ML19361A075
| ML19361A075 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/27/2019 |
| From: | Mel Holmberg NRC/RGN-III/DRS/EB1 |
| To: | Craven R Point Beach |
| References | |
| IR 2020001 | |
| Download: ML19361A075 (9) | |
See also: IR 05000266/2020001
Text
December 27, 2019
Mr. Robert Craven
Site Director
NextEra Energy Point Beach, LLC
6610 Nuclear Road
Two Rivers, WI 54241-9516
SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 2NOTIFICATION OF NRC
BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000266/2020001; 05000301/2020001
Dear Mr. Craven:
On March 16, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin the Baseline
Inservice Inspection Procedure 71111.08. This on-site inspection is scheduled to be performed
March 16, 2020, through March 26, 2020.
Experience has shown that this inspection is resource intensive both for the NRC inspector
and your staff. 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
on-site 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. Thomas Schneider, 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.
R. Craven -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 2.390, Public Inspections,
Exemptions, Requests for Withholding.
Sincerely,
/RA/
Mel Holmberg, Reactor Inspector
Engineering Branch 1
Division of Reactor Safety
Docket Nos: 50-266; 50-301
Enclosure:
Baseline Inservice Inspection
Document Request
cc w/encl: Distribution via LISTSERV
R. Craven -3-
Letter to Robert Craven from M Holmberg dated December 27, 2019.
SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 2NOTIFICATION OF NRC
BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000266/2020001; 05000301/2020001
DISTRIBUTION:
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ADAMS Accession Number: ML19361A075
OFFICE RIII
NAME MHolmberg:jw
DATE 12/27/19
OFFICIAL RECORD COPY
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Report 05000266/2020001; 05000301/2020001
Inspection Dates: March 16 - 26, 2020
Inspection Procedures: Inspection Procedure 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
March 2, 2020, 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 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 (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 NDE planned for other systems performed
as part of a Risk-Informed (RI)-ISI Program, or other augmented inspection
programs (e.g., ASME Code Case N-770-2 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 (10 CFR) 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
d. Welding on Code Class 1, 2, or 3 components (including contingency repair
welding for dissimilar metal welds); and
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
e. Inspections required under Nuclear Energy Institute (NEI) 03-08 such as
MRP 227, 146, 192 or other Mandatory, Needed or Good Practice
requirements under the material initiative.
2. A copy of the NDE procedures and welding procedures (including contingency weld
repair procedures for dissimilar metal weld repairs) 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 NRC approved Relief Request for
implementing a RI-ISI Program (if applicable). This should include relief request
for extension of RVH inspections 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. Also, provide a list
that identifies the 37 welds within the Unit 2 risk-based ISI program plan sample to
be credited for risk category R1.20 Elements not Subject to a Damage
Mechanism.
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 issues identified
during containment, piping or 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. Additionally,
provide a list of any issues entered into the corrective action system associated with
the Class 3 service water piping segment in the cable spreading room identified as
high safety significance within the risk-based ISI program.
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.
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BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
10. Copy of SG history documentation given to vendors performing eddy current (ET)
testing of the SGs during the upcoming outage. 1
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
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 Guidelines.1
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).
15. Provide procedures with guidance/instructions for identifying (e.g., physically
locating the tubes that require repair) and plugging SG tubes. 2
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. Point of contact information (name and site number) for the following activities:
a. Inservice Inspection-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. NEI 03-08 Program Owner; and
f. Baffle Former Bolt examinations.
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 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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BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
B. On-Site 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 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 qualification;
e. Applicable weld procedures (WPS) used to fabricate the welds;
f. Copies of procedure qualification records (PQRs) supporting the WPS;
g. Copies of welders performance qualification records (WPQ);
h. Copies of mechanical test reports identified in the PQRs above;
i. Copies of the nonconformance 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 non-destructive examination 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-related components (since beginning
of last refueling outage); 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.
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BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
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. 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. 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).
7. Copy of volumetric, surface and visual examination records for the prior inspection
of the reactor vessel head and head penetration J-groove welds.
8. 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 inspections. 1
9. Provide a copy of the guidance to be followed if a loose part or foreign material
is identified in the SGs. 1
10. 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
11. Copy of document describing actions to be taken if a new SG tube degradation
mechanism is identified. 1
12. 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).
13. Provide procedures with guidance/instructions for identifying (e.g., physically
locating the tubes that require repair) and plugging SG tubes.1
14. 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
inservice inspection 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.
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BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
c. EPRI and industry standards referenced in the site procedures used to
perform the SG tube eddy current 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, Pressurized Water
Reactor Steam Generator Examination Guidelines;1 and
d. Boric Acid Corrosion Guidebook, Revision 2 - EPRI Technical Report 1000975.
15. Provide training (e.g., Scaffolding, Fall Protection, FME) if required to access the
NDES selected by the inspector for observation.
16. Site records that establish the basis for the baffle former bolt inspection and
reinspection schedules for both Units. Specifically, documents that applied the
MRP 2017-009 guidance related to untestable baffle former bolts (e.g., that these
bolts should be reviewed on a plant-specific basis consistent with WCAP-17096-
NP-A for determination if these should be considered when evaluating clustering).
17. Site visual examination records that identify the number and locations of baffle
former bolts that could not be examined by ultrasonic methods and dates for last
baffle former bolt visual and ultrasonic examinations (both Units).
If you have questions regarding the information requested, please contact the lead inspector.
6