ML090350754
| ML090350754 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/04/2009 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Edington R Arizona Public Service Co |
| References | |
| IR-09-003 | |
| Download: ML090350754 (13) | |
See also: IR 05000530/2009003
Text
February 4, 2009
Randall K. Edington, Executive
Vice President, Nuclear/CNO
Mail Station 7602
Arizona Public Service Company
P.O. Box 52034
Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNIT 3-
NOTIFICATION OF INSPECTION (NRC INSPECTION
REPORT 05000530/2009003) AND REQUEST FOR INFORMATION
Dear Mr. Edington:
From April 13 to 24, 2009, reactor inspectors from the U. S. Nuclear Regulatory
Commissions (NRC) Region IV office will perform the baseline inservice inspection at
Palo Verde Nuclear Generating Station, Unit 3, using NRC Inspection
Procedure 71111.08 and Temporary Instruction 2515/172, Reactor 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 on-site 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 Del Elkington of your
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, James Adams, @ 817-860-8294
or e-mail him (James.Adams@nrc.gov).
UNITED STATES
NUCLEAR REGULATORY COMMISSION
R E GI ON I V
612 EAST LAMAR BLVD, SUITE 400
ARLINGTON, TEXAS 76011-4125
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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/
Thomas Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No: 50-530
License No. 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 Kent Porter
Senior Counsel
Southern California Edison Company
Law Department, Generation Resources
P.O. Box 800
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
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Mr. Scott Bauer, Director
Regulatory Affairs
Palo Verde Nuclear Generating Station
Mail Station 7636
P.O. Box 52034
Phoenix, AZ 85072-2034
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. Jeffrey T. Weikert
Assistant General Counsel
El Paso Electric Company
Mail Location 167
123 W. Mills
El Paso, TX 79901
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
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Mr. Brian Almon
Public Utility Commission
William B. Travis Building
P.O. Box 13326
1701 North Congress Avenue
Austin, TX 78701-3326
Mr. Phil McNeely
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, Radiological Emergency Preparedness Section
National Preparedness Directorate
Technological Hazards Division
Department of Homeland Security
1111 Broadway, Suite 1200
Oakland, CA 94607-4052
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Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov )
Deputy Regional Administrator (Chuck.Casto@nrc.gov )
DRP Director (Dwight.Chamberlain@nrc.gov)
DRP Deputy Director (Anton.Vegel@nrc.gov )
DRS Director (Roy.Caniano@nrc.gov )
DRS Deputy Director (Troy.Pruett@nrc.gov)
Senior Resident Inspector (Ryan.Treadway@nrc.gov )
Resident Inspector (Michelle.Catts@nrc.gov )
Resident Inspector (Jim.Melfi@nrc.gov )
Resident Inspector (Joe.Bashore@nrc.gov )
Branch Chief, DRP/D (Michael.Hay@nrc.gov)
PV Site Secretary (Patricia.Coleman@nrc.gov )
Senior Project Engineer, DRP/D (Don Allen@nrc.gov )
Public Affairs Officer (Victor.Dricks@nrc.gov )
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov )
RITS Coordinator (Marisa.Herrera@nrc.gov )
File located: : S:\\DRS\\REPORTS\\PV US ISI RFI-JPA ML
SUNSI Rev Compl.
X Yes
No
X Yes No
Reviewer Initials
TRF
Publicly Avail
X Yes
No
Sensitive
Yes XNo
Sens. Type
Initials
TRF
EB1
EB1
C:EB1
JPAdams
MRYoung
TFarnholtz
/RA/
/RA/
/RA/
1/30/09
2/3/09
2/4/09
OFFICIAL RECORD COPY
T=Telephone E=E-mail F=Fax
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Enclosure
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates:
April 13 to 24, 2009
Inspection Procedures:
IP 71111.08 Inservice Inspection (ISI) Activities
TI 2515/172 Reactor Coolant System Dissimilar Metal Butt
Inspectors:
James Adams, Reactor Inspector (Lead Inspector - ISI)
Matthew R. Young, 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 (CD or IMS preferred), in care of James Adams by March 30,
2009, to facilitate the selection of specific items that will be reviewed during the
onsite inspection weeks. The inspector will select specific items from the
information requested below and then request from your staff additional
documents needed at the beginning of the first 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 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 refueling outage.
iii)
Examinations planned for Alloy 82/182/600 components that are
not included in the Section XI scope (If applicable).
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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 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 NDE reports with
relevant conditions 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 relevant condition 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 in 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 commitments made in response to NRC
Bulletin 2002-02 and NRC Order EA-03-009. Also, include examination
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Enclosure
scope expansion criteria and planned expansion sample sizes if relevant
conditions are identified (if applicable).
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 walkdown
inspections performed as part of the BACCP.
c)
Please provide a copy of the most recent self-assessment performed for
the BACCP.
A.4
Steam Generator Tube (SGT) Inspections
a)
A detailed schedule of:
i)
SGT inspection, data analyses, and repair activities for the
upcoming outage (if occurring).
ii)
SG secondary side inspection activities for the upcoming outage
(if occurring).
b)
Please provide a copy of your SG ISI 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 TSTF-449, please provide copies of your
correspondence with the NRC regarding deviations from the STS.
d)
Copy of SG history documentation given to vendors performing eddy
current (ET) testing of the SGs during the upcoming outage.
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Enclosure
e)
Copy of SG Eddy Current Data Analyst Guidelines and Site Validated
Eddy Current Technique Specification Sheets (ETSS). Additionally,
please provide a copy of EPRI Appendix H ETSS Qualification Records.
f)
Identify and quantify any SGT leakage experienced during the previous
operating cycle. Also provide documentation identifying which SG 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 SG
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 SGT 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
Metals Reliability (MRP-139) Program Activities
a)
A list of, with verification that, the baseline inspections of all applicable
Dissimilar Metal Butt Welds (DMBWs) that have been completed.
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 (examination dates) of all DMBW 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 DMBWs in the
upcoming outage. If no welding will be performed then provide records of
previous welding on DMBWs and postweld NDE documentation.
e)
A list and schedule of any stress improvement (SI) activities planned for
the upcoming refueling outage. If none are scheduled then have
qualification reports for any SIs previously performed.
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Enclosure
f)
Documentation and description of how the baseline and inservice
inspection specifications in MRP-139 are satisfied at your facility.
A.6
Additional information related to all ISI activities
a)
A list with a brief description of ISI, BACCP, and SGT inspection related
issues (e.g., condition reports) entered into your corrective action
program since the beginning of the last refueling outage (for Unit 3). For
example, a list based upon data base searches using key words related
to piping or SG tube degradation such as: ISI, ASME Code,Section XI,
NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors
in piping/SGT examinations.
b)
Please provide names and phone numbers for the following program
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
SG Inspection Activities (site lead and vendor contact)
DMBW/MRP-139 Program
B.
Information to be provided onsite to the inspector(s) at the entrance
meeting (April 13, 2009):
B.1
ISI / Welding Programs and Schedule Information
a)
Updated schedules for ISI/NDE activities, including SGT 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 (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
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Enclosure
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
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 WPS (at least six months prior to the date of
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(s)
from section A of this enclosure, provide a copy of the corrective actions
and supporting documentation.
d)
For the NDE reports with relevant conditions 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 qualification 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
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Enclosure
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.
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 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 (SGT) Inspections
a)
Copies of the Examination Technique Specification Sheets (ETSS) 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 SGs.
c)
Please provide a copy of the ET procedures used to perform the SGT
inspections (specifically calibration and flaw characterization/sizing
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Enclosure
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 SGT 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 SG inspection activities.
B.5
Codes and Standards
a)
Ready access to (i.e., 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 SGT eddy current examination.
Inspector Contact Information:
James P. Adams
Matthew R. Young
Reactor Inspector
Reactor Inspector
817-860-8294
817-276-6545
james.adams@nrc.gov
matt.young@nrc.gov
Mailing Address:
US NRC Region IV
Attn: J. Adams
612 East Lamar Blvd, Suite 400
Arlington, TX 76011