IR 05000341/2021010
| ML21123A219 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/03/2021 |
| From: | Karla Stoedter Division of Reactor Safety III |
| To: | Peter Dietrich DTE Electric Company |
| References | |
| IR 2021010 | |
| Download: ML21123A219 (12) | |
Text
May 3, 2021
SUBJECT:
FERMI POWER PLANT, UNIT 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000341/2021010
Dear Mr. Dietrich:
On March 19, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2 and discussed the results of this inspection with Eric Olsen, Site Vice President 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. 05000341 License No. NPF-43
Enclosure:
As stated
Inspection Report
Docket Number: 05000341 License Number: NPF-43 Report Number: 05000341/2021010 Enterprise Identifier: I-2021-010-0012 Licensee: DTE Electric Company Facility: Fermi Power Plant, Unit 2 Location: Newport, MI Inspection Dates: January 11, 2021 to March 19, 2021 Inspectors: M. Farnan, Mechanical Engineer B. Jose, Senior Reactor Inspector 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 (programs) inspection at Fermi Power Plant, Unit 2, 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 Disease (COVID-19), regional inspectors were directed to begin telework. During this time regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. In some cases, portions of an IP were completed remotely and on-site. For the inspection documented below it was determined that the objectives and requirements stated in the IP could be completed remotely.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
The inspectors:
a. Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.
b. Determined whether the sampled POVs are capable of performing their design basis functions.
c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design basis conditions.
d. Evaluate maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) C4104F004A; Standby Liquid Control Explosive Valve
- (2) E4150F006; High Pressure Coolant Injection Main Pump Outlet Valve
- (3) E5150F013; Reactor Core Isolation Cooling Pump Supply to Feed Water Header Isolation Valve
- (4) E4150F012; High Pressure Core Spray Main Pump Minimum Flow to Suppression Chamber Isolation Valve
- (5) G3352F001; Reactor Water Cleanup Reactor Vessel Primary Containment Drain Line Recirculation Valve
- (6) T2300F409; Primary Containment Suppression Chamber Reactor Building Vacuum Breaker Valve
- (7) P4400F603A; Division 1 Reactor Building Component Cooling Water Supply Isolation Valve
- (8) E2150F005A; Division 1 Core Spray Inboard Isolation Valve
- (9) B2103F022A; Main Steam Line "A" Inboard Primary Containment Isolation Valve
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 19, 2021, the inspectors presented the design basis assurance inspection (programs) inspection results to Eric Olsen, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.21N.02 Calculations 021 014 AW1 DSN. 021 014 AW1/DC-5719 Vol I / DC-6083 Vol I / TSR- 8
37565
455597 Reevaluation of Thrust Capacities for Powell Valves 09/14/1994
29190 Survivable Thrust Capacities for Powell Valves 08/30/1994
A31-00 Gate and Globe Valve Efficiency Chart I
DC-5040 MOV Torque Switch Setting Calculation Input B
DC-5401 Maximum Expected Differential Pressure for Valves 0
E2150F005A and E2150F005B
DC-5405 Third Party Review for Thrust Capabilities of Wm Powell I
Co. MOVs
DC-5719 Minimum Required Target Thrust (MRTT) for Generic W
Letter 89-10 Gate, Globe and Quarter-turn Valves
(Torque)
DC-5812 Evaluation of Thrust Requirements for E4150F7004 Using 0
DC-5814 Evaluation of Thrust Requirements for E4150F042 Using 0
DC-5817 Evaluation of Thrust Requirements for G3352F001 and 0
G3352F004 Using the EPRI MOV Methods
DC-6397 MOV Terminal Voltage Calculation Results D
DE-FR-004 MOV Weak Link Allowable Thrust for Continuous 00
Operation
DE-M-001 MOV - P4400F603A Allowable Thrust 0
Corrective Action CARD 01-16089 Actuator Allowable Torque Values Exceeded During WR 06/28/2001
Documents 870940929
CARD 15-23250 PILAR for AOV Actuator Maintenance 05/06/2015
CARD 15-24958 Non-Training Solutions Identified for AOV Actuator 07/17/2015
Maintenance
CARD 16-22049 Lessons Learned for Troubleshooting Efforts 03/04/2016
CARD 16-26535 2016 CDBI: Potential Discrepancies with EDG LOP/LOCA 08/17/2016
Acceptance Criteria and R3000 System Monitoring Plan
CARD 16-26536 2016 CDBI: EDG12 and EDG14 LOP/LOCA Minimum 08/17/2016
Inspection Type Designation Description or Title Revision or
Procedure Date
Voltage Values Do Not Meet Reg Guide 1.9 Criteria
CARD 18-28164 Cracking Visually Observed on Squib Valve A Wiring 10/11/2018
Harness
CARD 18-303308 P4400F603A Negative Analytical Torque Margin under 12/21/2018
Design Conditions per DC-5719 Vol 1
CARD 19-23863 2019 DBAI: Margin Issues with AC Motor Operated Valves 05/20/2019
CARD 19-23915 2019 DBAI: Methodology Error Found in MOV Torque 05/21/2019
Calculation
CARD 19-23915 2019 DBAI: Methodology Error Found in MOV Torque 05/21/2019
Calculation
CARD 20-22360 P4400F603A Did Not Stroke Closed 03/03/2020
CARD 20-23884 E2150F005A - Update CECO for Maximum TSS 04/05/2020
CARD 20-25272 SLC Squib Primer Service Life Will Expire Prior to RF22 04/27/2020
(Fall 2023)
CARD 20-33247 P4400F606A Negative Analytical MOV Torque Margin 12/29/2020
Corrective Action CARD 21-20233 Squib Valve B Qualified Life Will Expire before RF21 01/07/2021
Documents CARD 21-20235 MOV Stall Times during Large LOCA Motor Starts on 01/07/2021
Resulting from EDGs Not Addressed in a Calculation
Inspection CARD 21-20407 2021 NRC DBA-POV Inspection - MGA11-100 Process 01/13/2021
Improvement Needed
CARD 21-20408 2021 NRC DBA-POV Inspection - NRC Identified - 01/13/2021
Conservative E4150F012 Design Temp in MPR
Calc. 021 014 AW1
CARD 21-20410 2021 NRC DBA-POV Inspection - TSR-36713 Torque 01/13/2021
Values for G3352F001 Hex Head Hub
CARD 21-20412 2021 NRC DBA-POV Inspection - Conservative 01/13/2021
Calculated Actuator Torque Capacity (Open) for
E4150F012 Identified in DC-5719 Vol 1
CARD 21-20413 2021 NRC DBA-POV Inspection - NRC Identified - 01/13/2021
E4150F012 Overall Gear Ration Discrepancy in MPR
Calculation 021 014 AW1
CARD 21-20489 2021 NRC DBA-POV Inspection - NRC Identified - 01/15/2021
Process Discrepancy Between Measured Packing Loads
and Updates to CECO and MPR Calculation 021 014
Inspection Type Designation Description or Title Revision or
Procedure Date
AW1
CARD 21-20756 2021 NRC DBA-POV Inspection - NRC Identified - Minor 01/26/2021
Conservative Discrepancy in E2150F005A Post-Test
Analysis
CARD 21-20778 2021 NRC DBA-POV Inspection - Update DC-5719 Vol 1 01/27/2021
Max Open/Close TSS for E2150F005A
CARD 21-20796 2021 NRC DBA POV Inspection - NRC Identified - Update 01/27/2021
DC-5405 Vol 1 Document Interface Summary and
Section 2.0 Summary of Results and Conclusion Table for
E2150F005A
CARD 21-20816 2021 NRC DBA-POV Inspection - NRC Identified - Revise 01/27/2021
DSN: MOV JOG Classification for E4150F004,
E4150F041, and E4150F042
CARD 21-20889 2021 NRC DBA-POV Inspection - NRC Identified - Revise 01/29/2021
PEP03 for Clarity Regarding Long Torque Switch Bypass
CARD 21-20890 2021 NRC DBA-POV Inspection - NRC Identified - Revise 01/29/2021
MOP01 for Guidance on Manually Stroking Quarter Turn
CARD 21-20894 2021 NRC DBA-POV Inspection - Evaluate Vendor 01/29/2021
Manual Maintenance Recommendations for Jamesbury
Butterfly Valves
CARD 21-21112 2021 NRC DBA-POV Inspection - NRC Observation - 02/05/2021
Document Quality
CARD 21-21130 2021 NRC DBA-POV Inspection - NRC Observation - 02/05/2021
Procedure Clarity
CARD 21-22456 2021 NRC DBA-POV Inspection - NRC Identified - 03/18/2021
G3352F001 Potential Green Non-Cited Violation
Drawings 5M721-6038 12" - 900# OSY Gate Valve with Limitorque Operator 0
61721-2131-01 Schematic Diagram, SLC Pumps C4103C001A & B K
6M721-2082 Piping and Instrumentation Diagram (P&ID), SLC System AB
Engineering EDP 27422 Engineering Design Package (EDP) for Pressure Locking 0
Changes Mitigation for Valve E4150F006
Engineering Card 19-23915 Methodology Error Found in MOV Torque Calculation 2 and 3
Evaluations White Paper
Inspection Type Designation Description or Title Revision or
Procedure Date
CARD 20-33247 P4400F606A Negative Analytical MOV Torque Margin 0
White Paper
D64061 Design Analysis Report for 6", 900# Gate Valve with 2
Limitorque SMB-0-25 Operator
EDP-26355 Replacement of Valve B2103F016 0
EDP-26858 Actuator and Motor Change on Motor Operated Valve B
G3352F001
TE-ANL-10-035 Motor Operated Valve Risk Ranking for PSA Model Fermi A
V9
TSR-3671 Revise BCDDs for Removed Handwheel on Valve 0
G3352F001
TSR-36940 Evaluate Valve Factor Impact on B2103F016 & F019 due 0
to Change of Solid Wedge to a Flex Wedge
Miscellaneous TMIS-19-0030 AOV Population for AOV Program Categorization Update 10/03/2019
TSR-27122 Technical Service Request (TSR); Gearing Change for 0
MOV E5150F013
TSR-38303 Technical Service Request Document for DC-5719 Vol 1 0
TU 92-01 Limitorque Technical Update: Thrust Rating Increase 11/25/1991
TU 98-01 Technical Update 98-01 and Technical Update 98-01 07/17/1998
Supplement 1
White Paper 125 Installed Motor Capability Evaluation 3
Procedures 23.707 Reactor Water Cleanup 150
24.139.03 Standby Liquid Control (SLC) Manual Initiation, Reactor 47
Water Cleanup (RWCU) Isolation and Storage Tank
Heater Operability Test
24.202.05 HPCI System Cold Shutdown Valve Operability Test 48
29.ESP.05 Emergency Support Procedure - Reactor Pressure Vessel 7
(RPV) Injection Using SLC Test Tank
35.139.002 SLC System Explosive Valve Insert Replacement 31
43.401.100 Integrated Leak Rate Test - Type A - General 33
43.401.200 Local Leakage Rate Test Type B - General 36
43.401.300 Local Leakage Rate Test Type C - General 55B
43.401.303 Local Leakage Rate Testing for Penetration X-9A 37
43.401.510 Local Leakage Rate Test, Purge, and Vent Valves 28B
Inspection Type Designation Description or Title Revision or
Procedure Date
43.401.511 Local Leakage Rate Test, Bypass Leakage Valves 41B
47.306.01 Analysis of Motor Operated Valves 42
47.306.01 Springpack Correction Guidelines N/A
47.306.03 MOV MCC Based Testing 12
47.306.06 MOV Diagnostic Testing with the Quiklook 3 System 2
MES15 Design Calculations 29
MES28 Leakage Reduction and Primary Containment Leakage 22
Rate Programs
MOP01 Conduct of Operations 41
MOP03 Fermi Policy on Preconditioning 40
PEP03 MOV Program Manual 10
ST-OP-315- Operations Training Procedure - Standby Liquid Control 20
0014-001
TE-ANL-10-035 Motor Operated Valve Risk Ranking C
TRVEND MOV JOG Classification 3
Shipping Records 44240567 Perform 24.203 Sec-5.1 CSS Cold Shutdown Valve 02/25/2016
Operability
57151446 Perform 24.203.04 Sec 5.1 Div 1 Core Spray Valve 07/08/2020
Operability and Position Verification Test
57518249 Perform 24.137.03 Sec 5.2 & 5.4 MSIV Cold Shutdown 07/22/2020
Stroke Time Logic Functional
F337110100 Inspect/Test 480VAC MCC 72C-3A POS 7D 09/14/2011
Work Orders 34797737 Perform MOV Thrust (Viper) Testing Per GL 96-05 07/19/2012
Program G3352F001
245763 Perform MOV Thrust Testing per GL 96-05 Program for 03/24/2014
E5150F013 Valve
245806 Perform MOV Thrust (Viper) Testing per GL 96-05 03/18/013
Program
3672660 Perform MOV Thermal O/L Test P4400F603A 03/09/2015
37545524 Final 43.401.303 LLRT for X-9A (Test 2: B2100F076A and 10/21/2015
E4150F006)
38117535 Stem Nut Replacement for MOV E5150F013 02/05/2016
38117535 Stem Nut Replacement for E5150F013 RF17 03/05/2014
Inspection Type Designation Description or Title Revision or
Procedure Date
38199743 Perform RCIC Cold Shutdown Valve Operability Test 03/27/2015
44151592 Perform 24.20.04 SEC-5.3 Div 1 CSS Local Valve 03/27/2017
Position Indication Verification
47500473 Perform RCIC Valve Position Indication 10/21/2018
Verification/Manual Initiate
47510367 Perform 24.202.05 Section 5.2 & 5.3; HPCI Local Valve 10/21/2018
Position Indication Verification
47548208 Final RCIC Pressure Isolation Valve Leakage Test 04/13/2020
E5150F013
47548556 Final 43.401.514; HPCI Pressure Isolation Valve Leakage 05/24/2020
Test - 1: E4150F006
50349522 Perform Mini Periodic MOV Inspection 09/03/2019
2180413 Final 43.401.500 LLRT for X-7A B2103F022A & F028A 03/21/2020
53088670 Perform MOV Thrust Testing (E2150-F005A) 01/29/2019
56864247 P4400F603A Division 1 EECW Supply Isolation Valve Did 03/03/2020
Not Stroke Close
E394060100 Perform MOV Thrust Testing per GL 96-05 Program 03/13/2006
G352F001
E439060100 Perform MOV Thrust Testing per GL 96-05 Program for 05/26/2010
E4150F006, HPC I Main Pump Outlet Valve
G202970107 Perform MOV Thrust Verification Testing G3352F001 07/06/1998
Q870080100 Perform Maxi Periodic MOV Inspection and Diagnostic 12/16/2008
Strike Test
10