ML080420505
| ML080420505 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/11/2008 |
| From: | Russ Bywater Region 4 Engineering Branch 1 |
| To: | Mitchell T Entergy Operations |
| References | |
| IR-08-003 | |
| Download: ML080420505 (11) | |
See also: IR 05000313/2008003
Text
UNITED STATES
NU CLE AR RE GU LATOR Y C O M M I S S I O N
R EGI ON I V
611 R YAN PLAZA D R IV E, SU ITE 400
AR LI N GTON , TEXAS 76011-4005
February 11, 2008
Timothy G. Mitchell
Vice President Operations
Arkansas Nuclear One
Entergy Operations, Inc.
1448 S.R. 333
Russellville, AR 72802-0967
SUBJECT: ARKANSAS NUCLEAR ONE - NOTIFICATION OF INSPECTION (NRC
INSPECTION REPORT 05000313/2008003 AND 05000368/2008003) AND
REQUEST FOR INFORMATION
Dear Mr. Mitchel:
From March 17 - 28, 2008, reactor inspectors from NRCs Region IV office will perform the
baseline inservice inspection at Arkansas Nuclear One, Unit 2, using NRC Inspection
Procedure 71111.08 and Temporary Instruction 2515/172, Rector Coolant System Dissimilar
Metal Butt Welds. Experience has shown that this inspection is resource intensive 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) 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. Fred Vanbuskirk 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 Wayne Sifre at (817) 860-8193 (wcs@nrc.gov).
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 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/
Russell L. Bywater, Chief
Engineering Branch 1
Division of Reactor Safety
Dockets: 50-313; 50-368
Enclosure:
Inservice Inspection Document Request
cc: w/enclosure
Senior Vice President
Entergy Operations, Inc.
P.O. Box 31995
Jackson, MS 39286-1995
Senior Vice President
& Chief Operating Officer
Entergy Operations, Inc.
P.O. Box 31995
Jackson, MS 39286-1995
Vice President
Operations Support
Entergy Operations, Inc.
P.O. Box 31995
Jackson, MS 39286-1995
Site Vice President
Entergy Operations, Inc.
Arkansas Nuclear One
1448 S. R. 333
Russellville, AR 72802
Entergy Operations, Inc. -3-
General Manager Plant Operations
Entergy Operations, Inc.
Arkansas Nuclear One
1448 S. R. 333
Russellville, AR 72802
Director, Nuclear Safety Assurance
Entergy Operations, Inc.
Arkansas Nuclear One
1448 S. R. 333
Russellville, AR 72802
Manager, Licensing
Entergy Operations, Inc.
Arkansas Nuclear One
1448 S. R. 333
Russellville, AR 72802
Director, Nuclear Safety & Licensing
Entergy Operations, Inc.
1340 Echelon Parkway
Jackson, MS 39213-8298
Section Chief, Division of Health
Radiation Control Section
Arkansas Department of Health and
Human Services
4815 West Markham Street, Slot 30
Little Rock, AR 72205-3867
Section Chief, Division of Health
Emergency Management Section
4815 West Markham Street, Slot 30
Little Rock, AR 72205-3867
County Judge of Pope County
Pope County Courthouse
100 West Main Street
Russellville, AR 72801
Entergy Operations, Inc. -4-
Electronic distribution by RIV:
Regional Administrator (EEC)
DRP Director (DDC)
DRS Director (RJC1)
DRS Deputy Director (ACC)
Senior Resident Inspector (AAS1)
Branch Chief, DRP/E (JAC)
Senior Project Engineer, DRP/E (GDR)
Senior Project Engineer, DRP/E (GBM)
Team Leader, DRP/TSS (CJP)
RITS Coordinator (MSH3)
SUNSI Review Completed: __Y___ ADAMS: 6 Yes No Initials: __WCS____
6 Publicly Available Non-Publicly Available Sensitive 6 Non-Sensitive
S:\DRS\REPORTS\AN2008003lt-wcs.doc
SRI:EB1 RI:EB1 C:EB1
WCSifre/lmb STGraves RLBywater
/RA/ /RA/ /RA/
2/7/08 2/11/08 2/11/08
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: March 17, 2008 - March 28, 2008
Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities
TI 2515/172 Reactor Coolant Dissimilar Metal Butt Welds
Inspectors: W. Sifre, Senior Reactor Inspector (Lead Inspector - ISI)
S. Graves, 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 W. Sifre, by February 25, 2008,
to facilitate the selection of specific items that will be reviewed during the onsite
inspection week. The inspector 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 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 (RPVH) 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)
-1- 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 penetrant,
visual VT-1, VT-2, and VT-3) which have identified recordable indications
(geometric or flaw) 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 NDE reports with recorded indications
in the RPVH penetration nozzles which have been accepted for continued
service. The list of NDE reports should include a brief description of the SSC
where the recordable indication 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. 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 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 non-code 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 (RPVH)
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 NRC 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 indications are identified.
(If applicable)
-2- 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 (BACCP)
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 walk-down inspections performed as part of the
BACCP.
c) Please provide a copy of the most recent self-assessment performed for the
BACCP.
A.4 Metals Reliability (MRP-139) Program Activities
a) A list and verification that the baseline inspections of all Dissimilar Metal Butt
Welds (DMBWs)have been completed by December 31, 2007.
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 of all DMBW examinations that will occur in the coming
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 coming
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 (SI) activities planned for the
coming refueling outage. If none are scheduled then have qualification reports
for any SIs previously performed.
f) Documentation and description of how the baseline and inservice inspection
specifications in MRP-139 are satisfied at your facility.
-3- Enclosure
A.5 Additional Information Related To All ISI Activities
a) A list with a brief description of ISI and BACCP related issues (e.g., condition
reports) entered into your corrective action program since the beginning of the
last refueling outage (for the applicable Unit). For example, a list based upon
data base searches using key words related to piping such as: ISI, ASME Code,
Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or
errors in piping examinations.
b) Please provide names and phone numbers for the following program leads:
ISI contacts (Examination, planning)
Containment Exams
RPVH Exams
Snubbers and Supports
Repair and Replacement Program Manager
Licensing Contact
Site Welding Engineer
Boric Acid Corrosion Control Program
B. Information To Be Provided Onsite To The Inspector At The Entrance Meeting
(March 17, 2008):
B.1 ISI / Welding Programs and Schedule Information
a) Updated schedules for ISI/NDE activities, planned welding activities, and
schedule showing contingency repair plans, if available.
b) For ASME 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 (WPS) used to fabricate the welds
vi) Copies of procedure qualification records (PQRs) supporting the WPS
from B.1.b.v
vii) Copies of mechanical test reports identified in the PQRs 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.
-4- Enclosure
xi) Copies of welder performance qualifications records applicable to WPS,
including documentation that welder maintained proficiency in the
applicable welding processes specified in the WPS (At least six months
prior to date 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 from
Section A of this enclosure, provide a copy of the corrective actions and
supporting documentation.
d) For the NDE reports with recordable indications on Code Class 1 & 2 systems
selected by the inspector 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 inspector 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 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 RPVH.
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.
-5- Enclosure
d) Copy of evaluation or calculation demonstrating that the scope of the visual
examination of the upper head will meet the 95% 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 (BACCP)
a) Please provide boric acid walk down 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
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 inspector to use for the duration of
the inspection at the on-site inspection location, or room number and location
where available)
b) Applicable editions of the ASME Code (Sections V, IX and XI) for the inservice
inspection program and the repair/replacement program.
Inspector Contact Information:
W. Sifre Sam Graves
Senior Reactor Inspector Reactor Inspector
817-860-8193 817-860-8102
lee1@nrc.gov stg2@nrc.gov
-6- Enclosure
Mailing Address:
US NRC Region IV
Attn: W. Sifre
611 Ryan Plaza Drive, Suite 400
Arlington, TX 76011
-7- Enclosure