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

August 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

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

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 Aspect Report Section Mitigating Systems Green NCV 05000346/2019002-01 Open/Closed

[H.5] - Work Management 71152 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 Sample)

(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) (2 Samples)

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 Sample)

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

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 Sample)

(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) (1 Sample)

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) (4 Samples)

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) (2 Samples)

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) (1 Sample)

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) (3 Samples)

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 Sample)

(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) (1 Sample)

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) (1 Sample)

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 Aspect Report Section Mitigating Systems

Green NCV 05000346/2019002-01 Open/Closed

[H.5] - Work Management 71152 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

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Calculations

C-EE-01.03-008

AC Power System Analysis

71111.01

Procedures

DB-OP-01300

Switchyard Management

71111.01

Procedures

DB-OP-0246

Degraded Grid

71111.01

Procedures

DB-OP-06913

Seasonal Plant Preparation Checklist

71111.01

Procedures

DB-SC-03023

Off-Site AC Sources Lined Up and Available

71111.01

Procedures

NOP-OP-1003

Grid Reliability Protocol

71111.04

Corrective Action

Documents

CR 2019-04161

LT2787 Minor Diesel Fuel Leak, EDG 1 Day Tank;

05/06/2019

71111.04

Drawings

M-017A

Diesel Generators

71111.04

Drawings

OS-003

Operational Schematic High Pressure Injection System

71111.04

Procedures

DB-OP-06011

HPI Train 1 Valve Checklist

71111.04

Procedures

DB-OP-06316

EDG 1 Valve Checklist

71111.04S

Corrective Action

Documents

CR 2018-04538

BACC: DH Pump 2 Outboard Seal Boric Acid

06/14/2018

71111.04S

Corrective Action

Documents

CR 2018-11174

BACC: Small Deposits on DH1A Stem

2/21/2018

71111.04S

Corrective Action

Documents

CR 2019-00643

Time Between DH1A MOV Closed Seat Contact to Control

Switch Trip Greater than 0.15 Seconds

01/22/2019

71111.04S

Corrective Action

Documents

CR 2019-02380

CCW Leak from DH Pump 2 Bearing Cooling Connection

03/15/2019

71111.04S

Corrective Action

Documents

CR 2019-04402

NRC Identified Suspect Weld

05/15/2019

71111.04S

Drawings

OS-003

High Pressure Injection System

71111.04S

Drawings

OS-004-SH 1

Decay Heat Removal/Low Pressure Injection System

71111.04S

Procedures

DB-OP-06012

Decay Heat and Low Pressure Injection System Operating

Procedure

71111.04S

Procedures

DB-PF-000

Preservice/In-Service Weld Preparation, Identification and

Data Recording

71111.04S

Procedures

DB-SP-03213

ECCS Flow Path Verification

71111.04S

Procedures

NA-QC-00252

Quality Control Review of Brazing and Weld Travelers

71111.04S

Procedures

NA-QC-00253

ASME/ANSI Visual Weld Inspection

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04S

Work Orders

200635686

Perform Filling and Venting DH Train 1 Post-Maintenance

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

10/10/2016

71111.04S

Work Orders

200678232

Operation and Control of Locked Valves - Decay Heat

Pump 2

2/22/2018

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

24F

Fire Protection General Floor Plan Elevation 6030

71111.05Q Miscellaneous

Davis-Besse Unit

Fire Hazard

Analysis Report

Fire Hazards Analysis

71111.05Q Miscellaneous

Davis-Besse Unit

Fire Hazard

Analysis Report

Fire Area Evaluation

71111.05Q Procedures

DB-EP-04023

Fire Rated Barrier Visual Inspection

71111.05Q Procedures

PFP-AB-303

No. 3 Mechanical Penetration Room, Rooms 303 and 303PC

71111.05Q Procedures

PFP-AB-304

Risk Significant Area

71111.05Q Procedures

PFP-AB-402

No. 1 Electrical Penetration Room, Room 402

71111.05Q Procedures

PFP-B-250

Service Water Pipe Tunnel, Room 250, Fire Area BG

71111.05Q Procedures

PFP-IS-52

Service Water Pump Room, Room 52, Fire Area BF

71111.06

Drawings

C-53

Yard Utilities Plan - Sheet 7

71111.06

Drawings

C-55

Yard Utilities - Details Oil Separators

71111.06

Drawings

M-172

Drainage Systems Auxiliary Building 585-0

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

71111.11Q Miscellaneous

FENOC Simulator

Guide

OTLC 2019SA DBS102 CSRO Drill

71111.11Q Procedures

DB-SC-03272

Control Rod Exercising Test

71111.11Q Procedures

NOP-OP-1002

Conduct of Operations

71111.12

Calculations

C-ICE-048.01-

004

SFAS BWST Low Level Setpoint

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

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

71111.12

Corrective Action

Documents

CR 2018-11015

SFAS Channel 3 BWST LT125C Indicating Erratically

2/16/2018

71111.12

Corrective Action

Documents

CR 2019-00579

BWST Level Transmiter for Channel 4 is Failed

01/20/2019

71111.12

Corrective Action

Documents

CR 2019-00596

Water Found in LT1525D

01/21/2019

71111.12

Corrective Action

Documents

CR 2019-01625

SW38 Excessive Leakage Most Likely due to a Degraded

Valve Liner

2/22/2019

71111.12

Corrective Action

Documents

CR 2019-02906

Incomplete Mounting Details on Drawings for BWST Level

Transmitters

03/28/2019

71111.12

Corrective Action

Documents

CR 2019-03616

Perform Performance GAP Analysis to Determine if There is

a GAP in Skills and Knowledge Regarding EDG PM Scope

04/18/2019

71111.12

Corrective Action

Documents

CR 2019-03884

NRC 1Q2019 Integrated Exit - Minor Violation of 10 CR 50

App B Crit III, Design Control

04/26/2019

71111.12

Drawings

M-041B

Primary Service Water System

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

71111.12

Procedures

DB-MI-03147

Functional Test/Calibration of LT-12C BWST Level

Transmitter of SFAS Channel 3

71111.12

Procedures

NOP-OP-1001

Clearance Tagging Program

71111.13

Drawings

E-1 SH.1

A.C. Electrical System One Line Diagram

71111.13

Drawings

E-1 SH.2

A.C. Electrical System One Line Diagram

71111.13

Drawings

OS-041A SH 2

Operational Schematic Emergency Diesel Generator

Systems

71111.13

Drawings

OS-057 SH.2

Operational Schematic 13 BKV System

71111.13

Procedures

DB-OP-06311

345 KV Switchyard No. 1 (Main) Transformer, No. 11

(Auxiliary) Transformer, and Startup Transformers

(01 and 02)

71111.13

Procedures

DB-SC-03023

Off-Site AC Sources Lined up and Available

71111.13

Procedures

DBBP-OPS-0011

Protected Equipment Posting

71111.13

Procedures

NOP-OP-1007

Risk Management

71111.13

Work Orders

200788640

Turbine Shaft/ Station Ground Volts > 1

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.15

Calculations

C-ICE-048.01-

004

SFAS BWST Low Level Setpoint

71111.15

Calculations

C-ME-099.16-010 Service Water System Check Valves

71111.15

Corrective Action

Documents

CR 2017-02906

Incomplete Mounting Details on Drawings for BWST Level

Transmitters

03/28/2019

71111.15

Corrective Action

Documents

CR 2018-11015

SFAS Channel 3 BWST LT125C Indicating Erratically

2/16/2018

71111.15

Corrective Action

Documents

CR 2019-00579

BWST Level Transmiter for Channel 4 is Failed

01/20/2019

71111.15

Corrective Action

Documents

CR 2019-00596

Water Found in LT1525D

01/21/2019

71111.15

Corrective Action

Documents

CR 2019-03884

NRC 1Q2019 Integrated Exit - Minor Violation of 10 CR 50

App B Crit III, Design Control

04/26/2019

71111.15

Corrective Action

Documents

CR 2019-04242

SW280 Leaking by Closed Seat

05/09/2019

71111.15

Corrective Action

Documents

CR 2019-04973

EDG 2 184 Day Test, Speed and Voltage Variations

06/06/2019

71111.15

Drawings

M-041C

Service Water System for Containment Air Coolers

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

71111.15

Procedures

DB-MI-03147

Functional Test/Calibration of LT-12C BWST Level

Transmitter of SFAS Channel 3

71111.15

Procedures

DB-OP-06316

Starting EDG 2

71111.15

Procedures

DB-PF-03027

Service Water Train 2 Valve Test

71111.15

Work Orders

200715992

PF3027-032 05.000 SW279/SW280 Forward Flow and

Closure

05/08/2019

71111.18

Corrective Action

Documents

2017-04079

OTSG Monitoring - Operating Range Level

04/10/2017

71111.18

Corrective Action

Documents

2018-01897

All SG Operate Levels Not Tracking Actual SG Levels

03/04/2018

71111.18

Corrective Action

Documents

2018-03130

S/G Operate Levels for both Steam Generator Margin to Tech

Spec Limit Lower-Than-Normal Following Refueling

04/04/2018

71111.18

Engineering

15-0269-01

SG Operate Range Indication Adjusted Down 3%

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Changes

71111.18

Engineering

Changes

17-0397-001

SG Operate Range Indication Adjusted Down 3%

71111.18

Work Orders

200734969

SG 2 Operate Range Level

04/22/2019

71111.19

Corrective Action

Documents

CR 2018-07377

Found Pressurizer Heater that did not Meet Acceptance

Criteria

08/20/2018

71111.19

Corrective Action

Documents

CR 2019-04847

Pressurizer Essential Heater Bank 1 Breaker BE1213 Tripped

During Rod Testing

06/02/2019

71111.19

Corrective Action

Documents

CR 2019-04973

EDG 2 184-Day Test, Speed and Voltage Variations

06/06/2019

71111.19

Corrective Action

Documents

CR 2019-05150

Pressurizer Heater Readings Slightly Out-of-Acceptance

Criteria Limits

06/12/2019

71111.19

Procedures

DB-OP-01101

Containment Entry

71111.19

Procedures

DB-OP-03006

Miscellaneous Instrument Shift Checks

71111.19

Procedures

DB-OP-03013

Containment Daily Inspection and Containment Closeout

Inspection

71111.19

Procedures

DB-OP-06316

Starting EDG 2

71111.19

Procedures

DB-PF-04813

Miscellaneous Periodic Valve Test

71111.19

Procedures

DB-SC-03110

SFAS Chanel 1 Functional Test

71111.19

Work Orders

200767617

Order Walkdown/Preparation

06/19/2019

71111.22

Calculations

C-NSA-052.01-

003

HPI Pump Acceptance Criteria

71111.22

Corrective Action

Documents

CR 2019-04429

Suspect M& TE Readings for HPI Pump 2 Flow During

Performance of DB-SP-03219

05/16/2019

71111.22

Corrective Action

Documents

CR 2019-04429-

ATA-01

Follow-Up to not Being Able to Obtain a Zero No-Flow

Reading on M& TE Used for Testing

05/24/2019

71111.22

Drawings

E-65B SH.13A

Control Rod Drive Mechanism Control System CRDM Trip

Breaker B (Channel 1)

71111.22

Drawings

OS-017A SH 1

Operational Schematic Auxiliary Feedwater System

71111.22

Procedures

DB-MI-03011

Channel Functional Test of Reactor Trip Breaker B, RPS

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

Pressure Transducers

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.22

Procedures

DB-PF-03291

Containment Personnel and Emergency Airlocks Seal

Leakage Test

71111.22

Procedures

DB-SP-03152

Surveillance Test Procedure

71111.22

Procedures

DB-SP-03218

HPI Train 1 Pump and Valve Test

71111.22

Procedures

DB-SP-03219

HPI Train 2 Pump and Valve Test

71111.22

Procedures

DB-SP-03506

AFP 2 Monthly Test

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

Test

01/31/2019

71111.22

Work Orders

200707472

Perform DB-SP3219-003 HPI Pump 2 Quarterly FA Norm

2/18/2019

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

Records

DB-0125-4

Calibration Data Sheet - Small Article Monitor; LI 2.12.59

10/03/2017

71124.05

Calibration

Records

DB-0141-3

Frisker Calibration Data Sheet; LI 2.7.539

05/03/2018

71124.05

Calibration

Records

DB-0178-3

AMS-4 Calibration Record; LI 2.8.171

07/24/2018

71124.05

Calibration

Records

DB-0199-3

Calibration Data Sheet: AMP - 50/100/200; LI 2.7.510

04/19/2018

71124.05

Calibration

Records

DB-0395-2

Model 89 Standardization Check

10/30/2018

71124.05

Calibration

Records

DB-0432-1

Counting System QC Report; LI 2.12.57

05/22/2018

71124.05

Calibration

Records

DB-0516-3

Ion Chamber Calibration Data Sheet; LI 2.7.314E

04/27/2018

71124.05

Calibration

Records

DB-0556-3

Calibration Data Sheet - MG Telepole; LI 2.7.346

07/18/2018

71124.05

Calibration

Records

DB-0558-0

Calibration Data Sheet: ASP-1 NRD; LI 2.7.233

03/02/2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.05

Calibration

Records

DB-0560-2

Calibration Data Sheet: Air Sampler; LI ECP.0.36

04/23/2018

71124.05

Calibration

Records

DB-0561-1

Calibration Data Sheet: Lapel Sample Pump; LI 2.8.456

07/17/2018

71124.05

Calibration

Records

DB-0774-0

ARGOS Calibration Record; LI 2.12.107

1/26/2018

71124.05

Calibration

Records

DB-0787-0

Calibration Data Sheet - Cronos-4; LI 2.12.98

2/26/2018

71124.05

Calibration

Records

DB-0788-0

Calibration Data Sheet - GEM-5; LI 2.12.117

08/22/2018

71124.05

Calibration

Records

DB-HP-01322

FASCTSCAN Efficiency Calibration Verification; LI 2.12.42

05/22/2018

71124.05

Calibration

Records

DB-HP-01324

ACCUSCAN Efficiency Calibration Verification; LI 2.12.71

01/17/2018

71124.05

Calibration

Records

LI 2.12.19

Gamma Spectrometer Calibration

07/20/2018

71124.05

Calibration

Records

NOP-OP-4410-01 Fluke 451B Calibration Record; LI 2.7.518

2/08/2018

71124.05

Corrective Action

Documents

CR-2019-00858

Radiochemistry Cross Check Program in Disagreement for

Annual Gas Sample

01/28/2019

71124.05

Corrective Action

Documents

CR-2019-01866

Davis Besse QAQC Cross Check Program Performance

Declining Trend

2/28/2019

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

Control Program

71124.05

Procedures

DB-HP-00011

Quality Control for Radiation Protection Counting Equipment

71124.05

Procedures

DB-HP-01112

Calibration of the Gamma Spectrometer System

71124.05

Procedures

DB-HP-01320

Operation of Whole Body Counters

71124.05

Procedures

DB-HP-01322

Body Counter Calibration and Performance Testing

71124.05

Procedures

DB-HP-01324

ACCUSCAN-II Whole Body Counter Calibration and

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Performance Checks

71124.05

Procedures

DB-HP-01325

Operation of the ABACOS 2000 ACCUSCAN II Whole Body

Counting System

71124.05

Procedures

DB-HP-01407

Calibration and Use of the J.L. Shepherd Model 89

71124.05

Procedures

DB-HP-01418

Air Vented Ion Chamber Calibration

71124.05

Procedures

DB-HP-01432

ASP-1 Calibration and Use

71124.05

Procedures

DB-HP-01438

Frisker Calibration

71124.05

Procedures

DB-HP-01442

MGP Telepole Calibration and Use

71124.05

Procedures

DB-HP-01447

Small Article Monitor Calibration

71124.05

Procedures

DB-HP-01454

Calibration and Use of Lapel Air Samplers

71124.05

Procedures

DB-HP-01456

Calibration of the Eberline AMS-4

71124.05

Procedures

DB-HP-01457

MGP AMP-50/100/200 Calibration and Use

71124.05

Procedures

DB-HP-01463

GEM-5 Gamma Exit Monitor Calibration and Use

71124.05

Procedures

DB-HP-01464

Cronos-4 Object/Tool Monitor Calibration and Use

71124.05

Procedures

DB-HP-01465

ARGOS-5 Personnel Contamination Monitor Calibration and

Use

71124.05

Procedures

DB-HP-01466

AVS-20T Constant Flow Air Sampler Calibration

71124.05

Procedures

DB-HP-06024

Calibration and Use of Tennelec S5XLB Low Background

Counting System

71124.05

Procedures

NOP-OP-4206

Bioassay Program

71124.05

Procedures

NOP-OP-4410

Fluke 451B Calibration and Use

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

71152

Corrective Action

Documents

CR 2018-05767

Emergency Diesel Generator 2 Water Jacket Monthly Sample

is Brown and Cloudy in Appearance

06/22/2018

71152

Corrective Action

CR 2018-10927

EDG 1 Cylinder 19 Injector Linkage

2/13/2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

71152

Corrective Action

Documents

CR 2019-03346

Misposition: Unexpected Annunciator 7-6-C, RAD Monitoring

System Trouble, Channel 1

04/09/2019

71152

Procedures

DB-SC-03212

Monthly Functional Test of RE 4597AA, CTMT Vessel (East)

Normal Range Radiation Monitor

71152

Procedures

DB-SC-03213

Monthly Functional Test of RE 4597BA, CTMT Vessel (West)

Normal Range Radiation Monitor

71152

Procedures

NOP-OP-1007

Risk Management

29