ML19353D108

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Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000341/2020001
ML19353D108
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 12/19/2019
From: John Bozga
Division of Reactor Safety III
To: Peter Dietrich
DTE Energy
References
IR 2020001
Download: ML19353D108 (6)


See also: IR 05000341/2020001

Text

December 19, 2019

Mr. Peter Dietrich, 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 2NOTIFICATION OF NRC BASELINE

INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000341/2020001

Dear Mr. Dietrich:

On March 26, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin the Baseline

Inservice Inspection Procedure 71111.08. This onsite inspection is scheduled to be

performed March 26, 2020, through March 31, 2020.

Experience has shown that this inspection is resource intensive both for the NRC inspector and

your staff. In order to minimize the impact to your onsite resources, and to ensure a productive

inspection for both sides, we have enclosed a request for documents needed for this inspection.

These documents have been divided into two groups.

The first group identifies information necessary to ensure that the inspector is adequately

prepared. The second group identifies the information the inspector will need upon arrival at

the site. 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 inspection.

We have discussed the schedule for inspection activities with your staff and understand

that our regulatory contact for this inspection will be Mr. Shane Gatter, of your organization.

If there are any questions about this inspection or the material requested, please contact the

lead inspector, Mr. John V. Bozga, at 630-829-9613.

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 3150-0011. 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.

P. Dietrich -2-

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 10 of the Code of Federal Regulations, Part 2.390, Public

Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

John V. Bozga

Senior Reactor Inspector

Engineering Branch 1

Division of Reactor Safety

Docket No. 50-341

License No. NPF-43

Enclosure:

Document Request for Baseline

Inservice Inspection

cc: Distribution via LISTSERV

P. Dietrich -3-

Letter to Peter Dietrich from John V. Bozga dated December 19, 2019.

SUBJECT: FERMI POWER PLANT, UNIT 2NOTIFICATION OF NRC BASELINE

INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000341/2020001

DISTRIBUTION:

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ADAMS Accession Number: ML19353D108

OFFICE RIII

NAME JBozga:jw

DATE 12/19/19

OFFICIAL RECORD COPY

DOCUMENT REQUEST FOR BASELINE INSERVICE INSPECTION

Inspection Report: 05000341/2020001

Inspection Dates: March 26, 2020, through March 31, 2020

Inspection Procedures: Inspection Procedure 71111-08, Inservice Inspection

Lead Inspector: John V. Bozga, DRS

630-829-9613

A. Information for the In-Office Preparation Week

The following information (electronic copy CD ROM if possible) is requested by

March 2, 2020, to facilitate the selection of specific items that will be reviewed during the

onsite inspection week. The inspector will select specific items from the information

requested below and request a list of additional documents needed onsite to your staff.

We request that the specific items selected from the lists be available and ready for

review on the first day of inspection. If you have any questions regarding this

information, please call the inspector as soon as possible.

1. For the upcoming outage, a detailed schedule and description of:

a. Non-Destructive Examinations (NDEs) planned for Class 1 and 2 Systems

and containment, performed as part of your American Society of Mechanical

Engineers (ASME) Code Inservice Inspection (ISI) Program (include edition and

addenda of Code committed to), and NDEs planned for other systems performed

as part of a Risk-Informed ISI Program, or other augmented inspection programs

commitments, as part of an industry initiative. For each weld examination,

include the weld identification number, description of weld (component name),

category, class, type of exam and procedure number, and date of examination;

and

b. Welding on Code Class 1, 2, or 3 components.

2. A copy of the NDE procedures and welding procedures used to perform the

activities identified in A.1 (including NDE calibration and flaw characterization/sizing

procedures and Welding Procedure Qualification Records). For ultrasonic

examination procedures qualified in accordance with Appendix VIII, of Section XI

of the ASME Code, provide documentation supporting the procedure qualification

(e.g., the Electric Power Research Institute performance demonstration qualification

summary sheets).

3. A copy of ASME Section XI, Code Relief Requests applicable to the

examinations identified in A.1.

4. A copy of the 10-year ISI Program showing those required exams scheduled to

be performed this outage, and those which have been completed.

Enclosure

DOCUMENT REQUEST FOR BASELINE INSERVICE INSPECTION

5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye

penetrant), which have identified relevant indications on Code Class 1 and 2 systems

since the beginning of the last refueling outage.

6. List with short description of the welds in Code Class 1 and 2 systems, which have

been fabricated due to component repair/replacement activities since the beginning

of the last refueling outage and identify the system, weld number, and reference

applicable documentation (e.g., NIS-2 forms with definitions of system and

component acronyms).

7. If reactor vessel weld examinations required by the ASME Code are scheduled to

occur during the inspection period, provide a detailed description of the welds to be

examined, and the extent of the planned examination.

8. List with description of ISI-related issues such as piping degradation or damage

(e.g., cracks, wall thinning, wear, microbiologically induced corrosion) or errors

identified in piping examinations that have been entered into your corrective

action system since the beginning of the last refueling outage. Also, include a list of

corrective action records associated with foreign material introduced/identified in the

reactor vessel or reactor coolant system since the beginning of the last refueling

outage.

9. Copy of any Title 10 of the Code of Federal Regulations, Part 21 reports applicable to

your structures, systems, or components within the scope of Section XI of the ASME

Code that have been identified since the beginning of the last refueling outage.

10. Point of contact information (name and site number) for the Inservice Inspection

Program, Aging Management Programs, Site Welding Engineer, and Reactor

Internals Inspection ProgramsSite and vendor leads.

B. Onsite Information to be Provided to the Inspector on the First Day of the

Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies

(e.g., Paper Records) of the Following Documents.

1. For welds selected by the inspector from A.1.b and A.6 above, provide copies of the

following documents:

a. Document of the weld number and location (e.g., system, train, branch);

b. Document with a detail of the weld construction (e.g., drawing);

c. Applicable portions of the Design Specification and applicable Code of

construction for the weldment (e.g., B31.1 or ASME Section III);

d. Applicable Code Edition and Addenda for weld procedure qualification;

e. Applicable weld procedure specifications and completed weld data sheets used

to fabricate the welds;

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DOCUMENT REQUEST FOR BASELINE INSERVICE INSPECTION

f. Copies of procedure qualification records supporting the weld procedure

specifications;

g. Copies of welders performance qualification records;

h. Copies of mechanical test reports identified in the procedure qualification records

above;

i. Copies of the non-conformance reports for the selected welds;

j. Access to radiographs and equipment to view radiographs of the selected welds;

k. ASME Code Section XI repair replacement plan and reconciliation for

replacement components/materials;

l. Certified Material Test Reports for replacement pressure boundary materials;

and

m. Copies of the NDE required by the construction Code and the pre-service

examination records required by the ASME Code Section XI for the selected

welds.

2. For the ISI-related corrective action issues selected by the inspector from Item A.7

above, provide a copy of the corrective actions and supporting documentation.

3. For the NDE reports with relevant indications on Code Class 1 and 2 Systems

selected by the inspector from Item A.4 above, provide a copy of the examination

records and associated corrective action documents.

4. Updated schedules for Item A.1 (including schedule showing contingency repair

plans if available).

5. Fabrication Drawings (D size) of the reactor vessel welds if any are to be examined

during the outage. Also provide any drawings used by NDE vendors to locate these

welds.

6. Provide copies of the following standards at the onsite U.S. Nuclear Regulatory

Commission inspection location for the duration of the inspection:

a. Sections V, IX, and XI of the ASME Code with Editions applicable to the ISI

Program and the Repair/Replacement Program; and

b. Copy of the performance demonstration initiative (PDI) generic procedures with

the latest applicable Revisions that support site qualified ultrasonic examination of

piping welds and components (e.g., PDI-UT-1, PDI-UT-2, PDI-UT-3, PDI-UT-10

etc.).

If you have questions regarding the information requested, please contact the lead inspector.

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