ML13266A150
| ML13266A150 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/23/2013 |
| From: | Vias S Division of Reactor Safety II |
| To: | James Shea Tennessee Valley Authority |
| References | |
| Download: ML13266A150 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 September 23, 2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNIT 1 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Shea:
From October 21 - 25, 2013, the U.S. Nuclear Regulatory Commission (NRC) will perform a baseline inspection at the Sequoyah Nuclear Plant, Unit 1, in accordance with NRC Inspection Procedure (IP) 71111.08, Inservice Inspection (ISI) Activities. Experience has shown that this inspection is resource intensive for both 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 classified 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 additional 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 portion of the inspection.
Additionally, the NRC during the same timeframe, will perform inspections in accordance with NRC IP 71002, License Renewal Inspection, to allow visual observation of equipment inaccessible during power operation. This license renewal inspection is related to the review of the license renewal application submitted by TVA for Sequoyah Nuclear Plant on January 7, 2013. The inspectors will perform walkdowns of selected structures, systems, and components in containment and in-scope of license renewal following the guidance in IP 71002.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. Jonathan Johnson 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, Joel Rivera-Ortiz, at 404-997-4825 (Joel.Rivera-Ortiz@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
J. Shea 2
document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, RA Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety Docket No.: 50-327 License No.: DPR-77
Enclosure:
Inservice Inspection Document Request cc: Distribution via Listserv
ML13266A150 X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE RA RA NAME J. Rivera-Ortiz S. VIAS DATE 9/ 23 /2013 9/ 23 /2013 E-MAIL COPY YES NO YES NO
Letter to Joseph W. Shea from Steven J. Vias dated September 23, 2013.
Distribution:
RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource
Enclosure INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates:
October 21 - 25, 2013 Inspection Procedures:
IP 71111.08, Inservice Inspection (ISI) Activities IP 71002, License Renewal Inspections Inspectors:
Joel Rivera-Ortiz, Senior Reactor Inspector (Lead)
Louis Lake, Senior 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 (compact disk (CD) preferred), in care of the lead inspector by October 11, 2013, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. Alternatively, the information can be made available through a web-based document control system. The inspectors will select specific items from the information requested below and then request additional documents needed for 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, 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 American Society of Mechanical Engineers (ASME) Class 1 and 2 systems, and reactor building containment during the upcoming outage as part of your ASME Section XI Program, including augmented ISI examinations.
Provide a status summary of the NDE inspection activities versus the required inspection period percentages for this Interval by category per ASME Section XI, IW_-2400. (Do not provide separately if other documentation requested contains this information.)
ii) Examinations planned for Alloy 82/182/600 welds/components that are not included in the scope of ASME Section XI, if applicable.
iii) Welding activities scheduled to be completed during the upcoming outage for ASME Class 1, 2, or 3 components.
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, and dye penetrant)
2 Enclosure associated with surface or volumetric indications that were analytically evaluated, and accepted for continued service on ASME Code Class 1, 2, and 3 systems since the beginning of the last refueling outage. This should include the previousSection XI pressure test(s) conducted during start up and any evaluations associated with the results of the pressure tests.
d) A list with a brief description (e.g., system, material, pipe size, weld number, and NDE performed) of welds in ASME Code Class 1, 2, and 3 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. Also, please indicate which of those welds are risk significant.
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 systems and components within the scope of ASME,Section XI that have been identified since the beginning of the last refueling outage.
g) A list of any temporary repairs in service for ASME Class components (e.g., pinhole leaks).
h) Copies of the most recent self assessments for the ISI and Welding programs.
A.2 Reactor Pressure Vessel Head (RPVH) a) If applicable, please provide the detailed scope of any planned NDE of the reactor vessel upper closure head to meet the augmented inspection requirements of 10CFR50.55a(g)(6)(ii)(D).
b) If applicable, provide a list of NDE reports from previous examinations associated with existing surface or volumetric indications in the RPVH penetration nozzles that have been analytically evaluated and accepted for continued service.
A.3 Boric Acid Corrosion Control Program (BACCP) a) Please provide a copy of the procedures that govern the scope, equipment, and implementation of the inspections required to identify boric acid leakage. Please include 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 last refueling outage and associated corrective action documentation.
If during the last cycle, the Unit was shutdown, please provide documentation of containment walkdown inspections performed as part of the BACCP.
c) Please provide a copy of the most recent self-assessment performed for the BACCP.
3 Enclosure A.4 Steam Generator (SG) Inspections a) Please provide a detailed schedule of:
i)
SG tube inspection, data analyses, and repair activities for the upcoming outage. (If occurring) ii) SG secondary side inspection activities for the upcoming outage. (If occurring) b) Please provide a copy of the last Condition Monitoring and Operational Assessment Report for Unit 1.
A.5 Additional information related to all ISI activities a) Provide a list with a brief description of ISI related issues (e.g., condition reports) entered into your corrective action program since the beginning of the last refueling outage. For example, a list based upon data base searches using key words such as: ISI, ASME Code,Section XI, NDE, welding, cracks, wear, thinning, leakage, rust, corrosion, or errors in piping examinations.
b) Please provide names and phone numbers for the following program leads:
ISI (Examination, planning)
Containment Exams RPVH Exams Repair and Replacement Program Licensing Site Welding Boric Acid Corrosion Control Program SG Inspection Activities (site lead and vendor contact)
B.
Information to be provided onsite to the inspector at the entrance meeting (October 21, 2013):
B.1 ISI / Welding Programs and Schedule Information a) Updated schedules for ISI/NDE activities, planned welding activities, and schedule showing contingency repair plans, if available.
b) For the welding sample of ASME Class 1, 2 and 3 welds selected by the inspector from the information provided for Section A of this enclosure, please provide copies of the following documentation for each selected 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
4 Enclosure v) Applicable weld procedures (WPS) used to fabricate the welds vi) Copies of procedure qualification records (PQRs) supporting the WPSs above vii) Copies of mechanical test reports identified in the PQRs above viii) Copies of 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 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.
xii) Copies of NDE personnel qualifications, 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 indications analytically evaluated for continuous service in ASME Code Class 1, 2 and 3 systems selected by the inspector from Section A above, provide a copy of the examination records, technical evaluations, and associated corrective action documents.
e) A copy of (or ready access to) the 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 (If Applicable) a) Please provide the NDE personnel qualification records for the examiners who will perform examinations of the RPVH.
b) If a visual examination is planned for the upcoming refueling outage, please provide drawings showing the following:
i)
RPVH and CRDM nozzle configurations ii) RPVH insulation configuration
5 Enclosure c) Please provide a copy of NDE reports from the last RPVH examination.
d) Please provide a copy of evaluation or calculation demonstrating that the scope of the visual examination of the upper head will meet the 95% minimum coverage required by ASME Code Case N-729-1 (If a visual examination is planned for the upcoming refueling outage).
e) Please provide a copy of the procedures that will be used to identify the source of any boric acid deposits identified on the RPVH.
f) Please provide a copy of the updated calculation of effective degradation years (EDY) and re-inspection years (RIY) for the RPVH crack initiation and propagation susceptibility parameters.
g) Please provide a copy of the vendor qualification report(s) that demonstrates the detection capability of the NDE equipment used for the RPVH examinations. Also, please identify any changes in equipment configurations used for the RPVH examinations that differ from that used in the vendor qualification or demonstration report(s).
B.3 Boric Acid Corrosion Control Program a) Please provide boric acid walkdown inspection results, an updated list of boric acid leaks identified during the current 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 would like to conduct an independent boric acid walkdown of the reactor containment building early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspector during the walkdown.
B.4 Steam Generator Inspections (If Applicable) a) Please provide copies of the Examination Technique Specification Sheets (ETSS) and associated justification for any revisions.
b) Please provide a copy of the guidance to be followed if a loose part or foreign material is identified in the steam generators (SGs).
c) Please provide a copy of the ET procedures used to perform the SG ISI (specifically calibration and flaw characterization/sizing procedures, etc.). Also, include documentation for the specific equipment to be used.
d) Please provide copies of your responses to NRC and industry operating experience communications associated with SG tube integrity issues such as; Generic Letters,
6 Enclosure e) Information Notices, etc. *Do not provide these documents separately if already included in other information requested such as the degradation assessment.
f) Please provide a list of corrective action documents generated by the vendor and/or site with respect to SG inspection activities.
B.5 Codes and Standards a) Please provide ready access to:
i)
Applicable editions of the ASME Code for the Inservice Inspection Program and the Repair/Replacement Program.
ii) EPRI and industry standards referenced in the procedures used to perform the SG tube eddy current examination if SG tube inspections are scheduled for the upcoming outage.
B.6 License Renewal Inspections a) In accordance with NRC inspection procedure 71002, the inspectors would like to conduct an independent walkdown of structures, systems, and components in-scope of license renewal and located in normally inaccessible areas during power operation, such as the reactor containment building, to verify that any observable aging effects were identified by the applicant. The purpose of these walkdowns is to assess how plant equipment is currently being maintained and to visually observe examples of nonsafety-related equipment determined to be in scope due to their proximity to safety-related equipment and their potential for failure due to aging effects. Please have knowledgeable staff available to accompany the inspector during the walkdown.
Additionally, please provide ready access to scoping and aging management review documents developed in support to the license renewal application for structures, systems, and components in the reactor containment building.
Inspector Contact Information:
Mailing Address:
Joel Rivera-Ortiz US NRC Region 2 Senior Reactor Inspector Attn: Joel Rivera-Ortiz 404-997-4825 245 Peachtree Center Ave, NE Joel.Rivera-Ortiz@nrc.gov Suite 1200, Atlanta, GA 30303