ML100560603
| ML100560603 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/24/2010 |
| From: | Greg Werner NRC/RGN-IV/DRS/PSB-2 |
| To: | Flores R Luminant Generation Co |
| References | |
| IR-10-003 | |
| Download: ML100560603 (11) | |
See also: IR 05000445/2010003
Text
UNITED STATES
NUC LE AR RE G UL AT O RY C O M M I S S I O N
R E GI ON I V
612 EAST LAMAR BLVD , SU I TE 400
AR LI N GTON , TEXAS 76011-4125
February 24, 2010
Rafael Flores, Senior Vice President
and Chief Nuclear Officer
Attention: Regulatory Affairs
Luminant Generation Company LLC
P.O. Box 1002
Glen Rose, TX 76043
SUBJECT: Comanche Peak Steam Electric Station - NOTIFICATION OF INSPECTION
(NRC INSPECTION REPORT 05000445/2010003) AND REQUEST FOR
INFORMATION
Dear Mr. Flores:
From April 5-9 and April 19-23, 2010, reactor inspectors from the Nuclear Regulatory
Commissions (NRC) Region IV office will perform the baseline inservice inspection at
Comanche Peak Steam Electric Station, Unit 1, using NRC Inspection Procedure 71111.08,
"Inservice Inspection Activities," and TI 2515/172, "Reactor Coolant System Dissimilar Metal
Butt Welds." 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. Barnet 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 (wayne.sifre@nrc.gov) or Matthew
Young at (817) 276-6545 (matt.young@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
Luminant Generation Company LLC -2-
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
Mike Blevins, Chief Operating Officer
Luminant Generation Company LLC
Comanche Peak Steam Electric Station
P.O. Box 1002
Glen Rose, TX 76043
Mr. Fred W. Madden, Director
Oversight and Regulatory Affairs
Luminant Generation Company LLC
P.O. Box 1002
Glen Rose, TX 76043
Timothy P. Matthews, Esq.
Morgan Lewis
1111 Pennsylvania Avenue, NW
Washington, DC 20004
County Judge
P.O. Box 851
Glen Rose, TX 76043
Luminant Generation Company LLC -3-
Mr. Richard A. Ratliff, Chief
Bureau of Radiation Control
Texas Department of Health
P.O. Box 149347, Mail Code 2835
Austin, TX 78714-9347
Environmental and Natural
Resources Policy Director
Office of the Governor
P.O. Box 12428
Austin, TX 78711-3189
Honorable Walter Maynard
County Judge
P.O. Box 851
Glen Rose, TX 76043
Mr. Brian Almon
Public Utility Commission
William B. Travis Building
P.O. Box 13326
Austin, TX 78711-3326
Ms. Susan M. Jablonski
Office of Permitting, Remediation
and Registration
Texas Commission on
Environmental Quality
MC-122
P.O. Box 13087
Austin, TX 78711-3087
Anthony Jones
Chief Boiler Inspector
Texas Department of Licensing
and Regulation
Boiler Division
E.O. Thompson State Office Building
P.O. Box 12157
Austin, TX 78711
Chief, Technological Hazards
Branch
FEMA Region VI
800 North Loop 288
Federal Regional Center
Denton, TX 76209
Luminant Generation Company LLC -4-
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 (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)
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 (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
Inspection Reports/MidCycle and EOC Letters to the following:
ROPreports
Only inspection reports to the following:
DRS/TSB STA (Dale.Powers@nrc.gov)
OEDO RIV Coordinator (Leigh.Trocine@nrc.gov)
SUNSI Review Completed: __Y__ ADAMS: 7 Yes No Initials: ____
7 Publicly Available Non-Publicly Available Sensitive 7 Non-Sensitive
R:\REACTORS\CP U1 ISI RFI 2010 - WCS.
SRI:EB1 C:PSB2
W. Sifre G. Werner
/RA/ /RA/
2/18/10 2/24/10
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: April 5-9 and April 19-23, 2010
Inspection Procedures: IP 71111.08 "Inservice Inspection (ISI) Activities"
TI 2515/172 "Reactor Coolant System Dissimilar Metal Butt Welds"
Inspectors: Wayne Sifre, Senior Reactor Inspector (Lead Inspector - ISI)
Matthew 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 (ims.certrec.com preferred), in care of Wayne Sifre, by March 22, 2010,
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 (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 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.).
-1- Enclosure
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 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 tests 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 reactor pressure vessel head
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 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 noncode 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
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 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
-2- Enclosure
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 Materials Reliability (MRP-139) Program Activities
a) A list of, with verification, that the baseline inspections of all applicable Dissimilar
Metal Butt Welds (DMBWs) have been completed by December 31, 2009.
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 records of previous welding on
DMBWs and postweld NDE documentation.
e) A list and schedule of any stress improvement activities planned for the
upcoming refueling outage. If none are scheduled, then have qualification
reports for any stress improvements previously performed.
f) Documentation and description of how the baseline and ISI specifications in
MRP-139 are satisfied at your facility.
g) A list of weld locations controlled by MRP-139 which includes the MRP-139 weld
category, pre-mitigation volumetric examination date, type of mitigation or stress
improvement, post mitigation volumetric examination date, and plans for future
MRP-139 required examinations.
-3- Enclosure
A.6 Additional information related to all ISI activities
a) A list with a brief description of ISI, 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 1). For example, a list based upon data base searches using
key words related to piping or steam generator tube degradation such as: ISI,
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:
ISI 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
B. Information to be provided onsite to the inspectors at the entrance meeting (April 5,
2010):
B.1 ISI/Welding Programs and Schedule Information
a) Updated schedules for ISI/NDE 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 welding procedures used to fabricate the welds
vi) Copies of procedure qualification records supporting the welding
procedures from B.1.b.v
vii) Copies of mechanical test reports identified in the procedure qualification
records above
-4- 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 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 NDE personnel qualifications (VT, PT, UT, RT), as applicable
c) For the ISI 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 NDE reports with relevant conditions on Code Class 1 & 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 ISI Program Manual
and Plan for the current interval.
f) For the activities selected by the inspectors 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
a) Provide the NDE 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
-5- Enclosure
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 NDE 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.
g) Provide copy of the vendor qualification reports that demonstrates the detection
capability of the NDE 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 reports.
B.3 Boric Acid Corrosion Control Program
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 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 ISI
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
-6- Enclosure
Inspector Contact Information:
Wayne Sifre Matthew Young
Senior Reactor Inspector Reactor Inspector
817-860-8193 817-276-6545
wayne.sifre@nrc.gov matt.young@nrc.gov
Mailing Address:
US NRC Region IV
Attn: Wayne Sifre
612 E. Lamar Blvd, Suite 400
Arlington, TX 76011
-7- Enclosure