IR 05000341/2021010

Design Basis Assurance Inspection (Programs) Inspection Report 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

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

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

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.02 Calculations

21 014 AW1

DSN. 021 014 AW1/DC-5719 Vol I / DC-6083 Vol I / TSR-

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

E2150F005A and E2150F005B

DC-5405

Third Party Review for Thrust Capabilities of Wm Powell

Co. MOVs

I

DC-5719

Minimum Required Target Thrust (MRTT) for Generic Letter 89-10 Gate, Globe and Quarter-turn Valves

(Torque)

W

DC-5812

Evaluation of Thrust Requirements for E4150F7004 Using

the EPRI MOV Methods

DC-5814

Evaluation of Thrust Requirements for E4150F042 Using

the EPRI MOV Methods

DC-5817

Evaluation of Thrust Requirements for G3352F001 and

G3352F004 Using the EPRI MOV Methods

DC-6397

MOV Terminal Voltage Calculation Results

D

DE-FR-004

MOV Weak Link Allowable Thrust for Continuous

Operation

DE-M-001

MOV - P4400F603A Allowable Thrust

Corrective Action

Documents

CARD 01-16089

Actuator Allowable Torque Values Exceeded During WR 870940929

06/28/2001

CARD 15-23250

PILAR for AOV Actuator Maintenance

05/06/2015

CARD 15-24958

Non-Training Solutions Identified for AOV Actuator

Maintenance

07/17/2015

CARD 16-22049

Lessons Learned for Troubleshooting Efforts

03/04/2016

CARD 16-26535

2016 CDBI: Potential Discrepancies with EDG LOP/LOCA

Acceptance Criteria and R3000 System Monitoring Plan

08/17/2016

CARD 16-26536

2016 CDBI: EDG12 and EDG14 LOP/LOCA Minimum

08/17/2016

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Voltage Values Do Not Meet Reg Guide 1.9 Criteria

CARD 18-28164

Cracking Visually Observed on Squib Valve A Wiring

Harness

10/11/2018

CARD 18-303308 P4400F603A Negative Analytical Torque Margin under

Design Conditions per DC-5719 Vol 1

2/21/2018

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

Calculation

05/21/2019

CARD 19-23915

2019 DBAI: Methodology Error Found in MOV Torque

Calculation

05/21/2019

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

(Fall 2023)

04/27/2020

CARD 20-33247

P4400F606A Negative Analytical MOV Torque Margin

2/29/2020

Corrective Action

Documents

Resulting from

Inspection

CARD 21-20233

Squib Valve B Qualified Life Will Expire before RF21

01/07/2021

CARD 21-20235

MOV Stall Times during Large LOCA Motor Starts on

EDGs Not Addressed in a Calculation

01/07/2021

CARD 21-20407

21 NRC DBA-POV Inspection - MGA11-100 Process

Improvement Needed

01/13/2021

CARD 21-20408

21 NRC DBA-POV Inspection - NRC Identified -

Conservative E4150F012 Design Temp in MPR

Calc. 021 014 AW1

01/13/2021

CARD 21-20410

21 NRC DBA-POV Inspection - TSR-36713 Torque

Values for G3352F001 Hex Head Hub

01/13/2021

CARD 21-20412

21 NRC DBA-POV Inspection - Conservative

Calculated Actuator Torque Capacity (Open) for

E4150F012 Identified in DC-5719 Vol 1

01/13/2021

CARD 21-20413

21 NRC DBA-POV Inspection - NRC Identified -

E4150F012 Overall Gear Ration Discrepancy in MPR

Calculation 021 014 AW1

01/13/2021

CARD 21-20489

21 NRC DBA-POV Inspection - NRC Identified -

Process Discrepancy Between Measured Packing Loads

and Updates to CECO and MPR Calculation 021 014

01/15/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AW1

CARD 21-20756

21 NRC DBA-POV Inspection - NRC Identified - Minor

Conservative Discrepancy in E2150F005A Post-Test

Analysis

01/26/2021

CARD 21-20778

21 NRC DBA-POV Inspection - Update DC-5719 Vol 1

Max Open/Close TSS for E2150F005A

01/27/2021

CARD 21-20796

21 NRC DBA POV Inspection - NRC Identified - Update

DC-5405 Vol 1 Document Interface Summary and

Section 2.0 Summary of Results and Conclusion Table for

E2150F005A

01/27/2021

CARD 21-20816

21 NRC DBA-POV Inspection - NRC Identified - Revise

DSN: MOV JOG Classification for E4150F004,

E4150F041, and E4150F042

01/27/2021

CARD 21-20889

21 NRC DBA-POV Inspection - NRC Identified - Revise

PEP03 for Clarity Regarding Long Torque Switch Bypass

01/29/2021

CARD 21-20890

21 NRC DBA-POV Inspection - NRC Identified - Revise

MOP01 for Guidance on Manually Stroking Quarter Turn

MOVs

01/29/2021

CARD 21-20894

21 NRC DBA-POV Inspection - Evaluate Vendor

Manual Maintenance Recommendations for Jamesbury

Butterfly Valves

01/29/2021

CARD 21-21112

21 NRC DBA-POV Inspection - NRC Observation -

Document Quality

2/05/2021

CARD 21-21130

21 NRC DBA-POV Inspection - NRC Observation -

Procedure Clarity

2/05/2021

CARD 21-22456

21 NRC DBA-POV Inspection - NRC Identified -

G3352F001 Potential Green Non-Cited Violation

03/18/2021

Drawings

5M721-6038

2" - 900# OSY Gate Valve with Limitorque Operator

61721-2131-01

Schematic Diagram, SLC Pumps C4103C001A & B

K

6M721-2082

Piping and Instrumentation Diagram (P&ID), SLC System

AB

Engineering

Changes

EDP 27422

Engineering Design Package (EDP) for Pressure Locking

Mitigation for Valve E4150F006

Engineering

Evaluations

Card 19-23915

Methodology Error Found in MOV Torque Calculation

White Paper

and 3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CARD 20-33247

P4400F606A Negative Analytical MOV Torque Margin

White Paper

D64061

Design Analysis Report for 6", 900# Gate Valve with

Limitorque SMB-0-25 Operator

EDP-26355

Replacement of Valve B2103F016

EDP-26858

Actuator and Motor Change on Motor Operated Valve

G3352F001

B

TE-ANL-10-035

Motor Operated Valve Risk Ranking for PSA Model Fermi

V9

A

TSR-3671

Revise BCDDs for Removed Handwheel on Valve

G3352F001

TSR-36940

Evaluate Valve Factor Impact on B2103F016 & F019 due

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

MOV E5150F013

TSR-38303

Technical Service Request Document for DC-5719 Vol 1

TU 92-01

Limitorque Technical Update: Thrust Rating Increase

11/25/1991

TU 98-01

Technical Update 98-01 and Technical Update 98-01

Supplement 1

07/17/1998

White Paper 125

Installed Motor Capability Evaluation

Procedures

23.707

Reactor Water Cleanup

150

24.139.03

Standby Liquid Control (SLC) Manual Initiation, Reactor

Water Cleanup (RWCU) Isolation and Storage Tank

Heater Operability Test

24.202.05

HPCI System Cold Shutdown Valve Operability Test

29.ESP.05

Emergency Support Procedure - Reactor Pressure Vessel

(RPV) Injection Using SLC Test Tank

35.139.002

SLC System Explosive Valve Insert Replacement

43.401.100

Integrated Leak Rate Test - Type A - General

43.401.200

Local Leakage Rate Test Type B - General

43.401.300

Local Leakage Rate Test Type C - General

55B

43.401.303

Local Leakage Rate Testing for Penetration X-9A

43.401.510

Local Leakage Rate Test, Purge, and Vent Valves

28B

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

43.401.511

Local Leakage Rate Test, Bypass Leakage Valves

41B

47.306.01

Analysis of Motor Operated Valves

47.306.01

Springpack Correction Guidelines

N/A

47.306.03

MOV MCC Based Testing

47.306.06

MOV Diagnostic Testing with the Quiklook 3 System

MES15

Design Calculations

MES28

Leakage Reduction and Primary Containment Leakage

Rate Programs

MOP01

Conduct of Operations

MOP03

Fermi Policy on Preconditioning

PEP03

MOV Program Manual

ST-OP-315-

0014-001

Operations Training Procedure - Standby Liquid Control

TE-ANL-10-035

Motor Operated Valve Risk Ranking

C

TRVEND

MOV JOG Classification

Shipping Records 44240567

Perform 24.203 Sec-5.1 CSS Cold Shutdown Valve

Operability

2/25/2016

57151446

Perform 24.203.04 Sec 5.1 Div 1 Core Spray Valve

Operability and Position Verification Test

07/08/2020

57518249

Perform 24.137.03 Sec 5.2 & 5.4 MSIV Cold Shutdown

Stroke Time Logic Functional

07/22/2020

F337110100

Inspect/Test 480VAC MCC 72C-3A POS 7D

09/14/2011

Work Orders

34797737

Perform MOV Thrust (Viper) Testing Per GL 96-05

Program G3352F001

07/19/2012

245763

Perform MOV Thrust Testing per GL 96-05 Program for

E5150F013 Valve

03/24/2014

245806

Perform MOV Thrust (Viper) Testing per GL 96-05

Program

03/18/013

3672660

Perform MOV Thermal O/L Test P4400F603A

03/09/2015

37545524

Final 43.401.303 LLRT for X-9A (Test 2: B2100F076A and

E4150F006)

10/21/2015

38117535

Stem Nut Replacement for MOV E5150F013

2/05/2016

38117535

Stem Nut Replacement for E5150F013 RF17

03/05/2014

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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

Position Indication Verification

03/27/2017

47500473

Perform RCIC Valve Position Indication

Verification/Manual Initiate

10/21/2018

47510367

Perform 24.202.05 Section 5.2 & 5.3; HPCI Local Valve

Position Indication Verification

10/21/2018

47548208

Final RCIC Pressure Isolation Valve Leakage Test

E5150F013

04/13/2020

47548556

Final 43.401.514; HPCI Pressure Isolation Valve Leakage

Test - 1: E4150F006

05/24/2020

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

Not Stroke Close

03/03/2020

E394060100

Perform MOV Thrust Testing per GL 96-05 Program

G352F001

03/13/2006

E439060100

Perform MOV Thrust Testing per GL 96-05 Program for

E4150F006, HPC I Main Pump Outlet Valve

05/26/2010

G202970107

Perform MOV Thrust Verification Testing G3352F001

07/06/1998

Q870080100

Perform Maxi Periodic MOV Inspection and Diagnostic

Strike Test

2/16/2008