ML103630579
| ML103630579 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/29/2010 |
| From: | Greg Werner NRC/RGN-I/DRS/PSB2 |
| To: | Berryman B Entergy Operations |
| References | |
| IP 71111.08 | |
| Download: ML103630579 (11) | |
See also: IR 05000368/2011002
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
R E GI ON I V
612 EAST LAMAR BLVD, SUITE 400
ARLINGTON, 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
Commissions (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 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 NRCs 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
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
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
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.
7 Yes No
7 Yes No
Reviewer Initials
DRR
Publicly Avail
7 Yes No
Sensitive
Yes 7No
Sens. Type Initials
DRR
EB 1
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
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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.)
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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
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.
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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
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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
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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
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.
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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
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Enclosure
Mailing Address:
US NRC, Region IV
Attn: Jim Melfi
612 E. Lamar Blvd, Suite 400
Arlington, TX 76011