ML103630579
| ML103630579 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/29/2010 |
| From: | Werner G E NRC/RGN-I/DRS/PSB2 |
| To: | Berryman B Entergy Operations |
| References | |
| IP 71111.08 | |
| Download: ML103630579 (11) | |
See also: IR 05000368/2011002
Text
UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 EAST LAMAR BLVD, SUITE 400ARLINGTON, TEXAS 76011-4125 December 29, 2010
Brad Berryman, Vice President, Operations
Arkansas Nuclear One Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802
SUBJECT: ARKANSAS NUCLEAR ONE, UNIT 2 - NOTIFICATION OF INSPECTION (NRC INSPECTION REPORT 050-368/2011002) AND REQUEST FOR INFORMATION
Dear Mr. Berryman:
From February 22 to March 5, 2011, reactor inspectors from the Nuclear Regulatory Commission's (NRC) Region IV office will perform the baseline inservice inspection at Arkansas Nuclear One, 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 (Section A of the enclosure), due by February 1, 2011, 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. Stephanie Pyle 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 Jim Melfi, lead inspector, at (817) 276-6523 (jim.melfi@nrc.gov) or Dustin Reinert at (817) 860-8244 (dustin.reinert@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
requesting document displays a currently valid Office of Management and Budget control number.
Entergy Operations, Inc. - 2 -
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: 50-368 License: NPF-06
Enclosure: Senior Vice President & Chief Operating Officer Entergy Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995
Thomas Palmisano Vice President, Oversight
Entergy Operations, Inc. P.O. Box 31995 Jackson, MS 39286-1995
Mark Giles
Acting Manager, Licensing Arkansas Nuclear One 1448 SR 333 Russellville, AR 72802
Joseph A. Aluise Associate General Counsel - Nuclear Entergy Services, Inc 639 Loyola Avenue New Orleans, LA 70113
Senior Manager, Nuclear Safety & Licensing
Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995
Entergy Operations, Inc. - 3 -
Chief, Radiation Control Section Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867
Jim E. Gibson County Judge of Pope County 100 West Main Street Russellville, AR 72801
Arkansas Department of Health Radiation Control Section 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867
David E. Maxwell, Director
Arkansas Department of Emergency Management, Bldg. 9501 Camp Joseph T. Robinson North Little Rock, AR 72199
Chief, Technological Hazards Branch FEMA Region VI 800 North Loop 288 Federal Regional Center
Denton, TX 76209
Entergy Operations, Inc. - 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) Senior Resident Inspector (Alfred.Sanchez@nrc.gov) Resident Inspector (Jeff.Rotton@nrc.gov) Branch Chief, DRP/E (Jeff.Clark@nrc.gov)
Senior Project Engineer, DRP/E (Ray.Azua@nrc.gov) Project Engineer (Jim.Melfi@nrc.gov) Project Engineer (William.Schaup@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Public Affairs Officer (Lara.Uselding@nrc.gov) Project Manager (Kaly.Kalyanam@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
File located: S:/DRS/REPORTS/reports final/ANO 2011002 RFI-JFM ML 103630579 SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials DRRPublicly Avail Yes No Sensitive Yes No Sens. Type Initials DRR
EB 1 TSB C:PSB 2 D. Reinert J. Melfi G. Werner
/RA/ /RA/ /RA/ 12/20/2010 12/23/2010 12/29/2010 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
- 1 - Enclosure INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: February 22 through March 5, 2011
Inspection Procedures: IP 71111.08 "Inservice Inspection (ISI) Activities"
Inspectors: Jim Melfi, Project Engineer (Lead Inspector - ISI) Dustin Reinert, 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 Melfi, by February 1, 2011, 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 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 and 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 versus 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 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 startup 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
a) Provide the detailed scope of the planned nondestructive examinations of the reactor vessel head which identifies the types of nondestructive examination 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 nondestructive examination 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) 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 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 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 Unit 2 refueling outage. 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, NDE, 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
- 4 - Enclosure B. Information to be Provided Onsite to the Inspectors at the Entrance Meeting February 22, 2011
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 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 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
- 5 - Enclosure 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 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 Reactor Pressure Vessel Head
a) Provide the nondestructive personnel qualification records for the examiners who will perform examinations of the reactor pressure vessel head.
b) If a visual examination is planned for the upcoming refueling outage, provide drawings showing the following:
i) Reactor pressure vessel head and control rod drive mechanism nozzle configurations ii) Reactor pressure vessel head insulation configuration
The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.
c) Copy of nondestructive examination reports from the last reactor pressure vessel head examination.
d) If a visual examination is planned for the upcoming refueling outage provide a copy of the 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.
- 6 - Enclosure e) Provide a copy of the procedures that will be used to identify the source of any boric acid deposits identified on the reactor pressure vessel head. 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 for the reactor pressure vessel head susceptibility ranking.
g) Provide a copy of the vendor qualification report(s) that demonstrates the detection capability of the nondestructive examination equipment used for the
reactor pressure vessel head examinations. Also, identify any changes in equipment configurations used for the reactor pressure vessel head 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 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.
ii) EPRI and industry standards referenced in the procedures used to perform the steam generator tube eddy current examination.
Inspector Contact Information:
Project Engineer Reactor Inspector 817-276-6523 817-860-8244 Jim.Melfi@nrc.gov Dustin.Reinert@nrc.gov
- 7 - Enclosure Mailing Address: US NRC, Region IV Attn: Jim Melfi 612 E. Lamar Blvd, Suite 400 Arlington, TX 76011