ML102371285
| ML102371285 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/24/2010 |
| From: | Greg Werner NRC/RGN-IV/DRS/PSB-2 |
| To: | Edington R Arizona Public Service Co |
| References | |
| IR-10-005 | |
| Download: ML102371285 (13) | |
See also: IR 05000530/2010005
Text
UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 EAST LAMAR BLVD, SUITE 400ARLINGTON, TEXAS 76011-4125August 24, 2010
Randall K. Edington, Executive Vice President, Nuclear/CNO Arizona Public Service Company P.O. Box 52034, Mail Stop 7602 Phoenix, AZ 85072-2034
SUBJECT: PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 - NOTIFICATION OF INSPECTION (NRC INSPECTION REPORT 05000530/2010005) AND REQUEST FOR INFORMATION
Dear Mr. Edington:
From October 4 through 15, 2010, reactor inspectors from the U.S. Nuclear Regulatory Commission's (NRC) Region IV office will perform the baseline inservice inspection at Palo Verde Nuclear Generating Station (Unit 3), using NRC Inspection Procedure 71111.08,
"Inservice Inspection Activities," and Temporary Instruction 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 September 29, 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. Delbert Elkinton 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, Matthew Young at (817) 276-6545 (matt.young@nrc.gov), or Theresa Buchanan at (817) 276-6503 (theresa.buchanan@nrc.gov) or Blake Rice at (817) 276-6563 (blake.rice@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
Arizona Public Service Company - 2 -
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 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: 50-530 License: NPF-74
Enclosure: Inservice Inspection Document Request
cc w/Enclosure: Mr. Steve Olea
Arizona Corporation Commission 1200 W. Washington Street Phoenix, AZ 85007
Mr. Douglas K. Porter, Esq
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, CA 91770
Chairman
Maricopa County Board of Supervisors 301 W. Jefferson, 10th Floor Phoenix, AZ 85003
Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street
Phoenix, AZ 85040
Arizona Public Service Company - 3 -
Mr. Dwight C. Mims Vice President Regulatory Affairs and Plant Improvement
Palo Verde Nuclear Generating Station Mail Station 7605 P.O. Box 52034 Phoenix, AZ 85072-2034
Mr. Ron Barnes, Director Regulatory Affairs Palo Verde Nuclear Generating Station MS 7638 P.O. Box 52034 Phoenix, AZ 85072-2034
Mr. Jeffrey T. Weikert Assistant General Counsel El Paso Electric Company Mail Location 167 123 W. Mills
El Paso, TX 79901
Michael S. Green Senior Regulatory Counsel Pinnacle West Capital Corporation
P.O. Box 52034, MS 8695 Phoenix, AZ 85072-2034
Mr. Eric Tharp Los Angeles Department of Water & Power
Southern California Public Power Authority P.O. Box 51111, Room 1255-C Los Angeles, CA 90051-0100
Mr. James Ray
Public Service Company of New Mexico 2401 Aztec NE, MS Z110 Albuquerque, NM 87107-4224
Mr. Geoffrey M. Cook Southern California Edison Company 5000 Pacific Coast Hwy. Bldg. D21
San Clemente, CA 92672
Mr. Robert Henry Salt River Project 6504 East Thomas Road
Scottsdale, AZ 85251
Arizona Public Service Company - 4 -
Mr. Brian Almon Public Utility Commission
William B. Travis Building P.O. Box 13326 Austin, TX 78701-3326
Environmental Program Manager
City of Phoenix Office of Environmental Programs 200 West Washington Street Phoenix, AZ 85003
Mr. John C. Taylor Director, Nuclear Generation
El Paso Electric Company 340 East Palm Lane, Suite 310 Phoenix, AZ 85004
Chief, Technological Hazards
Branch FEMA Region IX 1111 Broadway, Suite 1200 Oakland, CA 94607-4052
Jake Lefman Southern California Edison Company 5000 Pacific Coast Hwy, Bldg. D21 San Clemente, CA 92672
Arizona Public Service Company - 5 -
Electronic distribution by RIV: Regional Administrator (Elmo.Collins@nrc.gov) Deputy Regional Administrator (Chuck.Casto@nrc.gov)
DRP Acting Director (Anton.Vegel@nrc.gov) DRP Acting Deputy Director (Troy.Pruett@nrc.gov) DRS Director (Roy.Caniano@nrc.gov) DRS Acting Deputy Director (Jeff.Clark@nrc.gov) Resident Inspector (Joseph.Bashore@nrc.gov)
Resident Inspector (Mica.Baquera@nrc.gov) Branch Chief, DRP/D (Ryan.Lantz@nrc.gov) PV Administrative Assistant (Regina.McFadden@nrc.gov) Senior Project Engineer, DRP/D (Don.Allen@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) Executive Technical Assistant (John.Giessner@nrc.gov)
SUNSI Review Completed: ___Y___ ADAMS: Yes No Initials: ___MRY_ Publicly Available Non-Publicly Available Sensitive Non-Sensitive
ML102371285 RI:EB1 C:PSB2 MYoung GWerner MY GW 8/20/2010 8/23/2010 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
- 1 - Enclosure INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October 4 through 15, 2010
Inspection Procedures: IP 71111.08 "Inservice Inspection Activities" TI 2515/172 "Reactor Coolant System Dissimilar Metal Butt Welds"
Inspectors: Matthew Young, Reactor Inspector (Lead Inspector - Inservice Inspection)
Theresa Buchanan, Reactor Inspector Blake Rice, 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 Matthew Young, by
September 27, 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 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 Inservice Inspection/Welding Programs and Schedule Information
a) A detailed schedule (including preliminary dates) of:
i) Nondestructive examinations planned for Class 1 & 2 systems and containment, performed as part of your ASME,Section XI, risk informed (if applicable), and augmented inservice inspection programs during the upcoming outage
Provide a status summary of the nondestructive examination 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)
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 nondestructive examination reports (ultrasonic, radiography, magnetic particle, dye penetrate, Visual VT-1, VT-2, and VT-3), which have identified relevant conditions on Code Class 1 & 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 nondestructive examination reports with relevant conditions in the reactor pressure vessel head penetration nozzles
that have been accepted for continued service. The list of nondestructive examination reports should include a brief description of the structures, systems, or components where the relevant condition was identified.
d) A list with a brief description (e.g., system, material, pipe size, weld number, and nondestructive examinations 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 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.
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 inservice inspection, welding, and Alloy 600 programs.
A.2 Reactor Pressure Vessel Head
This section will not be completed due to replacement of the reactor pressure vessel
head.
- 3 - Enclosure 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) 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 shut down, please provide documentation of containment walkdown inspections performed as part of the
boric acid corrosion control program.
c) Please provide a copy of the most recent self-assessment performed for the boric acid corrosion control program.
A.4 Steam Generator Tube Inspections
a) A detailed schedule of:
i) Steam generator tube inspection, data analyses, and repair activities for the upcoming outage (If occurring)
ii) Steam generator secondary side inspection activities for the upcoming outage (if occurring)
b) Please provide a copy of your steam generator inservice 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, please provide copies of your correspondence with the NRC regarding deviations from the standard technical specification.
d) Copy of steam generator history documentation given to vendors performing Eddy Current testing of the steam generators during the upcoming outage.
e) Copy of steam generator Eddy Current data analyst guidelines and site validated Eddy Current technique specification sheets. Additionally, please provide a copy of the Electric Power Research Institute (EPRI), Appendix H, Eddy Current technique specification sheets qualification records.
f) Identify and quantify any steam generator tube leakage experienced during the previous operating cycle. Also provide documentation identifying which steam
- 4 - Enclosure generator 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 steam generators (including items such as loose parts, fouling, top of tube
sheet condition, crud removal amounts, etc.).
h) Please provide copies of your most recent self assessments of the steam generator monitoring, loose parts monitoring, and secondary side water chemistry control programs.
i) Please also indicate where the primary, secondary, and resolution analyses are scheduled to take place.
j) Please provide a summary of the scope of the steam generator tube 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-139 Activities
a) A list of, with verification, that the baseline inspections of all applicable dissimilar metal butt welds have been completed by July 31, 2010.
b) Verification that baseline inspection of hot leg and cold leg temperature dissimilar metal butt welds have been included in the inspection program and that the schedules for the baseline inspections are consistent with the baseline schedules
in Materials Reliability Program-139.
c) A list and schedule (examination dates) of all dissimilar metal butt weld 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 dissimilar metal butt welds in the upcoming outage. If no welding will be performed, then records of previous welding on dissimilar metal butt welds and postweld nondestructive examination 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 inservice inspection specifications in Materials Reliability Program-139 are satisfied at your facility.
g) A list of weld locations controlled by Materials Reliability Program-139 which includes the Materials Reliability Program-139 weld category, pre-mitigation volumetric examination date, type of mitigation or stress improvement,
- 5 - Enclosure post mitigation volumetric examination date, and plans for future Materials Reliability Program-139 required examinations.
A.6 Additional Information Related to All Inservice Inspection Activities
a) A list with a brief description of inservice inspection, boric acid corrosion control program, and steam generator-tube 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 steam generator tube degradation
such as: inservice inspection, ASME Code,Section XI, nondestructive examination, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping/steam generator tube examinations.
b) Please provide names and phone numbers for the following program leads:
Inservice inspection contacts (examination, planning)
Containment exams Reactor pressure vessel head exams Snubbers and supports Repair and replacement program manager Licensing contact
Site welding engineer Boric acid corrosion control program Steam generator inspection activities (site lead and vendor contact)
B. Information to be provided onsite to the inspector(s) at the entrance meeting (October 4, 2010):
B.1 Inservice Inspection/Welding Programs and Schedule Information
a) Updated schedules for inservice inspection/nondestructive examination activities, including steam generator tube 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, 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 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 inservice inspection related corrective action issues selected by the inspectors from Section A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d) For the nondestructive examination reports with relevant conditions on Code Class 1 and 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 inservice inspection program manual and plan for the Current interval.
f) For the nondestructive examinations selected by the inspectors from Section A of this enclosure, provide copy of the nondestructive examination 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 nondestructive examination personnel qualification records.
B.2 Reactor Pressure Vessel Head
This section will not be completed due to replacement of the reactor pressure vessel
head.
- 7 - Enclosure B.3 Boric Acid Corrosion Control Program
a) Please 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) 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 identify specifically which known leaks, if any, have remained in service or will remain in
service as active leaks.
B.4 Steam Generator Tube Inspections
a) Copies of the examination technique specification sheets 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 steam generators.
c) Please provide a copy of the Eddy Current testing procedures used to perform the steam generator tube inspections (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 such as Generic Letters, Information Notices, etc.
(as applicable to steam generator tube 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 steam generator inspection activities.
B.5 Codes and Standards
a) Ready access to (e.g., 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 inservice inspection program and the repair/replacement program
ii) EPRI and industry standards referenced in the procedures used to perform the steam generator tube Eddy Current examination
- 8 - Enclosure Inspector Contact Information:
Matthew Young Theresa Buchanan Blake Rice Reactor Inspector Reactor Inspector Reactor Inspector 817-276-6545 817-276-6503 817-276-6563
matt.young@nrc.gov theresa.buchanan@nrc.gov blake.rice@nrc.gov
Mailing Address: US NRC Region IV Attn: Matthew Young
612 E. Lamar Blvd, Suite 400 Arlington, TX 76011