Text

Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004
	ML16193A654
Person / Time
Site:	Cook
Issue date:	07/11/2016
From:	James Neurauter; NRC/RGN-III/DRS/EB1
To:	Gebbie J; Indiana Michigan Power Co, Nuclear Generation Group
References
	IR 2016004
	Download: ML16193A654 (9)
	v • d • e

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE RD. SUITE 210

LISLE, IL 60532-4352

July 11, 2016

Mr. Joel 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 2 - NOTIFICATION

OF NRC INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000315/2016004; 05000316/2016004

Dear Mr. Gebbie:

On October 11, 2016, the U. S. Nuclear Regulatory Commission (NRC) will begin the Baseline

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

October 11, 2016, through November 10, 2016.

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 Ms. K. Harper, of your organization. If there are any

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

Mr. J. Neurauter at 630-829-9828, or via e-mail at James.Neurauter@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-

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public

Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy

of this letter, its enclosure, and your response (if any) will be available electronically for public

inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)

component of the NRC's Agencywide Documents Access and Management System (ADAMS).

ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html

(the Public Electronic Reading Room).

Sincerely,

/RA/

James E. Neurauter, Senior Reactor Inspector

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 50-315; 50-316

License Nos. DPR-58; DPR-74

Enclosure:

Baseline Inservice Inspection Document Request

cc: Distribution via LISTSERV

BASELINE INSERVICE INSPECTION DOCUMENT REQUEST

Inspection Report: 05000315/2016004; 05000316/2016004

Inspection Dates: October 11, 2016, through November 10, 2016

Inspection Procedures: IP 71111-08, Inservice Inspection

Lead Inspector: James Neurauter, DRS

630-829-9828

James.Neurauter@nrc.gov

I. Information for the In-Office Preparation Week

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

September 26, 2016, 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 a list of additional documents needed onsite 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 2

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-770-1 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 examinations1;

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

e. Baffle-former bolt examinations performed in accordance with the D.C. Cook

Nuclear Plant, Units 1 and 2, Reactor Vessel Internals Aging Management

Program.

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

BASELINE 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 [Electric Power Research Institute] 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, SG

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

9. Copy of any Title 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 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.

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

BASELINE INSERVICE INSPECTION DOCUMENT REQUEST

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

of the SGs1.

13. 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 Guidelines1.

14. 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.

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

the tubes that require repair) and plugging SG tubes1.

16. 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.

17. 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.

18. 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. SG Inspection - Site and vendor leads

e. Baffle-former bolt examinations - Site and vendor leads

II. 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);

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

BASELINE INSERVICE INSPECTION DOCUMENT REQUEST

c. Applicable Code Edition and Addenda for construction of the weldment

(e.g., B31.1 or ASME Section III);

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

e. Applicable WPs and weld data sheets used to fabricate the welds;

f. Copies of procedure qualification records supporting the WPs;

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; and

k. Copies of the pre-service examination records 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. 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).

4

BASELINE INSERVICE INSPECTION DOCUMENT REQUEST

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

documents, which support qualification of the ET probes to be used during the

upcoming SG tube inspections1.

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

identified in the SGs1.

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 tubes1.

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

mechanism is identified1.

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 tubes1.

16. Provide procedures for baffle-former bolt NDE performed in accordance with

the D.C. Cook Nuclear Plant, Units 1 and 2, Reactor Vessel Internals Aging

Management Program including associated vendor procedures and ultrasonic and

visual examination qualification documents for the vendor procedures.

17. Provide degraded/missing baffle bolt/repair/replacement plans; vendor documents

that establish acceptance criteria for minimum acceptable baffle bolt patterns; and

drawings associated with reactor internal areas to be inspected during the outage.

18. Provide a copy of Unit 1 records related to degraded or missing baffle bolts including

site acceptance criteria used to allow continued operation with the identified

degraded or missing fasteners.

19. Provide copies of the following standards at the onsite 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.);

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

BASELINE INSERVICE INSPECTION DOCUMENT REQUEST

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,

SG Management Program: Steam Generator Integrity Assessment Guidelines,

Part 10, and 1003138, Pressurized Water Reactor Steam Generator

Examination Guidelines1;

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

baffle-former bolt ultrasonic and visual examination, which includes: MRP-227-A,

Pressurized Water Reactor Internals Inspection and Evaluation Guidelines,

MRP-228, Materials Reliability Program: Inspection Standard for PWR

Internals, and WCAP-17096, Reactor Internals Acceptance Criteria

Methodology and Data Requirements; and

e. 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.

6

J. Gebbie -2-

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public

Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy

of this letter, its enclosure, and your response (if any) will be available electronically for public

inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)

component of the NRC's Agencywide Documents Access and Management System (ADAMS).

ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html

(the Public Electronic Reading Room).

Sincerely,

/RA/

James E. Neurauter, Senior Reactor Inspector

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 50-315; 50-316

License Nos. DPR-58; DPR-74

Enclosure:

Baseline Inservice Inspection Document Request

cc: Distribution via LISTSERV

DISTRIBUTION:

Jeremy Bowen

RidsNrrDorlLpl3-1 Resource

RidsNrrPMDCCook Resource

RidsNrrDirsIrib Resource

Cynthia Pederson

DRPIII

DRSIII

ADAMS Accession Number ML16193A654

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To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy

OFFICE RIII RIII RIII RIII

NAME JNeurauter:

DATE 07/11/16

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ML16193A654

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