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| number = ML18156A553 | | number = ML18156A553 | ||
| issue date = 06/05/2018 | | issue date = 06/05/2018 | ||
| title = | | title = Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2018004; 05000306/2018004 (DRS-M.Holmberg) | ||
| author name = Holmberg M | | author name = Holmberg M | ||
| author affiliation = NRC/RGN-III/DRS/EB1 | | author affiliation = NRC/RGN-III/DRS/EB1 | ||
| addressee name = Sharp S | | addressee name = Sharp S | ||
Line 14: | Line 14: | ||
| page count = 9 | | page count = 9 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000282/2018004]] | ||
=Text= | =Text= | ||
{{#Wiki_filter:June 5, 2018 | {{#Wiki_filter:June 5, 2018 | ||
S. Sharp -2- | Mr. Scott Sharp | ||
S. Sharp -2- | Site Vice President | ||
INSERVICE INSPECTION DOCUMENT REQUEST | Prairie Island Nuclear Generating Plant | ||
INSERVICE INSPECTION DOCUMENT REQUEST | Northern States Power Company, Minnesota | ||
INSERVICE INSPECTION DOCUMENT REQUEST | 1717 Wakonade Drive East | ||
INSERVICE INSPECTION DOCUMENT REQUEST | Welch, MN 55089-9642 | ||
INSERVICE INSPECTION DOCUMENT REQUEST | SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1NOTIFICATION | ||
INSERVICE INSPECTION DOCUMENT REQUEST | OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION; | ||
INSPECTION REPORT 05000282/2018004; 05000306/2018004 | |||
Dear Mr. Sharp: | |||
On October 1, 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 | |||
October 1, 2018, through October 19, 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. P. Johnson, 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. | |||
S. Sharp -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/ | |||
Mel Holmberg, Reactor Inspector | |||
Engineering Branch 1 | |||
Division of Reactor Safety | |||
Docket Nos. 50-282, 50-306 | |||
License Nos. DPR-42, DPR-60 | |||
Enclosure: | |||
Inservice Inspection Document Request | |||
cc: Distribution via LISTSERV | |||
S. Sharp -2- | |||
Letter to Scott Sharp from Mel Holmberg dated June 5, 2018 | |||
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1NOTIFICATION | |||
OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION; | |||
INSPECTION REPORT 05000282/2018004; 05000306/2018004 | |||
DISTRIBUTION: | |||
Jeremy Bowen | |||
RidsNrrPMPrairieIsland Resource | |||
RidsNrrDorlLpl3 | |||
RidsNrrDirsIrib Resource | |||
Steven West | |||
Darrell Roberts | |||
Richard Skokowski | |||
Allan Barker | |||
DRPIII | |||
DRSIII | |||
ADAMS Accession Number ML: 18156A553 | |||
OFFICE RIII RIII RIII RIII | |||
NAME MHolmberg:cl | |||
DATE 06/05/18 | |||
OFFICIAL RECORD COPY | |||
INSERVICE INSPECTION DOCUMENT REQUEST | |||
Inspection Dates: October 1, 2018, through October 19, 2018 | |||
Inspection Procedures: IP 71111-08, Inservice Inspection | |||
Lead Inspector: M. 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 | |||
September 11, 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 the | |||
outage unit unless otherwise indicated. If you have any questions regarding this | |||
information, please call the inspector as soon as possible. | |||
1. For the upcoming outage, a detailed schedule and description of: | |||
a. Non-destructive examinations (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 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; and | |||
d. Welding on Code Class 1, 2, or 3 components. | |||
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 | |||
INSERVICE INSPECTION DOCUMENT REQUEST | |||
2. A copy of the NDE procedures, SG eddy current examination (ET) acquisition | |||
and analysis procedures, and welding procedures used to perform the activities | |||
identified in Item A.1 (including NDE calibration and flaw characterization/sizing | |||
procedures and Welding Procedure Qualification Records). For ultrasonic | |||
examination procedures qualified in accordance with Appendix VIII, of Section XI | |||
of the ASME Code, provide documentation supporting the procedure qualification | |||
(e.g., the Electric Power Research Institute (EPRI) performance demonstration | |||
qualification summary sheets). For SG tube ET testing this includes the | |||
acquisition and analysis procedures. | |||
3. A copy of ASME Section XI, Code Relief Requests applicable to the | |||
examinations identified in Item A.1. | |||
4. A copy of the 10-year ISI Program showing those required exams scheduled to | |||
be performed this outage, and those which have been completed. | |||
5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye | |||
penetrant), which have identified relevant indications on Code Class 1 and 2 | |||
Systems since the beginning of the last refueling outage. | |||
6. List with short description of the welds in Code Class 1 and 2 Systems, which | |||
have been fabricated due to component repair/replacement activities since the | |||
beginning of the last refueling outage and identify the system, weld number, and | |||
reference applicable documentation (e.g., NIS-2 forms with definitions of system | |||
and component acronyms). | |||
7. If reactor vessel weld examinations required by the ASME Code are scheduled to | |||
occur during the inspection period, provide a detailed description of the welds to | |||
be examined, and the extent of the planned examination. | |||
8. List with description of ISI and SG-related issues such as piping or SG tube | |||
degradation or damage (e.g., cracks, wall thinning, wear, microbiologically | |||
induced corrosion) or errors identified during piping/SG tube examinations that | |||
have been entered into your corrective action system since the beginning of the | |||
last refueling outage. Also, include a list of corrective action records associated | |||
with foreign material introduced/identified in the reactor vessel, primary coolant | |||
system, 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 ET testing of the | |||
SGs during the upcoming outage1. | |||
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 | |||
INSERVICE INSPECTION DOCUMENT REQUEST | |||
11. Copy of procedure containing screening criteria used for selecting tubes for | |||
in-situ pressure testing and the procedure to be used for in-situ pressure testing1. | |||
12. Copy of previous outage SG tube operational assessment completed following | |||
ET of the SGs (provide this document even if no SG ET is planned for current | |||
outage). | |||
13. Copy of most recent SG Degradation Assessment (provide this document even if | |||
no SG ET is planned for current outage). | |||
14. Copy of most recent SG Condition Monitoring Assessments1. | |||
15. Copy of the document defining the planned SG ET scope (e.g., 100 percent of | |||
unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion | |||
transition regions with rotating probe) and identify the scope expansion criteria, | |||
which will be applied. Also identify and describe any deviations in this scope or | |||
expansion criteria from the EPRI Guidelines1. | |||
16. Copy of the document describing the ET acquisition equipment to be applied | |||
including ET probe types. Also identify the extent of planned tube examination | |||
coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches | |||
pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus | |||
3 inches to minus 12 inches). | |||
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. Deleted. | |||
20. Point of contact information (name and site number) for the following activities: | |||
a. ISISite and vendor leads | |||
b. Boric Acid Inspections and Evaluations | |||
c. Reactor Vessel Head InspectionSite and vendor leads | |||
d. SG InspectionSite and vendor leads | |||
e. Aging Management Programs | |||
f. Site Welding Engineer | |||
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 | |||
INSERVICE INSPECTION DOCUMENT REQUEST | |||
B. Onsite Information to be Provided to the Inspector on the First Day of the | |||
Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies | |||
(e.g., Paper Records) of the Following Documents. | |||
1. For welds selected by the inspector from Item A.1.d and A.6 above, provide | |||
copies of the following documents: | |||
a. Document of the weld number and location (e.g., system, train, branch); | |||
b. Document with a detail of the weld construction (e.g., drawing); | |||
c. Applicable portions of the Design Specification and applicable Code of | |||
construction for the weldment (e.g., B31.1 or ASME Section III); | |||
d. Applicable Code Edition and Addenda for weld procedure qualification; | |||
e. Applicable weld procedure specifications and weld data sheets used to | |||
fabricate the welds; | |||
f. Copies of procedure qualification records supporting the weld procedure | |||
specifications; | |||
g. Copies of welders performance qualification records; | |||
h. Copies of mechanical test reports identified in the weld procedure | |||
qualification records above; | |||
i. Copies of the nonconformance reports for the selected welds; | |||
j. Access to radiographs and equipment to view radiographs of the selected | |||
welds; | |||
k. ASME Code Section XI repair replacement plan and reconciliation for | |||
replacement components/materials; | |||
l. Certified Material Test Reports for replacement pressure boundary materials; | |||
and | |||
m. Copies of the NDE required by the construction Code and the pre-service | |||
examination records required by the ASME Code Section XI for the selected | |||
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 | |||
INSERVICE INSPECTION DOCUMENT REQUEST | |||
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). | |||
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 related 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 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. | |||
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). | |||
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. | |||
5 | |||
INSERVICE INSPECTION DOCUMENT REQUEST | |||
15. Provide procedures with guidance/instructions for identifying (e.g., physically | |||
locating the tubes that require repair) and plugging SG tubes1. | |||
16. Provide copies of the following standards at the onsite U.S. Nuclear Regulatory | |||
Commission inspection location for the duration of the inspection: | |||
a. Sections V, IX, and XI of the ASME Code with Editions applicable to the | |||
ISI Program and the Repair/Replacement Program; | |||
b. Copy of the performance demonstration initiative (PDI) generic procedures | |||
with the latest applicable revisions that support site qualified ultrasonic | |||
examination of piping welds and components (e.g., PDI-UT-1, PDI-UT-2, | |||
PDI-UT-3, PDI-UT-10 etc.); | |||
c. EPRI and industry standards referenced in the site procedures used to | |||
perform the SG tube ET, which includes EPRI documents: SG Examination | |||
Guidelines, SG Integrity Assessment Guidelines, SG In-Situ Pressure Test | |||
Guidelines1; and | |||
d. Boric Acid Corrosion Guidebook Revision 1EPRI Technical | |||
Report 1000975. | |||
17. 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. | |||
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 | |||
}} | }} |
Latest revision as of 16:57, 15 November 2019
ML18156A553 | |
Person / Time | |
---|---|
Site: | Prairie Island ![]() |
Issue date: | 06/05/2018 |
From: | Mel Holmberg NRC/RGN-III/DRS/EB1 |
To: | Sharp S Northern States Power Company, Minnesota |
References | |
IR 2018004 | |
Download: ML18156A553 (9) | |
See also: IR 05000282/2018004
Text
June 5, 2018
Mr. Scott Sharp
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089-9642
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1NOTIFICATION
OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000282/2018004; 05000306/2018004
Dear Mr. Sharp:
On October 1, 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
October 1, 2018, through October 19, 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. P. Johnson, 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.
S. Sharp -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/
Mel Holmberg, Reactor Inspector
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-282, 50-306
Enclosure:
Inservice Inspection Document Request
cc: Distribution via LISTSERV
S. Sharp -2-
Letter to Scott Sharp from Mel Holmberg dated June 5, 2018
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1NOTIFICATION
OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000282/2018004; 05000306/2018004
DISTRIBUTION:
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3
RidsNrrDirsIrib Resource
DRPIII
DRSIII
ADAMS Accession Number ML: 18156A553
OFFICE RIII RIII RIII RIII
NAME MHolmberg:cl
DATE 06/05/18
OFFICIAL RECORD COPY
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October 1, 2018, through October 19, 2018
Inspection Procedures: IP 71111-08, Inservice Inspection
Lead Inspector: M. 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
September 11, 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 the
outage unit unless otherwise indicated. If you have any questions regarding this
information, please call the inspector as soon as possible.
1. For the upcoming outage, a detailed schedule and description of:
a. Non-destructive examinations (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 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; and
d. Welding on Code Class 1, 2, or 3 components.
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
INSERVICE INSPECTION DOCUMENT REQUEST
2. A copy of the NDE procedures, SG eddy current examination (ET) acquisition
and analysis procedures, and welding procedures used to perform the activities
identified in Item A.1 (including NDE calibration and flaw characterization/sizing
procedures and Welding Procedure Qualification Records). For ultrasonic
examination procedures qualified in accordance with Appendix VIII, of Section XI
of the ASME Code, provide documentation supporting the procedure qualification
(e.g., the Electric Power Research Institute (EPRI) performance demonstration
qualification summary sheets). For SG tube ET testing this includes the
acquisition and analysis procedures.
3. A copy of ASME Section XI, Code Relief Requests applicable to the
examinations identified in Item A.1.
4. A copy of the 10-year ISI Program showing those required exams scheduled to
be performed this outage, and those which have been completed.
5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye
penetrant), which have identified relevant indications on Code Class 1 and 2
Systems since the beginning of the last refueling outage.
6. List with short description of the welds in Code Class 1 and 2 Systems, which
have been fabricated due to component repair/replacement activities since the
beginning of the last refueling outage and identify the system, weld number, and
reference applicable documentation (e.g., NIS-2 forms with definitions of system
and component acronyms).
7. If reactor vessel weld examinations required by the ASME Code are scheduled to
occur during the inspection period, provide a detailed description of the welds to
be examined, and the extent of the planned examination.
8. List with description of ISI and SG-related issues such as piping or SG tube
degradation or damage (e.g., cracks, wall thinning, wear, microbiologically
induced corrosion) or errors identified during piping/SG tube examinations that
have been entered into your corrective action system since the beginning of the
last refueling outage. Also, include a list of corrective action records associated
with foreign material introduced/identified in the reactor vessel, primary coolant
system, 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 ET testing of the
SGs during the upcoming outage1.
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
INSERVICE INSPECTION DOCUMENT REQUEST
11. Copy of procedure containing screening criteria used for selecting tubes for
in-situ pressure testing and the procedure to be used for in-situ pressure testing1.
12. Copy of previous outage SG tube operational assessment completed following
ET of the SGs (provide this document even if no SG ET is planned for current
outage).
13. Copy of most recent SG Degradation Assessment (provide this document even if
no SG ET is planned for current outage).
14. Copy of most recent SG Condition Monitoring Assessments1.
15. Copy of the document defining the planned SG ET scope (e.g., 100 percent of
unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion
transition regions with rotating probe) and identify the scope expansion criteria,
which will be applied. Also identify and describe any deviations in this scope or
expansion criteria from the EPRI Guidelines1.
16. Copy of the document describing the ET acquisition equipment to be applied
including ET probe types. Also identify the extent of planned tube examination
coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches
pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus
3 inches to minus 12 inches).
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. Deleted.
20. Point of contact information (name and site number) for the following activities:
a. ISISite and vendor leads
b. Boric Acid Inspections and Evaluations
c. Reactor Vessel Head InspectionSite and vendor leads
d. SG InspectionSite and vendor leads
e. Aging Management Programs
f. Site Welding Engineer
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
INSERVICE INSPECTION DOCUMENT REQUEST
B. Onsite Information to be Provided to the Inspector on the First Day of the
Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies
(e.g., Paper Records) of the Following Documents.
1. For welds selected by the inspector from Item A.1.d and A.6 above, provide
copies of the following documents:
a. Document of the weld number and location (e.g., system, train, branch);
b. Document with a detail of the weld construction (e.g., drawing);
c. Applicable portions of the Design Specification and applicable Code of
construction for the weldment (e.g., B31.1 or ASME Section III);
d. Applicable Code Edition and Addenda for weld procedure qualification;
e. Applicable weld procedure specifications and weld data sheets used to
fabricate the welds;
f. Copies of procedure qualification records supporting the weld procedure
specifications;
g. Copies of welders performance qualification records;
h. Copies of mechanical test reports identified in the weld procedure
qualification records above;
i. Copies of the nonconformance reports for the selected welds;
j. Access to radiographs and equipment to view radiographs of the selected
welds;
k. ASME Code Section XI repair replacement plan and reconciliation for
replacement components/materials;
l. Certified Material Test Reports for replacement pressure boundary materials;
and
m. Copies of the NDE required by the construction Code and the pre-service
examination records required by the ASME Code Section XI for the selected
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
INSERVICE INSPECTION DOCUMENT REQUEST
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
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 related 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 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.
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).
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.
5
INSERVICE INSPECTION DOCUMENT REQUEST
15. Provide procedures with guidance/instructions for identifying (e.g., physically
locating the tubes that require repair) and plugging SG tubes1.
16. Provide copies of the following standards at the onsite U.S. Nuclear Regulatory
Commission inspection location for the duration of the inspection:
a. Sections V, IX, and XI of the ASME Code with Editions applicable to the
ISI Program and the Repair/Replacement Program;
b. Copy of the performance demonstration initiative (PDI) generic procedures
with the latest applicable revisions that support site qualified ultrasonic
examination of piping welds and components (e.g., PDI-UT-1, PDI-UT-2,
PDI-UT-3, PDI-UT-10 etc.);
c. EPRI and industry standards referenced in the site procedures used to
perform the SG tube ET, which includes EPRI documents: SG Examination
Guidelines, SG Integrity Assessment Guidelines, SG In-Situ Pressure Test
Guidelines1; and
d. Boric Acid Corrosion Guidebook Revision 1EPRI Technical
Report 1000975.
17. 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.
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