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17 Donald C. Cook Nuclear Power Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information (05000315/2017003; 05000316/2017003) (Msh)
	ML17108A777
Person / Time
Site:	Cook
Issue date:	04/18/2017
From:	Mel Holmberg; NRC/RGN-III/DRS/EB1
To:	Gebbie J; Indiana Michigan Power Co
References
	IR 2017003
	Download: ML17108A777 (9)
	v • d • e

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE RD. SUITE 210

LISLE, IL 60532-4352

April 18, 2017

Mr. Joel P. Gebbie

Senior VP and Chief Nuclear Officer

Indiana Michigan Power Company

Nuclear Generation Group

One Cook Place

Bridgman, MI 49106

SUBJECT: DONALD C. COOK NUCLEAR POWER PLANT, UNIT 1 - NOTIFICATION OF

NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION

(05000315/2017003; 05000316/2017003)

Dear Mr. Gebbie:

On September 18, 2017, the U. S. Nuclear Regulatory Commission (NRC) will begin the

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

performed September 18, 2017, through September 28, 2017.

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 on-site 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. M. Ellet, of your organization. If there are any

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

Mr. M. Holmberg at 630-829-9748 or via e-mail at msh@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.

J. Gebbie -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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Mel Holmberg

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 50-315; 50-316

License Nos. DPR-58; DPR-74

Enclosure:

Inservice Inspection Document Request

cc: Distribution via LISTSERV

J. Gebbie -3-

Letter to Joel P. Gebbie from Mel Holmberg dated April 18, 2017

SUBJECT: DONALD C. COOK NUCLEAR POWER PLANT, UNIT 1 - NOTIFICATION OF

NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION

(05000315/2017003; 05000316/2017003)

DISTRIBUTION:

Jeremy Bowen

RidsNrrDorlLpl3

RidsNrrPMDCCook Resource

RidsNrrDirsIrib Resource

Cynthia Pederson

DRPIII

DRSIII

ADAMS Accession Number ML17108A777

OFFICE RIII RIII RIII RIII

NAME MHolmberg:cl

DATE 04/18/17

OFFICIAL RECORD COPY

INSERVICE INSPECTION DOCUMENT REQUEST

Inspection Dates: September, 18 - 28, 2017

Inspection Procedures: IP 71111-08, Inservice Inspection

Lead Inspector: Mel Holmberg, DRS

630-829-9748

msh@nrc.gov

A. Information for the In-Office Preparation Week

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

August, 23, 2017, to facilitate the selection of specific items that will be reviewed during

the on-site inspection week. The inspector will select specific items from the information

requested below and a list of additional documents needed on-site from 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 Unit 1 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 (NDE) 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-770-1 examination of dissimilar metal welds and

examinations to meet 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;

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-729-1;

c. steam generator (SG) tube inspection and repair activities for the upcoming

outage or SG secondary side examinations 1;

d. welding on Code Class 1, 2, or 3 components; and

e. baffle former bolt examinations as identified in Westinghouse Nuclear Safety

Advisory Letter 16-1 Baffle-Former Bolts, Electric Power Research Institute

(EPRI) MRP 2017-009 Letter dated March 15, 2017 and MRP 2016-022 dated

July 27, 2016.

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.

Enclosure

INSERVICE INSPECTION DOCUMENT REQUEST

2. A copy of the NDE 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 EPRI performance demonstration qualification summary

sheets).

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

identified in Item A.1. This would include the U.S. Nuclear Regulatory Commission

(NRC) approved Relief Request for implementing a risk-informed ISI Program (if

applicable).

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 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 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, steam

generator or feed systems since the beginning of the last refueling outage.

9. Copy of any 10 CFR 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 eddy current (ET)

testing of the SGs during the upcoming outage.1.

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.

2

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 testing. 1

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).

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 Assessments.1

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 EPRI Guidelines.1

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).

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

the tubes that require repair) and plugging SG tubes.1

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

operating cycle. Also provide documentation identifying which SG was leaking and

corrective actions completed or planned for this condition.

19. Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1

that establish the volumetric and visual examination frequency for the reactor vessel

head and J-groove welds.

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

a. ISI - Site and vendor leads

b. Boric Acid Inspections and Evaluations

c. Reactor Vessel Head Inspection - Site and vendor leads

d. Baffle Former Bolt Inspection & Repairs - Site and vendor leads

e. SG Inspection - Site and vendor leads

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.

3

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);

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 prodecure 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. Updated schedules for Item

A.1 (including schedule showing contingency repair plans if available).

4

4. 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.

5. Copy of:

a. Engineering evaluations/assessments of boric acid related deposits and

associated wastage or corrosion for safety significant components; and

b. Corrective action records for coolant leakage including boric acid deposits on

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

outage.

6. 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.

7. 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.

8. 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).

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

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

10. Provide a copy of the EPRI Examination Technique Specification Sheets and vendor

Examination Technique Specification Sheets related documents, which support

qualification of the ET probes to be used during the upcoming SG tube inspections.1

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

identified in the SGs. 1

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

defective SG tubes (including any NRC reviews/evaluation/approval of this repair

process). Provide the flaw depth sizing criteria to be applied for ET indications

identified in the SG tubes. 1

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

mechanism is identified. 1

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.

5

14. 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).

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

the tubes that require repair) and plugging SG tubes.1

16. Provide a copy of the document that identifies the scope of the Unit 1 baffle former

bolt inspection.

17. Provide a copy of the engineering change, work order and procedures used for baffle

former bolt replacement.

18. Provide a copy of license basis analysis (and NRC acceptance review for this

analysis) for the Unit 1 baffle former assembly and provide a copy of applicable

vendor analysis completed to support inspections and/or anticipated repairs to baffle

former bolts.

19. Provide copies of the following standards at the on-site NRC 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.);

c. EPRI and industry standards referenced in the site procedures used to

perform the SG tube ET examination, which includes EPRI documents:

TR 107621-R1, Steam Generator Integrity Assessment Guidelines,

TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines, Steam

Generator Management Program: Steam Generator Integrity Assessment

Guidelines, Part 10, and 1003138, Pressurized1 Water Reactor Steam

Generator Examination Guidelines1; and

d. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975.

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

required to access the NDEs 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.

6

ML17108A777

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