IR 05000346/2019012
| ML19329E782 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/25/2019 |
| From: | Karla Stoedter Division of Reactor Safety III |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| References | |
| EPID I-2019-012-0034 IR 2019012 | |
| Preceding documents: |
|
| Download: ML19329E782 (11) | |
Text
November 25, 2019
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000346/2019012
Dear Mr. Bezilla:
On November 20, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Davis-Besse Nuclear Power Station and discussed the results of this inspection with Greg Michael, Director, Site Engineering 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,
/RA/
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:
Report Number:
Enterprise Identifier: I-2019-012-0034
Licensee:
FirstEnergy Nuclear Operating Co.
Facility:
Davis-Besse Nuclear Power Station
Location:
Oak Harbor, OH
Inspection Dates:
October 21, 2019 to November 20, 2019
Inspectors:
I. Hafeez, Reactor Inspector
B. Jose, Senior Reactor Inspector
L. Rodriguez, Reactor Inspector
Approved By:
Karla K. Stoedter, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) 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.
REACTOR SAFETY
===71111.21N - Design Bases Assurance Inspection (Programs)
Select Sample Components to Review - Risk Significant/Low Design (Inside/Outside Containment) (IP Section 02.01)===
- (1) SV100A; Main Steam Line #2 Isolation Valve Solenoid
- (2) ZC6451; Auxiliary Feedwater Pump #2 Discharge Flow Control Valve Position Controller
- (3) EV5889A; Terminal Block Box for SV5889A
- (4) MP42-1; Motor for Decay Heat Pump #1
- (5) BF11A; 480 V Motor Control Center
- (6) BE1157; Breaker for Borated Water Storage Tank Outlet Line #1 Valve DH7B
- (7) BF1139TD; Time Delay Relay for High Pressure Injection Line #2 to #1 Isolation Valve HP2A
- (8) Power Cables B24, B25, BF4 and BF6
Select Sample Components to Review - Primary Containment (Inside Containment)
(IP Section 02.01) (1 Sample)
- (1) HVRC11; Power Operated Relief Valve Block Valve RC11 Operator
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 20, 2019, the inspectors presented the design basis assurance inspection (programs) inspection results to Greg Michael, Director, Site Engineering and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N Calculations
1040-037-081
Thermal and Radiation Analysis for Stanwick Terminal
Blocks
C-ECS-050.03-
001
Thermal Lag Analysis for the Target Rock Electronic Control
Modules (ECMs) in Auxiliary Feed Water (AFW) Pump
Rooms 237 and 238
C-ECS-207.10-
001
Qualified Thermal Life of Various Equipment
C-EE-006.001-
030
Motor Control Center (MCC) Fuse Selection
Corrective Action
Documents
ATA-2018-11546
DCR DB-PF-09301
05/18/2018
ATL-2018-0961-
ATA-53
Motor Operated Valve (MOV) Grease Grading
08/14/2019
CR-10-79893
Cold Solder Joints Discovered on Control Board
07/19/2010
CR-10-79897
While Performing DB-MI-03658 Found Ripple Voltage Out of
Desired Range
07/20/2010
CR-2002-04804
Discolored Circuit Board for ZC6451
08/17/2002
CR-2004-04561
Westinghouse Technical Bulletin TB04-13
07/16/2004
CR-2005-02728
Labeling Fuses EQ When the Fuses are Not Qualified to
05/12/2005
CR-2006-01382
BF1260 PM Performed Past Late Date
03/27/2006
CR-2007-26552
Norm-ER-3103-D Rev.3 Does not Indicate Replacement
Frequency
09/12/2007
CR-2008-33671
Breaker for BF2142 is More Than 20 Years Old
01/17/2008
CR-2008-33948
Concern Over Use of 20-Year-Old Molded Case Breakers
01/21/2008
CR-2009-52750
Westinghouse Technical Bulletin Breaker Life Shorter Than
in Environmental Qualification (EQ) Program
01/29/2009
CR-2009-57013
BF1260 NRC PI&R 2009: CR 04-04561, Westinghouse TB-
04-13 Circuit Breaker Evaluation and Actions Preventive
Maintenance (PM) Performed Past Late Date
04/09/2009
CR-2010-78416
AF 6451 Issue During AFW Train #2 Flowpath Verification
DB-SP-03164
06/17/2010
CR-2010-85058
NRC-NCV Molded Case Circuit Breakers that Exceed their
10/28/2010
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Qualified Life
CR-2011-04831
Found Excessive Ripple Voltage on ZC6451 Control Board
Under DB-MI-03658
11/03/2011
CR-2012-14886
Extension of CA-2009-57013-32
09/12/2012
CR-2015-15705
Stock Code 100074753 Qualification Status
11/18/2015
CR-2018-06557
Schedule Challenges Implementation of Target Rock
Converters
07/23/2018
CR-2018-08408
Heat Rise from Hot Process Fluids Impact on EQ Equipment
09/24/2018
CR-2019-07040
Raychem WCSF-115-N Shrinkage/Recovery is Greater Than
Expected, With EQ Implications
08/22/2019
CR-G201-2010-
79809
AF6451 Found Filed Open and De-Energized
07/17/2010
CR-G201-2010-
273
Past Operability Review of AFW Positioner ZC6451
08/16/2010
Corrective Action
Documents
Resulting from
Inspection
CR-2019-08928
2019 NRC EQ DBAI Duratek Skid Discharge Hose Concern
10/25/2019
CR-2019-09108
2019 NRC EQ DBAI RFI # 034 Revised
10/30/2019
CR-2019-09441
NRC EQ DBAI 2019: Stock Codes and Procurement
Information not Updated for Use on EQ SSCs
11/07/2019
CR-2019-09442
NRC EQ DBAI 2019: Past Occurrence of Refurbished
Controller Installed in Environmentally Qualified Systems
Structures and Components (SSCs) without Reassessment
of Qualified Life
11/07/2019
CR-2019-09444
2019 NRC EQ DBAI Target Rock Controller Qualification
11/07/2019
CR-2019-09453
NRC EQ DBAI 2019: Need Clarification on Effect of Shelf
Life on Qualified Life for Electrolytic Capacitors for Target
Rock Controllers
11/07/2019
Drawings
E-1 Sh.2
Alternating Current (AC) Electrical System One Line Diagram 89
E-1039
Davis-Besse Nuclear Power Station - EQ Master Report
E-4 Sh-2
F Buses 480 V Unit Substations One-Line Diagram
E-4 Sh-4
480V Unit Sub-Station Lighting Distribution One Line
Diagram
E-6 Sh-2
480 Vac One Line Diagram
E-9
240 Vac and 120 Vac MCCs (Essential) One-Line Diagram
E52B SH 26B
Reactor Cooling System High Pressure (HP) Injection Line
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Valves
E52B SH-19A
Reactor Cooling System Borated Water Storage Tank
(BWST) Outlet Valve.
E52B SH-19C
Reactor Cooling System Containment Emergency Sump and
BWST Outlet Valve.
E52B SH26A
Reactor Cooling System HP Injection Line Valve
M-006D
Auxiliary Feedwater System
OS-004SH-1
Operational Schematic Decay Heat Removal/ Low Pressure
Injection System
WD-6
Westinghouse Electric Company Control Center Wiring
Diagram
T9
Engineering
Changes
ECR 02-0627-00
Environmental Qualification of the Connections/Terminations
of AFW System Equipment in Rooms 236, 237 and 238
EWR-02-0236-00
Refurbish Motor MVRC11 for Pressurizer Power Operated
Relief Valve (PORV) Isolation Valve RC11
MOD 94-0009
Modification to the Miscellaneous Liquid Radwaste System
Duratek Skid
TM 90-0027
Temporary Modification to Provide Design Verification of
Duratek Skid Hoses
06/26/1990
Engineering
Evaluations
DB1-023A
Environmental Qualification Binder for Kerite Power and
Control Cables
DB1-032
Environmental Qualification Binder for Stanwick Terminal
Blocks
DB1-036C
Environmental Qualification Binder for Large Pump Motors
DB1-100
Environmental Conditions
EQP: DB1-004C
Davis-Besse Nuclear Power Station Unit 1 Environmental
Qualification of Electrical Equipment - ASCO - Solenoid
Valve
EQP: DB1-004D
Davis-Besse Nuclear Power Station Unit 1 - Environmental
Qualification of Electrical Equipment - AVCO - U02 Series -
EQP: DB1-037B
Davis-Besse Nuclear Power Station Unit 1 Environmental
Qualification of Electrical Equipment - Limitorque - SMB-00,
SMB-000 - Valve Actuators
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EQP: DB1-037G
Davis-Besse Nuclear Power Station Unit 1 Environmental
Qualification of Electrical Equipment - Limitorque - Fibrite
Electrical Insulating Material
EQP: DB1-037H
Davis-Besse Nuclear Power Station Unit 1 Environmental
Qualification of Electrical Equipment - Schulz Electric
Company - Harsh Environment Random Wound Insulation
Systems
EQP: DB1-055B
Davis-Besse Nuclear Power Station Unit 1 Environmental
Qualification of Electrical Equipment - Crompton Corporation
- MOV Long Life Grease - Lubricants and Greases
EQP: DB1-084
Davis-Besse Nuclear Power Station Unit 1 Environmental
Qualification of Electrical Equipment - Target Rock -
Solenoid Valve, Valve Position Control Center
Miscellaneous
4714A
Qualification Analysis Report - Valve Models 87J-001, 87J-
2 - Solenoid Operated Globe Valves
A
DB1-101
EQ Master List (EQML)
E-008-00154
Instruction and Maintenance Manual for Motor Control
Center 44692
10/2014
E-008Q-00029
Westinghouse Instruction and Maintenance Manual for Five
Star Motor Control Centers
04/2011
PM5872
ZC6451 Replacement of Circuit Boards
11/06/2019
Procedures
2477-CCR-O
Certificate of Conformance and Elevated Temperature Test
Report for Class 1E Nuclear Safety Related Motor Control
Centers
01/20/1986
DB-ME-09100
Maintenance of Motor Control Centers
DB-ME-09114
Molded Case Breaker Inspection and Test
DB-MI-03658
Channel Calibration of 63A-ISLSP09A3-1 Steam Generator
Start-Up Level Control
DB-MI-09009
Maintenance of ASCO Solenoid Valves
DB-OP-06226
Startup Feed Pump Operating Procedure
DB-OP-06233
Auxiliary Feedwater System
DB-PF-09301
Preventive Maintenance for Type SMB and SB Limitorque
Operators
DB1-001A
Environmental Qualification Binder for Amerace
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(Agastat/Tyco) E7000 Series Agastat Time Delay Relays
DB1-036A
Environmental Qualification Binder for Westinghouse Electric
Corp Type W and Type Five Star MCC
DB1-036D
Environmental Qualification Binder for Westinghouse Electric
Corp HFB Spare Circuit Breakers and Other Miscellaneous
Items for MCCs
DB1-036H
Environmental Qualification Binder for Cutler Hammer
HFD,HFD3175 Replacement Molded Case Circuit Breakers
for Motor Control Centers
NOBP-CC-7004
Shelf Life Evaluation
NOBP-MS-2005
Nuclear Warehousing
NOP-MS-4001
Warehousing
NORM-ER-3107
First Energy Nuclear Operating Company (FENOC) Power
Fuses
Self-Assessments SA-BN-2019-
1342
Davis-Besse 2019 Pre-NRC Environmental Qualification
Design Bases Assurance Inspection
Work Orders
200002532
ZC6451: Replace Circuit Board
06/24/2003
200295297
ECP 08-0026-00 MVRC11 - Splice Cables
01/22/2008
200415169
Troubleshoot/ Repair/ Replace Components for FV6451
05/11/2010
200420441
Troubleshoot/ Repair/ Replace Components for FV6451
06/20/2010
200423484
PM 3923 SV100A *RPLC* MN STM LN #2
2/03/2011
200424235
Troubleshoot/ Repair/ Replace Components for FV6451
07/20/2010
200424614
Inspect Fuses, F1 and F2, at ZC6451, ZC6452, ZC6460 and
ZC6459
07/21/2010
200424712
Calibrate Target Rock Circuit Boards ZC6451 and LY6451K. 07/29/2010
200429526
Inspect Fuses, F1 and F2, at ZC6451, ZC6452, ZC6460 and
ZC6459
09/03/2010
200449014
Inspect Fuses ZC6451, ZC6460, ZC6459, and/or ZC6452
2/22/2011
200481399
DB-ZC6451: Troubleshoot/Replace Controller
11/02/2011
200496999
Inspect Fuses ZC6451, ZC6460, ZC6459, and/or ZC6452
03/22/2012
200540152
DB-ZC6451: Replace Controller
01/30/2013
200606820
PM 0042 MVRC11 Inspect Pressurizer Relief Valve #1
03/31/2016
200607054
PM 3923 SV100A *RPLC* MN STM LN #2
05/27/2016
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200607515
PM 1696 AF70 Check AFPT Room Flood Valve
05/25/2016
200612699
SP3444-001 05.000 SFRCS Chanel #1 Trip Test
05/06/2016
200612700
SP3445-001 05.000 SFRCS Chanel #2 Trip 100/101
05/06/2016
200635681
DB-Sub049-02 Decay Heat and Low Pressure Injection
2/28/2019
200636203
Measure Ripple/ Noise Content ZC6451, ZC6452, ZC6459,
ZC6460
04/04/2016
200648167
Inspect Fuses for Target Rock Controllers:
ZC6451/6460/6459/6452
07/20/2015
200687804
PM 0042 MVRC11 Inspect Pressurizer Relief Valve #1
03/11/2018
200687805
PM 4878 MVRC11 Replace Limit and Torque Switches
03/14/2018
200715962
PF3811-001 05.100 Train 1 Stroke
05/02/2019
200726407
PF3811-001 05.100 Train 1 Stroke
07/26/2019