ML102300672
| ML102300672 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/18/2010 |
| From: | Greg Werner NRC/RGN-IV/DRS/PSB-2 |
| To: | Ridenoure R Southern California Edison Co |
| References | |
| Download: ML102300672 (13) | |
See also: IR 05000036/2020005
Text
August 18, 2010
Mr. Ross T. Ridenoure Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station
P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT: SAN ONOFRE NUCLEAR GENERATING STATION UNIT 3 - NOTIFICATION OF INSPECTION (NRC INSPECTION REPORT 05000362005) AND REQUEST FOR INFORMATION
Dear Mr.Ridenoure:
From November 29 to December 10, 2010, reactor inspectors from the U.S. Nuclear Regulatory
Commission's (NRC) Region IV office will perform the baseline inservice inspection at San Onofre Nuclear Generating Station Unit 3, using NRC Inspection Procedure 71111.08, "Inservice Inspection Activities," and TI 2515/172, "Reactor Coolant System Dissimilar Metal Butt Welds." Experience has shown that this inspection is a resource intensive inspection both for the NRC inspectors and your staff. In order to minimize the impact to your onsite 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, due by September 1, 2010, (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 Mr. Dave Axeline of your licensing 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 Jim Drake, at (817) 276-6558 or (James.Drake@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 UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 EAST LAMAR BLVD, SUITE 400ARLINGTON, TEXAS 76011-4125
Southern California Edison Company - 2 -
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.
In accordance with 10 CFR 2.390 of the NRC's "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). ADAMS is accessible from the NRC web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA/ Gregory E. Werner, Chief
Plant Support Branch 2 Division of Reactor Safety
Docket: 50-362 License: NPF-15
Enclosure: Inservice Inspection Document Request
Chairman, Board of Supervisors
County of San Diego 1600 Pacific Highway, Room 335 San Diego, CA 92101
Gary L. Nolff
Assistant Director-Resources City of Riverside 3900 Main Street Riverside, CA 92522
Mark L. Parsons Deputy City Attorney City of Riverside 3900 Main Street Riverside, CA 92522
Gary H. Yamamoto, P.E., Chief
Division of Drinking Water and Environmental Management 1616 Capitol Avenue, MS 7400 P.O. Box 997377 Sacramento, CA 95899-7377
Southern California Edison Company - 3 -
Michael L. DeMarco San Onofre Liaison San Diego Gas & Electric Company 8315 Century Park Ct. CP21C
San Diego, CA 92123-1548
Director, Radiological Health Branch State Department of Health Services P.O. Box 997414 (MS 7610)
Sacramento, CA 95899-7414
The Mayor of the City of San Clemente 100 Avenida Presidio San Clemente, CA 92672
James D. Boyd, Commissioner
California Energy Commission 1516 Ninth Street (MS 34) Sacramento, CA 95814
Douglas K. Porter, Esquire
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, CA 91770
Albert R. Hochevar
Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
Steve Hsu Department of Health Services Radiologic Health Branch MS 7610, P.O. Box 997414 Sacramento, CA 95899-7414
R. St. Onge Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
Chief, Technological Hazards Branch FEMA Region IX 1111 Broadway, Suite 1200 Oakland, CA 94607-4052
Southern California Edison Company - 4 -
Institute of Nuclear Power Operations (INPO) Records Center 700 Galleria Parkway SE, Suite 100 Atlanta, GA 30339
Southern California Edison Company - 5 -
Electronic distribution by RIV: Regional Administrator (Elmo.Collins@nrc.gov) Deputy Regional Administrator (Chuck.Casto@nrc.gov) Acting DRP Director (Tony.Vegel@nrc.gov)
Acting DRP Deputy Director (Troy.Pruett@nrc.gov) DRS Director (Roy.Caniano@nrc.gov) Acting DRS Deputy Director (Jeff.Clark@nrc.gov) Senior Resident Inspector (Greg.Warnick@nrc.gov) Resident Inspector (John.Reynoso@nrc.gov)
Branch Chief, DRP/D (Ryan.Lantz@nrc.gov) Senior Project Engineer, DRP/D (Don.Allen@nrc.gov) SONGS Administrative Assistant (Heather.Hutchinson@nrc.gov) Project Engineer, DRP/D (Peter.Jayroe@nrc.gov) Project Engineer, DRP/D (Zachary.Hollcraft@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Randy.Hall@nrc.gov) Branch Chief, DRS/TSB (Michael.Hay@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov) Congressional Affairs Officer (Jenny.Weil@nrc.gov)
OEMail Resource
Inspection Reports/MidCycle and EOC Letters to the following: ROPreports
Only inspection reports to the following: DRS/TSB STA (Dale.Powers@nrc.gov) OEDO RIV Coordinator (Margie.Kotzalas@nrc.gov)
SUNSI Review Completed: ___Y___ ADAMS: Yes No Initials: ___JFD_
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
R:_Reactors/_SONGS/2010/2010005-LTR-JFD.docx ML RI:EB1 C:PSB2 JDrake GWerner
8/16/2010 8/18/2010 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
- 1 - Enclosure INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: November 29 through December 10, 2010
Inspection Procedures: IP 71111.08 "Inservice Inspection (ISI) Activities" TI 2515/172 "Reactor Coolant System Dissimilar Metal Butt Welds"
Inspectors: J. Drake, Senior Reactor Inspector (Lead Inspector - ISI) S. Makor, Reactor Inspector
A. Fairbanks, Reactor Inspector
A. Information Requested for the In-Office Preparation Week
The following information should be sent to the Region IV office in hard copy or electronic format (ims.certrec.com preferred), in care of Jim Drake, by September 1, 2010, to facilitate the selection of specific items that will be reviewed
during the onsite inspection week. The inspectors 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 inspectors, 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) Reactor pressure vessel head examinations planned for the upcoming outage. iii) Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope (if applicable).
- 2 - Enclosure iv) Examinations planned as part of your Boric Acid Corrosion Control Program (Mode 3 walkdowns, bolted connection walkdowns, etc.).
v) Welding activities that are scheduled to be completed during the upcoming outage (ASME, Class 1, 2, or 3 structures, systems, or
components (SSCs)).
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 penetrate, Visual VT-1, VT-2, and VT-3), which have identified relevant conditions on Code Class 1 and 2 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. Also, include in the list the NDE reports with relevant conditions in the reactor pressure vessel head penetration nozzles that have been accepted for continued service.
The list of NDE reports should include a brief description of the SSC where the relevant condition 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. 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 noncode 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
a) 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 commitments made in response to NRC Bulletin 2002-02 and NRC Order EA-03-009. Also, include examination scope expansion criteria and planned expansion sample sizes if relevant conditions are identified (if applicable).
- 3 - Enclosure
b) 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).
A.3 Boric Acid Corrosion Control Program
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) 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, provide documentation of containment walkdown inspections performed as part of the Boric Acid Corrosion Control Program.
c) Provide a copy of the most recent self-assessment performed for the Boric Acid Corrosion Control Program.
A.4 Steam Generator Tube (SGT) Inspections
a) A detailed schedule of:
i) SGT inspection, data analyses, and repair activities for the upcoming outage (if occurring).
ii) Steam Generator (SG) secondary side inspection activities for the upcoming outage (if occurring).
b) Provide a copy of your SG ISI Inspection Program and Plan. Please include a copy of the Operational Assessment from last outage and a copy of the following documents as they become available:
i) Degradation Assessment ii) Condition Monitoring Assessment
c) If you are planning on modifying your technical specifications such that they are consistent with Technical Specification Task Force-449, provide copies of your correspondence with the NRC regarding deviations from the standard technical specifications.
d) Copy of SG history documentation given to vendors performing Eddy Current (ET) testing of the SGs during the upcoming outage.
- 4 - Enclosure e) Copy of SG Eddy Current Data Analyst Guidelines and Site Validated Eddy Current Technique Specification Sheets (ETSS). Additionally, provide a copy of EPRI, Appendix H, ETSS Qualification Records.
f) Identify and quantify any SGT 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).
g) Provide past history of the condition and issues pertaining to the secondary side of the SG (including items such as loose parts, fouling, top of tube sheet
condition, crud removal amounts, etc.).
h) Provide copies of your most recent self-assessments of the SG monitoring, loose parts monitoring, and secondary side water chemistry control programs.
i) Indicate where the primary, secondary, and resolution analyses are scheduled to take place.
j) Provide a summary of the scope of the SGT examinations, including examination methods such as bobbin, rotating pancake, or plus point, and the percentage of tubes to be examined. *Do not provide these documents separately if already included in other information requested. A.5 Materials Reliability Program (MRP-139) Activities
a) A list of, with verification, that the baseline inspections of all applicable Dissimilar Metal Butt Welds (DMBWs) have been completed by July 31 2010.
b) Verification that baseline inspection of hot-leg and cold-leg temperature DMBWs have been included in the inspection program and that the schedules for the baseline inspections are consistent with the baseline schedules in MRP-139.
c) A list and schedule (examination dates) of all DMBW examinations planned for the upcoming refueling outage. If none are scheduled, then data from previous examinations should be available for review.
d) A list and schedule for any welding to be performed on DMBWs in the upcoming outage. If no welding will be performed then records of previous welding on DMBWs and post-weld NDE documentation.
e) A list and schedule of any stress improvement activities planned for the upcoming refueling outage. If none are scheduled then have qualification reports for any stress improvements previously performed.
f) Documentation and description of how the baseline and ISI specifications in MRP-139 are satisfied at your facility.
- 5 - Enclosure g) A list of weld locations controlled by MRP-139, which includes the MRP-139 weld category, pre-mitigation volumetric examination date, type of mitigation or stress improvement, post-mitigation volumetric examination date, and plans for future MRP-139 required examinations.
A.6 Additional information related to all ISI activities
a) A list with a brief description of ISI, Boric Acid Corrosion Control Program, and SGT inspection related issues (e.g., condition reports) entered into your corrective action program since the beginning of the last refueling outage (for
Unit 2). For example, a list based upon data base searches using key words related to piping or SG tube degradation such as: ISI, ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping/SGT examinations.
b) Provide names and phone numbers for the following program leads:
ISI contacts (examination, planning) Containment Examinations RPVH Examinations Snubbers and Supports Repair and Replacement Program Manager
Licensing Contact Site Welding Engineer Boric Acid Corrosion Control Program SG Inspection Activities (site lead and vendor contact)
B. Information to be provided onsite to the inspector(s) at the entrance meeting (November 29, 2010).
B.1 ISI / Welding Programs and Schedule Information
a) Updated schedules for ISI/NDE activities, including SGT inspections, planned welding activities, and schedule showing contingency repair plans, if available.
b) For ASME, Code Class 1 and 2 welds selected by the inspector from the lists provided from Section A of this enclosure, 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 used to fabricate the welds
- 6 - Enclosure
vi) Copies of procedure qualification records supporting the weld procedures from B.1.b.v vii) Copies of mechanical test reports identified in the procedure qualification records 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
xi) Copies of welder performance qualifications records applicable to the selected welds, including documentation that welder maintained proficiency in the applicable welding processes specified in the weld
procedures (at least 6 months prior to the date of 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(s) from Section A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d) For the NDE reports with relevant conditions on Code Class 1 & 2 systems selected by the inspectors 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 inspectors 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 qualification 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 the NDE personnel qualification records for the examiners who will perform examinations of the reactor pressure vessel head
- 7 - Enclosure b) Provide drawings showing the following: (If a visual examination is planned for the upcoming refueling outage).
i) RPVH and CRDM nozzle configurations ii) RPVH insulation configuration
The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.
c) Copy of NDE reports from the last RPVH examination.
d) Copy of evaluation or calculation demonstrating that the scope of the visual examination of the upper head will meet the 95 percent minimum coverage required by NRC Order EA-03-009 (If a visual examination is planned for the upcoming refueling outage).
e) Provide a copy of the procedures that will be used to identify the source of any boric acid deposits identified on the RPVH. If no explicit procedures exist which govern this activity, provide a description of the process to be followed including personnel responsibilities and expectations.
f) Provide a copy of the updated calculation of effective degradation years (EDY) for the RPVH susceptibility ranking.
g) 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).
B.3 Boric Acid Corrosion Control Program
a) Provide boric acid walkdown 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) 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 identify specifically which known leaks, if any, have remained in service or will remain in service as active leaks.
B.4 SGT Inspections
a) Copies of the Examination Technique Specification Sheets (ETSS) and associated justification for any revisions.
b) Copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.
- 8 - Enclosure
c) Provide a copy of the ET procedures used to perform the SGT inspections (specifically calibration and flaw characterization/sizing procedures, etc.). Also include documentation for the specific equipment to be used.
d) Provide copies of your responses to NRC and industry operating experience communications such as Generic Letters, Information Notices, etc. (as applicable to SGT inspections) *Do not provide these documents separately if already included in other information requested such as the degradation assessment.
e) List of corrective action documents generated by the vendor and/or site with respect to SG inspection activities.
B.5 Codes and Standards
a) Ready access to (i.e., copies provided to the inspector(s) for use during the inspection at the onsite inspection location, or room number and location where
available):
i) Applicable Editions of the ASME Code, Sections V, IX and XI for the ISI program and the repair/replacement program.
ii) EPRI and industry standards referenced in the procedures used to perform the SGT Eddy Current examination.
Inspector Contact Information:
Jim Drake Abin Fairbanks Shiattin Makor Senior Reactor Inspector Reactor Inspector Reactor Inspector 817-276-6558 817-860-8158 817-276-6507 James.Drake@nrc.gov Abin.Fairbanks@nrc.gov
Shiattin.Makor@nrc.gov
Mailing Address: US NRC Region IV Attn: Jim Drake 612 E. Lamar Blvd, Suite 400 Arlington, TX 76011