ML110200305
| ML110200305 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/19/2011 |
| From: | Greg Werner NRC/RGN-IV/DRS/PSB-2 |
| To: | Conway J Pacific Gas & Electric Co |
| References | |
| IR-11-003 | |
| Download: ML110200305 (10) | |
See also: IR 05000323/2011003
Text
January 19, 2011
John T. Conway Senior Vice President and Chief Nuclear Officer Pacific Gas and Electric Company 77 Beale Street, B32
San Francisco, CA
SUBJECT: DIABLO CANYON POWER PLANT, UNIT 2 - NOTIFICATION OF INSPECTION (NRC INTEGRATED INSPECTION REPORT 05000323/2011003) AND
REQUEST FOR INFORMATION
Dear Mr. Conway:
From May 9 through 20, 2011, reactor inspectors from the U.S. Nuclear Regulatory
Commission's (NRC) Region IV office will perform the baseline inservice inspection (ISI) at the Diablo Canyon Power Plant Unit 2, using NRC Inspection Procedure 71111.08, "Inservice Inspection Activities." 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 April 25, 2011, (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. McCoy 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 Wayne Sifre, lead inspector, at (817) 860-8193 (wayne.sifre@nrc.gov) or Isaac Anchondo at (817) 860-8152 (isaac.anchondo@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
Pacific Gas and Electric 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: 50-323 License: DPR-82
Enclosure: Inservice Inspection Document Request
cc:
Sierra Club Santa Lucia Chapter ATTN: Andrew Christie P.O. Box 15755 San Luis Obispo, CA 93406
Jane Swanson San Luis Obispo Mothers for Peace P.O. Box 3608 San Luis Obispo, CA 93403
James Grant, County Administrative Officer San Luis Obispo County Board of Supervisors 1055 Monterey Street, Suite D430 San Luis Obispo, CA 93408
Truman Burns\Robert Kinosian California Public Utilities Commission 505 Van Ness Ave., Rm. 4102 San Francisco, CA 94102
Pacific Gas and Electric Company - 3 -
Jennifer Post, Esq. Pacific Gas & Electric Co. 77 Beale Street, Room 2496
Mail Code B30A San Francisco, CA 94120
Gary Butner Chief, Radiologic Health Branch
California Department of Public Health 3 P.O. Box 997414 (MS 7610) Sacramento, CA 95899-7414
The City Editor of The Tribune 3825 South Higuera Street
P.O. Box 112 San Luis Obispo, CA 93406-0112
James D. Boyd, Commissioner California Energy Commission
1516 Ninth Street (MS 31) Sacramento, CA 95814
James R. Becker, Site Vice President Pacific Gas and Electric Company
Diablo Canyon Nuclear Plant P.O. Box 56, Mail Station 104/6/601 Avila Beach, CA 93424
Jennifer Tang
Field Representative United States Senator Barbara Boxer 1700 Montgomery Street, Suite 240 San Francisco, CA 94111
Chief, Technological Hazards Branch FEMA Region IX 1111 Broadway, Suite 1200 Oakland, CA 94607-4052
Pacific Gas and Electric Company - 4 -
Electronic distribution by RIV: Regional Administrator (Elmo.Collins@nrc.gov ) Deputy Regional Administrator (Art.Howell@nrc.gov ) DRP Director (Kriss.Kennedy@nrc.gov ) DRP Deputy Director (Troy.Pruett@nrc.gov ) DRS Director (Anton.Vegel@nrc.gov ) DRS Deputy Director (Vacant) Senior Resident Inspector (Michael.Peck@nrc.gov ) Resident Inspector (Laura.Micewski@nrc.gov ) Acting Branch Chief, DRP/B (Don.Allen@nrc.gov ) Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov ) Project Engineer, DRP/B (Greg.Tutak@nrc.gov ) Project Engineer, DRP/B (Nestor.Makris@nrc.gov ) DC Administrative Assistant (Agnes.Chan@nrc.gov ) Public Affairs Officer (Victor.Dricks@nrc.gov) Public Affairs Officer (Lara.Uselding@nrc.gov ) Project Manager (Alan.Wang@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 OEDO RIV Coordinator (James.Trapp@nrc.gov ) DRS/TSB STA (Dale.Powers@nrc.gov )
R:_\REACTORS\DC\ 2011003 ISI RFI LTR-WS ADAMS ML
ADAMS: No Yes SUNSI Review Complete Reviewer Initials: WCS
Publicly Available Non-Sensitive
Non-publicly Available Sensitive RI:EB1 C:PSB2 W. Sifre G. Werner 1/18/11 1/19/11 /RA/ /RA/. OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
- 1 - Enclosure INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: May 9 through 20, 2011
Inspection Procedures: IP 71111.08, "Inservice Inspection (ISI) Activities"
Inspectors: Wayne Sifre, Senior Reactor Inspector (Lead Inspector - ISI) Isaac A. Anchondo, 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 Wayne Sifre by April 25, 2011, to facilitate the selection of specific items that will be reviewed during the onsite inspection weeks. The inspectors will select specific items from the information requested below and then request from your staff additional documents needed during
the onsite inspection weeks (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 inspectors as soon as possible.
A.1 ISI / 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)
iv) Examinations planned as part of your boric acid corrosion control program (Mode 3 walkdowns, bolted connection walkdowns, etc.)
- 2 - Enclosure 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 penetrant, 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 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
- 3 - Enclosure 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.3 Steam Generator Tube Inspections
a) A detailed schedule of: i) Steam generator secondary side inspection activities for the upcoming outage. b) Please provide a copy of your steam generator inservice inspection program and plan. Please include a copy of the operational assessment from the 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 Traveler TSTF-449, "Steam Generator Tube Integrity," please provide copies of your correspondence with the NRC regarding deviations from the standard technical specifications.
d) Identify and quantify any steam generator tube leakage experienced during the previous operating cycle. Also provide documentation identifying which steam generator was leaking and corrective actions completed or planned for this
condition (If applicable).
e) 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.).
f) Please provide copies of your most recent self-assessments of the steam generator monitoring, loose parts monitoring, and secondary side water chemistry control programs.
A.4 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.
- 4 - Enclosure
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 inspectors at the entrance meeting:
B.1 ISI/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 inspectors 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
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 radiographic testing was performed)
x) Copies of the preservice examination records for the selected welds
- 5 - Enclosure 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 nondestructive examination personnel qualifications (Visual inspection, penetrant testing, ultrasonic testing, radiographic testing), 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) the 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 a 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 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.3 Steam Generator Tube Inspections
a) Copies of the examination technique specification sheets and associated justification for any revisions.
- 6 - Enclosure b) Copy of the guidance to be followed if a loose part or foreign material is identified in the steam generators.
c) 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.
d) List of corrective action documents generated by the vendor and/or site with respect to steam generator inspection activities.
B.4 Codes and Standards
a) Ready access to (i.e., copies provided to the inspectors 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.
Inspector Contact Information
- Wayne Sifre Isaac Anchondo Senior Reactor Inspector Reactor Inspector
817-860-8193 817-860-8152 wayne.sifre@nrc.gov isaac.anchondo@nrc.gov Mailing Address
- US NRC Region IV
Attn: Wayne Sifre 612 E. Lamar Blvd, Suite 400 Arlington, TX 76011