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| number = ML17249A923 | | number = ML17249A923 | ||
| issue date = 09/06/2017 | | issue date = 09/06/2017 | ||
| title = | | title = Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf) | ||
| author name = Fernandez E | | author name = Fernandez E | ||
| author affiliation = NRC/RGN-III/DRS/EB1 | | author affiliation = NRC/RGN-III/DRS/EB1 | ||
| addressee name = Northard S | | addressee name = Northard S | ||
| addressee affiliation = Northern States Power Co | | addressee affiliation = Northern States Power Co | ||
| docket = 05000282, 05000306 | | docket = 05000282, 05000306 | ||
Line 14: | Line 14: | ||
| page count = 8 | | page count = 8 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000282/2017004]] | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL | {{#Wiki_filter:UNITED STATES | ||
S. Northard -2- | NUCLEAR REGULATORY COMMISSION | ||
S. Northard -3- | REGION III | ||
INSERVICE INSPECTION DOCUMENT REQUEST | 2443 WARRENVILLE RD. SUITE 210 | ||
LISLE, IL 60532-4352 | |||
September 6, 2017 | |||
Mr. Scott D. Northard | |||
Site Vice President | |||
Prairie Island Nuclear Generating Plant | |||
Northern States Power Company, Minnesota | |||
1717 Wakonade Drive East | |||
Welch, MN 55089-9642 | |||
SUBJECT: PRAIRIE ISLAND STATION, UNIT 2NOTIFICATION OF NRC BASELINE | |||
INSPECTION AND REQUEST FOR INFORMATION; INSPECTION | |||
REPORT 05000282/2017004; 05000306/2017004 | |||
Dear Mr. Northard: | |||
On October 16, 2017, 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 16, 2017, through October 26, 2017. | |||
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. Pam Johnson, of your organization. If there are | |||
any questions about this inspection or the material requested, please contact the lead inspector | |||
Mr. Edison Fernandez at 630 829-9754 or via e-mail at Edison.Fernandez@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. Northard -2- | |||
This letter and its enclosure will be made available for public inspection and copying at | |||
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in | |||
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding. | |||
Sincerely, | |||
/RA/ | |||
Edison Fernandez | |||
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. Northard -3- | |||
Letter to Scott Northard from Edison Fernandez dated September 6, 2017 | |||
SUBJECT: PRAIRIE ISLAND STATION, UNIT 2NOTIFICATION OF NRC BASELINE | |||
INSPECTION AND REQUEST FOR INFORMATION; INSPECTION | |||
REPORT 05000282/2017004; 05000306/2017004 | |||
DISTRIBUTION: | |||
Jeremy Bowen | |||
RidsNrrPMPrairieIsland Resource | |||
RidsNrrDorlLpl3 | |||
RidsNrrDirsIrib Resource | |||
Cynthia Pederson | |||
James Trapp | |||
Richard Skokowski | |||
Allan Barker | |||
Carole Ariano | |||
Linda Linn | |||
DRPIII | |||
DRSIII | |||
ADAMS Accession Number ML17249A923 | |||
OFFICE RIII RIII RIII RIII | |||
NAME EFernandez:cl | |||
DATE 09/06/17 | |||
OFFICIAL RECORD COPY | |||
INSERVICE INSPECTION DOCUMENT REQUEST | |||
Inspection Dates: October, 16, 2017, through October, 26, 2017 | |||
Inspection Procedures: IP 71111-08, Inservice Inspection | |||
Lead Inspector: Edison Fernandez, DRS | |||
630-829-9754 | |||
Edison.Fernandez@nrc.gov | |||
A. Information for the In-Office Preparation Week | |||
The following information is requested as an (electronic copy CD ROM if possible) by | |||
October 9, 2017, 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 ASME Code Inservice Inspection (ISI) | |||
Program (include edition and addenda of Code committed to), and NDE | |||
examinations 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. | |||
2. A copy of the NDE procedures and welding procedures used to perform | |||
the activities identified in Item A.1 (including NDE calibration and flaw | |||
characterization/sizing procedures and Welding Procedure Qualification | |||
Records). For ultrasonic examination procedures qualified in accordance | |||
with Appendix VIII, of Section XI of the ASME Code, provide documentation | |||
supporting the procedure qualification (e.g., the Electric Power Research | |||
Institute (EPRI) performance demonstration qualification summary sheets). | |||
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 | |||
3. A copy of ASME Section XI, Code Relief Requests applicable to the | |||
examinations identified in Item A.1. This would include the U.S. Nuclear | |||
Regulatory Commission (NRC) approved Relief Request for implementing a | |||
risk-informed ISI Program (if applicable). | |||
4. A copy of the 10-year ISI Program showing those required exams scheduled to | |||
be performed this outage, and those which have been completed. | |||
5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye | |||
penetrant), which have identified relevant indications on Code Class 1 and 2 | |||
Systems since the beginning of the last refueling outage. | |||
6. List with short description of the welds in Code Class 1 and 2 Systems, which | |||
have been fabricated due to component repair/replacement activities since the | |||
beginning of the last refueling outage and identify the system, weld number, and | |||
reference applicable documentation (e.g., NIS-2 forms with definitions of system | |||
and component acronyms). | |||
7. If reactor vessel weld examinations required by the ASME Code are scheduled to | |||
occur during the inspection period, provide a detailed description of the welds to | |||
be examined, and the extent of the planned examination. | |||
8. List with description of ISI and SG-related issues such as piping or SG tube | |||
degradation or damage (e.g., cracks, wall thinning, wear, microbiologically | |||
induced corrosion) or errors identified during piping/SG tube examinations that | |||
have been entered into your corrective action system since the beginning of the | |||
last refueling outage. Also, include a list of corrective action records associated | |||
with foreign material introduced/identified in the reactor vessel, primary coolant | |||
system, SG or feed systems since the beginning of the last refueling outage. | |||
9. Copy of any 10 CFR Part 21 reports applicable to your structures, systems or | |||
components within the scope of Section XI of the ASME Code that have been | |||
identified since the beginning of the last refueling outage. | |||
10. Copy of SG history documentation given to vendors performing eddy current (ET) | |||
testing of the SGs during the upcoming outage1. | |||
11. Copy of procedure containing screening criteria used for selecting tubes for | |||
in-situ pressure testing and the procedure to be used for in-situ pressure testing1. | |||
12. Copy of previous outage SG tube operational assessment completed following | |||
ET of the SGs1. | |||
13. Copy of the document defining the planned SG ET scope (e.g., 100 percent of | |||
unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion | |||
transition regions with rotating probe) and identify the scope expansion criteria, | |||
which will be applied. Also identify and describe any deviations in this scope or | |||
expansion criteria from the EPRI Guidelines1. | |||
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 | |||
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 tubes1. | |||
16. Identify and quantify any SG tube leakage experienced during the previous | |||
operating cycle. Also provide documentation identifying which SG was leaking | |||
and corrective actions completed or planned for this condition. | |||
17. Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1 | |||
that establish the volumetric and visual examination frequency for the reactor | |||
vessel head and J-groove welds. | |||
18. Point of contact information (name and site number) for the following activities: | |||
a. 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 | |||
B. Onsite Information to be Provided to the Inspector on the First Day of the | |||
Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies | |||
(e.g., Paper Records) of the Following Documents. | |||
1. For welds selected by the inspector from Item A.1.d and A.6 above, provide | |||
copies of the following documents: | |||
a. Document of the weld number and location (e.g., system, train, branch); | |||
b. Document with a detail of the weld construction (e.g., drawing); | |||
c. Applicable portions of the Design Specification and applicable Code of | |||
construction for the weldment (e.g., B31.1 or ASME Section III); | |||
d. Applicable Code Edition and Addenda for weld procedure qualification; | |||
e. Applicable weld procedures and weld data sheets used to fabricate the | |||
welds; | |||
f. Copies of procedure qualification records supporting the weld procedures; | |||
g. Copies of welders performance qualification records; | |||
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 | |||
h. Copies of mechanical test reports identified in the procedure qualification | |||
records above; | |||
i. Copies of the nonconformance reports for the selected welds; | |||
j. Access to radiographs and equipment to view radiographs of the selected | |||
welds; and | |||
k. Copies of the pre-service examination records for the selected welds. | |||
2. For the ISI-related corrective action issues selected by the inspector from | |||
Item A.8 above, provide a copy of the corrective actions and supporting | |||
documentation. | |||
3. For the NDE reports with relevant indications on Code Class 1 and 2 Systems | |||
selected by the inspector from Item A.5 above, provide a copy of the examination | |||
records and associated corrective action documents. Updated schedules for | |||
Item A.1 (including schedule showing contingency repair plans if available). | |||
4. Copy of the procedures which govern the scope, equipment used, and | |||
implementation of the inspections required to identify boric acid leakage | |||
from systems and components above the vessel head. | |||
5. Copy of: | |||
a. Engineering evaluations/assessments of boric acid related deposits and | |||
associated wastage or corrosion for safety significant components; and | |||
b. Corrective action records for coolant leakage including boric acid deposits on | |||
safety-related components identified since the beginning of the last refueling | |||
outage. | |||
6. Copy of the plant procedures used to perform inspections to identify reactor | |||
coolant system leaks or boric acid deposits and the procedures for resolution of | |||
leaks or boric acid deposits. | |||
7. Fabrication Drawings (D size) of the reactor vessel welds (including vessel head | |||
J-groove welds) if any are to be examined during the outage. Also provide any | |||
drawings used by NDE vendors to locate these welds.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). | |||
8. Copy of volumetric, surface and visual examination records for the prior | |||
inspection of the reactor vessel head and head penetration J-groove welds. | |||
9. Provide a copy of the EPRI Examination Technique Specification Sheets and | |||
vendor documents, which support qualification of the ET probes to be used | |||
during the upcoming SG tube inspections1. | |||
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur | |||
and no further information is required for the items identified above requesting SG related information. | |||
4 | |||
10. Provide a copy of the guidance to be followed if a loose part or foreign material is | |||
identified in the SGs1. | |||
11. Identify the types of SG tube repair processes which will be implemented for | |||
defective SG tubes (including any NRC reviews/evaluation/approval of this repair | |||
process). Provide the flaw depth sizing criteria to be applied for ET indications | |||
identified in the SG tubes1. | |||
12. Copy of document describing actions to be taken if a new SG tube degradation | |||
mechanism is identified1. | |||
13. 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). | |||
14. Provide procedures with guidance/instructions for identifying (e.g., physically | |||
locating the tubes that require repair) and plugging SG tubes1. | |||
15. 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 | |||
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 examination, which includes EPRI documents: | |||
TR-107621-R1, Steam Generator Integrity Assessment Guidelines, | |||
TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines, | |||
SG Management Program: SG Integrity Assessment Guidelines, Part 10, | |||
and 1003138, Pressurized Water Reactor Steam Generator Examination | |||
Guidelines1; and | |||
d. Boric Acid Corrosion Guidebook Revision 2-EPRI Technical Report 1000975. | |||
16. Provide training (e.g., Scaffolding, Fall Protection, FME) 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. | |||
5 | |||
}} | }} |
Latest revision as of 09:47, 16 November 2019
ML17249A923 | |
Person / Time | |
---|---|
Site: | Prairie Island ![]() |
Issue date: | 09/06/2017 |
From: | Edison Fernandez NRC/RGN-III/DRS/EB1 |
To: | Northard S Northern States Power Co |
References | |
IR 2017004 | |
Download: ML17249A923 (8) | |
See also: IR 05000282/2017004
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
September 6, 2017
Mr. Scott D. Northard
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089-9642
SUBJECT: PRAIRIE ISLAND STATION, UNIT 2NOTIFICATION OF NRC BASELINE
INSPECTION AND REQUEST FOR INFORMATION; INSPECTION
REPORT 05000282/2017004; 05000306/2017004
Dear Mr. Northard:
On October 16, 2017, 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 16, 2017, through October 26, 2017.
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. Pam Johnson, of your organization. If there are
any questions about this inspection or the material requested, please contact the lead inspector
Mr. Edison Fernandez at 630 829-9754 or via e-mail at Edison.Fernandez@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. Northard -2-
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-282, 50-306
Enclosure:
Inservice Inspection Document Request
cc: Distribution via LISTSERV
S. Northard -3-
Letter to Scott Northard from Edison Fernandez dated September 6, 2017
SUBJECT: PRAIRIE ISLAND STATION, UNIT 2NOTIFICATION OF NRC BASELINE
INSPECTION AND REQUEST FOR INFORMATION; INSPECTION
REPORT 05000282/2017004; 05000306/2017004
DISTRIBUTION:
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3
RidsNrrDirsIrib Resource
Cynthia Pederson
DRPIII
DRSIII
ADAMS Accession Number ML17249A923
OFFICE RIII RIII RIII RIII
NAME EFernandez:cl
DATE 09/06/17
OFFICIAL RECORD COPY
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October, 16, 2017, through October, 26, 2017
Inspection Procedures: IP 71111-08, Inservice Inspection
Lead Inspector: Edison Fernandez, DRS
630-829-9754
Edison.Fernandez@nrc.gov
A. Information for the In-Office Preparation Week
The following information is requested as an (electronic copy CD ROM if possible) by
October 9, 2017, 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 ASME Code Inservice Inspection (ISI)
Program (include edition and addenda of Code committed to), and NDE
examinations 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.
2. A copy of the NDE procedures and welding procedures used to perform
the activities identified in Item A.1 (including NDE calibration and flaw
characterization/sizing procedures and Welding Procedure Qualification
Records). For ultrasonic examination procedures qualified in accordance
with Appendix VIII, of Section XI of the ASME Code, provide documentation
supporting the procedure qualification (e.g., the Electric Power Research
Institute (EPRI) performance demonstration qualification summary sheets).
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
3. A copy of ASME Section XI, Code Relief Requests applicable to the
examinations identified in Item A.1. This would include the U.S. Nuclear
Regulatory Commission (NRC) approved Relief Request for implementing a
risk-informed ISI Program (if applicable).
4. A copy of the 10-year ISI Program showing those required exams scheduled to
be performed this outage, and those which have been completed.
5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye
penetrant), which have identified relevant indications on Code Class 1 and 2
Systems since the beginning of the last refueling outage.
6. List with short description of the welds in Code Class 1 and 2 Systems, which
have been fabricated due to component repair/replacement activities since the
beginning of the last refueling outage and identify the system, weld number, and
reference applicable documentation (e.g., NIS-2 forms with definitions of system
and component acronyms).
7. If reactor vessel weld examinations required by the ASME Code are scheduled to
occur during the inspection period, provide a detailed description of the welds to
be examined, and the extent of the planned examination.
8. List with description of ISI and SG-related issues such as piping or SG tube
degradation or damage (e.g., cracks, wall thinning, wear, microbiologically
induced corrosion) or errors identified during piping/SG tube examinations that
have been entered into your corrective action system since the beginning of the
last refueling outage. Also, include a list of corrective action records associated
with foreign material introduced/identified in the reactor vessel, primary coolant
system, SG or feed systems since the beginning of the last refueling outage.
9. Copy of any 10 CFR Part 21 reports applicable to your structures, systems or
components within the scope of Section XI of the ASME Code that have been
identified since the beginning of the last refueling outage.
10. Copy of SG history documentation given to vendors performing eddy current (ET)
testing of the SGs during the upcoming outage1.
11. Copy of procedure containing screening criteria used for selecting tubes for
in-situ pressure testing and the procedure to be used for in-situ pressure testing1.
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 Guidelines1.
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
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 tubes1.
16. Identify and quantify any SG tube leakage experienced during the previous
operating cycle. Also provide documentation identifying which SG was leaking
and corrective actions completed or planned for this condition.
17. Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1
that establish the volumetric and visual examination frequency for the reactor
vessel head and J-groove welds.
18. Point of contact information (name and site number) for the following activities:
a. 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
B. Onsite Information to be Provided to the Inspector on the First Day of the
Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies
(e.g., Paper Records) of the Following Documents.
1. For welds selected by the inspector from Item A.1.d and A.6 above, provide
copies of the following documents:
a. Document of the weld number and location (e.g., system, train, branch);
b. Document with a detail of the weld construction (e.g., drawing);
c. Applicable portions of the Design Specification and applicable Code of
construction for the weldment (e.g., B31.1 or ASME Section III);
d. Applicable Code Edition and Addenda for weld procedure qualification;
e. Applicable weld procedures and weld data sheets used to fabricate the
f. Copies of procedure qualification records supporting the weld procedures;
g. Copies of welders performance qualification records;
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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h. Copies of mechanical test reports identified in the procedure qualification
records above;
i. Copies of the nonconformance reports for the selected welds;
j. Access to radiographs and equipment to view radiographs of the selected
welds; and
k. Copies of the pre-service examination records for the selected welds.
2. For the ISI-related corrective action issues selected by the inspector from
Item A.8 above, provide a copy of the corrective actions and supporting
documentation.
3. For the NDE reports with relevant indications on Code Class 1 and 2 Systems
selected by the inspector from Item A.5 above, provide a copy of the examination
records and associated corrective action documents. Updated schedules for
Item A.1 (including schedule showing contingency repair plans if available).
4. Copy of the procedures which govern the scope, equipment used, and
implementation of the inspections required to identify boric acid leakage
from systems and components above the vessel head.
5. Copy of:
a. Engineering evaluations/assessments of boric acid related deposits and
associated wastage or corrosion for safety significant components; and
b. Corrective action records for coolant leakage including boric acid deposits on
safety-related components identified since the beginning of the last refueling
outage.
6. Copy of the plant procedures used to perform inspections to identify reactor
coolant system leaks or boric acid deposits and the procedures for resolution of
leaks or boric acid deposits.
7. Fabrication Drawings (D size) of the reactor vessel welds (including vessel head
J-groove welds) if any are to be examined during the outage. Also provide any
drawings used by NDE vendors to locate these welds.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).
8. Copy of volumetric, surface and visual examination records for the prior
inspection of the reactor vessel head and head penetration J-groove welds.
9. Provide a copy of the EPRI Examination Technique Specification Sheets and
vendor documents, which support qualification of the ET probes to be used
during the upcoming SG tube inspections1.
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur
and no further information is required for the items identified above requesting SG related information.
4
10. Provide a copy of the guidance to be followed if a loose part or foreign material is
identified in the SGs1.
11. Identify the types of SG tube repair processes which will be implemented for
defective SG tubes (including any NRC reviews/evaluation/approval of this repair
process). Provide the flaw depth sizing criteria to be applied for ET indications
identified in the SG tubes1.
12. Copy of document describing actions to be taken if a new SG tube degradation
mechanism is identified1.
13. 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).
14. Provide procedures with guidance/instructions for identifying (e.g., physically
locating the tubes that require repair) and plugging SG tubes1.
15. 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
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 examination, which includes EPRI documents:
TR-107621-R1, Steam Generator Integrity Assessment Guidelines,
TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines,
SG Management Program: SG Integrity Assessment Guidelines, Part 10,
and 1003138, Pressurized Water Reactor Steam Generator Examination
Guidelines1; and
d. Boric Acid Corrosion Guidebook Revision 2-EPRI Technical Report 1000975.
16. Provide training (e.g., Scaffolding, Fall Protection, FME) 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.
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