ML23310A115

Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002

ML23310A115
Person / Time
Site:	Cook
Issue date:	11/06/2023
From:	Magnuson E NRC/RGN-III/DORS/ERPB
To:	Lies Q Indiana Michigan Power Co
References
IR 2024002
Download: ML23310A115 (1)

See also: IR 05000316/2024002

Text

Q. Shane Lies

Senior VP and Chief Nuclear Officer

Indiana Michigan Power Company

Nuclear Generation Group

One Cook Place

Bridgman, MI 49106

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNIT 2 - NOTIFICATION OF NRC

BASELINE INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000316/2024002

Dear Q. Shane Lies:

On March 25, 2024, 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 25, 2024, through April 12, 2024.

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 Steve Mitchell, of your organization. If there are any

questions about this inspection or the material requested, please contact the lead inspector

Eric A. Magnuson at 630-829-9798, or via email at eric.magnuson@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 3150-0011. 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.

November 6, 2023

Q. Lies

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,

Eric Magnuson, Reactor Inspector

Engineering and Reactor Projects Branch

Division of Operating Reactor Safety

Docket No. 5000316

License No. DPR-74

Enclosure:

Document Request for Inservice Inspection

cc: Distribution via LISTSERV

Signed by Magnuson, Eric

on 11/06/23

ML23310A115

SUNSI Review

Non-Sensitive

Sensitive

Publicly Available

Non-Publicly Available

OFFICE

RIII

NAME

EMagnuson:sw

DATE

11/06/2023

DOCUMENT REQUEST FOR INSERVICE INSPECTION

Enclosure

Inspection Dates:

March 25, 2024-April 12, 2024

Inspection Procedures:

Inspection Procedure 71111-08, Inservice Inspection

Lead Inspector:

Eric A. Magnuson, DORS

630-829-9798

eric.magnuson@nrc.gov

A.

Information for the In-Office Preparation Week

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

February 26, 2024, 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. The following information is applicable to the outage

Unit, unless otherwise indicated. 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 (e.g., ASME Code Case N-770 examination of dissimilar

metal welds and examinations to meet an industry initiative).

b.

Reactor vessel upper head examinations required by Title 10 of the Code of

Federal Regulations (CFR), Part 50.55a(g)(6)(ii)(D) and Code Case N-729;

c.

Steam generator (SG) tube inspection and repair activities for the upcoming

outage or SG secondary side examinations1; and

d.

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

1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur

and no further information is required for the items identified above requesting SG related information.

DOCUMENT REQUEST FOR INSERVICE INSPECTION

2

2.

A copy of the NDE procedures, SG eddy current examination (ET) acquisition and

analysis procedures, and welding procedures used to perform the activities identified

in Item 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). For SG tube ET this includes the acquisition and analysis procedures.

3.

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

identified in Item 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.

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, 2, and 3 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 and SG-related issues such as piping or SG tube

degradation or damage (e.g., cracks, wall thinning, wear, microbiologically induced

corrosion) or errors identified during piping/SG tube 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, primary coolant system, SG, or

feed systems 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. Copy of SG history documentation given to vendors performing ET of the SGs during

the upcoming outage1.

11. Copy of procedure containing screening criteria used for selecting tubes for in-situ

pressure testing and the procedure to be used for in-situ pressure testing1.

12. Copy of previous outage SG tube operational assessment completed following ET of

the SGs (provide this document even if no SG ET is planned for current outage).

1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur

and no further information is required for the items identified above requesting SG-related information.

DOCUMENT REQUEST FOR INSERVICE INSPECTION

3

13. Copy of most recent SG Degradation Assessment (provide this document even if no

SG ET is planned for current outage).

14. Copy of most recent SG Condition Monitoring Assessments1.

15. Copy of the document defining the planned SG ET scope (e.g., 100 percent of

unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion

transition regions with rotating probe) and identify the scope expansion criteria,

which will be applied. Also identify and describe any deviations in this scope or

expansion criteria from the Electric Power Research Institute Guidelines1.

16. Copy of the document describing the ET acquisition equipment to be applied

including ET probe types. Also identify the extent of planned tube examination

coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches

pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus

3 inches to minus 12 inches) 1.

17. Provide procedures with guidance/instructions for identifying (e.g., physically locating

the tubes that require repair) and plugging SG tubes1.

18. Identify and quantify any SG tube leakage experienced during the previous operating

cycle. Provide documentation identifying which SG was leaking and/or

documentation of any significant chemistry excursion events (e.g., EPRI 1008224

Pressurized Water Reactor Secondary Water Chemistry Guidelines Action Levels 1,

2, or 3) and corrective actions completed or planned for these conditions.

19. Point of contact information (name and site number) for the following activities:

a.

ISISite and vendor leads;

b.

Boric Acid Inspections and Evaluations;

c.

Reactor Vessel Head InspectionSite and vendor leads;

d.

SG InspectionSite and vendor leads;

e.

Aging Management Programs;

f.

Site Welding Engineer.

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 Item A.1.d and A.6 above, provide copies of

the following documents:

a.

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

1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur

and no further information is required for the items identified above requesting SG related information.

DOCUMENT REQUEST FOR INSERVICE INSPECTION

4

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 weld data sheets used to fabricate

the welds;

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 weld procedure qualification

records above;

i.

Copies of the nonconformance 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.8

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.5 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 (including vessel head

J-groove welds) if any are to be examined during the outage. Also provide any

drawings used by NDE vendors to locate these welds.

6.

Copy of the procedures which govern the scope, equipment used, and

implementation of the inspections required to identify boric acid leakage from

systems and components above the vessel head.

7.

Copy of:

a.

Engineering evaluations/assessments of boric acid related deposits and

associated wastage or corrosion for safety-related components; and

DOCUMENT REQUEST FOR INSERVICE INSPECTION

5

b.

Corrective action records for coolant leakage including boric acid deposits on

safety-related components identified since the beginning of the last refueling

outage.

8.

Copy of the plant procedures used to perform inspections to identify reactor coolant

system leaks or boric acid deposits and the procedures for resolution of leaks or

boric acid deposits.

9.

Copy of the documents which demonstrate that the procedures to be used for

volumetric examination of the reactor vessel head penetration J-groove welds were

qualified by a blind demonstration test in accordance with 10 CFR 50.55a(g)(6)(ii)(D).

10. Copy of volumetric, surface, and visual examination records for the prior inspection

of the reactor vessel head and head penetration J-groove welds.

11. Provide a copy of the Electric Power Research Institute Examination Technique

Specification Sheets and vendor related documents, which support qualification of

the ET probes to be used during the upcoming SG tube inspections1.

12. Provide a copy of the guidance to be followed if a loose part or foreign material is

identified in the SGs1.

13. Identify the types of SG tube repair processes which will be implemented for

defective SG tubes (including any U.S. Nuclear Regulatory Commission

reviews/evaluation/approval of this repair process). Provide the flaw depth sizing

criteria to be applied for ET indications identified in the SG tubes1.

14. Copy of document describing actions to be taken if a new SG tube degradation

mechanism is identified1.

15. Provide document which defines the scope of SG secondary side examinations (if

any are planned) and identify site-specific operational history related to degradation

of SG secondary side components (if any).

16. Provide procedures with guidance/instructions for identifying (e.g., physically locating

the tubes that require repair) and plugging SG tubes1.

17. 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;

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.);

1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur

and no further information is required for the items identified above requesting SG related information.

DOCUMENT REQUEST FOR INSERVICE INSPECTION

6

c.

Electric Power Research Institute and industry standards referenced in the site

procedures used to perform the SG tube ET, which includes Electric Power

Research Institute documents: SG Examination Guidelines, SG Integrity

Assessment Guidelines, SG In-Situ Pressure Test Guidelines1; and

d.

Boric Acid Corrosion Guidebook Revision 1Electric Power Research Institute

Technical Report 1000975.

18. Provide training (e.g., Scaffolding, Fall Protection, Foreign Material Exclusion) if

required to access the non-destructive examinations selected by the inspector for

observation.

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

1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur

and no further information is required for the items identified above requesting SG related information.