ML18012A511
| ML18012A511 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/10/2018 |
| From: | Laura Smith NRC/RGN-III/DRS/EB1 |
| To: | Gebbie J Indiana Michigan Power Co |
| References | |
| IR 2018002 | |
| Download: ML18012A511 (9) | |
See also: IR 05000315/2018002
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, ILLINOIS 60532-4352
January 10, 2018
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 2NOTIFICATION OF
NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000315/2018002; 05000316/2018002
Dear Mr. Gebbie:
On March 5 2018, 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 5, 2018, to April 20, 2018.
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. Kristen Harper of your organization. If there are
any questions about this inspection or the material requested, please contact the lead inspector
Dr. Laura Smith at 630-829-9688 or via e-mail at Laura.Smith@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 Acting for/
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-315; 50-316
Enclosure:
Document Request for Inservice Inspection
cc: Distribution via LISTSERV
J. Gebbie
-3-
Letter to Joel P. Gebbie from Laura Smith dated January 10, 2018
SUBJECT: DONALD C. COOK NUCLEAR POWER PLANT, UNIT 2NOTIFICATION OF
NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000315/2018002; 05000316/2018002
DISTRIBUTION:
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Kenneth OBrien
DRPIII
DRSIII
ADAMS Accession Number ML18012A511
OFFICE
RIII
RIII
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NAME
MHolmberg:cl
DATE
01/10/18
OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR INSERVICE INSPECTION
Enclosure
Inspection Dates:
March 5, 2018, through April 20, 2018
Inspection Procedures:
IP 71111-08, Inservice Inspection
Lead Inspector:
630-829-9688
Laura.Smith@nrc.gov
A.
Information for the In-Office Preparation Week
The following information is requested as an (electronic copy CD ROM if possible) by
February 14, 2018, 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 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 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-729-4;
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. Planned baffle former bolt and edge bolt examinations as identified in
Westinghouse Nuclear Safety Advisory Letter-16-1 Baffle-Former Bolts,
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.
2
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, MIC) 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 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.
3
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).
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. 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-729-4
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 and 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.
4
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 procedures and weld data sheets used to fabricate the
f. Copies of procedure qualification records supporting the weld procedures;
g. Copies of welders performance qualification records;
h. Copies of mechanical test reports identified in the 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
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 NDEs 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. 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
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
8.
J-groove welds) if any are to be examined during the outage. Also provide any
drawings used by NDE vendors to locate these welds.
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.
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 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
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 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.
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.
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
17.
Provide a copy of the document that identifies the scope of the Unit 2
baffle-former bolt and baffle-edge bolt inspection. Additionally, (when available)
provide the scope and schedules for baffle former bolt and if required baffle-edge
bolt repairs.
18.
Provide a copy of the engineering change, work order and procedures used for
baffle former bolt replacement. Also provide vendor documents supporting
qualification of new equipment (e.g., if different vendor equipment is applied than
used during last Unit 2 outage) for this work.
19.
Provide a copy of license basis analysis (and NRC acceptance review for this
analysis) for the Unit 2 baffle former assembly and provide a copy of applicable
vendor analysis completed to support inspections and/or anticipated repairs to
baffle former bolts.
20.
Provide a copy of operability evaluations for the Unit 2 degraded baffle-former
bolts (if any were returned to service) and the degraded baffle-edge bolts.
21.
Provide a copy of ARs related to baffle former bolts in Unit 2 issued since the
beginning of the previous Unit 2 outage.
22.
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.);
c. EPRI and industry standards referenced in the site procedures used to
perform the SG tube ET, 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, Pressurized Water Reactor Steam Generator Examination
Guidelines1; and
d. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report
1000975.
23.
Provide training (e.g., Scaffolding, Fall Protection, FME) 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.