ML11215A205
| ML11215A205 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/03/2011 |
| From: | Greg Werner NRC/RGN-IV/DRS/PSB-2 |
| To: | Flores R Luminant Generation Co |
| References | |
| IR-11-005 | |
| Download: ML11215A205 (9) | |
See also: IR 05000445/2011005
Text
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGI ON I V
612 EAST LAMAR BLVD, SUITE 400
ARLINGTON, TEXAS 76011-4125
August 3, 2011
Rafael Flores, Senior Vice President
and Chief Nuclear Officer
Attention: Regulatory Affairs
Luminant Generation Company LLC
Comanche Peak Nuclear Power Plant
P.O. Box 1002
Glen Rose, TX 76043
SUBJECT: COMANCHE PEAK NUCLEAR POWER PLANT - NOTIFICATION OF
INSPECTION (NRC INSPECTION REPORT (05000445/2011005) AND
REQUEST FOR INFORMATION
Dear Mr. Flores:
On October 3, 2011, reactor inspectors from the Nuclear Regulatory Commissions (NRC)
Region IV office will perform the baseline inservice inspection at Comanche Peak, Unit 1, 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) identified 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. James Barnette of your licensing
organization. The tentative inspection schedule is as follows:
Preparation week: September 26-30, 2011
Onsite weeks: October 3-14, 2011
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 Isaac Anchondo at (817) 860-8152 (isaac.anchondo@nrc.gov.
R. Flores, Sr. Vice President -2-
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
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: 50-445
License: NPF-87
Enclosure:
Inservice Inspection Document Request
Distribution ListServ for Comanche Peak
R. Flores, Sr. Vice President -3-
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
Deputy Regional Administrator (Art.Howell@nrc.gov)
DRP Director (Kriss.Kennedy@nrc.gov)
Acting DRP Deputy Director (Jeff.Clark@nrc.gov)
DRS Director (Anton.Vegel@nrc.gov)
Acting DRS Deputy Director (Robert.Caldwell@nrc.gov)
Senior Resident Inspector (John.Kramer@nrc.gov)
Resident Inspector (Brian.Tindell@nrc.gov)
Branch Chief, DRP/A (Wayne.Walker@nrc.gov)
Senior Project Engineer, DRP/A (David.Proulx@nrc.gov)
Project Engineer, DRP/A (Christopher.Henderson@nrc.gov)
CP Administrative Assistant (Sue.Sanner@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Balwant.Singal@nrc.gov)
Branch Chief, DRS/TSB (Dale.Powers@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
OEMail Resource
Inspection Reports/MidCycle and EOC Letters to the following:
ROPreports
Only inspection reports to the following:
RIV/ETA: OEDO (John.McHale@nrc.gov)
DRS/TSB STA (Dale.Powers@nrc.gov)
SUNSI Review Completed: ___Y___ ADAMS: Yes No Initials: ___IAA_
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
RI:PSB2 C:PSB2
IAnchondo G. Werner
07/29/2011 08/03/2011
/RA/ /RA/
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October 3 through October 14, 2011
Inspection Procedures: IP 71111.08 "Inservice Inspection (ISI) Activities"
Inspectors: I. Anchondo, Reactor Inspector (Lead Inspector - ISI)
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 Isaac Anchondo, by
September 12, 2011, 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 planned for ASME Class 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.); and
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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 & 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 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 the
requirements of ASME Code Case 729-1. Also, include examination scope
expansion criteria and planned expansion sample sizes if relevant conditions are
identified, (If applicable).
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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
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 ISI 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, 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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B. Information to be provided onsite to the inspector(s) at the entrance meeting (October
3, 2011):
B.1 Inservice Inspection / Welding Programs and Schedule Information
a) Updated schedules for inservice inspection/nondestructive examination activities,
planned welding activities, and schedule showing contingency repair plans, if
available.
b) For ASME Code Class 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 supporting the WPS 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); and
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 ASME
Code Class systems selected by the inspectors from Section A above, provide a
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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) Provide drawings showing the following: (If a visual examination is planned for
the upcoming refueling outage)
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) Copy of 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 (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 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.
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g) Provide 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 (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 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:
Reactor Inspector
(817) 860-8152
isaac.anchondo@nrc.gov
Mailing Address:
US NRC Region IV
Attn: Isaac Anchondo
612 E. Lamar Blvd, Suite 400
Arlington, TX 76011
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