IR 05000346/2021011
ML21301A162 | |
Person / Time | |
---|---|
Site: | Davis Besse |
Issue date: | 11/01/2021 |
From: | Karla Stoedter NRC/RGN-III/DRS/EB2 |
To: | Tony Brown Energy Harbor Nuclear Corp |
References | |
IR 2021011 | |
Download: ML21301A162 (14) | |
Text
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000346/2021011
Dear Mr. Brown:
On October 21, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station and 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.
No findings or violations of more than minor significance were identified during this inspection.
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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 05000346 License No. NPF-3
Enclosure:
As stated
Inspection Report
Docket Number: 05000346
License Number: NPF-3
Report Number: 05000346/2021011
Enterprise Identifier: I-2021-011-0039
Licensee: Energy Harbor Nuclear Corp.
Facility: Davis-Besse Nuclear Power Station
Location: Oak Harbor, OH
Inspection Dates: October 04, 2021 to October 21, 2021
Inspectors: C. Bickett, Senior Reactor Inspector J. Corujo-Sandin, Senior Reactor Inspector B. Daley, Senior Reactor Inspector C. Hobbs, Reactor Inspector G. O'Dwyer, Reactor Engineer E. Sanchez Santiago, Senior Reactor Inspector
Approved By: Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)
=
- (1) D1_ED - 125/250 VDC Motor Control Center 1. Updated Safety Analysis Report/Technical Specification/Technical Requirements Manual Licensing Basis Requirements 2. Component Walkdown 3. Operating Procedures 4. Maintenance Effectiveness 5. Translation of Vendor Specifications 6. Electrical Design Calculations and Considerations:
a. Short Circuit Calculations b. Motor Control Center Capacity c.
Degraded Voltage d. Overcurrent Protection e. Coordination Calculations
- (2) DH12 - Reactor Coolant System to Decay Heat System Isolation Valve 1. Updated Safety Analysis Report/Technical Specification/Technical Requirements Manual Licensing Basis Requirements 2. System Walkdown 3. Operating Procedures 4. Maintenance Effectiveness 5. System Health 6. Translation of Vendor Specifications
7. Environmental Qualification
8. Protection Against External Events:
a. Seismic b. Fire 9. Mechanical Design:
a. Weak Link Analysis b. Required Thrust c.
Pressure Locking and/or Thermal Binding d. Closure/Opening Time e. Maximum Differential Pressure 10.Test/Inspection Procedures, Acceptance Criteria, and Recent Results:
a. Leakage b. In-service Testing c.
Technical Specification Required Surveillance d. Actuation Test 11.Motor Power Requirements:
a. Voltage Drop b. Control Logic c.
Control Voltage Drop d. Load Flow e. Thermal Overload f.
Required Minimum Voltage g. Degraded Voltage Effects h. Brake Horsepower i.
Motor Thermal Overload Protection j.
Cable Ampacity k.
Protective Devices l.
Emergency Power
- (3) DB1CP - Battery Charger 1. Updated Safety Analysis Report/Technical Specification/Technical Requirements Manual Licensing Basis Requirements 2. Component Walkdown 3. Operating Procedures 4. System Health 5. Translation of Vendor Specifications 6. Electrical Design Calculations and Considerations:
a. Sizing b. Current Limiting Setting c.
Duty Cycle d. Contribution to Short Circuit Fault Current e. Sizing of Protective Fuses/Breakers/Relays f.
Voltage Drop Calculation
- (4) Bus D1 - 4160V Switchgear 1. Updated Safety Analysis Report/Technical Specification/Technical Requirements Manual Licensing Basis Requirements 2. Component Walkdown 3. Operating Procedures 4. Maintenance Effectiveness 5. System Health
6. Translation of Vendor Specifications
7. Environmental Qualification 8. Protection Against External Events:
a. Flooding b. Seismic c.
HELB d. Fire 9. Test/Inspection Procedures, Acceptance Criteria, and Recent Results:
a. Load Testing b. Technical Specification Surveillance c.
Relay Calibration d. Terminal Corrosion Resistance 10.Electrical Design Calculations and Considerations:
a. Loading Calculations b. Short Circuit Calculations c.
Voltage Regulation d. Coordination Calculations e. Temperature Effects and Equipment Qualification f.
Degraded Voltage Protection g. Loss of Voltage h. Breaker Settings and Ratings to Prevent Spurious Tripping i.
Breaker Control Voltage j.
Breaker Control Logic k.
Harmonic Content l.
Transmission System Protection m. Fast Bus Transfer Scheme n. Surge Protection o. Cable Ampacity p. Protective Relays and Trip Setpoints
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)
- (1) T10 - Borated Water Storage Tank 1. Updated Final Safety Analysis Report/ Technical Specifications/ Technical Requirements Manual 2. Component Walkdown 3. Operating Procedures 4. System Health 5. Protection against Seismic Events 6. Mechanical Design Calculations and Considerations:
a. Available and Required Volume (Loss of Coolant Accident)b. Level Setpoints c.
Instrument Uncertainty 7. Test/Inspection Procedures, Acceptance Criteria and Recent Results:
a. Instrument Setpoints b. Technical Specification Surveillances c.
Aging Management Program
Modification Review - Permanent Mods (IP Section 02.03) (5 Samples)
- (2) EC 15-138-002, Target Rock Auxiliary Power Supply Isolation
- (3) EC 16-050-001, Station Blackout Generator Radiator Tube Bundle Replacement
- (4) EC 16-478-002, Loop Seal in Borated Water Storage Tank to Spent Fuel Pool Purification Supply Pipe
- (5) EC 18-236-001, Replacement Breaker for BE1168
Review of Operating Experience Issues (IP Section 02.06) (2 Samples)
- (1) Information Notice (IN) 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto-start Circuits on Loss of Main Feedwater Pumps
- (2) IN 2017-06, Battery and Battery Charger Short-circuit Current Contributions to a Fault on the Direct Current Distribution System
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 21, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to Terry Brown, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.21M Calculations 35.004 Borated Water Storage Tank 2
35.013 BWST Capacity Study 0
36.023 BWST Heater 2
C-EE-002.01-010 DC CALC - Battery and Charger Sizing, Short Circuit, and 33
Voltage Drop
C-EE-002.01-011 Low Voltage Coordination Calculation 7
C-EE-004.01-049 4.16 kV Bus C1/D1 Degraded Voltage, Loss of Voltage, and 15
27X-6 Relay Setpoints
C-EE-015.03-008 AC Power System Analysis 7
C-FC-013.10-018 NFPA 805 Safe Shutdown, Non-Power Operation, and Fire 1
PRA Cable Selection Calculation
C-ICE-048.01-SFAS BWST Low Level Setpoint 8
004
C-ME-049-02-110 Maximum Differential Pressure Across DH11 and DH12 1
C-ME-049.01-130 BWST Purification Hydraulic Model 0
C-ME-099.16-006 Recalculate Thrust Torque Capability for MOVs CFIA, CFIB, 1
DH11, and DH12
C-ME-099.16-006 Clearly Establish Calculation Addendum's Informational Use01/24/2008
Rev. 1 Add 1
C-ME-49.01-078 Tank Level Curve Calculation - Borated Water Storage Tank 1
(T-10)
C-NSA-028.01-Hazard to Control Room Operators from Materials Stored 3
004 Onsite
C-NSA-049.01-Vortex Formation with ECCS Pump Suction from BWST 06/04/1997
004
C-NSA-049.01-Determination of Analytical Limit for Borated Water Storage 3
004 Tank Transfer Permissive
C-NSA-049.01-Vortex Formation with ECCS Pump Suction from the BWST 1
004
C-NSA-049.02-LPI, CS, and HPI Pump NPSH with Suction from the BWST 0
048
C-NSA-049.02-LPI, CS, and HPI Pump NPSH with Suction from the BWST 0
Inspection Type Designation Description or Title Revision or
Procedure Date
048 Addendum 1
C-NSA-049.02-LPI, CS, and HPI Pump NPSH with Suction from the BWST 0
048 Addendum 2
VA04-B001-001 Borated Storage Tank Foundation 2
Corrective Action 03-04356 RFA-CR for Additional Shielding at BWST 06/04/2003
Documents 04-04502 RFA Annual Engineering Evaluation of Installed Shielding 7/12/2004
(DB-HP-04027, Step 5.2)
CR-2015-01817 NRC CDBI 2015 - Operability of BWST while on SFP 02/11/2015
Purification
CR-2015-02476 NRC CDBI 2015 - EDG Powering Nonessential 4160V Bus 02/26/2015
CR-2016-04735 19R BACC - Packing Leak Found on DH12 04/06/2016
CR-2017-01853 Paint Degraded on BWST DB-T10 02/20/2017
CR-2018-00607 T10 BWST Tank 1-1 Coating Deteriorated 01/23/2018
CR-2018-02257 20R BACC - Packing Leak Found on DH12 03/10/2018
CR-2018-07962 Relays 27A-3 and 27A-4 Found Unsat During Monthly 09/08/2018
Surveillance
CR-2018-08352 NRC DBAI 2018 - UFSAR Descriptions of SBODG Function 09/21/2018
Are Inconsistent
CR-2018-08578 NRC DBAI 2018 - Potential Deficiency Identified in 09/28/2018
Procedure DB-OP-02511
CR-2018-08883 DC Bus Ground Received During Restoration of FW6459, 10/09/2018
MDFP Discharge to OTSG 1
CR-2018-09725 D1 Under Voltage Relay as Found Condition Out of 11/02/2018
Tolerance
CR-2018-10598 EFWF Camper HA 1350 Will Not Fully Close 12/03/2018
CR-2019-00687 D1 Under Voltage Relay as Found Condition Out of 01/23/2019
Tolerance
CR-2019-08598 BACC Leak on 46-HSC-155-1 Shop Weld C on ECCS 1 10/18/2019
Sump Pump Discharge
CR-2020-01949 1R21 BACC: Packing Leak on DH12 03/08/2020
CR-2021-01130 D1 Under Voltage Relay 27A-4 Out of Calibration 02/19/2021
CR-2021-01131 D1 Under Voltage Relay 27A-2 Out of Calibration 02/19/2021
CR-2021-05590 BACC New Leak on 1 ECCS Rm Sump Pump Piping 07/22/2021
Inspection Type Designation Description or Title Revision or
Procedure Date
Corrective Action CR 2021-07171 Part 21 Equalize Circuit of AMETEK Battery Chargers 09/24/2021
Documents CR-2021-07352 Updated Calculated DC Short Circuit Current in Calculation 10/01/2021
Resulting from C-EE-002.01-010 Exceeds Short Circuit Ratings for 125VDC
Inspection Distribution Panel DAP
CR-2021-07458 NRC DBAI 2021 - Clarification of Result and Conclusions 10/06/2021
Summary in C-EE-002.01-010
CR-2021-07464 HV5336B (EDG2 Room HVAC Recirc Damper Hydramotor 10/06/2021
Position Indicator Labels Incorrectly Depict "Open" and
"Shut"
CR-2021-07512 NRC DBAI 2021 - Excessive Grease Identified on 1P Battery 10/08/2021
Connector
CR-2021-07515 NRC DBAI 2021 - Clarification of Output Documents to 10/08/2021
Calculation C-EE-004.01-049 (4.16 kV Bus C1/D1 Degraded
Voltage, Loss of Voltage, and 27X-6 Relay Setpoints)
CR-2021-07710 NRC DBAI 2021 - Clarification of the Battery Charger 10/14/2021
Description in SD-007
CR-2021-07904 NRC DBAI 2021 - Error in Previous Revision 30 of 10/20/2021
C-EE-002.01-010
CR-2021-07914 NRC DBAI 2021 - Unable to Identify CRs Related to WO 10/20/2021
200751566 and WO 200679064 Regarding Instrument o
As-Found Out of Tolerance
Drawings E-1 Electrical System One-Line Diagram, Sheet 1 39
E-1 Electrical System One-Line Diagram, Sheet 2 90
E-3 4.16 kV Metering and Relaying One-Line Diagram 45
E-4 480 V Unit Sub-Station Lighting Distribution One-Line 53
Diagram, Sheet 4
E-6 480 V MCC (Essential) One-Line Diagram, Sheet 1 96
E-7 250/125V DC and Instrumentation AC One Line Diagram
P-35216-1 10 - 12 Forged Bolted Bonnet Nuclear Gate Valve T3
Engineering 15-00138-002 Target Rock Auxillary Power Supply Isolation 10
Changes 16-0050-001 Station Blackout Diesel Generator Radiator Tube Bundle 3
Replacement
ADL-13-195-016 Affected Documents List for ECP 13-195-016 Revision 3 3
ECP 13-195-016 Engineering Change Package EFW Facility Air Intake 3
Inspection Type Designation Description or Title Revision or
Procedure Date
Damper HA1350 Installation
ECP 16-0478-002 Loop Seal in BWST to SFP Purification Supply Pipe - Piping 2
and Mechanical
ECP-18-0236-001 Replacement of Breaker BE1168 11/06/2018
Engineering 601189516 DB-EER: DB-OP-02511 SWP Restart Direction 10/01/2018
Evaluations B-0027 Limitorque Valve Actuator Temperature Related to High 10/18/1978
Superheat Ambient Temperatures
Miscellaneous DB-ME3003-002 Station Battery Charger Test 2
DBRM-EMER-Davis-Besse Emergency Action Level Basis Document 9
1500A
ML060400472 Davis-Besse Nuclear Power Station, Unit No. 1, Issuance of 08/09/2006
Amendment, RE: Safety Features Actuation System
Instrumentation Setpoints and Surveillance Testing
Requirements (TAC No. MC3084)
ML081410652 Davis-Besse Nuclear Power Station Unit No. 1, Issuance of 06/30/2008
Amendment, RE: Measurement Uncertainty Recapture
ML15103A639 Davis-Besse Nuclear Power Station Component Design 04/10/2015
Basis Inspection, NCV 2015-008-01, Vulnerability of EDG
Crosstie to a Non-Essential Bus
OE 2015-0524 Evaluation of Information Notice 2015-05 05/20/2015
OE-2017-0561-1-Operating Experience Review of IN 2017-06 11/28/2017
FA003
OPS-SYS-1213 Auxillary Feedwater Training Lesson Plan 9
RFA 99-0271 BWST Shielding 09/07/1999
SD-007 System Description for 125/250V and 120V Instrumentation 6
SD-042 System Description for Decay Heat Removal System 7
SUS #048-01 System Monitoring Plan - SFAS 1
VMAN E-018Q-GNB Station Batteries 10
00017
VMAN-E-855Q-Ametek Solidstate Controls Instruction/Technical Manual 4
00001
Procedures DB-HP-01802 Control of Shielding 13
DB-HP-04027 Installed Shielding Inspection 9
Inspection Type Designation Description or Title Revision or
Procedure Date
DB-ME3046-001 D1 Bus Undervoltage Units Monthly Functional Test 01/24/2020
DB-ME3051-001 D1 Bus Degraded Voltage Relay Calibration 03/15/2021
DB-ME3052-001 D1 Bus Loss of Voltage Relay Calibration 02/18/2019
DB-MM-09118 EDG Governor Removal, Installation, and Adjustment 11
DB-OP-02000 RPS, SFAS, SFRCS Trip or SG Tube Rupture 3
DB-OP-02000 RPS, SFAS, SFRCS Trip, or SG Tube Rupture 31
DB-OP-02003 ECCS Alarm Panel 3 Annunciators 18
DB-OP-02511 Loss of Service Water Pumps/Systems 21
DB-OP-03006 Miscellaneous Instrument Shift Checks 66
DB-OP-06015 Borated Water Storage Tank Operating Procedure 23
DB-OP-06261 Service Water System Operating Procedure 74
DB-OP-06901 Plant Startup 45
DB-SP-04457 External Surfaces Monitoring Inspections 1
DBBP-ESAF-Operation of the Drager Gas Detection Pump 0
2008
NG-EN-00561 Above Ground Steel Tanks Inspection Program 1
NOP-CC-3002 Calculations 8
NOP-ER-3030 Surveillance Frequency Control Program 0
NOP-LP-2001 Corrective Action Program 48
NORM-OP-1009 SRO Review of Condition Reports 11
RA-EP-02850 Hazardous Chemical and Oil Spills 11
Work Orders 200817863 Performance of DB-PF-03272 Post Maintenance Valve Test 03/14/2020
Completed 03/14/2020
200229795 Replace Limit Switch for Valve DH12 01/20/2008
200634198 PM 9241 T10 Perform External Inspection 02/22/2017
200634813 PM 11756 T10 External Volumetric Inspection 10/20/2016
200638292 Auxillary Feed Pump 1-1 Discharge Control Valve Position 09/28/2019
Controller
200679064 M13148-001 08.000 LT1525D BWST LEVEL CAL 07/31/2018
200679882 Install Tornado Check Dampers in EFWF 05/19/2017
200688077 Clean, Inspect, and Test MVDH12, RCS to Decay Heat 03/17/2018
System Isolation Valve Motor (DH12)
200698909 M13147-001 08.000 LT1525C BWST LEVEL CAL 01/04/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
200707583 T-10 Repair Coatings 02/20/2017
200712553 18 Month Fire Damper Inspection 05/13/2020
200740520 Inspection Indicates Tank T-10 has Loose Paint/Coating 01/23/2018
200746407 Fix Packing Leak Found on DH12 03/12/2020
200751566 MI3145-001 08.000 LT1525A BWST LEVEL CAL 07/16/2020
200756176 Performance of Test Procedure Decay Heat Removal 03/09/2020
Isolation Test DB-SP-03130
200774792 Replace LT1525C BWST Level SFAS CH 3 01/04/2019
200799975 SBODG Monthly Test 08/21/2021
200801860 SBODG Monthly Test 09/25/2021
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