ML070450020
| ML070450020 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 02/08/2007 |
| From: | Hopper G NRC/RGN-II/DRS/EB3 |
| To: | Gordon Peterson Duke Energy Carolinas, Duke Power Co |
| References | |
| Inspection Procedure No. 71111.08 | |
| Download: ML070450020 (11) | |
Text
February 8, 2007 Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC ATTN: Mr. G. R. Peterson Vice President McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
McGUIRE NUCLEAR STATION, UNIT 1 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Peterson:
From March 19 to May 7, 2007, the NRC will perform the baseline inservice inspections (ISI) at the McGuire Nuclear Station, Unit 1 (NRC Inspection Procedure 71111.08 and Temporary Instruction 2515/150, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles).
Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection.
These documents have been divided into two groups. The first group (Section A of the enclosure) identifies information to be provided prior to the inspection to ensure that the inspectors are adequately prepared. The second group (Section B of the enclosure) identifies the information the inspectors 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 these inspection activities with your staff and understand that our regulatory contact for this inspection will be Ms. Kay Crane of your organization. Our inspection dates are subject to change based on your updated schedule of outage activities. If there are any questions about this inspection or the material requested, please contact the lead inspector Steven J. Vias at (404) 562-4505 (sjv@nrc.gov).
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS).
DPC 2 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
George T. Hopper, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-369, 50-370 License Nos. NPF-9, NPF-17
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST
DPC 3 cc w/encl:
C. J. Thomas Regulatory Compliance Manager (MNS)
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC Electronic Mail Distribution R. L. Gill, Jr., Manager Nuclear Regulatory Issues and Industry Affairs Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC 526 S. Church Street Charlotte, NC 28201-0006 Lisa F. Vaughn Associate General Counsel and Managing Attorney Duke Energy Carolinas, LLC 526 South Church Street-EC07H Charlotte, NC 28202 Kathyrn B. Nolan Senior Counsel Duke Energy Carolinas, LLC 526 South Church Street-EC 07H Charlotte, NC 28202 David A. Repka Winston & Strawn LLP Electronic Mail Distribution Beverly Hall, Chief, Radiation Proctection Section N. C. Department of Environmental Health & Natural Resources Electronic Mail Distribution County Manager of Mecklenburg County 720 East Fourth Street Charlotte, NC 28202
OFFICE RII:DRS RII:DRS RII:DRS RII:DRS SIGNATURE /RA/ /RA/ /RA via email/ /RA/
NAME G.Hopper S. Vias J. Rivera-Oriz J.Moorman DATE 2/08/2007 2/08/2007 2/09/2007 2/08/2007 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: March 19-23, 2007 Week 2 (to be determined)
Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities TI 2515/150 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles Inspectors: Steven J. Vias, Senior Reactor Inspector Joel Rivera-Ortiz, Reactor Inspector A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region II office in hard copy or electronic format (CD preferred), in care of Steven J. Vias by March 9, 2007, 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 then request from your staff additional documents needed during the onsite inspection week (Section B of this enclosure). We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. *Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the inspector(s), and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the inspector as soon as possible.
A.1 ISI / Welding Programs and Schedule Information a) A detailed schedule (including preliminary dates) of:
i) Nondestructive examinations (NDEs) planned for Class 1 & 2 systems and containment, performed as part of your ASME Section XI, Risk Informed (if applicable), and augmented ISI Programs during the upcoming outage.
Provide a status summary of the NDE inspection activities vs. the required inspection period percentages for this Interval by category per ASME Section XI, IWX-2400 (Do not provide separately if other documentation requested contains this information) ii) Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope. (If applicable) iii) Welding activities that are scheduled to be completed during the upcoming outage (ASME Class 1, 2, or 3 structures, systems, or components (SSCs))
Enclosure
2 b) A copy of ASME Section XI Code Relief Requests and associated NRC Safety Evaluations applicable to the examinations identified above.
c) A list of NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual VT-1, VT-2, and VT-3) which have identified recordable indications (geometric or flaw) on Code Class 1 & 2 systems since the beginning of the last refueling outage. Also, include in the list the NDE reports with recorded indications in the RPVH penetration nozzles which have been accepted for continued service. The list of NDE reports should include a brief description of the SSC where the recordable indication was identified.
d) A list with a brief description (e.g. system, material, pipe size, weld number, and NDE performed) 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, or are planned to be fabricated this refueling outage.
e) If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined, and the extent of the planned examination. Please also provide reference numbers for applicable procedures that will be used to conduct these examinations.
f) Copy of any 10 CFR Part 21 reports applicable to your SSCs within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage.
g) A list of any temporary non-code repairs in service (e.g. pinhole leaks).
h) Please provide copies of the most recent self assessments for the ISI, Welding, and Alloy 600 Programs.
A.2 Reactor Pressure Vessel Head (RPVH) a) Provide a detailed schedule of planned NDEs of the reactor vessel head. The schedule should include preliminary dates for the volumetric, surface, and bare metal visual examinations.
b) Provide the detailed scope of the planned NDE of the reactor vessel head which identifies the types of NDE methods to be used on each specific part of the vessel head to fulfill NRC commitments made in response to NRC Bulletin 2002-02 and NRC Order EA-03-009.
c) A list of the standards and/or requirements that will be used to evaluate indications identified during NDE of the reactor vessel head (e.g. the specific industry or procedural standards which will be used to evaluate potential leakage and/or flaw indications).
Enclosure
3 A.3 Boric Acid Corrosion Control Program (BACCP) a) Copy of the procedures that govern the scope, equipment and implementation of the inspections required to identify boric acid leakage and the procedures for boric acid leakage/corrosion evaluation.
b) Please provide a list of leaks (including code class of the components) that have been identified since the beginning of the last refueling outage and associated corrective action documentation. If during the last cycle, the Unit was shutdown, please provide documentation of containment walk-down inspections performed as part of the BACCP. Provide the engineering evaluation that was performed for each leak.
c) Please provide a copy of the most recent self-assessment performed for the BACCP.
d) Examinations planned as part of your Boric Acid Corrosion Control Program (Mode 3 walkdowns, bolted connection walkdowns, etc.)
A.4 Steam Generator (SG) Inspections a) Provide the evaluation and justification for not performing the primary side eddy current examinations this refueling outage.
b) 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. (If applicable) c) Provide past history of the condition and issues pertaining to the secondary side of the steam generators (including items such as loose parts, fouling, top of tube sheet condition, crud removal amounts and trend chart, etc.)
d) Please provide copies of your most recent self assessments of the SG monitoring, loose parts monitoring, and secondary side water chemistry control programs.
A.5 Additional information related to all ISI activities a) A list with a brief description of ISI, BACCP, and SG ISI related issues (e.g.,
condition reports) entered into your corrective action program since the beginning of the last refueling outage (for Units 1 and 2). For example, a list based upon corrective action data base searches using key words related to piping or SG tube degradation such as: ISI, ASME Code,Section XI, Section III, Relief Requests, Repair and Replacement, Code Case, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping/SG tube examinations.
Enclosure
4 b) Please provide names and phone numbers for the following program leads:
ISI contacts (Examination, planning)
Containment Exams RPVH Exams Snubbers and Supports Repair and Replacement Program Manager Licensing Contact Site Welding Engineer Boric Acid Corrosion Control Program Coordinator B. Information to be provided on-site to the inspector at the entrance meeting (March 19, 2007):
B.1 ISI / Welding Programs and Schedule Information a) Updated schedules for ISI/NDE activities, including SG ISI, planned welding activities, and schedule showing contingency repair plans, if available.
b) For ASME Class 1 and 2 welds selected by the inspector from the lists provided from Section A of this enclosure, please provide copies of the following documentation for each subject weld:
i) Weld data sheet (traveler) ii) Weld configuration and system location iii) Applicable Code Edition and Addenda for weldment iv) Applicable Code Edition and Addenda for welding procedures v) Applicable weld procedures (WPS) used to fabricate the welds vi) Copies of procedure qualification records (PQRs) supporting the WPS from B.1.b.v vii) Copies of mechanical test reports identified in the PQRs above viii) Copies of the nonconformance reports for the selected welds (If Applicable) ix) Radiographs of the selected welds and access to equipment to allow viewing radiographs (If RT was performed) x) Copies of the preservice examination records for the selected welds.
Enclosure
5 xi) Copies of welder performance qualifications records applicable to WPS, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (At least six months prior to date subject work) xii) Copies of NDE personnel qualifications (VT, PT, UT, RT) As applicable c) For the ISI related corrective action issues selected by the inspector from Section A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d) For the NDE reports with recordable indications on Code Class 1 & 2 systems selected by the inspector from Section A above, provide a copy of the examination records, examiner qualification records, and associated corrective action documents.
e) A copy of (or ready access to) most current revision of the ISI Program Manual and Plan for the current Interval.
f) For the NDEs selected by the inspector from Section A of this enclosure, provide copy of the NDE procedures used to perform the examinations (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Also, include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.
B.2 Reactor Pressure Vessel Head (RPVH) a) Provide all NDE personnel qualification records for the examiners who will perform examinations of the RPVH (volumetric, surface, and visual) b) Copy of NDE procedures that will be used for all NDE examinations.
c) Copy of NDE equipment certifications (e.g. PT consumables certifications, and UT probe certification reports).
d) Copy of NDE equipment calibration records e) Provide copy of the vendor qualification report(s) that demonstrates the detection capability of the NDE equipment used for the RPVH examinations. Also, identify any changes in equipment configurations used for the RPVH examinations which differ from that used in the vendor qualification report(s).
f) Provide access to review acquired volumetric and visual examination data (as applicable)
Enclosure
6 g) Provide a drawing showing a top view of the RPVH and CRDM nozzle configurations (drawn to scale).
h) Provide fabrication drawings for the CRDM nozzle attachment welds (drawn to scale).
i) If available, provide a copy of the evaluation or calculation demonstrating that the scope of the visual examination of the upper head will meet the 95% minimum coverage required by NRC Order EA-03-009 (If a visual examination is planned for the upcoming refueling outage).
j) Provide a copy of the procedures that will be used to inspect pressure-retaining components above the RPVH that could be the source of boric acid deposits on the head. If no explicit procedures exist which govern this activity, provide a description of the process to be followed including personnel responsibilities and expectations.
k) Provide a copy of the updated calculation of effective degradation years (EDY) for the RPVH susceptibility category.
l) Provide a copy of the stress calculation performed to support the examination coverage that will be obtained in the volumetric examination of the CRDM nozzles (if applicable).
m) Copy of NDE reports from the last RPVH examination (as applicable).
B.3 Boric Acid Corrosion Control Program (BACCP) a) Please provide boric acid walk down inspection results, an updated list of boric acid leaks identified so far this outage, associated corrective action documentation, and overall status of planned boric acid inspections.
b) Please provide any engineering evaluations completed for boric acid leaks identified since the end of the last refueling outage. Please include a status of corrective actions to repair and/or clean these boric acid leaks. Please specify which known leaks, if any, have remained in service or will remain in service as active leaks.
c) In accordance with NRC inspection procedure 71111.08, the inspector(s) would like to conduct an independent boric acid walk down of the Reactor Building early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspector(s) during the walk down.
B.4 Steam Generator (SG) Inspections None Enclosure
7 B.5 Codes and Standards a) Ready access to: (i.e. copies provided to the inspector to use for the duration of the inspection at the on-site inspection location, or room number and location where available) i) Applicable editions of the ASME Code (Sections III, V, IX and XI) for the inservice inspection program and the repair/replacement program.
Inspector Contact Information:
Steven J. Vias Joel Rivera-Ortiz Senior Reactor Inspector Reactor Inspector 404-562-4505 404-562-4825 sjv@nrc.gov jer6@nrc.gov Mailing Address:
US NRC Region 2 Attn: Steven J. Vias 61 Forsyth Street SW, Suite 23T85 Atlanta, GA 30303 Enclosure