IR 05000346/2019002

Integrated Inspection Report 05000346/2019002

ML19214A124
Person / Time
Site:	Davis Besse
Issue date:	08/01/2019
From:	Billy Dickson NRC/RGN-III/DRP/B2
To:	Bezilla M FirstEnergy Nuclear Operating Co
References
IR 2019002
Download: ML19214A124 (23)

Text

ust 1, 2019

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATIONINTEGRATED INSPECTION REPORT 05000346/2019002

Dear Mr. Bezilla:

On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On July 18, 2019, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Davis-Besse Nuclear Power 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 III; and the NRC Resident Inspector at Davis-Besse. 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/

Billy C. Dickson, Chief Branch 2 Division of Reactor Projects Docket No. 05000346 License No. NPF-3

Enclosure:

As stated

Inspection Report

Docket Number: 05000346 License Number: NPF-3 Report Number: 05000346/2019002 Enterprise Identifier: I-2019-002-0064 Licensee: FirstEnergy Nuclear Operating Co.

Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Inspection Dates: April 01, 2019 to June 30, 2019 Inspectors: J. Cassidy, Senior Health Physicist J. Harvey, Resident Inspector V. Meghani, Reactor Inspector D. Mills, Senior Resident Inspector J. Rutkowski, Project Engineer J. Steffes, Senior Resident Inspector Approved By: Billy C. Dickson, JR, Chief Branch 2 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Davis-Besse Nuclear Power Station 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 Failure to Follow the Train 2 Containment Radiation Monitor Surveillance Procedure Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.5] - Work 71152 Systems NCV 05000346/2019002-01 Management Open/Closed A Green finding with an associated non-cited violation of Title 10 CFR Part 50, Appendix B,

Criterion V, "Instructions, Procedures, and Drawings," was self-revealed on April 9, 2019, when the licensee failed to accomplish the train 2 normal containment radiation monitor surveillance in accordance with the appropriate procedure.

Additional Tracking Items None.

PLANT STATUS

The Unit reduced power to nine percent on June 1, 2019, for planned control rod drive and turbine valve testing and returned to full power on June 2, 2019. Otherwise, the Unit operated at or near full rated thermal power for the entire inspection period.

On April 25, 2018, FirstEnergy Solutions (FES) / FirstEnergy Nuclear Operating Company (FENOC) notified the U.S. Nuclear Regulatory Commission (NRC) that they intend to shut down all four of their operating nuclear power plants (ADAMS Accession Number ML18115A007).

Based on that notification, the first to shut down will be Davis-Besse, by May 31, 2020. On March 31, 2018, FES, FirstEnergy Nuclear Generation (FENGEN), and FENOC filed for bankruptcy. The NRC continues to maintain focus on public health and safety and the protection of the environment. This will include a continuous evaluation by inspectors to determine whether the licensees financial condition is impacting safe operation of the plant.

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.

71111.01 - Adverse Weather Protection

Summer Readiness Sample (IP Section 03.01)

(1) The inspectors evaluated summer readiness of offsite and alternate Alternating Current (AC) power systems during the week ending May 25, 2019

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) High Pressure Injection train 1 following planned testing during the week ending April 27, 2019

(2) Emergency Diesel Generator 1 during Safety Features Actuation System Channel 2 testing during the week ending May 18, 2019

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

(1) Decay Heat/Low Pressure Injection system during the week ending June 8, 2019

71111.05Q - Fire Protection

Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Service Water Pipe Tunnel, Fire Area BG, during the week ending May 11, 2019

(2) Service Water Pump Room, Fire Area BF, during the week ending May 11, 2019

(3) Mechanical Penetration Room 3 and Corridor to Mechanical Penetration Rooms 3 and 4, Fire Areas AB and V, during the week ending April 27, 2019

(4) Electrical Penetration Room 1, Fire Area DG, during the week ending May 18, 2019

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 02.02a.)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Emergency Diesel Generator 1 and 2 rooms during the week ending May 25, 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) Reactor power reduction and control rod exercising on June 1, 2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator requalification activities in the simulator on May 14, 2019

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Component Cooling Water train 2 isolated due to Component Cooling Water Heat Exchanger 2 Outlet Isolation Valve Leak-By during the week ending April 13, 2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Start-Up Transformer X01 planned outage concurrent with unexpected loss of the Lemoyne line during the week ending May 4, 2019

(2) Start-Up Transformer X02 planned outage and Electro-Hydraulic Control accumulator pressure check activities during the week ending May 18, 2019

(3) Emergency Diesel Generator 1 unavailable during planned testing and subsequent turbine generator planned maintenance during the week ending June 1, 2019

(4) Pressurizer Essential Heater bank 1 emergent work concurrent with Component Cooling Water heat exchanger 2 outlet isolation valve planned maintenance during the week ending June 8, 2019

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) CR 2019-04242, Service Water valve SW280, containment air cooler 2 service water, leaking by closed seat during the week ending June 1, 2019

(2) CR 2019-04973, Emergency Diesel Generator 2, 184-Day Test with unexpected speed and voltage variations during the week ending June 8, 2019

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

The inspectors evaluated the following temporary or permanent modifications:

(1) Engineering Change Package 17-0397-001, Steam Generator operate range indication adjusted down 3 percent, during the week ending May 25, 2019

71111.19 - Post-Maintenance Testing

Post Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance tests:

(1) Emergency Diesel Generator 2 Testing following Seal-In Contact Replacement during the week ending June 8, 2019

(2) Pressurizer Essential Heater Testing following modification during the week ending June 8, 2019

(3) Safety Features Actuation System Channel 1 Testing following Power Supply Replacement during the week ending June 22, 2019

71111.22 - Surveillance Testing

===The inspectors evaluated the following surveillance tests:

Containment Isolation Valve Testing (IP Section 03.01)===

(1) Containment Personnel Hatch Local Leak Rate Testing following Containment Entry during the week ending June 8, 2019

Inservice Testing (IP Section 03.01) (2 Samples)

(1) High Pressure Injection 1 Quarterly Test during the week ending April 27, 2019

(2) High Pressure Injection 2 Quarterly Test during the week ending May 18, 2019

Surveillance Tests (other) (IP Section 03.01) (3 Samples)

(1) Reactor Protection System Channel 1, Reactor Trip Breaker B testing during the week ending April 27, 2019

(2) Auxiliary Feedwater Pump train 2 Monthly Test during the week ending May 11, 2019

(3) Auxiliary Feedwater train 1 Level Control, Interlock, and Flow Transmitter Test during the week ending May 4,

71124.05 - Radiation Monitoring Instrumentation

Calibration and Testing Program (IP Section 02.02)

The inspectors evaluated the calibration and testing program implementation.

(1) Alarm setpoint and calibration method check of personnel contamination monitors, portal monitors and small article monitors

• Small Article Monitors; SAM-11

• Personnel Contamination Monitor; ARGOS-5AB

• Portal Monitor; GEM-5 Failure to meet calibration or source check acceptance criteria

• None were available during this inspection

Walkdowns and Observations (IP Section 02.01) (1 Sample)

The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.

(1) Portable survey instruments

• Telepole Number LI 2.7.584

• Fluke 451B Number LI 2.7.518

• Fluke 451B Number LI 2.7.513

• Fluke 451B Number LI 2.7.521

• Fluke 451P Number LI 2.7.614

• Ludlum Model 12 Number LI 2.7.622 Source check demonstration

• Fluke 451B

• Fluke 451P

• Telepole Area radiation monitors and continuous air monitors

• Continuous Air Monitor; AMS-4, 411 Chemistry Corridor

• Continuous Air Monitor; AMS-4, Spent Fuel Pool Area

• Area Radiation Monitor; RE/RI 2387A, Containment Equiptment Hatch

• Area Radiation Monitor; RE/RI 8417A, Fuel Handling Area

• Area Radiation Monitor; RE/RI 8421, Penetration Room

• Area Radiation Monitor; RE/RI 8420, Penetration Room

• Area Radiation Monitor; RE/RI 8429, 411 Chemistry Corridor Personnel contamination monitors, portal monitors and small article monitors

• Personnel Contamination Monitor; ARGOS-5AB, LI 2.12.106

• Portal Monitor; GEM-5, LI 2.12.94

• Small Article Monitors; SAM-11, LI 2.12.86

• Small Article Monitor; Cronos-4, LI

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) ===

(1) (April 2018 to April 2019)

MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)

(1) (April 2018 to April 2019)

MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)

(1) (April 2018 to April 2019)

71152 - Problem Identification and Resolution

Annual Follow-Up of Selected Issues (IP Section 02.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) CR 2019-03346, unexpected annunciator 7-6-C, RAD (radiation) monitor system trouble Ch 1 (channel 1)

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60854.1 - Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants Pre-Operational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants (1 Partial)

(1) (Partial)

This inspection is on-going and is anticipated to be documented in Inspection Report 2019004.

60856.1 - Review of 10 CFR 72.212(b) Evaluations at Operating Plants Review of 10 CFR 72.212(b) Evaluations at Operating Plants (1 Partial)

(1) (Partial)

This inspection is on-going and is anticipated to be documented in Inspection Report

INSPECTION RESULTS

Failure to Follow the Train 2 Containment Radiation Monitor Surveillance Procedure Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.5] - Work 71152 Systems NCV 05000346/2019002-01 Management Open/Closed A Green finding with an associated non-cited violation of Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was self-revealed on April 9, 2019, when the licensee failed to accomplish the train 2 Normal Containment Radiation Monitor Surveillance in accordance with the appropriate procedure.

Description:

On April 9, 2019, the licensee was performing surveillance test DB-SC-03213, Monthly Functional Test of RE4597BA, CTMT (containment) Vessel (West) Normal Range Radiation Monitor, Revision 21, for the train 2 Safety-Related Containment Atmosphere Radiation element. During the test, the control room received unexpected annunciator RAD MON SYSTEM TRBLE CH 1 for the opposite containment atmosphere radiation element train.

Upon receiving the alarm, the licensee declared the train 1 Containment Atmosphere Radiation Element inoperable. The train 2 element was previously declared inoperable for testing, so the licensee entered technical specification limiting condition for operation (LCO)3.4.15, RCS (reactor coolant system) Leakage Detection Instrumentation, condition B. The licensee subsequently restored the train 1 Radiation Element to operable status.

As described in section B 3.4.15 of the technical specification bases, the containment radiation monitors, in combination with the containment sump level/flow monitoring system, are used to detect reactor coolant pressure boundary degradation to minimize the potential for propagation to a gross failure and allow for mitigation strategies to be employed.

Upon investigation, the licensee determined the operator in the field had been given the wrong surveillance procedure by a senior reactor operator, that is, they were given a section from DB-SC-03212, which applies, to train 1 rather than train 2. Additionally, the operator had initially gone to the correct train, however, upon reviewing the procedure he had been given, the individual moved to the incorrect train component without asking for clarification.

The inspectors noted that train 1 was the protected equipment train at the time. Section 4.5.1 of NOP-OP-1007 states, in part, protected equipment postings are designed to limit plant risk, transients, and to prevent inadvertent Tech Spec entry due to maintenance, testing, or inadvertent equipment manipulations through increased personnel awareness. Additionally, section 4.5.7 states, in part, generally, work on protected equipment will not be allowed.

The inspectors discussed the importance of maintaining control over protected equipment with the licensee. Additionally, the inspectors reviewed the licensees corrective actions and questioned the licensee on the use of human performance tools.

Corrective Actions: The test was re-performed with 100 percent oversight. The individual was taken off-shift, provided remedial training regarding human performance tool use, and was subject to enhanced oversight when placed back on-shift. Additionally, the licensee discussed the importance of using a controlled procedure copy with the operations crews.

Corrective Action References: Condition report 2019-03346.

Performance Assessment:

Performance Deficiency: The licensee failed to accomplish the train 2 normal containment radiation monitor surveillance in accordance with the appropriate procedure as required by Title 10 CFR Part 50, Appendix B, Criterion V. Specifically, the licensee provided the incorrect procedure section to an individual in the field, which resulted in the individual manipulating the incorrect component and rendering the alternate train of normal range containment radiation inoperable.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone. Specifically, the containment radiation monitors respond to a loss of coolant accident by detecting elevated radiation monitors in containment and alerting the operators. This allows for early detection and mitigation of a loss of coolant accident to prevent undesirable consequences. The licensee failed to accomplish the surveillance test for the train 2 containment atmosphere radiation element in accordance with an appropriate procedure, which resulted in negatively impacting the availability of the alternate train radiation element.

Significance: The inspectors screened the issue in accordance with IMC 0612, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, dated June 19, 2012.

The inspectors answered No to all questions under Exhibit 2, Mitigating Systems Screening Questions. Specifically, the SSC did not maintain its operability, the finding did not represent a loss of system or function because the containment sump monitor was unaffected, there was not an actual loss of a single train for greater than its technical specification allowed outage time and the finding did not represent a loss of a non-technical specification train designated as high safety significant for greater than 24-hours. Therefore, the finding was screened as having very low safety significance (Green).

Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities. The licensee failed to plan, control and execute a work activity, which unexpectedly rendered a containment radiation monitor inoperable. Specifically, the licensee failed to provide the correct procedure section to the individual working in the field. Additionally, individuals in the pre-job brief did not use component identification, so the incorrect procedure section was not identified. Lastly, the individual executed the work on equipment that was protected at the time.

Enforcement:

Violation: Step 4.5.4.b of test procedure DB-SC-03213, Monthly Functional Test of RE 4597BA, CTMT (Containment) Vessel (West) Normal Range Radiation Monitor, Revision 21, states, in part, close CV203, containment sample supply isolation to RE4597BA.

Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures and Drawings, states, in part, activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances, and shall be accomplished in accordance with these instructions, procedures, or drawings.

Contrary to the above, on April 9, 2019, the licensee failed to accomplish an activity affecting quality in accordance with a prescribed procedure of a type appropriate to the circumstances.

Specifically, the licensee failed to close CV203 in accordance with DB-SC-03213. Instead, the licensee closed CV106, the containment sample supply isolation to RE4597AA and RE4597AB.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On April 12, 2019, the inspectors presented the Radiation Protection Program to Mr. D. Noble, Radiation Protection Manager, and other members of the licensee staff.

• On July 18, 2019, the inspectors presented the integrated inspection results to Mr. M. Bezilla and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Calculations C-EE-01.03-008 AC Power System Analysis 7

71111.01 Procedures DB-OP-01300 Switchyard Management 14

71111.01 Procedures DB-OP-0246 Degraded Grid 7

71111.01 Procedures DB-OP-06913 Seasonal Plant Preparation Checklist 34

71111.01 Procedures DB-SC-03023 Off-Site AC Sources Lined Up and Available 34

71111.01 Procedures NOP-OP-1003 Grid Reliability Protocol 9

71111.04 Corrective Action CR 2019-04161 LT2787 Minor Diesel Fuel Leak, EDG 1 Day Tank; 05/06/2019

Documents

71111.04 Drawings M-017A Diesel Generators 22

71111.04 Drawings OS-003 Operational Schematic High Pressure Injection System 40

71111.04 Procedures DB-OP-06011 HPI Train 1 Valve Checklist 32

71111.04 Procedures DB-OP-06316 EDG 1 Valve Checklist 63

71111.04S Corrective Action CR 2018-04538 BACC: DH Pump 2 Outboard Seal Boric Acid 06/14/2018

Documents

71111.04S Corrective Action CR 2018-11174 BACC: Small Deposits on DH1A Stem 12/21/2018

Documents

71111.04S Corrective Action CR 2019-00643 Time Between DH1A MOV Closed Seat Contact to Control 01/22/2019

Documents Switch Trip Greater than 0.15 Seconds

71111.04S Corrective Action CR 2019-02380 CCW Leak from DH Pump 2 Bearing Cooling Connection 03/15/2019

Documents

71111.04S Corrective Action CR 2019-04402 NRC Identified Suspect Weld 05/15/2019

Documents

71111.04S Drawings OS-003 High Pressure Injection System 40

71111.04S Drawings OS-004-SH 1 Decay Heat Removal/Low Pressure Injection System 60

71111.04S Procedures DB-OP-06012 Decay Heat and Low Pressure Injection System Operating 73

Procedure

71111.04S Procedures DB-PF-000 Preservice/In-Service Weld Preparation, Identification and 5

Data Recording

71111.04S Procedures DB-SP-03213 ECCS Flow Path Verification 8

71111.04S Procedures NA-QC-00252 Quality Control Review of Brazing and Weld Travelers 6

71111.04S Procedures NA-QC-00253 ASME/ANSI Visual Weld Inspection 4

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04S Work Orders 200635686 Perform Filling and Venting DH Train 1 Post-Maintenance 10/10/2016

MODEs 1 to 3 in Accordance with DB-OP-06012

71111.04S Work Orders 200678232 Operation and Control of Locked Valves - Decay Heat 02/22/2018

Pump 2

71111.04S Work Orders 200686502 Locked Valve Verification Test 03/19/2018

71111.04S Work Orders 200693246 Capped Valve Verification 03/20/2018

71111.05Q Drawings A-224F Fire Protection General Floor Plan Elevation 6030 26

71111.05Q Miscellaneous Davis-Besse Unit Fire Hazards Analysis 27

Fire Hazard

Analysis Report

71111.05Q Miscellaneous Davis-Besse Unit Fire Area Evaluation 26

Fire Hazard

Analysis Report

71111.05Q Procedures DB-EP-04023 Fire Rated Barrier Visual Inspection 20

71111.05Q Procedures PFP-AB-303 No. 3 Mechanical Penetration Room, Rooms 303 and 303PC 6

71111.05Q Procedures PFP-AB-304 Risk Significant Area 6

71111.05Q Procedures PFP-AB-402 No. 1 Electrical Penetration Room, Room 402 5

71111.05Q Procedures PFP-B-250 Service Water Pipe Tunnel, Room 250, Fire Area BG 5

71111.05Q Procedures PFP-IS-52 Service Water Pump Room, Room 52, Fire Area BF 3

71111.06 Drawings C-53 Yard Utilities Plan - Sheet 7 46

71111.06 Drawings C-55 Yard Utilities - Details Oil Separators 11

71111.06 Drawings M-172 Drainage Systems Auxiliary Building 585-0 20

71111.06 Procedures PFP-AB-318 Pre-Fire Plan Diesel Generator 1-1 Room 07/22/2010

71111.06 Procedures PFP-AB-321A Pre-Fire Plan Diesel Fuel Oil Day Tank 1-1 Room 07/22/2010

71111.06 Procedures RA-EP-02880 Internal Flooding 4

71111.11Q Miscellaneous FENOC Simulator OTLC 2019SA DBS102 CSRO Drill 0

Guide

71111.11Q Procedures DB-SC-03272 Control Rod Exercising Test 6

71111.11Q Procedures NOP-OP-1002 Conduct of Operations 13

71111.12 Calculations C-ICE-048.01- SFAS BWST Low Level Setpoint 8

004

71111.12 Calculations C-NSA-011.01-26 Calculation Computation R00

71111.12 Corrective Action CR 2016-03466 Liner Torn in SW37 03/15/2016

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents

71111.12 Corrective Action CR 2018-11015 SFAS Channel 3 BWST LT125C Indicating Erratically 12/16/2018

Documents

71111.12 Corrective Action CR 2019-00579 BWST Level Transmiter for Channel 4 is Failed 01/20/2019

Documents

71111.12 Corrective Action CR 2019-00596 Water Found in LT1525D 01/21/2019

Documents

71111.12 Corrective Action CR 2019-01625 SW38 Excessive Leakage Most Likely due to a Degraded 02/22/2019

Documents Valve Liner

71111.12 Corrective Action CR 2019-02906 Incomplete Mounting Details on Drawings for BWST Level 03/28/2019

Documents Transmitters

71111.12 Corrective Action CR 2019-03616 Perform Performance GAP Analysis to Determine if There is 04/18/2019

Documents a GAP in Skills and Knowledge Regarding EDG PM Scope

71111.12 Corrective Action CR 2019-03884 NRC 1Q2019 Integrated Exit - Minor Violation of 10 CR 50 04/26/2019

Documents App B Crit III, Design Control

71111.12 Drawings M-041B Primary Service Water System 72

71111.12 Miscellaneous LER 2018-001 Borated Water Storage Tank Level Transmitter Out of

Tolerance Due to Reaching End of Expected Life

71111.12 Miscellaneous NOP-CC-2007-01 BWST Level Transmitter Replacement 0

71111.12 Procedures DB-MI-03147 Functional Test/Calibration of LT-12C BWST Level 12

Transmitter of SFAS Channel 3

71111.12 Procedures NOP-OP-1001 Clearance Tagging Program 26

71111.13 Drawings E-1 SH.1 A.C. Electrical System One Line Diagram 39

71111.13 Drawings E-1 SH.2 A.C. Electrical System One Line Diagram 89

71111.13 Drawings OS-041A SH 2 Operational Schematic Emergency Diesel Generator 33

Systems

71111.13 Drawings OS-057 SH.2 Operational Schematic 13 BKV System 13

71111.13 Procedures DB-OP-06311 345 KV Switchyard No. 1 (Main) Transformer, No. 11 49

(Auxiliary) Transformer, and Startup Transformers

(01 and 02)

71111.13 Procedures DB-SC-03023 Off-Site AC Sources Lined up and Available 34

71111.13 Procedures DBBP-OPS-0011 Protected Equipment Posting 14

71111.13 Procedures NOP-OP-1007 Risk Management 29

71111.13 Work Orders 200788640 Turbine Shaft/ Station Ground Volts > 1

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Calculations C-ICE-048.01- SFAS BWST Low Level Setpoint 8

004

71111.15 Calculations C-ME-099.16-010 Service Water System Check Valves 2

71111.15 Corrective Action CR 2017-02906 Incomplete Mounting Details on Drawings for BWST Level 03/28/2019

Documents Transmitters

71111.15 Corrective Action CR 2018-11015 SFAS Channel 3 BWST LT125C Indicating Erratically 12/16/2018

Documents

71111.15 Corrective Action CR 2019-00579 BWST Level Transmiter for Channel 4 is Failed 01/20/2019

Documents

71111.15 Corrective Action CR 2019-00596 Water Found in LT1525D 01/21/2019

Documents

71111.15 Corrective Action CR 2019-03884 NRC 1Q2019 Integrated Exit - Minor Violation of 10 CR 50 04/26/2019

Documents App B Crit III, Design Control

71111.15 Corrective Action CR 2019-04242 SW280 Leaking by Closed Seat 05/09/2019

Documents

71111.15 Corrective Action CR 2019-04973 EDG 2 184 Day Test, Speed and Voltage Variations 06/06/2019

Documents

71111.15 Drawings M-041C Service Water System for Containment Air Coolers 47

71111.15 Miscellaneous LER 2018-001 Borated Water Storage Tank Level Transmitter Out of

Tolerance Due to Reaching End of Expected Life

71111.15 Miscellaneous NOP-CC-2007-01 BWST Level Transmitter Replacement 0

71111.15 Procedures DB-MI-03147 Functional Test/Calibration of LT-12C BWST Level 12

Transmitter of SFAS Channel 3

71111.15 Procedures DB-OP-06316 Starting EDG 2 63

71111.15 Procedures DB-PF-03027 Service Water Train 2 Valve Test 38

71111.15 Work Orders 200715992 PF3027-032 05.000 SW279/SW280 Forward Flow and 05/08/2019

Closure

71111.18 Corrective Action 2017-04079 OTSG Monitoring - Operating Range Level 04/10/2017

Documents

71111.18 Corrective Action 2018-01897 All SG Operate Levels Not Tracking Actual SG Levels 03/04/2018

Documents

71111.18 Corrective Action 2018-03130 S/G Operate Levels for both Steam Generator Margin to Tech 04/04/2018

Documents Spec Limit Lower-Than-Normal Following Refueling

71111.18 Engineering 15-0269-01 SG Operate Range Indication Adjusted Down 3% 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Changes

71111.18 Engineering 17-0397-001 SG Operate Range Indication Adjusted Down 3% 1

Changes

71111.18 Work Orders 200734969 SG 2 Operate Range Level 04/22/2019

71111.19 Corrective Action CR 2018-07377 Found Pressurizer Heater that did not Meet Acceptance 08/20/2018

Documents Criteria

71111.19 Corrective Action CR 2019-04847 Pressurizer Essential Heater Bank 1 Breaker BE1213 Tripped 06/02/2019

Documents During Rod Testing

71111.19 Corrective Action CR 2019-04973 EDG 2 184-Day Test, Speed and Voltage Variations 06/06/2019

Documents

71111.19 Corrective Action CR 2019-05150 Pressurizer Heater Readings Slightly Out-of-Acceptance 06/12/2019

Documents Criteria Limits

71111.19 Procedures DB-OP-01101 Containment Entry 16

71111.19 Procedures DB-OP-03006 Miscellaneous Instrument Shift Checks 62

71111.19 Procedures DB-OP-03013 Containment Daily Inspection and Containment Closeout 10

Inspection

71111.19 Procedures DB-OP-06316 Starting EDG 2 63

71111.19 Procedures DB-PF-04813 Miscellaneous Periodic Valve Test 7

71111.19 Procedures DB-SC-03110 SFAS Chanel 1 Functional Test 22

71111.19 Work Orders 200767617 Order Walkdown/Preparation 06/19/2019

71111.22 Calculations C-NSA-052.01- HPI Pump Acceptance Criteria

003

71111.22 Corrective Action CR 2019-04429 Suspect M& TE Readings for HPI Pump 2 Flow During 05/16/2019

Documents Performance of DB-SP-03219

71111.22 Corrective Action CR 2019-04429- Follow-Up to not Being Able to Obtain a Zero No-Flow 05/24/2019

Documents ATA-01 Reading on M& TE Used for Testing

71111.22 Drawings E-65B SH.13A Control Rod Drive Mechanism Control System CRDM Trip 4

Breaker B (Channel 1)

71111.22 Drawings OS-017A SH 1 Operational Schematic Auxiliary Feedwater System 35

71111.22 Procedures DB-MI-03011 Channel Functional Test of Reactor Trip Breaker B, RPS 35

Channel 1 Reactor Trip Module Logic, and Arts Channel 1

Output Logic

71111.22 Procedures DB-MI-09024 Installation and Removal of Foxboro I/A Series Differential 4

Pressure Transducers

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Procedures DB-PF-03291 Containment Personnel and Emergency Airlocks Seal 14

Leakage Test

71111.22 Procedures DB-SP-03152 Surveillance Test Procedure 30

71111.22 Procedures DB-SP-03218 HPI Train 1 Pump and Valve Test 30

71111.22 Procedures DB-SP-03219 HPI Train 2 Pump and Valve Test 28

71111.22 Procedures DB-SP-03506 AFP 2 Monthly Test 2

71111.22 Work Orders 200695772 HPI Pump 1 Quarterly 10/16/2018

71111.22 Work Orders 200704314 HPI Pump 1 Quarterly 01/07/2019

71111.22 Work Orders 200706426 AW Train 1 Level Control, Interlock and Flow Transmitter 01/31/2019

Test

71111.22 Work Orders 200707472 Perform DB-SP3219-003 HPI Pump 2 Quarterly FA Norm 02/18/2019

71111.22 Work Orders 200712534 HPI Pump 1 Quarterly FA Norm 04/23/2019

71111.22 Work Orders 200714753 Channel 1 RTB TRM/ARTS Logic Breaker B 04/23/2019

71111.22 Work Orders 200715403 Inlet Isolation FA Norm 04/26/2019

71111.22 Work Orders 200716610 HP31 Forward Flow Valve Test 05/14/2019

71111.22 Work Orders 200716619 AFP 2 Monthly Test 05/07/2019

71124.05 Calibration DB-0125-4 Calibration Data Sheet - Small Article Monitor; LI 2.12.59 10/03/2017

Records

71124.05 Calibration DB-0141-3 Frisker Calibration Data Sheet; LI 2.7.539 05/03/2018

Records

71124.05 Calibration DB-0178-3 AMS-4 Calibration Record; LI 2.8.171 07/24/2018

Records

71124.05 Calibration DB-0199-3 Calibration Data Sheet: AMP - 50/100/200; LI 2.7.510 04/19/2018

Records

71124.05 Calibration DB-0395-2 Model 89 Standardization Check 10/30/2018

Records

71124.05 Calibration DB-0432-1 Counting System QC Report; LI 2.12.57 05/22/2018

Records

71124.05 Calibration DB-0516-3 Ion Chamber Calibration Data Sheet; LI 2.7.314E 04/27/2018

Records

71124.05 Calibration DB-0556-3 Calibration Data Sheet - MG Telepole; LI 2.7.346 07/18/2018

Records

71124.05 Calibration DB-0558-0 Calibration Data Sheet: ASP-1 NRD; LI 2.7.233 03/02/2018

Records

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.05 Calibration DB-0560-2 Calibration Data Sheet: Air Sampler; LI ECP.0.36 04/23/2018

Records

71124.05 Calibration DB-0561-1 Calibration Data Sheet: Lapel Sample Pump; LI 2.8.456 07/17/2018

Records

71124.05 Calibration DB-0774-0 ARGOS Calibration Record; LI 2.12.107 1/26/2018

Records

71124.05 Calibration DB-0787-0 Calibration Data Sheet - Cronos-4; LI 2.12.98 02/26/2018

Records

71124.05 Calibration DB-0788-0 Calibration Data Sheet - GEM-5; LI 2.12.117 08/22/2018

Records

71124.05 Calibration DB-HP-01322 FASCTSCAN Efficiency Calibration Verification; LI 2.12.42 05/22/2018

Records

71124.05 Calibration DB-HP-01324 ACCUSCAN Efficiency Calibration Verification; LI 2.12.71 01/17/2018

Records

71124.05 Calibration LI 2.12.19 Gamma Spectrometer Calibration 07/20/2018

Records

71124.05 Calibration NOP-OP-4410-01 Fluke 451B Calibration Record; LI 2.7.518 02/08/2018

Records

71124.05 Corrective Action CR-2019-00858 Radiochemistry Cross Check Program in Disagreement for 01/28/2019

Documents Annual Gas Sample

71124.05 Corrective Action CR-2019-01866 Davis Besse QAQC Cross Check Program Performance 02/28/2019

Documents Declining Trend

71124.05 Miscellaneous Results of Radiochemistry Cross Check Program 01/12/2018

71124.05 Miscellaneous Results of Radiochemistry Cross Check Program 01/28/2019

71124.05 Miscellaneous Results of Radiochemistry Cross Check Program 11/01/2018

71124.05 Miscellaneous Results of Radiochemistry Cross Check Program 01/30/2018

71124.05 Miscellaneous Results of Radiochemistry Cross Check Program 04/06/2018

71124.05 Procedures DB-HP-00010 Radiation Measuring and Test Equipment Calibration and 10

Control Program

71124.05 Procedures DB-HP-00011 Quality Control for Radiation Protection Counting Equipment 5

71124.05 Procedures DB-HP-01112 Calibration of the Gamma Spectrometer System 7

71124.05 Procedures DB-HP-01320 Operation of Whole Body Counters 12

71124.05 Procedures DB-HP-01322 Body Counter Calibration and Performance Testing 6

71124.05 Procedures DB-HP-01324 ACCUSCAN-II Whole Body Counter Calibration and 2

Inspection Type Designation Description or Title Revision or

Procedure Date

Performance Checks

71124.05 Procedures DB-HP-01325 Operation of the ABACOS 2000 ACCUSCAN II Whole Body 3

Counting System

71124.05 Procedures DB-HP-01407 Calibration and Use of the J.L. Shepherd Model 89 9

71124.05 Procedures DB-HP-01418 Air Vented Ion Chamber Calibration 5

71124.05 Procedures DB-HP-01432 ASP-1 Calibration and Use 4

71124.05 Procedures DB-HP-01438 Frisker Calibration 6

71124.05 Procedures DB-HP-01442 MGP Telepole Calibration and Use 4

71124.05 Procedures DB-HP-01447 Small Article Monitor Calibration 6

71124.05 Procedures DB-HP-01454 Calibration and Use of Lapel Air Samplers 9

71124.05 Procedures DB-HP-01456 Calibration of the Eberline AMS-4 5

71124.05 Procedures DB-HP-01457 MGP AMP-50/100/200 Calibration and Use 3

71124.05 Procedures DB-HP-01463 GEM-5 Gamma Exit Monitor Calibration and Use 2

71124.05 Procedures DB-HP-01464 Cronos-4 Object/Tool Monitor Calibration and Use 3

71124.05 Procedures DB-HP-01465 ARGOS-5 Personnel Contamination Monitor Calibration and 4

Use

71124.05 Procedures DB-HP-01466 AVS-20T Constant Flow Air Sampler Calibration 0

71124.05 Procedures DB-HP-06024 Calibration and Use of Tennelec S5XLB Low Background 4

Counting System

71124.05 Procedures NOP-OP-4206 Bioassay Program 4

71124.05 Procedures NOP-OP-4410 Fluke 451B Calibration and Use 1

71124.05 Work Orders DB-MI3408-001 RE4596B Channel Calibration 03/14/2018

71124.05 Work Orders DB-MI4508-002 RE2389 Channel Check 03/18/2018

71151 Miscellaneous LER 2017-002 Auxiliary Feed Water Pump Turbine Bearing Damaged Due

to Improperly Marked Lubricating Oil Sight Glass

71151 Miscellaneous LER 2017-002-01 Auxiliary Feed Water Pump Turbine Bearing Damaged Due

to Improperly Marked Lubricating Oil Sight Glass

71151 Miscellaneous LER 2018-001 Borated Water Storage Tank Level Transmitter Out-of-

Tolerance Due to Reaching End of Expected Life

71151 Miscellaneous NEI 99-02 Regulator Assessment Performance Indicator Guideline 7

71152 Corrective Action CR 2018-05767 Emergency Diesel Generator 2 Water Jacket Monthly Sample 06/22/2018

Documents is Brown and Cloudy in Appearance

71152 Corrective Action CR 2018-10927 EDG 1 Cylinder 19 Injector Linkage 12/13/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents

71152 Corrective Action CR 2019-03346 Misposition: Unexpected Annunciator 7-6-C, RAD Monitoring 04/09/2019

Documents System Trouble, Channel 1

71152 Procedures DB-SC-03212 Monthly Functional Test of RE 4597AA, CTMT Vessel (East) 21

Normal Range Radiation Monitor

71152 Procedures DB-SC-03213 Monthly Functional Test of RE 4597BA, CTMT Vessel (West) 21

Normal Range Radiation Monitor

71152 Procedures NOP-OP-1007 Risk Management 29

20