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{{Adams
{{Adams
| number = ML18199A069
| number = ML19004A119
| issue date = 07/17/2018
| issue date = 01/02/2019
| title = 07/17/18 Letter - Fermi Power Plant-Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests and Experiments) Baseline Inspection 05000341/2018010 (Drs-A.Shaikh)
| title = NRC Triennial Inspection of Evaluation of Changes, Tests and Experiments Inspection Report 05000341/2018010 (DRS-A.Dahbur)
| author name = Shaikh A A
| author name = Daley R C
| author affiliation = NRC/RGN-III
| author affiliation = NRC/RGN-III/DRS/EB3
| addressee name = Polson K
| addressee name = Polson K
| addressee affiliation = Detroit Edison, Co
| addressee affiliation = DTE Energy
| docket = 05000341
| docket = 05000341
| license number = NPF-043
| license number = NPF-043
| contact person =  
| contact person =  
| document report number = IR 2018010
| document report number = IR 2018010
| document type = Letter
| document type = Inspection Report, Letter
| page count = 6
| page count = 7
}}
}}


Line 19: Line 19:
=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:
[[Issue date::July 17, 2018]]
[[Issue date::January 2, 2019]]


Mr. Keith Polson, Senior VP and Chief Nuclear Officer DTE Energy Company Fermi 2 - 260 TAC 6400 North Dixie Highway Newport, MI 48166
Mr. Keith Polson, Senior VP and Chief Nuclear Officer DTE Energy Company Fermi 2 - 260 TAC 6400 North Dixie Highway Newport, MI 48166


SUBJECT: FERMI POWER PLANT
SUBJECT: FERMI POWER PLANT, UNIT 2
-INFORMATION REQUEST FOR AN NRC TRIENNIAL 10 CFR 50.59 (EVALUATION OF CHANGES, TESTS AND EXPERIMENTS) BASELINE INSPECTION 05000 341/2018 010 Dear Mr. Polson
-NRC TRIEN NIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS INSPECTION REPORT 05000341/2018 010 Dear Mr. Polson
: On December 10, 2018 , the U.S. Nuclear Regulatory Commission (NRC) will begin a Title 10 of the Code of Federal Regulations, Part 50.59, (Evaluation of Changes, Tests and Experiments), Baseline inspection at the Fermi Power Plan This inspection will be performed in accordance with the NRC Baseline Inspection Procedure 71111.17 The onsite portion s of the inspection will take place on December 10
: On December 13, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluation of Changes, Tests and Experiments Inspection at your Fermi Power Plant, Unit On December 13, 2018, the NRC inspectors discussed the results of this inspection with you and other members of your staf The results of this inspection are documented in the enclosed repor The NRC inspectors did not identify any findings or violations of more
-1 4, 2018. Experience has shown that these baseline inspections are extremely resource intensive
-than-minor significanc This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading
, both for the NRC inspectors and the licensee staf In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for documents needed for the inspectio These documents have been divided into three group The first group of information is necessary to ensure that the inspection team is adequately prepared for the inspectio This information should be made available via compact disc and delivered to the regional office no later than October 26, 201 The inspection team will review this information and, by November 9, 2018 , will request specific items that should be provided for review in the regional office by November 23
-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations, Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."
, 201 The second group of requested documents contains additional items that the team will review, or need access to, during the inspectio Certain documents contained within Group II (i.e. Item (1)), will be requested for review in the regional office prior to the inspection by November 23, 2018 , as identified abov The remaining documents should be available by the first day of the onsite inspection, December 10, 201 The third group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspectio It is requested that this information be provided to the lead inspector as the information is generated during the inspectio It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspectio K. Polson -2- The lead inspector for this inspection is Atif Shaik We understand that our regulatory contact for this inspection is Kyle Mann of your organizatio If there are any questions about the inspection or the material requested, please contact the lead inspector at 630-829-9824 , o r via e-mail at Atif.Shaikh@nrc.gov
. This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150
-001 The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number. This letter and its enclosure 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 1 0 of the Code of Federal Regulation, Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."


Sincerely,/RA/ Atif Shaikh, Senior Inspector Engineering Branch 3 Division of Reactor Safety Docket No. 50
Sincerely,/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50
-341 License No. NPF
-341 License No. NPF
-43  
-43  


===Enclosure:===
===Enclosure:===
10 CFR 5
Inspection Report 05000341/2018010 cc: Distribution via LISTSERV
 
Letter to Keith Polson from Robert
 
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensee's performance by conducting an Evaluations of Changes, Tests and Experiments Inspection at Fermi Power Plant , Unit 2 , in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
 
A NRC and self-revealed findings, violations, and additional items are summarized in the table below. List of Findings and Violations No findings or violations were identified.
 
Additional Tracking Item s  None 3
 
=INSPECTION SCOPE=
 
S  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 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==
71111.17 T-Evaluations of Changes, Tests and Experiments (24 Samples)  The inspectors evaluated the following
:  10 CFR 50.59 Evaluation s-71111.17T
: (1) 15-0209; Unretrievable screw dropped into the reactor pressure vessel during refueling outage RF17 dispositioned as de facto design change by TSR 37586; Revision 0
: (2) 16-0251; Rev. A of DC
-4804 VOL I, "Secondary Containment Drawdown During DBA-LOCA", and related LCR 082-UFS Rev. 0, affecting UFSAR section 6.2.3.3.2 and figure 6.2
-21; Revision 0
: (3) 18-0206; TSR-38055 / LCR 18 UFS - Revision of Main Steam Isolation Valve Closing Force Description; Revision 0
: (4) 14-0175; Use of US Army Corps of Engineers Manual EM 1110 2502 in Design Calculations SS
-0026, Vol. I, Revision G, to Calculate Static Lateral Soil Pressure on Subsurface Exterior Reactor Building Walls; Revision 0
: (5) 16-0226; Resolution of ECCS Suction Strainer Modification Calculation Deficiencies; Revision 0
: (6) 17-0166; UFSAR Revision to Incorporate AutoPIPE and GTSTRUDL; Revision 0
: (7) 17-0108; Installation of Pomona Terminal Jacks on HFA relays to Facilitate MSIV Channel Functional Testing Using MSIV Test Box; Revision 0 10 CFR 50.59 Screening/Applicability Determination s-71111.17T
: (1) 15-0009; Replace Cooling Coils in T4700B001 and T4700B002 Drywell Coolers; Revision D
: (2) 15-0150; Installation and Usage of Rigging Brackets on RB
-5 Roof Girders for RB Main Crane Repairs; Revision 0
: (3) 16-0011; Hardened Vent System Modifications; Revision N
 
4
: (4) 17-0256; Changes to Appendix B of the UFSAR Aging Management Program Descriptions; Revision 0
: (5) 14-0256; Maximum Expected Differential Pressure (MEDP) for Valves T4803F601, 602, T4804F601 A/B, F602A/B, F603A/B, F604A/B, F605A/B, F606A/B, FO1A/B, F002A/B, F003A/B; Revision 0
: (6) 15-0022; Minimum Required Target Thrust (MRTT) for Generic Letter 89
-10 Gate, Globe and Quarter
-turn Valves (torque); Revision 0
: (7) 15-0183; Revise DC
-5719 Vol I, DC
-6083 Vol I, and CECO due to Limitorque Tech Update 13-02 and as-built changes per MES21; Revision 0
: (8) 16-0213; Reactor Core Isolation Cooling (RCIC) Hydraulic Analysis; Revision 0
: (9) 17-0116; Update the Fermi 2 Commitment to Fuel Channel Deflection Monitoring; Revision 0
: (10) 17-0256; Changes to Appendix B of the UFSAR Aging Management Program Descriptions; Revision 0
: (11) 15-0245; Control Rod Drift; Revisi on 0
: (12) 16-0180; Fuel Bundle Upper Tie Plate Removal/Replacement and Individual Rod Handling; Revision 0
: (13) 17-0211; Failed Safety Relief Valve; Revision 0
: (14) 17-0261; Loss of Feedwater or Feedwater Control; Revision 0
: (15) 18-0247; EDP 80065; Revision A
: (16) 17-0031; TSR 37800; Revision A
: (17) 16-0008; EDP 37281; Revision 0
 
==INSPECTION RESULTS==
No findings or violations were identified
 
==EXIT MEETING S AND DEBRIEFS==
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
 
The inspectors verified no proprietary information was documented in this report.
 
On December 13, 2018, the inspector s presented the Evaluation of Charges, Tests and Experiments Inspection results to Mr. Keith Polson
, and other members of the licensee staff.
 
5
 
=DOCUMENTS REVIEWED=
 
71111.17T-Evaluations of Changes, Tests and Experiments
Condition Reports
-Issued During Inspection
  - 18-29955; STAAD Pro Error Reports; 12/11/2018
- 18-30012; Screen 16-0226 Potentially Inadequate; 12/12/2018
- 18-30013; UFSAR Not Updated in 1998 to Reflect Changes to ECCS Strainers; 12/12/2018
-  Condition Reports
-Reviewed During Inspection
  - 10-24322; Revision to DC
-0502 Predicts SOP 23.206 Specified RCIC Flow of 650 gallon-p er-minutes may Exceed RCIC Turbine Rated Horsepower; 05/25/2010
- 10-28455; CARD 07-23892 Did Not Update All Documents; 09/24/2010
- 16-26697; MSIV Calculation DC-0469 Discrepancy with UFSAR 5.5.5.1.e; 08/24/2016
- 16-27189; MSIV TS SR 3.6.1.3.7 not correlated to Plant Safety Analysis; 09/09/2016
- 17-25117; Revise 20.000.25, Abnormal Operating Procedure, Failed Safety Relief Valve; 06/07/2017
- 15-22957; Scaffolding Remaining in Place Greater Than 90 Days, Request for 50.59; 04/24/2015
- 16-23935; Inadequate 50.59 Screen for Temporary Modification 15
-0044 - Remove "High Offgas % Oxygen" HWC Trip Signal; 05/12/2016
- 17-26060; 50.59 Evaluation Required per MMA21; 07/18/2017
- 18-20479; Request 50.59 Evaluation for Scaffolding to Vent Valves; 01/19/2018
- 18-25119; Screen 18-0008 for Changes to E11R608A Unsatisfactory; 07/02/2018
- 18-25120; TSR 37522 Incorrectly Changed Safety Classification of Torus Spray; 07/02/2018
- 18-25124; Rigging Plan and 50.59 Screen for 125% Load Test Unsatisfactory; 07/02/2018
- 18-26241; Screen 17-0037 for 003N9976 Is Not Satisfactory; 07/09/2018
- 18-27294; TSR 37785 Revision 0 Issued without 50.59 Screen; 09/25/2018
Procedures
  - 20.000.25; Failed Safety Relief Valve; Revision 26 and 27
- 20.129.01; Loss of Station and/or Control Air; Revision 35
- 35.137.002; MSIV
- Assembly, Disassembly, Repair and Adjustment; Revision 55A
Drawings  - 6SD721-2500-08; One Line Diagram
- 4160V Diesel Generator Buses; Revision U
Other s  - GE Nuclear Services SIL No. 477; Main Steam Isolation Valve Closure; 12/13/1988
- FER 175797; Calculation: Hydrodynamic Load Factors; Revision 1
- LCR 17-054-UFS; Alternate Methodology to Calculate Static Lateral Pressure on Reactor/Auxiliary Building Subsurface Exterior Walls; Revision 0
}}
}}

Revision as of 19:06, 12 February 2019

NRC Triennial Inspection of Evaluation of Changes, Tests and Experiments Inspection Report 05000341/2018010 (DRS-A.Dahbur)
ML19004A119
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 01/02/2019
From: Daley R C
Engineering Branch 3
To: Polson K
DTE Energy
References
IR 2018010
Download: ML19004A119 (7)
v • d • e


Text

January 2, 2019

Mr. Keith Polson, Senior VP and Chief Nuclear Officer DTE Energy Company Fermi 2 - 260 TAC 6400 North Dixie Highway Newport, MI 48166

SUBJECT: FERMI POWER PLANT, UNIT 2

-NRC TRIEN NIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS INSPECTION REPORT 05000341/2018 010 Dear Mr. Polson

On December 13, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluation of Changes, Tests and Experiments Inspection at your Fermi Power Plant, Unit On December 13, 2018, the NRC inspectors discussed the results of this inspection with you and other members of your staf The results of this inspection are documented in the enclosed repor The NRC inspectors did not identify any findings or violations of more

-than-minor significanc 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, Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely,/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50

-341 License No. NPF

-43

Enclosure:

Inspection Report 05000341/2018010 cc: Distribution via LISTSERV

Letter to Keith Polson from Robert

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensee's performance by conducting an Evaluations of Changes, Tests and Experiments Inspection at Fermi Power Plant , Unit 2 , in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

A NRC and self-revealed findings, violations, and additional items are summarized in the table below. List of Findings and Violations No findings or violations were identified.

Additional Tracking Item s None 3

INSPECTION SCOPE

S 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 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

71111.17 T-Evaluations of Changes, Tests and Experiments (24 Samples) The inspectors evaluated the following

10 CFR 50.59 Evaluation s-71111.17T
(1) 15-0209; Unretrievable screw dropped into the reactor pressure vessel during refueling outage RF17 dispositioned as de facto design change by TSR 37586; Revision 0
(2) 16-0251; Rev. A of DC

-4804 VOL I, "Secondary Containment Drawdown During DBA-LOCA", and related LCR 082-UFS Rev. 0, affecting UFSAR section 6.2.3.3.2 and figure 6.2

-21; Revision 0

(3) 18-0206; TSR-38055 / LCR 18 UFS - Revision of Main Steam Isolation Valve Closing Force Description; Revision 0
(4) 14-0175; Use of US Army Corps of Engineers Manual EM 1110 2502 in Design Calculations SS

-0026, Vol. I, Revision G, to Calculate Static Lateral Soil Pressure on Subsurface Exterior Reactor Building Walls; Revision 0

(5) 16-0226; Resolution of ECCS Suction Strainer Modification Calculation Deficiencies; Revision 0
(6) 17-0166; UFSAR Revision to Incorporate AutoPIPE and GTSTRUDL; Revision 0
(7) 17-0108; Installation of Pomona Terminal Jacks on HFA relays to Facilitate MSIV Channel Functional Testing Using MSIV Test Box; Revision 0 10 CFR 50.59 Screening/Applicability Determination s-71111.17T
(1) 15-0009; Replace Cooling Coils in T4700B001 and T4700B002 Drywell Coolers; Revision D
(2) 15-0150; Installation and Usage of Rigging Brackets on RB

-5 Roof Girders for RB Main Crane Repairs; Revision 0

(3) 16-0011; Hardened Vent System Modifications; Revision N

4

(4) 17-0256; Changes to Appendix B of the UFSAR Aging Management Program Descriptions; Revision 0
(5) 14-0256; Maximum Expected Differential Pressure (MEDP) for Valves T4803F601, 602, T4804F601 A/B, F602A/B, F603A/B, F604A/B, F605A/B, F606A/B, FO1A/B, F002A/B, F003A/B; Revision 0
(6) 15-0022; Minimum Required Target Thrust (MRTT) for Generic Letter 89

-10 Gate, Globe and Quarter

-turn Valves (torque); Revision 0

(7) 15-0183; Revise DC

-5719 Vol I, DC

-6083 Vol I, and CECO due to Limitorque Tech Update 13-02 and as-built changes per MES21; Revision 0

(8) 16-0213; Reactor Core Isolation Cooling (RCIC) Hydraulic Analysis; Revision 0
(9) 17-0116; Update the Fermi 2 Commitment to Fuel Channel Deflection Monitoring; Revision 0
(10) 17-0256; Changes to Appendix B of the UFSAR Aging Management Program Descriptions; Revision 0
(11) 15-0245; Control Rod Drift; Revisi on 0
(12) 16-0180; Fuel Bundle Upper Tie Plate Removal/Replacement and Individual Rod Handling; Revision 0
(13) 17-0211; Failed Safety Relief Valve; Revision 0
(14) 17-0261; Loss of Feedwater or Feedwater Control; Revision 0
(15) 18-0247; EDP 80065; Revision A
(16) 17-0031; TSR 37800; Revision A
(17) 16-0008; EDP 37281; Revision 0

INSPECTION RESULTS

No findings or violations were identified

EXIT MEETING S AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

The inspectors verified no proprietary information was documented in this report.

On December 13, 2018, the inspector s presented the Evaluation of Charges, Tests and Experiments Inspection results to Mr. Keith Polson

, and other members of the licensee staff.

5

DOCUMENTS REVIEWED

71111.17T-Evaluations of Changes, Tests and Experiments

Condition Reports

-Issued During Inspection

- 18-29955; STAAD Pro Error Reports; 12/11/2018

- 18-30012; Screen 16-0226 Potentially Inadequate; 12/12/2018

- 18-30013; UFSAR Not Updated in 1998 to Reflect Changes to ECCS Strainers; 12/12/2018

- Condition Reports

-Reviewed During Inspection

- 10-24322; Revision to DC

-0502 Predicts SOP 23.206 Specified RCIC Flow of 650 gallon-p er-minutes may Exceed RCIC Turbine Rated Horsepower; 05/25/2010

- 10-28455; CARD 07-23892 Did Not Update All Documents; 09/24/2010

- 16-26697; MSIV Calculation DC-0469 Discrepancy with UFSAR 5.5.5.1.e; 08/24/2016

- 16-27189; MSIV TS SR 3.6.1.3.7 not correlated to Plant Safety Analysis; 09/09/2016

- 17-25117; Revise 20.000.25, Abnormal Operating Procedure, Failed Safety Relief Valve; 06/07/2017

- 15-22957; Scaffolding Remaining in Place Greater Than 90 Days, Request for 50.59; 04/24/2015

- 16-23935; Inadequate 50.59 Screen for Temporary Modification 15

-0044 - Remove "High Offgas % Oxygen" HWC Trip Signal; 05/12/2016

- 17-26060; 50.59 Evaluation Required per MMA21; 07/18/2017

- 18-20479; Request 50.59 Evaluation for Scaffolding to Vent Valves; 01/19/2018

- 18-25119; Screen 18-0008 for Changes to E11R608A Unsatisfactory; 07/02/2018

- 18-25120; TSR 37522 Incorrectly Changed Safety Classification of Torus Spray; 07/02/2018

- 18-25124; Rigging Plan and 50.59 Screen for 125% Load Test Unsatisfactory; 07/02/2018

- 18-26241; Screen 17-0037 for 003N9976 Is Not Satisfactory; 07/09/2018

- 18-27294; TSR 37785 Revision 0 Issued without 50.59 Screen; 09/25/2018

Procedures

- 20.000.25; Failed Safety Relief Valve; Revision 26 and 27

- 20.129.01; Loss of Station and/or Control Air; Revision 35

- 35.137.002; MSIV

- Assembly, Disassembly, Repair and Adjustment; Revision 55A

Drawings - 6SD721-2500-08; One Line Diagram

- 4160V Diesel Generator Buses; Revision U

Other s - GE Nuclear Services SIL No. 477; Main Steam Isolation Valve Closure; 12/13/1988

- FER 175797; Calculation: Hydrodynamic Load Factors; Revision 1

- LCR 17-054-UFS; Alternate Methodology to Calculate Static Lateral Pressure on Reactor/Auxiliary Building Subsurface Exterior Walls; Revision 0

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