ML16193A654
| 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) | |
See also: IR 05000315/2016004
Text
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
Enclosure:
Baseline Inservice Inspection Document Request
cc: Distribution via LISTSERV
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
Enclosure
Inspection Report: 05000315/2016004; 05000316/2016004
Inspection Dates:
October 11, 2016, through November 10, 2016
Inspection Procedures:
IP 71111-08, Inservice Inspection
Lead Inspector:
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.
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
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 [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.
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
3
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.
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
4
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).
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
5
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.
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
6
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.
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
Enclosure:
Baseline Inservice Inspection Document Request
cc: Distribution via LISTSERV
DISTRIBUTION:
RidsNrrDorlLpl3-1 Resource
RidsNrrPMDCCook Resource
RidsNrrDirsIrib Resource
Cynthia Pederson
DRPIII
DRSIII
ADAMS Accession Number ML16193A654
Publicly Available
Non-Publicly Available
Sensitive
Non-Sensitive
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
OFFICIAL RECORD COPY