Text

NRC Integrated Inspection Report 05000482/2019001 (EA-19-023)
	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)
	v • d • e

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

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number: 05000482 License Number: NPF-42 Report Number: 05000482/2019001 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 Enclosure

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: 71152.

List of Findings and Violations Failure to Provide Unfettered Access to an NRC Resident Inspector Cornerstone Severity Cross-cutting Inspection Aspect Procedure Not Applicable Severity Level IV Not Applicable 71111.22 -

NCV 05000482/2019001-01 Surveillance Closed 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)

Main article: IP 71111.01

The inspectors evaluated summer readiness of offsite and alternate alternating current (AC)power systems.

71111.04 - Equipment Alignment Partial Walkdown (IP Section 02.01)

Main article: IP 71111.04

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)

Main article: IP 71111.05Q

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)

Main article: IP 71111.11Q

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)

Main article: IP 71111.12

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)

Main article: IP 71111.13

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)

Main article: IP 71111.15

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)

Main article: IP 71111.19

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)

Main article: IP 71111.22

(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)

Main article: IP 71114.06

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)

Main article: IP 71124.02

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 186020, "ALARA Review Package Reactor Vessel Head"

RWP 183000, "Non-Destructive Testing/ISI"

RWP 183220, "Primary Steam Generator Eddy Current Testing" Additionally, the inspectors reviewed the following radiological outcome evaluations:

RWP 186020, "In-Progress and Post ALARA Review"

RWP 184420, "Maintenance Support/Scaffolding In-Progress and Post ALARA"

RWP 183220, "Primary Steam Generator Eddy Current Testing"

71124.04 - Occupational Dose Assessment External Dosimetry (IP Section 02.02)

Main article: IP 71124.04

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) ===

Main article: IP 71151

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)

Main article: IP 71152

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 Inspection Aspect Procedure Not Applicable Severity Level IV Not

71111.22 - NCV 05000482/2019001-01 Applicable Surveillance

Closed 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 69

KD-7496A Distribution System Equipment Lineup Limitations 10

71111.04Equipment Alignment

Procedures

Number Title Revision

CKL EC-120 Fuel Pool Cooling and Cleanup System Normal Valve 18A

Lineup/Breaker Checklist

CKL EG-120 Component Cooling Water System Valve, Switch and 49

Breaker Lineup

CKL EJ-120 RHR System Lineup 46

CKL KA-120 Compressed Air Valve, Breaker and Switch Lineup 36A

SYS EC-121 Recirc of the RWST Through The Fuel Pool Cleanup 21

System

SYS EC-201 Filling Spent Fuel Pool From Reactor Makeup Water 6

SYS KA-201 Instrument Air Dryer Operation 18

Drawings

Number Title Revision

M-12BN01 Piping & Instrumentation Diagram Borated Refueling 18

Water Storage System

M-12EC01 Piping & Instrumentation Diagram Fuel Pool Cooling and 23

Clean-Up System

M-12EC02 Piping & Instrumentation Diagram Fuel Pool Cooling and 7

Clean-Up System

M-12EJ01 Piping & Instrumentation Diagram Residual Heat 55

Removal System

M-12EG01 Piping & Instrumentation Diagram Component Cooling 24

Water System

M-12KA01 Piping & Instrumentation Diagram Compressed Air 34

System

M-12KA02 Piping & Instrumentation Diagram Compressed Air 31

System (Service Air)

Condition Reports

131029

Miscellaneous

Documents

Number Title Date

APF 21-001-02 Control Room Turnover Checklist - On-Coming 03/22/2019

CRS/WC SRO/RO/BOP Review - Night Shift

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk 03/18/2019 to

Assessment: Schedule Week 19-0112 03/24/2019

71111.05AQFire Protection Annual/Quarterly

Procedures

Number Title Revision

AP 10-106 Fire Preplans 18A

Miscellaneous

Documents Revision

Number Title or Date

APF 10-105-02 Fire Drill Scenario and Critique Report: 1974 Aux 02/08/2019

Building PC Storage Area

APF 10-105-02 Fire Drill Scenario and Critique Report: 1974 Aux 02/08/2019

Building PC Storage Area: Backshift

E-1F9905 Fire Hazard Analysis 10

71111.11Licensed Operator Requalification Program and Licensed Operator Performance

Procedures

Number Title Revision

AI 30B-015 Licensed Operator Requalification Examination 12

Guidelines

Miscellaneous

Documents

Number Title Date

APF 30E-003-05 Lesson Plan Coversheet - Simulator Discovery 01/29/2019

Scenario

STS NB-005 Surveillance Test Routing Sheet (STRS) - Breaker 03/04/2019

Alignment Verification

71111.12Maintenance Effectiveness

Drawings

Number Title Revision

M-12KA01 Piping & Instrumentation Diagram Compressed Air 33

System

M-12KA04 Piping & Instrumentation Diagram Instrument Air System 21

Condition Reports

28929 128970 130277 130471

Miscellaneous

Documents Revision

Number Title or Date

Final Scope Evaluation - Pending MREP Approval: 03/26/2019

EF - Essential Service Water

Functional Failure Determination Checklist for KA - 10/17/2018

CR 126897

Functional Failure Determination Checklist for KA - 01/23/2019

CR 128929

Maintenance Rule Expert Panel Meeting Agenda 02/19/2019

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 1

71111.13Maintenance Risk Assessments and Emergent Work Control

Procedures

Number Title Revision

AI 22C-013 Protected Equipment Program 22

AP 10-103 Fire Protection Impairment Control 33

AP 22C-003 On-Line Nuclear Safety and Generation Risk 22

Assessment

Condition Reports

130240

Work Orders

17-431786-006

Miscellaneous

Documents Revision

Number Title or Date

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk 01/07/2019 to

Assessment: Schedule Week 2019-0102 01/13/2019

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk 02/11/2019 to

Assessment: Schedule Week 19-0105 02/17/2019

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk 01/27/2019 to

Assessment: Schedule Week 19-0107 02/02/2019

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk 03/04/2019 to

Assessment: Schedule Week 2019-0110 03/10/2019

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk 03/11/2019 to

Assessment: Schedule Week 2019-0111 03/17/2019

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk 03/25/2019 to

Assessment: Schedule Week 19-0113 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 6

AP 26C-004 Operability Determination and Functionality Assessment 37

MPE NE-004 Alternator Inspection 14

Condition Reports

29066 129758 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 Revision

Number Title or Date

10466-E-029 Technical Specification for 5,000-Volt and 15,000Volt 9

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 48

STN AL-201 Auxiliary Feedwater System Valve Test 8

STN FP-211 Diesel Fire Pump 1FP01PB Monthly Operation and Fuel 41

Level Check

STS AB-201B TDAFP Steam Isolation Inservice Valve Test 11

STS AL-103 TDAFW Pump Inservice Pump Test 73B

STS AL-201C Turbine Driven Auxiliary Feedwater System Inservice 12

Valve Test

STS EN-100A Containment Spray Pump A Inservice Pump Test 29

STS IC-208B 4KV Loss of Voltage & Degraded Voltage TADOT NB02 5

BUS - SEP GRP 4

STS PE-052A Auxiliary Feedwater Pump Turbine Pressure Test 9

STS PE-007 Periodic Verification of Motor Operated Valves 5A

Drawings

Number Title Revision

E-K3EF06 Schematic Diagram ESW Pump Discharge Air Release 11

Valve

M-0023 P&ID Fire Protection System (FP) 70

M-12AB01 Piping & Instrumentation Diagram Main Steam System 16

M-12AB02 Piping & Instrumentation Diagram Main Steam System 15

M-12AB03 Piping & Instrumentation Diagram Main Steam System 24

M-12AL01 Piping & Instrumentation Diagram Auxiliary Feedwater 29

System

M-12BN01 Piping & Instrumentation Diagram Borated Refueling 18

Water Storage System

M-12EN01 Piping & Instrumentation Diagram Containment Spray 14

System

M-12FC02 Piping & Instrumentation Diagram Auxiliary Feedwater 25

Pump Turbine

M-12FC05 Piping & Instrumentation Diagram Auxiliary Turbines 2

SGFP Turbine A

M-12FC06 Piping & Instrumentation Diagram Auxiliary Turbines 2

SGFP Turbine B

M-K2EF01 Piping & Instrumentation Diagram Essential Service 70

Water Sys.

Condition Reports

130240

Miscellaneous

Documents Revision

Number Title or Date

APF 15C-002-01 Procedure Cover Sheet - Fire Pump Operations - 02/19/2019

SYS FP-293

APF 21-001-02 Control Room Turnover Checklist: Day Shift 02/19/2019

APF 21-001-02 Control Room Turnover Checklist: Night Shift 02/20/2019

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk 02/18/2019 to

Assessment: Schedule Week 19-0108 02/24/2019

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): Containment 01/16/2019

Spray Pump A Inservice Pump Test

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): ESW 01/29/2019

System Valve

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): Safety 01/16/2019

Injection Pump A Inservice Pump Test

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): Turbine 11/30/2018

Driven Auxiliary Feedwater System Inservice Valve

Test

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): Turbine 02/27/2019

Driven AFW Pump Inservice Pump Test

STN FP-211 Diesel Fire Pump 1FP01PB Monthly Operation and 02/29/2019

Fuel Level Check

STS EF-100B Surveillance Test Routing Sheet (STRS): ESW 01/29/2019

System Inservice Pump B & ESW B Check Valve

WCRE-34 Fourth Ten Year Interval Inservice Testing Program 10

71111.22Surveillance Testing

Procedures

Number Title Revision

AP 25A-100 Containment Entry 18A

I-ENG-003 Vibration Monitoring and Analysis 9

STN KU-010 Station Blackout Diesel and Non-Safety AFW Pump 11

Test

STN SF-001 Control Rod Parking 21

STS BB-006 RCS Water Inventory Balance Using the NPIS 19A

Computer

STS IC-217 RCP Loss of Voltage and Underfrequency TADOT 15C

STS IC-909B Accumulator Pressure Instrumentation Channel 7

Calibration

STS KJ-005B Manual/Auto Start, Sync & Loading of EDG NE02 64

STS SF-001 Control and Shutdown Rod Operability Verification 29

Drawings

Number Title Revision

E-13EJ08 Schematic Diagram Residual Heat Removal Pump 6

Miniflow Valve EJFCV0610

M-12EJ01 Piping and Instrumentation Diagram Residual Heat 55

Removal System

M-13EJ03 Piping Isometric Residual Heat Removal System 10

Auxiliary Building - A and B Train

Condition Reports

29583 129991 129992 130583 130759

130767

Miscellaneous

Documents Revision

Number Title or Date

Vibration Alert/Action Criteria 50

AIF 28A-100-27 Level of Effort Evaluation - Proposed Traditional 0

Violation Unfettered Access NRC: CR 130158

APF 15C-002-01 Procedure Cover Sheet - Diesel Generator NE01 and 52A

NE02 Lineup for Automatic Operation

APF 15C-002-01 Procedure Cover Sheet - Post Maintenance Run of 69

Emergency Diesel Generator B - SYS KJ-124

APF 15C-004-01 Document Revision Request (DRR): RCS Water 18

Inventory Balance Using the NPIS Computer

APF 15C-004-01 Document Revision Request (DRR): RCS Water 19

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 01/17/2019

Shutdown Rod Operability Verification

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): Control Rod 01/17/2019

Parking

APF 29B-00-01 Surveillance Test Routing Sheet (STRS): RCS Water 02/01/2019

Inventory Balance Using the NPIS Computer

APF 29B-00-01 Surveillance Test Routing Sheet (STRS): RCS Water 02/01/2019

Inventory Balance Using the NPIS Computer

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): RHR System 01/09/2019

Inservice Pump Test

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): Manual/Auto 03/06/2019

Start, Synchronization & Loading of Emergency D/G

NE02

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): Station 03/11/2019

Blackout Diesel and Non-Safety AFW Pump Test

APF 29B-003-01 Surveillance Test Routing Sheet (STRS): Train B RHR 01/09/2019

System Inservice Valve Testing

Miscellaneous

Documents Revision

Number Title or Date

RPF 02-105-01 Radiation Work Permit: 190036 000

RPF 02-210-01 WCGS Radiological Survey Map: 2000 Containment - 10/31/2018

Survey #M-20181031-6

RPF 02-210-01 WCGS Radiological Survey Map: Map 1: 2068 10/31/2018

Containment - Survey #M-20181031-7

RPF 02-210-01 WCGS Radiological Survey Map: Map 2: 2047 10/31/2018

Containment - Survey #M-20181031-7

RPF 02-210-01 WCGS Radiological Survey Map: Map 1: Containment 05/31/2018

Personnel Hatch- Survey #M-20180531-8

RPF 02-210-01 WCGS Radiological Survey Map: Map 2: 2026 05/31/2018

Containment - Survey #M-20180531-8

M-018-00309 Instruction Manual for Emergency Diesel Generator W139

System

71114.06Drill Evaluation

Procedures

Number Title Revision

EPP 06-006 Protective Action Recommendations 10

Condition Reports

29197 129732 129734 129735 129736

29739 129740 129741 129742 129745

29749 129751 129754 129770 129774

29783 129856 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 Revision

Number Title 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