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{{#Wiki_filter:January 24, 2019
{{#Wiki_filter:January 24, 2019
  Mr. Robert Craven
Mr. Robert Craven
Site Director
Site Director
NextEra Energy Point Beach, LLC
NextEra Energy Point Beach, LLC
6610 Nuclear Road
6610 Nuclear Road
Two Rivers, WI 54241
Two Rivers, WI 54241-9516
-9516 SUBJECT: POINT BEACH
SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 1NOTIFICATION OF NRC BASELINE
NUCLEAR PLANT, UNIT 1-NOTIFICATION OF NRC BASELINE INSPECTION AND REQUEST FOR
              INSPECTION AND REQUEST FOR INFORMATION; INSPECTION
INFORMATION; INSPECTION REPORT 05000 266/20 19 00 1 Dear Mr. Craven: The U.S. Nuclear Regulatory Commission (NRC) will soon begin the Baseline Inservice Inspection Procedure 71111.08. This onsite inspection is scheduled to be performed March 25, 2019, through April 12, 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.
              REPORT 05000266/2019001
The first group identifies information necessary for inspection preparation. The second group  
Dear Mr. Craven:
identifies information the inspector will need upon arrival at the
The U.S. Nuclear Regulatory Commission (NRC) will soon begin the Baseline Inservice
site. It is important that all of
Inspection Procedure 71111.08. This onsite inspection is scheduled to be performed
these documents are up
March 25, 2019, through April 12, 2019.
-to-date and complete
Experience has shown that this inspection is resource intensive both for the NRC inspector and
to minimize requests during the preparation and/or the onsite portions of the inspection.
your staff. In order to minimize the impact to your onsite resources, and to ensure a productive
We have discussed the schedule for inspection activities with your staff and understand that our regulatory contact for this inspection will be Ms.
inspection for both sides, we have enclosed a request for documents needed for this inspection.
Kim Locke, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector
These documents have been divided into two groups.
Mr. Matt hew Domke at 630-829-9562, or via e-mail at MJD4@nrc.gov
The first group identifies information necessary for inspection preparation. The second group
. This letter does not contain new or amended information collection requirements subject  
identifies information the inspector will need upon arrival at the site. It is important that all of
to the Paperwork Reduction Act
these documents are up-to-date and complete to minimize requests during the preparation
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
and/or the onsite portions of the inspection.
-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
We have discussed the schedule for inspection activities with your staff and understand that our
Budget Control Number.
regulatory contact for this inspection will be Ms. Kim Locke, of your organization. If there are
R. Craven -2- This letter and its enclosure will be made available for public inspection and copying
any questions about this inspection or the material requested, please contact the lead inspector
at http://www.nrc.gov/reading
Mr. Matthew Domke at 630-829-9562, or via e-mail at MJD4@nrc.gov.
-rm/adams.html
This letter does not contain new or amended information collection requirements subject
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."
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
  Sincerely, /RA/   Matt hew Domke, Reactor Inspector
collection requirements were approved by the Office of Management and Budget, Control
Engineering Branch 1
Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
Division of Reactor Safety
respond to, a request for information or an information collection requirement unless the
  Docket No. 50-266 License No. DPR-24 Enclosure:
requesting document displays a currently valid Office of Management and Budget Control
Document Request for Inservice Inspection
Number.
cc: Distribution via LISTSERV
 
 
R. Craven                                   -2-
R. Craven -3- Letter to  
This letter and its enclosure will be made available for public inspection and copying at
Robert Craven from Matthew Domke dated January 2 4, 2019. SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 1
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
-NOTIFICATION OF NRC BASELINE INSPECTION AND REQUEST FOR
accordance with Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
INFORMATION; INSPECTION REPORT 05000266/20 19 00 1 DISTRIBUTION
Exemptions, Requests for Withholding.
: Aida Rivera-Varona RidsNrrDorlLpl3
                                            Sincerely,
RidsNrrPMPointBeach
                                            /RA/
RidsNrrDirsIrib Resource
                                            Matthew Domke, Reactor Inspector
Darrell Roberts
                                            Engineering Branch 1
John Giessner
                                            Division of Reactor Safety
Jamnes Cameron
Docket No. 50-266
Allan Barker
License No. DPR-24
DRPIII DRSIII                             ADAMS Accession Number: ML19024A277
Enclosure:
  OFFICE RIII        NAME MDomke:jw   DATE 0 1/24/19   OFFICIAL RECORD COPY
Document Request for Inservice Inspection
 
cc: Distribution via LISTSERV
DOCUMENT REQUEST FOR INSERVICE INSPECTION
 
Enclosure Inspection Report
R. Craven                               -3-
: 05000 266/20 19 00 1 Inspection
Letter to Robert Craven from Matthew Domke dated January 24, 2019.
Dates: March 25, 2019
SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 1NOTIFICATION OF NRC BASELINE
, through April 12, 2019
            INSPECTION AND REQUEST FOR INFORMATION; INSPECTION
Inspection
            REPORT 05000266/2019001
Procedures
DISTRIBUTION:
: Inspection Procedure 71111.08, Inservice Inspection
Aida Rivera-Varona
Lead Inspector
RidsNrrDorlLpl3
: Matt hew Domke, DRS 630-829-9562 MJD4@nrc.gov
RidsNrrPMPointBeach
A. Information for the  
RidsNrrDirsIrib Resource
i n-office preparation  
Darrell Roberts
w eek The following information is requested by February 25
John Giessner
, 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. The following information is applicable to the outage Unit 1 unless otherwise indicated
Jamnes Cameron
. If you have any questions regarding this information, please call the inspector.
Allan Barker
1. For the upcoming outage, a detailed schedule and description of:
DRPIII
a. Non-Destructive Examination (NDE) planned for ASME Class 1 and 2 systems and containment performed as part of the Inservice Inspection (IS I) program (please indicate applicable code edition and
DRSIII
addenda) and NDE s planned for other systems including risk
ADAMS Accession Number: ML19024A277
-informed, augmented, license renewal, and industry initiative inspection programs
  OFFICE RIII
. b. Reactor vessel upper head examinations required by Title 10 of the Code of Federal Regulations
NAME       MDomke:jw
(CFR), Part 50.55a(g)(6)(ii)(D) and Code Case N
DATE       01/24/19
-729; c. Steam generator (SG) tube inspection and repair activities for the upcoming outage or SG secondary side examinations
                                OFFICIAL RECORD COPY
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
                        DOCUMENT REQUEST FOR INSERVICE INSPECTION
.                                      
Inspection Report:                   05000266/2019001
        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.
Inspection Dates:                   March 25, 2019, through April 12, 2019
 
Inspection Procedures:               Inspection Procedure 71111.08, Inservice Inspection
DOCUMENT REQUEST FOR INSERVICE INSPECTION
Lead Inspector:                     Matthew Domke, DRS
2 2. A copy of the NDE procedures, SG eddy current examination (ET) acquisition  
                                    630-829-9562
and analysis procedures
                                    MJD4@nrc.gov
, and welding procedures used to perform the activities identified
A.       Information for the in-office preparation week
in Item A.1. For NDE procedures, please include calibration and flaw characterization/sizing procedures
        The following information is requested by February 25, 2019, to facilitate the selection of
, and , for welding procedures, please include applicable qualification records with the weld procedure specification. For ultrasonic examination procedures qualified in accordance with ASME Section XI, Appendix VIII, provide documentation supporting the
        specific items that will be reviewed during the onsite inspection week. The inspector will
procedure qualification (e.g., the Electric Power Research Institute
        select specific items from the information requested below and request a list of additional
performance demonstration qualification
        documents needed onsite to your staff. The following information is applicable to the
summary sheets).
        outage Unit 1 unless otherwise indicated. If you have any questions regarding this
3. A copy of ASME Section XI, Code  
        information, please call the inspector.
relief requests applicable to the examinations identified in Item A.1. 4. A copy of the 10
        1. For the upcoming outage, a detailed schedule and description of:
-year ISI Program showing those required exams scheduled to be performed this outage
              a. Non-Destructive Examination (NDE) planned for ASME Class 1 and 2 systems
and those which have been completed.
                  and containment performed as part of the Inservice Inspection (ISI) program
5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye penetrant)
                  (please indicate applicable code edition and addenda) and NDEs planned for
which have identified relevant indications on  
                  other systems including risk-informed, augmented, license renewal, and industry
Code Class 1 an
                  initiative inspection programs.
d 2 systems since the beginning of the last refueling outage.
              b. Reactor vessel upper head examinations required by Title 10 of the Code of
6. A list with short description of the welds in Code Class 1 and 2 Systems
                  Federal Regulations (CFR), Part 50.55a(g)(6)(ii)(D) and Code Case N-729;
which have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage. Please identify the system, weld number, and reference applicable documentation for each (e.g., NIS
              c. Steam generator (SG) tube inspection and repair activities for the upcoming
-2 forms with definitions of system and component acronyms).
                  outage or SG secondary side examinations 1; and
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. A list of corrective actions initiated since the beginning of the last refueling outage with description of ISI and SG
              d. Welding on Code Class 1, 2, or 3 components. For each weld examination,
-related issues such as piping or SG tube degradation or damage (e.g., cracks, wall thinning, wear, and microbiologically
                  include the weld identification number, description of weld (component name),
induced corrosion) or errors identified during piping/SG tube examinations. Also, please include a list of corrective actions associated with foreign material identified in the reactor vessel, primary coolant system, SG
                  category, class, type of exam and procedure number, and date of examination.
, or feed systems for the same timeframe. 9. A copy of any 10 CFR 21 reports applicable to your structures, systems, or components within the scope of ASME Section XI that have been identified since the beginning of the last refueling outage.
1
10. A copy of SG history documentation given to vendors
  Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur
performing ET of the SGs during the upcoming outage
and no further information is required for the items identified above requesting SG related information.
1. 11. A copy of procedure containing screening criteria used for selecting tubes for in
                                                                                                        Enclosure
-situ pressure testing and the procedure to be used for in
 
-situ pressure testing
                        DOCUMENT REQUEST FOR INSERVICE INSPECTION
1. 12. A copy of previous outage SG tube operational assessment completed following ET of the SGs
        2. A copy of the NDE procedures, SG eddy current examination (ET) acquisition
(provide this document even if no SG ET is planned for current outage)
              and analysis procedures, and welding procedures used to perform the activities
.                                        
              identified in Item A.1. For NDE procedures, please include calibration and flaw
        1 Note 1- If no SG examinations are planned for this outage, simply state
              characterization/sizing procedures, and, for welding procedures, please include
when the next SG examination will occur.
              applicable qualification records with the weld procedure specification. For
 
              ultrasonic examination procedures qualified in accordance with ASME Section XI,
DOCUMENT REQUEST FOR INSERVICE INSPECTION
              Appendix VIII, provide documentation supporting the procedure qualification
3 13. A copy of most recent SG Degradation Assessment
              (e.g., the Electric Power Research Institute performance demonstration
(provide this document even if no SG ET is planned for current outage).
              qualification summary sheets).
14. A copy of most recent SG Condition Monitoring Assessments
        3. A copy of ASME Section XI, Code relief requests applicable to the examinations
1. 15. A copy of the document defining the
              identified in Item A.1.
planned SG ET scope (e.g., 100
        4. A copy of the 10-year ISI Program showing those required exams scheduled to be
percent of unrepaired
              performed this outage and those which have been completed.
tubes with bobbin probe and 20
        5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye
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 Electric Power Research Institute Guidelines
              penetrant) which have identified relevant indications on Code Class 1 and 2 systems
1. 16. A 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  
              since the beginning of the last refueling outage.
- 0.080 inches, 0.115
        6. A list with short description of the welds in Code Class 1 and 2 Systems which have
inches pancake coils and mid
              been fabricated due to component repair/replacement activities since the beginning
-range + point coil applied at the top
              of the last refueling outage. Please identify the system, weld number, and reference
-of-tube-sheet plus  
              applicable documentation for each (e.g., NIS-2 forms with definitions of system and
3 inches to minus 12
              component acronyms).
inches) 1. 17. Provide procedures with guidance/instructions for identifying (e.g.
        7. If reactor vessel weld examinations required by the ASME Code are scheduled to
, physically locating the tubes that require repair) and plugging SG tubes
              occur during the inspection period, provide a detailed description of the welds to be
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.
              examined, and the extent of the planned examination.
19. Point of contact information (name and
        8. A list of corrective actions initiated since the beginning of the last refueling outage
site number) for the following activities:
              with description of ISI and SG-related issues such as piping or SG tube degradation
a. ISI-Site and vendor leads
              or damage (e.g., cracks, wall thinning, wear, and microbiologically induced corrosion)
; b. Boric Acid Inspection
              or errors identified during piping/SG tube examinations. Also, please include a list of
s and Evaluations
              corrective actions associated with foreign material identified in the reactor vessel,
; c. Reactor Vessel Head Inspection
              primary coolant system, SG, or feed systems for the same timeframe.
-Site and vendor leads
        9. A copy of any 10 CFR 21 reports applicable to your structures, systems, or
; d. SG Inspection
              components within the scope of ASME Section XI that have been identified
-Site and vendor leads
              since the beginning of the last refueling outage.
; e. Aging Management Programs; and f. Site Welding Engineer
        10. A copy of SG history documentation given to vendors performing ET of the SGs
. B. On site information to be  
              during the upcoming outage 1.
provided to the Inspector on the  
        11. A copy of procedure containing screening criteria used for selecting tubes for in-situ
first day of the  
              pressure testing and the procedure to be used for in-situ pressure testing1.
inspection (e.g., following the  
        12. A copy of previous outage SG tube operational assessment completed following ET
entrance meeting). Please provide hard copies (e.g., paper records) of the  
              of the SGs (provide this document even if no SG ET is planned for current outage).
following documents. 1. For welds selected by the inspector from Item A.1.d and A.6 above, provide copies of the following documents:
1 Note 1- If no SG examinations are planned for this outage, simply state when the next SG examination will occur.
a. Document of the weld number and location (e.g., system, train, branch);
                                                          2
b. Document with a detail of the weld construction (e.g., drawing);
 
                                       
                        DOCUMENT REQUEST FOR INSERVICE INSPECTION
        1 Note 1- If no SG examinations are planned for this outage, simply state
        13. A copy of most recent SG Degradation Assessment (provide this document even if
when the next SG examination will occur.
              no SG ET is planned for current outage).
 
        14. A copy of most recent SG Condition Monitoring Assessments1.
DOCUMENT REQUEST FOR INSERVICE INSPECTION
        15. A copy of the document defining the planned SG ET scope (e.g., 100 percent of
4 c. Applicable portions of the Design Specification and applicable Code of  
              unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion
Construction for the weldment (e.g., B31.1 or ASME Section III);
              transition regions with rotating probe) and identify the scope expansion criteria,
d. Applicable Code Edition and Addenda for weld procedure qualification;
              which will be applied. Also identify and describe any deviations in this scope or
e. Applicable weld procedure
              expansion criteria from the Electric Power Research Institute Guidelines1.
specifications
        16. A copy of the document describing the ET acquisition equipment to be applied
and weld data sheets
              including ET probe types. Also identify the extent of planned tube examination
used to fabricate the welds;
              coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches
f. Copies of procedure qualification records supporting the weld procedure specifications
              pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus
; g. Copies of welders' performance qualification records;
              3 inches to minus 12 inches) 1.
h. Copies of mechanical test reports identified in the weld procedure qualification records above; i. Copies of the nonconformance reports for the selected welds;
        17. Provide procedures with guidance/instructions for identifying (e.g., physically locating
j. Access to radiographs and equipment to view radiographs of the selected welds;
              the tubes that require repair) and plugging SG tubes 1.
k. ASME Code Section XI repair replacement plan and reconciliation for replacement components/materials;
        18. Identify and quantify any SG tube leakage experienced during the previous operating
l. Certified Material Test Reports for replacement pressure boundary materials; and
              cycle. Also provide documentation identifying which SG was leaking and corrective
m. Copies of the  
              actions completed or planned for this condition.
NDE required by the construction Code and the pre
        19. Point of contact information (name and site number) for the following activities:
-service examination records required by the ASME Code Section XI for the selected welds. 2. For the ISI
              a. ISISite and vendor leads;
-related corrective action issues selected by the inspector from Item A.8 above, provide a copy of the corrective actions and supporting documentation.
              b. Boric Acid Inspections and Evaluations;
3. For the NDE reports
              c. Reactor Vessel Head InspectionSite and vendor leads;
with relevant indications on Code Class
              d. SG InspectionSite and vendor leads;
1 and 2 Systems selected by the inspector from
              e. Aging Management Programs; and
Item A.5 above, provide a copy of
              f. Site Welding Engineer.
the examination records and associated corrective action documents.
B.       Onsite information to be provided to the Inspector on the first day of the
4. Updated schedules for Item
        inspection (e.g., following the entrance meeting). Please provide hard copies
A.1 (including schedule showing contingency repair plans if available).
        (e.g., paper records) of the following documents.
5. Fabrication
        1. For welds selected by the inspector from Item A.1.d and A.6 above, provide copies of
Drawings (D size) of the reactor vessel welds (including vessel head  
              the following documents:
J-groove welds)
              a. Document of the weld number and location (e.g., system, train, branch);
, if any are to be examined during the outage. Also provide any drawings used by NDE vendors to locate these welds.
              b. Document with a detail of the weld construction (e.g., drawing);
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.
1 Note 1- If no SG examinations are planned for this outage, simply state when the next SG examination will occur.
7. Copy of: a. Engineering evaluations/assessments of boric acid related deposits and associated wastage or corrosion for safety significant components; and
                                                          3
 
 
DOCUMENT REQUEST FOR INSERVICE INSPECTION
            DOCUMENT REQUEST FOR INSERVICE INSPECTION
5 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.
  c. Applicable portions of the Design Specification and applicable Code of
9. Copy of the documents which demonstrate that the procedures to be used for volumetric examination of the reactor vessel head penetration J
      Construction for the weldment (e.g., B31.1 or ASME Section III);
-groove welds were qualified by a blind
  d. Applicable Code Edition and Addenda for weld procedure qualification;
demonstration test in accordance with 1
  e. Applicable weld procedure specifications and weld data sheets used to fabricate
0 CFR 50.55a(g)(6)(ii)(D).
      the welds;
10. Copy of volumetric, surface and visual examination records for the prior inspection of the reactor vessel head and head penetration  
  f. Copies of procedure qualification records supporting the weld procedure
J-groove welds
      specifications;
. 11. Provide a copy of the Electric Power Research Institute
  g. Copies of welders performance qualification records;
Examination Technique Specification Sheets and vendor
  h. Copies of mechanical test reports identified in the weld procedure qualification
related documents, which support qualification  
      records above;
of the ET probes to be used during the upcoming SG tube inspections
  i. Copies of the nonconformance reports for the selected welds;
1. 12. Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs 1. 13. Identify the types of SG tube repair processes
  j. Access to radiographs and equipment to view radiographs of the selected welds;
, which will be implemented for defective SG tubes (including any U.S. Nuclear Regulatory Commission
  k. ASME Code Section XI repair replacement plan and reconciliation for
reviews/evaluation/approval of this repair process).
      replacement components/materials;
  Provide the
  l. Certified Material Test Reports for replacement pressure boundary materials; and
flaw depth sizing criteria to be applied for ET indications identified in the SG tubes
  m. Copies of the NDE required by the construction Code and the pre-service
1. 14. Copy of document describing actions to be taken if a new SG tube degradation  
      examination records required by the ASME Code Section XI for the selected
mechanism is identified
      welds.
1. 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).
2. For the ISI-related corrective action issues selected by the inspector from Item A.8
16. Provide procedures
  above, provide a copy of the corrective actions and supporting documentation.
with guidance/instructions for identifying
3. For the NDE reports with relevant indications on Code Class 1 and 2 Systems
(e.g., physically locating the tubes that require
  selected by the inspector from Item A.5 above, provide a copy of the examination
repair) and plugging
  records and associated corrective action documents.
SG tubes 1. 17. Provide copies of the following standards at the onsite U.S. Nuclear Regulatory Commission
4. Updated schedules for Item A.1 (including schedule showing contingency repair
inspection location for the duration of the inspection:
  plans if available).
a. Sections V, IX, and XI of the ASME Code with Editions applicable to the ISI Program and the Repair/Replacement  
5. Fabrication Drawings (D size) of the reactor vessel welds (including vessel head
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
  J-groove welds), if any are to be examined during the outage. Also provide any
-UT-1, PD I-UT-2, PDI-UT-3, PDI-UT-10 etc.);                                        
  drawings used by NDE vendors to locate these welds.
        1 Note 1- If no SG examinations are planned for this outage, simply indicate
6. Copy of the procedures which govern the scope, equipment used, and
when the next SG examination will occur.
  implementation of the inspections required to identify boric acid leakage from
 
  systems and components above the vessel head.
DOCUMENT REQUEST FOR INSERVICE INSPECTION
7. Copy of:
6 c. Electric Power Research Institute
  a. Engineering evaluations/assessments of boric acid related deposits and
and industry standards referenced in the site procedures used to perform
      associated wastage or corrosion for safety significant components; and
the SG tube  
                                          4
ET, which includes Electric Power Research Institute
 
documents: S
                        DOCUMENT REQUEST FOR INSERVICE INSPECTION
G Examination Guidelines, SG
              b. Corrective action records for coolant leakage including boric acid deposits on
Integrity Assessment Guidelines, S G In-Situ Pressure Test Guidelines
                  safety-related components identified since the beginning of the last refueling
1; and d. Boric Acid Corrosion Guidebook Revision 1
                  outage.
-Electric Power Research Institute Technical Report 1000975
        8. Copy of the plant procedures used to perform inspections to identify reactor coolant
. 18. Provide training (e.g., Scaffolding, Fall Protection, Foreign Material Exclusion) if required to access the non
              system leaks or boric acid deposits and the procedures for resolution of leaks or
-destructive examinations selected by the inspector for observation.
              boric acid deposits.
If you have questions regarding the information requested, please contact the lead inspector
        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
        1Note 1- If no SG examinations are planned for this outage, simply indicate
              qualified by a blind demonstration test in accordance with 10 CFR 50.55a(g)(6)(ii)(D).
when the next SG examination will occur.
        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).
        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.);
1 Note 1- If no SG examinations are planned for this outage, simply indicate when the next SG examination will occur.
                                                          5
 
                        DOCUMENT REQUEST FOR INSERVICE INSPECTION
              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 1Electric 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, simply indicate when the next SG examination will occur.
                                                        6
}}
}}

Revision as of 06:16, 20 October 2019

Ltr 01/24/19 Point Beach Nuclear Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2019001 (DRS-M.Domke)
ML19024A277
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 01/24/2019
From: Matthew Domke
NRC/RGN-III/DRS/EB1
To: Craven R
Point Beach
References
IR 2019001
Download: ML19024A277 (9)


See also: IR 05000266/2019001

Text

January 24, 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 1NOTIFICATION OF NRC BASELINE

INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000266/2019001

Dear Mr. Craven:

The U.S. Nuclear Regulatory Commission (NRC) will soon begin the Baseline Inservice

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

March 25, 2019, through April 12, 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 for inspection preparation. The second group

identifies information the inspector will need upon arrival at the site. It is important that all of

these documents are up-to-date and complete to minimize requests 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. Kim Locke, of your organization. If there are

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

Mr. Matthew Domke at 630-829-9562, or via e-mail at MJD4@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, Part 2.390, Public Inspections,

Exemptions, Requests for Withholding.

Sincerely,

/RA/

Matthew Domke, Reactor Inspector

Engineering Branch 1

Division of Reactor Safety

Docket No. 50-266

License No. DPR-24

Enclosure:

Document Request for Inservice Inspection

cc: Distribution via LISTSERV

R. Craven -3-

Letter to Robert Craven from Matthew Domke dated January 24, 2019.

SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 1NOTIFICATION OF NRC BASELINE

INSPECTION AND REQUEST FOR INFORMATION; INSPECTION

REPORT 05000266/2019001

DISTRIBUTION:

Aida Rivera-Varona

RidsNrrDorlLpl3

RidsNrrPMPointBeach

RidsNrrDirsIrib Resource

Darrell Roberts

John Giessner

Jamnes Cameron

Allan Barker

DRPIII

DRSIII

ADAMS Accession Number: ML19024A277

OFFICE RIII

NAME MDomke:jw

DATE 01/24/19

OFFICIAL RECORD COPY

DOCUMENT REQUEST FOR INSERVICE INSPECTION

Inspection Report: 05000266/2019001

Inspection Dates: March 25, 2019, through April 12, 2019

Inspection Procedures: Inspection Procedure 71111.08, Inservice Inspection

Lead Inspector: Matthew Domke, DRS

630-829-9562

MJD4@nrc.gov

A. Information for the in-office preparation week

The following information is requested by February 25, 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. The following information is applicable to the

outage Unit 1 unless otherwise indicated. If you have any questions regarding this

information, please call the inspector.

1. For the upcoming outage, a detailed schedule and description of:

a. Non-Destructive Examination (NDE) planned for ASME Class 1 and 2 systems

and containment performed as part of the Inservice Inspection (ISI) program

(please indicate applicable code edition and addenda) and NDEs planned for

other systems including risk-informed, augmented, license renewal, and industry

initiative inspection programs.

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;

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

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. For NDE procedures, please include calibration and flaw

characterization/sizing procedures, and, for welding procedures, please include

applicable qualification records with the weld procedure specification. For

ultrasonic examination procedures qualified in accordance with ASME Section XI,

Appendix VIII, provide documentation supporting the procedure qualification

(e.g., the Electric Power Research Institute performance demonstration

qualification summary sheets).

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. A 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. Please identify the system, weld number, and reference

applicable documentation for each (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. A list of corrective actions initiated since the beginning of the last refueling outage

with description of ISI and SG-related issues such as piping or SG tube degradation

or damage (e.g., cracks, wall thinning, wear, and microbiologically induced corrosion)

or errors identified during piping/SG tube examinations. Also, please include a list of

corrective actions associated with foreign material identified in the reactor vessel,

primary coolant system, SG, or feed systems for the same timeframe.

9. A copy of any 10 CFR 21 reports applicable to your structures, systems, or

components within the scope of ASME Section XI that have been identified

since the beginning of the last refueling outage.

10. A copy of SG history documentation given to vendors performing ET of the SGs

during the upcoming outage 1.

11. A 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. A 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).

1 Note 1- If no SG examinations are planned for this outage, simply state when the next SG examination will occur.

2

DOCUMENT REQUEST FOR INSERVICE INSPECTION

13. A copy of most recent SG Degradation Assessment (provide this document even if

no SG ET is planned for current outage).

14. A copy of most recent SG Condition Monitoring Assessments1.

15. A 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 Electric Power Research Institute Guidelines1.

16. A 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; and

f. Site Welding Engineer.

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);

1 Note 1- If no SG examinations are planned for this outage, simply state when the next SG examination will occur.

3

DOCUMENT REQUEST FOR INSERVICE INSPECTION

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

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.

4. Updated schedules for Item A.1 (including schedule showing contingency repair

plans if available).

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

4

DOCUMENT REQUEST FOR INSERVICE INSPECTION

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).

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.);

1 Note 1- If no SG examinations are planned for this outage, simply indicate when the next SG examination will occur.

5

DOCUMENT REQUEST FOR INSERVICE INSPECTION

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 1Electric 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, simply indicate when the next SG examination will occur.

6