line Nuclear Safety and Generation Risk
Assessment: Schedule Week 19-0113
03/25/2019 to
03/31/2019
GPD-1353 7/76
Bechtel - Calculation Cover Sheet - Calc. No. HV-288 0
71111.15Operability Determinations and Functionality Assessments
Procedures
Number
Title
Revision
AI 16-003
Temporary Grounding
Operability Determination and Functionality Assessment 37
MPE NE-004
Alternator Inspection
Condition Reports
29066
29758
130243
130292
130332
130333
130334
130335
130336
130337
130338
130339
130340
130341
130342
130348
130399
130401
130402
130403
130404
130583
130835
Work Orders
2-240639-000
16-420222-000
Miscellaneous
Documents
Number
Title
Revision
or Date
10466-E-029
Technical Specification for 5,000-Volt and 15,000Volt
Single-Conductor Power Cable for the Standardized
Nuclear Unit Power Plant System
APF 28-001-01
Operability Evaluation: NE002 B-EDG Stator
09/12/2017
MPE NE-004
On the Spot Change (OTSC) - Alternator Inspection
10/19/2015
71111.19Post Maintenance Testing
Procedures
Number
Title
Revision
OFN SB-008
Instrument Malfunctions
STN AL-201
Auxiliary Feedwater System Valve Test
STN FP-211
Diesel Fire Pump 1FP01PB Monthly Operation and Fuel
Level Check
STS AB-201B
TDAFP Steam Isolation Inservice Valve Test
STS AL-103
TDAFW Pump Inservice Pump Test
73B
STS AL-201C
Turbine Driven Auxiliary Feedwater System Inservice
Valve Test
STS EN-100A
Containment Spray Pump A Inservice Pump Test
STS IC-208B
4KV Loss of Voltage & Degraded Voltage TADOT NB02
BUS - SEP GRP 4
STS PE-052A
Auxiliary Feedwater Pump Turbine Pressure Test
STS PE-007
Periodic Verification of Motor Operated Valves
5A
Drawings
Number
Title
Revision
E-K3EF06
Schematic Diagram ESW Pump Discharge Air Release
Valve
M-0023
P&ID Fire Protection System (FP)
M-12AB01
Piping & Instrumentation Diagram Main Steam System
M-12AB02
Piping & Instrumentation Diagram Main Steam System
M-12AB03
Piping & Instrumentation Diagram Main Steam System
M-12AL01
Piping & Instrumentation Diagram Auxiliary Feedwater
System
M-12BN01
Piping & Instrumentation Diagram Borated Refueling
Water Storage System
M-12EN01
Piping & Instrumentation Diagram Containment Spray
System
M-12FC02
Piping & Instrumentation Diagram Auxiliary Feedwater
Pump Turbine
M-12FC05
Piping & Instrumentation Diagram Auxiliary Turbines
SGFP Turbine A
M-12FC06
Piping & Instrumentation Diagram Auxiliary Turbines
SGFP Turbine B
M-K2EF01
Piping & Instrumentation Diagram Essential Service
Water Sys.
Condition Reports
130240
Miscellaneous
Documents
Number
Title
Revision
or Date
APF 15C-002-01
Procedure Cover Sheet - Fire Pump Operations -
SYS FP-293
2/19/2019
APF 21-001-02
Control Room Turnover Checklist: Day Shift
2/19/2019
APF 21-001-02
Control Room Turnover Checklist: Night Shift
2/20/2019
APF 22C-003-01
On-Line Nuclear Safety and Generation Risk
Assessment: Schedule Week 19-0108
2/18/2019 to
2/24/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Containment
Spray Pump A Inservice Pump Test
01/16/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): ESW
System Valve
01/29/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Safety
Injection Pump A Inservice Pump Test
01/16/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Turbine
Driven Auxiliary Feedwater System Inservice Valve
Test
11/30/2018
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Turbine
Driven AFW Pump Inservice Pump Test
2/27/2019
STN FP-211
Diesel Fire Pump 1FP01PB Monthly Operation and
Fuel Level Check
2/29/2019
STS EF-100B
Surveillance Test Routing Sheet (STRS): ESW
System Inservice Pump B & ESW B Check Valve
01/29/2019
WCRE-34
Fourth Ten Year Interval Inservice Testing Program
71111.22Surveillance Testing
Procedures
Number
Title
Revision
Containment Entry
18A
I-ENG-003
Vibration Monitoring and Analysis
STN KU-010
Station Blackout Diesel and Non-Safety AFW Pump
Test
STN SF-001
Control Rod Parking
STS BB-006
RCS Water Inventory Balance Using the NPIS
Computer
19A
STS IC-217
RCP Loss of Voltage and Underfrequency TADOT
15C
STS IC-909B
Accumulator Pressure Instrumentation Channel
Calibration
STS KJ-005B
Manual/Auto Start, Sync & Loading of EDG NE02
STS SF-001
Control and Shutdown Rod Operability Verification
Drawings
Number
Title
Revision
E-13EJ08
Schematic Diagram Residual Heat Removal Pump
Miniflow Valve EJFCV0610
M-12EJ01
Piping and Instrumentation Diagram Residual Heat
Removal System
M-13EJ03
Piping Isometric Residual Heat Removal System
Auxiliary Building - A and B Train
Condition Reports
29583
29991
29992
130583
130759
130767
Miscellaneous
Documents
Number
Title
Revision
or Date
Vibration Alert/Action Criteria
Level of Effort Evaluation - Proposed Traditional
Violation Unfettered Access NRC: CR 130158
APF 15C-002-01
Procedure Cover Sheet - Diesel Generator NE01 and
NE02 Lineup for Automatic Operation
2A
APF 15C-002-01
Procedure Cover Sheet - Post Maintenance Run of
Emergency Diesel Generator B - SYS KJ-124
APF 15C-004-01
Document Revision Request (DRR): RCS Water
Inventory Balance Using the NPIS Computer
APF 15C-004-01
Document Revision Request (DRR): RCS Water
Inventory Balance Using the NPIS Computer
APF 25A-401-01
ALARA Review Package: 190036
09/17/2018
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Control and
Shutdown Rod Operability Verification
01/17/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Control Rod
Parking
01/17/2019
APF 29B-00-01
Surveillance Test Routing Sheet (STRS): RCS Water
Inventory Balance Using the NPIS Computer
2/01/2019
APF 29B-00-01
Surveillance Test Routing Sheet (STRS): RCS Water
Inventory Balance Using the NPIS Computer
2/01/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): RHR System
Inservice Pump Test
01/09/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Manual/Auto
Start, Synchronization & Loading of Emergency D/G
NE02
03/06/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Station
Blackout Diesel and Non-Safety AFW Pump Test
03/11/2019
APF 29B-003-01
Surveillance Test Routing Sheet (STRS): Train B RHR
System Inservice Valve Testing
01/09/2019
Miscellaneous
Documents
Number
Title
Revision
or Date
RPF 02-105-01
Radiation Work Permit: 190036
000
RPF 02-210-01
WCGS Radiological Survey Map: 2000 Containment -
Survey #M-20181031-6
10/31/2018
RPF 02-210-01
WCGS Radiological Survey Map: Map 1: 2068
Containment - Survey #M-20181031-7
10/31/2018
RPF 02-210-01
WCGS Radiological Survey Map: Map 2: 2047
Containment - Survey #M-20181031-7
10/31/2018
RPF 02-210-01
WCGS Radiological Survey Map: Map 1: Containment
Personnel Hatch-Survey #M-20180531-8
05/31/2018
RPF 02-210-01
WCGS Radiological Survey Map: Map 2: 2026
Containment - Survey #M-20180531-8
05/31/2018
M-018-00309
Instruction Manual for Emergency Diesel Generator
System
W139
71114.06Drill Evaluation
Procedures
Number
Title
Revision
EPP 06-006
Protective Action Recommendations
Condition Reports
29197
29732
29734
29735
29736
29739
29740
29741
29742
29745
29749
29751
29754
29770
29774
29783
29856
130241
130280
130281
130282
130283
130284
130286
130287
130290
130291
130293
130294
130296
130300
130301
130303
130304
130305
130306
130307
130308
130309
130310
130312
130313
130314
Miscellaneous
Documents
Number
Title
Revision
or Date
19-SA-01
Wolf Creek Generating Station Emergency Planning Drill 02/21/2019
APF 06-002-03
EAL Classification Matrix - All Conditions
OA
APF 06-002-03
EAL Classification Matrix - All Conditions
OB
APF 06-002-03
EAL Classification Matrix - Cold Conditions
OA
APF 06-002-03
EAL Classification Matrix - Hot Conditions
OA
EPF 06-007-02
WCGS Immediate Emergency Notification - Message
No. CR-001
Miscellaneous
Documents
Number
Title
Revision
or Date
EPF 06-007-02
WCGS Immediate Emergency Notification - Message
No. EOF-001
EPF 06-007-02
WCGS Immediate Emergency Notification - Message
No. EOF-002
EPF 06-007-02
WCGS Immediate Emergency Notification - Message
No. EOF-003
EPF 06-007-02
WCGS Immediate Emergency Notification - Message
No. EOF-004
EPF 06-007-02
WCGS Immediate Emergency Notification - Message
No. TSC-002
EPF 06-007-03
WCGS Follow-Up Emergency Notification - Message
No. EOF-001
EPF 06-007-03
WCGS Follow-Up Emergency Notification - Message
No. EOF-002
EPF 06-007-03
WCGS Follow-Up Emergency Notification - Message
No. EOF-003
EPF 06-007-03
WCGS Follow-Up Emergency Notification - Message
No. TSC-001
EPF 06-013-04
Potassium Iodide Issue Record
71124.02 - Occupational ALARA Planning and Controls
Procedures
Number
Title
Revision
Radiation Protection Manual
ALARA Program
ALARA Committee
Radiation Worker Guidelines
RWP Program
24A
RPP-03-105
Radiological Work Permits
Audits and Self-Assessments
Number
Title
Date
18-01-RP/PC
Quality Assurance Audit Report: Radiological
Protection/Process Control
2/15/2018
QH-2018-1558
RP Effectiveness Implementing Stop Work Criteria
05/24/2018
QH-2019-1811
Quick Hit Assessment: NRC IP 71124.02 Assessment
2/07/2019
Corrective Action Reports (CRs)
113708
113736
113752
28580
29938
29940
29941
130433
Radiation Work Permits, ALARA Planning, In-Progress Reviews
Number
Title
Revision
183000
RFO 22 - Non-Destructive Testing ISI Exams
183220
RFO 22 - Primary Side Steam Generator Eddy Current Tests
184420
RFO 22 - Maintenance Support Scaffolding
186020
RFO 22 - Reactor Head and All Associated Work Activities
Miscellaneous Documents
Number
Title
Date
RF22 RP Summary Report
Scaling Factors - 10CFR Part 61 Waste Stream Sample
Screening and Evaluation
2/02/2108
Source Term Reduction Strategy: 5-Year Update
03/11/2019
WF3 2019 Radiation Work Permit Totals (millirem)
01/13/2019
WF3 Site Dose Totals Online/Outage for the past 3 years
(dose in Person-Rem)
01/09/2019
71124.04 - Occupational Dose Assessment
Procedures
Number
Title
Revision
RPP-01-105
Health Physics Organization, Responsibilities, and Code of
Conduct
RPP 03-121
Determination of Neutron Dose
RPP 03-122
Skin Dose Calculations
13A
RPP 03-205
DAC-Hour Tracking
17A
RPP 03-210
Internal Exposure Calculations and Evaluations
17A
RPP 03-215
Collection of Bioassay Samples
8B
RPP 03-406
RP Dosimetry / Records
RPP 05-707
Operation of Whole Body Counters
Audits and Self-Assessments
Number
Title
Date
18-01-RP/PC
Quality Assurance Audit Report: Radiological
Protection/Process Control
2/15/2018
QH-2017-1558
Benchmarking NRC PI Effectiveness
2/21/2017
QH-2019-1801
Quick Hit Assessment: NRC IP 71124.04 Assessment
2/07/2019
Corrective Action Reports (CRs)
113730
113756
113973
117700
118254
21163
21171
21729
Corrective Action Reports (CRs)
2130
2348
25779
26076
26614
27562
27564
29934
CFR Part 61 Waste Stream Analysis Reports
Number
Title
Date
446223
Dry Active Waste
03/12/2018
446223
RCS Filters
03/01/2018
446223
SFP Filters
2/28/2018
447547
CVCS Resins
03/27/2018
447769
Drum Dryer Waste Tank
03/12/2018
447769
Radwaste Resin
03/27/2018
Neutron Dose Assessments
Number
Title
Date
RWP-17-0036
Containment Entries at Power
2/31/2017
RWP-17-0036
Containment Entries at Power
03/10/2019
RWP-18-0036
Containment Entries at Power
2/31/2018
Dose Assessment and Air Sample Surveys
Number
Title
Date
18-0181
Air Sample:
04/20/2018
18-0631
Air Sample:
04/20/2018
18-0639
Air Sample:
04/20/2018
18-0665
Air Sample:
04/20/2018
ACAD 1356
Air Sample:
04/20/2018
ACAD 2364
Air Sample:
04/20/2018
ACAD 3933
Air Sample:
04/20/2018
ACAD 3635
Air Sample:
04/20/2018
Positive Whole-Body Counts (ACAD No.)
Number
Title
Date
1174
Airborne Radiodine Activity in Containment
04/20/2018
7657
Airborne Radiodine Activity in Containment
04/12/2018
23
Airborne Radiodine Activity in Containment
04/18/2018
Miscellaneous Documents
Number
Title
Date
2018 Whole Body Counting Reports
06/16/2017 to
2/25/2019
Dose Assessment Records for 5 Radworkers
05/21/2018
Miscellaneous Documents
Number
Title
Date
2018 Whole Body Counting Reports
06/16/2017 to
2/25/2019
17025:2005
NVLAP Certificate of Accreditation - Ionizing Radiation
Dosimetry
2/17/2018
TSC No.14-043 Neutron Dosimetry Evaluation at WCGS
04/30/2014
71151Performance Indicator Verification
Condition Reports
25935
25943
Miscellaneous
Documents
Number
Title
Date
Functional Failure Determination Checklist for AAPL -
CR 125935
08/30/2018
Functional Failure Determination Checklist for OF -
CR 125943
09/05/2018
Interoffice Correspondence - Plant Health Committee
Meeting Minutes
08/27/2018
71152Problem Identification and Resolution
Procedures
Number
Title
Revision
AP 06-002
Radiological Emergency Response Plan
AP 06-002
Radiological Emergency Response Plan
EMG F-0
Critical Safety Function Status Trees (CSFST)
EPP 06-005
Emergency Classification
Calculations
Number
Title
Revision
XX-E-009 CN003
System NB, NG, PG, Under Voltage/Degraded Voltage
XX-E-009 CN004
System NB, NG, PG, Under Voltage/Degraded Voltage
XX-E-009 CN006
System NB, NG, PG, Under Voltage/Degraded Voltage
Condition Reports
47771
103562
103849
104098
104139
104253
104266
104389
28267
29197
29228
29344
29904
Miscellaneous
Documents
Number
Title
Revision
or Date
Administrative Controls Page SR 3.3.5.3
Wolf Creek Generating Station - Issuance of
Amendment Regarding Emergency Action Level
Scheme Change (CAC No. MF8450)
08/28/2017
Procedure Users Guide for Abnormal Plant Conditions
APF 06-002-01
Emergency Action Levels
17A
APF 06-002-02
Emergency Action Levels Technical Bases
0A
APF 06-002-02
Emergency Action Levels Technical Bases
0B
APF 06-002-03
EAL Classification Matrix
0A
APF 06-002-03
EAL Classification Matrix
0B
HP-Rev. 3
Background Information for Westinghouse Owners
Group Emergency Response Guideline, FR-P.1,
Response to Imminent Pressurized Thermal Shock
03/31/2014
LO1732349
Lesson Plan, EMG FR-P1/P2 Pressurized Thermal
Shock
LR0010700
Lesson Plan, Mitigating Core Damage
LR1432305
Lesson Plan, EMG FR-P (Integrity) Series Procedures
000A
A Generic Assessment of Significant Flaw Extension,
Including Stagnant Loop Conditions, From Pressurized
Thermal Shock of Reactor Vessels on Westinghouse
Nuclear Power Plants
2/00/1983
Docket No. 50-482: Request to Adopt Emergency Action
Level Scheme Pursuant to NEI 99-01, Revision 6,
Development of Emergency Action Levels for Non-
Passive Reactors
09/30/2016
Docket No. 50-482: Response to Request for Additional
Information Regarding Adopting New EAL Scheme
03/16/2017
Docket No. 50-482: Supplement to RAI Response
Regarding Adopting New EAL Scheme
04/26/2017
The following items are requested for the
Occupational Radiation Safety Inspection
at Wolf Creek Generating Station
March 11 thru 15, 2019
Integrated Report 2019001
Inspection areas are listed in the attachments below.
Please provide the requested information on or before March 5, 2019.
Please submit this information using the same lettering system as below. For example, all
contacts and phone numbers for Inspection Procedure 71124.01 should be in a file/folder titled
1-A, applicable organization charts in file/folder 1-B, etc.
If information is placed on a regulatory compliance data management system, please ensure
the inspection exit date entered is at least 30 days later than the onsite inspection dates, so the
inspectors 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 Louis Carson at 817-200-1221 or
louis.carson@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: June 16, 2017
A.
List of contacts and telephone numbers for ALARA program personnel
B.
Applicable organization charts
C.
Copies of audits, self-assessments, and LERs, written since date of last inspection,
focusing on ALARA
D.
Procedure index for ALARA Program
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 Committee
3. Radiation Work Permit Preparation
F.
A summary list of corrective action documents (including corporate and sub-tiered
systems) written since date of last inspection, related to the ALARA program. In addition
to ALARA, the summary should also address Radiation Work Permit violations,
Electronic Dosimeter Alarms, and RWP Dose Estimates
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
G.
List of work activities greater than 1 rem, since date of last inspection,
Include original dose estimate and actual dose.
H.
Site dose totals and 3-year rolling averages for the past 3 years (based on dose of
record)
I.
Outline of source term reduction strategy
J.
If available, provide a copy of the ALARA outage report for the most recently completed
outages for each unit
K.
Please provide your most recent Annual ALARA Report.
4. Occupational Dose Assessment (Inspection Procedure 71124.04)
Date of Last Inspection: June 16, 2017
A.
List of contacts and telephone numbers for the following areas:
1. Dose Assessment personnel
B.
Applicable organization charts
C.
Audits, self-assessments, vendor or NUPIC audits of contractor support, and LERs
written since date of last inspection, related to:
1. Occupational Dose Assessment
D.
Procedure indexes for the following areas:
1. Occupational Dose Assessment
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. Radiological Posting and Warning Devices
5. Air Sample Analysis
6. Performance of High Exposure Work
7. Declared Pregnant Worker
8. Bioassay Program
F.
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: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
G.
List of positive whole body counts since date of last inspection, names redacted if
desired
H.
Part 61 analyses/scaling factors
I.
The most recent National Voluntary Laboratory Accreditation Program (NVLAP)
accreditation report or, if dosimetry is provided by a vendor, the vendors most recent
results
SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword:
By: NHT Yes No
Publicly Available Sensitive
OFFICE
SRI:DRP/B
RI:DRP/B
C:DRS/OB
C:DNMS/RIB
C:DRS/EB1
C:DRS/EB2
NAME
DDodson
FThomas
GWerner
GWarnick
VGaddy
JDrake
SIGNATURE
DED
GEW
GXW
vgg
JFD
DATE
5/6/19
05/07/19
04/29/2019
5/7/19
4/30/19
4/29/19
OFFICE
C:DRS/RCB
TL:DRS/IPAT
BC:DRP/B
NAME
NMakris
RKellar
NTaylor
SIGNATURE
NJM
RLK
NHT
DATE
4/29/19
04/29/2019
5/7/19