IR 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:
Report Number:
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
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.
REACTOR SAFETY
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,
RADIATION SAFETY
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
Calculations
C-EE-01.03-008
AC Power System Analysis
Procedures
DB-OP-01300
Switchyard Management
Procedures
DB-OP-0246
Degraded Grid
Procedures
DB-OP-06913
Seasonal Plant Preparation Checklist
Procedures
DB-SC-03023
Off-Site AC Sources Lined Up and Available
Procedures
NOP-OP-1003
Grid Reliability Protocol
Corrective Action
Documents
CR 2019-04161
LT2787 Minor Diesel Fuel Leak, EDG 1 Day Tank;
05/06/2019
Drawings
M-017A
Diesel Generators
Drawings
OS-003
Operational Schematic High Pressure Injection System
Procedures
DB-OP-06011
HPI Train 1 Valve Checklist
Procedures
DB-OP-06316
EDG 1 Valve Checklist
Corrective Action
Documents
CR 2018-04538
BACC: DH Pump 2 Outboard Seal Boric Acid
06/14/2018
Corrective Action
Documents
CR 2018-11174
BACC: Small Deposits on DH1A Stem
2/21/2018
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
Corrective Action
Documents
CR 2019-02380
CCW Leak from DH Pump 2 Bearing Cooling Connection
03/15/2019
Corrective Action
Documents
CR 2019-04402
NRC Identified Suspect Weld
05/15/2019
Drawings
OS-003
High Pressure Injection System
Drawings
OS-004-SH 1
Decay Heat Removal/Low Pressure Injection System
Procedures
DB-OP-06012
Decay Heat and Low Pressure Injection System Operating
Procedure
Procedures
DB-PF-000
Preservice/In-Service Weld Preparation, Identification and
Data Recording
Procedures
DB-SP-03213
ECCS Flow Path Verification
Procedures
NA-QC-00252
Quality Control Review of Brazing and Weld Travelers
Procedures
NA-QC-00253
ASME/ANSI Visual Weld Inspection
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
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
Work Orders
200678232
Operation and Control of Locked Valves - Decay Heat
Pump 2
2/22/2018
Work Orders
200686502
Locked Valve Verification Test
03/19/2018
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
No. 3 Mechanical Penetration Room, Rooms 303 and 303PC
71111.05Q Procedures
Risk Significant Area
71111.05Q Procedures
No. 1 Electrical Penetration Room, Room 402
71111.05Q Procedures
Service Water Pipe Tunnel, Room 250, Fire Area BG
71111.05Q Procedures
Service Water Pump Room, Room 52, Fire Area BF
Drawings
C-53
Yard Utilities Plan - Sheet 7
Drawings
C-55
Yard Utilities - Details Oil Separators
Drawings
M-172
Drainage Systems Auxiliary Building 585-0
Procedures
Pre-Fire Plan Diesel Generator 1-1 Room
07/22/2010
Procedures
Pre-Fire Plan Diesel Fuel Oil Day Tank 1-1 Room
07/22/2010
Procedures
RA-EP-02880
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
Calculations
C-ICE-048.01-
004
SFAS BWST Low Level Setpoint
Calculations
C-NSA-011.01-26 Calculation Computation
R00
Corrective Action
CR 2016-03466
Liner Torn in SW37
03/15/2016
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
CR 2018-11015
SFAS Channel 3 BWST LT125C Indicating Erratically
2/16/2018
Corrective Action
Documents
CR 2019-00579
BWST Level Transmiter for Channel 4 is Failed
01/20/2019
Corrective Action
Documents
CR 2019-00596
Water Found in LT1525D
01/21/2019
Corrective Action
Documents
CR 2019-01625
SW38 Excessive Leakage Most Likely due to a Degraded
Valve Liner
2/22/2019
Corrective Action
Documents
CR 2019-02906
Incomplete Mounting Details on Drawings for BWST Level
Transmitters
03/28/2019
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
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
Drawings
M-041B
Primary Service Water System
Miscellaneous
LER 2018-001
Borated Water Storage Tank Level Transmitter Out of
Tolerance Due to Reaching End of Expected Life
Miscellaneous
NOP-CC-2007-01 BWST Level Transmitter Replacement
Procedures
DB-MI-03147
Functional Test/Calibration of LT-12C BWST Level
Transmitter of SFAS Channel 3
Procedures
NOP-OP-1001
Clearance Tagging Program
Drawings
E-1 SH.1
A.C. Electrical System One Line Diagram
Drawings
E-1 SH.2
A.C. Electrical System One Line Diagram
Drawings
OS-041A SH 2
Operational Schematic Emergency Diesel Generator
Systems
Drawings
OS-057 SH.2
Operational Schematic 13 BKV System
Procedures
DB-OP-06311
345 KV Switchyard No. 1 (Main) Transformer, No. 11
(Auxiliary) Transformer, and Startup Transformers
(01 and 02)
Procedures
DB-SC-03023
Off-Site AC Sources Lined up and Available
Procedures
DBBP-OPS-0011
Protected Equipment Posting
Procedures
NOP-OP-1007
Risk Management
Work Orders
200788640
Turbine Shaft/ Station Ground Volts > 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
C-ICE-048.01-
004
SFAS BWST Low Level Setpoint
Calculations
C-ME-099.16-010 Service Water System Check Valves
Corrective Action
Documents
CR 2017-02906
Incomplete Mounting Details on Drawings for BWST Level
Transmitters
03/28/2019
Corrective Action
Documents
CR 2018-11015
SFAS Channel 3 BWST LT125C Indicating Erratically
2/16/2018
Corrective Action
Documents
CR 2019-00579
BWST Level Transmiter for Channel 4 is Failed
01/20/2019
Corrective Action
Documents
CR 2019-00596
Water Found in LT1525D
01/21/2019
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
Corrective Action
Documents
CR 2019-04242
SW280 Leaking by Closed Seat
05/09/2019
Corrective Action
Documents
CR 2019-04973
EDG 2 184 Day Test, Speed and Voltage Variations
06/06/2019
Drawings
M-041C
Service Water System for Containment Air Coolers
Miscellaneous
LER 2018-001
Borated Water Storage Tank Level Transmitter Out of
Tolerance Due to Reaching End of Expected Life
Miscellaneous
NOP-CC-2007-01 BWST Level Transmitter Replacement
Procedures
DB-MI-03147
Functional Test/Calibration of LT-12C BWST Level
Transmitter of SFAS Channel 3
Procedures
DB-OP-06316
Starting EDG 2
Procedures
DB-PF-03027
Service Water Train 2 Valve Test
Work Orders
200715992
PF3027-032 05.000 SW279/SW280 Forward Flow and
Closure
05/08/2019
Corrective Action
Documents
2017-04079
OTSG Monitoring - Operating Range Level
04/10/2017
Corrective Action
Documents
2018-01897
All SG Operate Levels Not Tracking Actual SG Levels
03/04/2018
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
Engineering
15-0269-01
SG Operate Range Indication Adjusted Down 3%
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
Engineering
Changes
17-0397-001
SG Operate Range Indication Adjusted Down 3%
Work Orders
200734969
SG 2 Operate Range Level
04/22/2019
Corrective Action
Documents
CR 2018-07377
Found Pressurizer Heater that did not Meet Acceptance
Criteria
08/20/2018
Corrective Action
Documents
CR 2019-04847
Pressurizer Essential Heater Bank 1 Breaker BE1213 Tripped
During Rod Testing
06/02/2019
Corrective Action
Documents
CR 2019-04973
EDG 2 184-Day Test, Speed and Voltage Variations
06/06/2019
Corrective Action
Documents
CR 2019-05150
Pressurizer Heater Readings Slightly Out-of-Acceptance
Criteria Limits
06/12/2019
Procedures
DB-OP-01101
Containment Entry
Procedures
DB-OP-03006
Miscellaneous Instrument Shift Checks
Procedures
DB-OP-03013
Containment Daily Inspection and Containment Closeout
Inspection
Procedures
DB-OP-06316
Starting EDG 2
Procedures
DB-PF-04813
Miscellaneous Periodic Valve Test
Procedures
DB-SC-03110
SFAS Chanel 1 Functional Test
Work Orders
200767617
Order Walkdown/Preparation
06/19/2019
Calculations
C-NSA-052.01-
003
HPI Pump Acceptance Criteria
Corrective Action
Documents
CR 2019-04429
Suspect M& TE Readings for HPI Pump 2 Flow During
Performance of DB-SP-03219
05/16/2019
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
Drawings
E-65B SH.13A
Control Rod Drive Mechanism Control System CRDM Trip
Breaker B (Channel 1)
Drawings
OS-017A SH 1
Operational Schematic Auxiliary Feedwater System
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
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
Procedures
DB-PF-03291
Containment Personnel and Emergency Airlocks Seal
Leakage Test
Procedures
DB-SP-03152
Surveillance Test Procedure
Procedures
DB-SP-03218
HPI Train 1 Pump and Valve Test
Procedures
DB-SP-03219
HPI Train 2 Pump and Valve Test
Procedures
DB-SP-03506
AFP 2 Monthly Test
Work Orders
200695772
HPI Pump 1 Quarterly
10/16/2018
Work Orders
200704314
HPI Pump 1 Quarterly
01/07/2019
Work Orders
200706426
AW Train 1 Level Control, Interlock and Flow Transmitter
Test
01/31/2019
Work Orders
200707472
Perform DB-SP3219-003 HPI Pump 2 Quarterly FA Norm
2/18/2019
Work Orders
200712534
04/23/2019
Work Orders
200714753
Channel 1 RTB TRM/ARTS Logic Breaker B
04/23/2019
Work Orders
200715403
Inlet Isolation FA Norm
04/26/2019
Work Orders
200716610
HP31 Forward Flow Valve Test
05/14/2019
Work Orders
200716619
AFP 2 Monthly Test
05/07/2019
Calibration
Records
DB-0125-4
Calibration Data Sheet - Small Article Monitor; LI 2.12.59
10/03/2017
Calibration
Records
DB-0141-3
Frisker Calibration Data Sheet; LI 2.7.539
05/03/2018
Calibration
Records
DB-0178-3
AMS-4 Calibration Record; LI 2.8.171
07/24/2018
Calibration
Records
DB-0199-3
Calibration Data Sheet: AMP - 50/100/200; LI 2.7.510
04/19/2018
Calibration
Records
DB-0395-2
Model 89 Standardization Check
10/30/2018
Calibration
Records
DB-0432-1
Counting System QC Report; LI 2.12.57
05/22/2018
Calibration
Records
DB-0516-3
Ion Chamber Calibration Data Sheet; LI 2.7.314E
04/27/2018
Calibration
Records
DB-0556-3
Calibration Data Sheet - MG Telepole; LI 2.7.346
07/18/2018
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
Calibration
Records
DB-0560-2
Calibration Data Sheet: Air Sampler; LI ECP.0.36
04/23/2018
Calibration
Records
DB-0561-1
Calibration Data Sheet: Lapel Sample Pump; LI 2.8.456
07/17/2018
Calibration
Records
DB-0774-0
ARGOS Calibration Record; LI 2.12.107
1/26/2018
Calibration
Records
DB-0787-0
Calibration Data Sheet - Cronos-4; LI 2.12.98
2/26/2018
Calibration
Records
DB-0788-0
Calibration Data Sheet - GEM-5; LI 2.12.117
08/22/2018
Calibration
Records
DB-HP-01322
FASCTSCAN Efficiency Calibration Verification; LI 2.12.42
05/22/2018
Calibration
Records
DB-HP-01324
ACCUSCAN Efficiency Calibration Verification; LI 2.12.71
01/17/2018
Calibration
Records
LI 2.12.19
Gamma Spectrometer Calibration
07/20/2018
Calibration
Records
NOP-OP-4410-01 Fluke 451B Calibration Record; LI 2.7.518
2/08/2018
Corrective Action
Documents
CR-2019-00858
Radiochemistry Cross Check Program in Disagreement for
Annual Gas Sample
01/28/2019
Corrective Action
Documents
CR-2019-01866
Davis Besse QAQC Cross Check Program Performance
Declining Trend
2/28/2019
Miscellaneous
Results of Radiochemistry Cross Check Program
01/12/2018
Miscellaneous
Results of Radiochemistry Cross Check Program
01/28/2019
Miscellaneous
Results of Radiochemistry Cross Check Program
11/01/2018
Miscellaneous
Results of Radiochemistry Cross Check Program
01/30/2018
Miscellaneous
Results of Radiochemistry Cross Check Program
04/06/2018
Procedures
DB-HP-00010
Radiation Measuring and Test Equipment Calibration and
Control Program
Procedures
DB-HP-00011
Quality Control for Radiation Protection Counting Equipment
Procedures
DB-HP-01112
Calibration of the Gamma Spectrometer System
Procedures
DB-HP-01320
Operation of Whole Body Counters
Procedures
DB-HP-01322
Body Counter Calibration and Performance Testing
Procedures
DB-HP-01324
ACCUSCAN-II Whole Body Counter Calibration and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Performance Checks
Procedures
DB-HP-01325
Operation of the ABACOS 2000 ACCUSCAN II Whole Body
Counting System
Procedures
DB-HP-01407
Calibration and Use of the J.L. Shepherd Model 89
Procedures
DB-HP-01418
Air Vented Ion Chamber Calibration
Procedures
DB-HP-01432
ASP-1 Calibration and Use
Procedures
DB-HP-01438
Frisker Calibration
Procedures
DB-HP-01442
MGP Telepole Calibration and Use
Procedures
DB-HP-01447
Small Article Monitor Calibration
Procedures
DB-HP-01454
Calibration and Use of Lapel Air Samplers
Procedures
DB-HP-01456
Calibration of the Eberline AMS-4
Procedures
DB-HP-01457
MGP AMP-50/100/200 Calibration and Use
Procedures
DB-HP-01463
GEM-5 Gamma Exit Monitor Calibration and Use
Procedures
DB-HP-01464
Cronos-4 Object/Tool Monitor Calibration and Use
Procedures
DB-HP-01465
ARGOS-5 Personnel Contamination Monitor Calibration and
Use
Procedures
DB-HP-01466
AVS-20T Constant Flow Air Sampler Calibration
Procedures
DB-HP-06024
Calibration and Use of Tennelec S5XLB Low Background
Counting System
Procedures
NOP-OP-4206
Bioassay Program
Procedures
NOP-OP-4410
Fluke 451B Calibration and Use
Work Orders
DB-MI3408-001
RE4596B Channel Calibration
03/14/2018
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
Regulator Assessment Performance Indicator Guideline
Corrective Action
Documents
CR 2018-05767
Emergency Diesel Generator 2 Water Jacket Monthly Sample
is Brown and Cloudy in Appearance
06/22/2018
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
Corrective Action
Documents
CR 2019-03346
Misposition: Unexpected Annunciator 7-6-C, RAD Monitoring
System Trouble, Channel 1
04/09/2019
Procedures
DB-SC-03212
Monthly Functional Test of RE 4597AA, CTMT Vessel (East)
Normal Range Radiation Monitor
Procedures
DB-SC-03213
Monthly Functional Test of RE 4597BA, CTMT Vessel (West)
Normal Range Radiation Monitor
Procedures
NOP-OP-1007
Risk Management
29