ML19037A384
| ML19037A384 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/04/2019 |
| From: | Edison Fernandez NRC/RGN-III/DRS/EB1 |
| To: | Gebbie J Indiana Michigan Power Co |
| References | |
| IR 2019001 | |
| Download: ML19037A384 (9) | |
See also: IR 05000315/2019001
Text
February 4, 2019
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 1NOTIFICATION OF
NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000315/2019001; 05000316/2019001
Dear Mr. Gebbie:
On March 11, 2019, 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 11, 2019 through March 22, 2019.
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. M. Ellett, of your organization. If there are any
questions about this inspection or the material requested, please contact the lead inspector
Mr. E. Fernandez at 630-829-9754, or via e-mail at Edison.Fernandez@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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
Exemptions, Requests for Withholding.
Sincerely,
/RA/
Edison Fernandez, Reactor Inspector
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-315, 50-316
License Nos. DRP-58; DRP-74
Enclosure:
Document Request for Inservice Inspection
cc: Distribution via LISTSERV
J. Gebbie -3-
Letter to Joel P. Gebbie from Edison Fernandez dated February 4, 2019.
SUBJECT: DONALD C. COOK NUCLEAR POWER PLANT, UNIT 1NOTIFICATION OF
NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000315/2019001; 05000316/2019001
DISTRIBUTION:
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ADAMS Accession Number: ML19037A384
OFFICE RIII RIII RIII RIII
NAME EFernandez:cl
DATE 02/04/19
OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR INSERVICE INSPECTION
Inspection Report: 05000315/2019001; 05000316/2019001;
Inspection Dates: March 11, 2019 through March 22, 2019
Inspection Procedures: Inspection Procedure 71111-08, Inservice Inspection
Lead Inspector: Edison Fernandez, DRS
630-829-9754
Edison.Fernandez@nrc.gov
A. Information for the In-Office Preparation Week
The following information (electronic copy CD ROM if possible) is requested by
March 4, 2019, 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-770-1 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-729-4;
c. Steam generator (SG) tube inspection and repair activities for the upcoming
outage or SG secondary side examinations 1; 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.
Enclosure
DOCUMENT REQUEST FOR INSERVICE INSPECTION
e. Planned 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.
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 EPRI
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 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 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 ET 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.
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DOCUMENT REQUEST FOR INSERVICE INSPECTION
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).
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 EPRI 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 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. 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
g. Baffle-former-boltSite and vendor project 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.
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DOCUMENT REQUEST FOR INSERVICE INSPECTION
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 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
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).
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DOCUMENT REQUEST FOR INSERVICE INSPECTION
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 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.
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 inspections 1.
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).
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.
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DOCUMENT REQUEST FOR INSERVICE INSPECTION
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.);
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 Guidelines 1; and
d. Boric Acid Corrosion Guidebook Revision 2Electric 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.
6