ML110280466
| ML110280466 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/27/2011 |
| From: | Greg Werner NRC/RGN-IV/DRS/PSB-2 |
| To: | Matthew Sunseri Wolf Creek |
| References | |
| IR-11-003 | |
| Download: ML110280466 (13) | |
See also: IR 05000482/2011003
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
January 27, 2011
Matthew W. Sunseri, President and
Chief Executive Officer
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, KS 66839
SUBJECT: WOLF CREEK GENERATING STATION - NOTIFICATION OF INSPECTION
(NRC INSPECTION REPORT 05000482/2011003) AND REQUEST FOR
INFORMATION
Dear Mr. Sunseri,
From March 25 to April 1, 2011, reactor inspectors from the Nuclear Regulatory
Commissions (NRC) Region IV office will perform the baseline inservice inspection at
Wolf Creek Generating Station, 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, due by
February 16, 2011, (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. William Muilenberg 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, James Drake, at (817) 276-6558 (James.Drake@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.
Wolf Creek Nuclear Operating Corporation -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/ James F. Drake for
Gregory E. Werner, Chief
Plant Support Branch 2
Division of Reactor Safety
Docket: 50-482
License: NPF-42
Enclosure:
Inservice Inspection Document Request
cc w/enclosure:
Site Vice President
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, KS 66839
Jay Silberg, Esq.
Pillsbury Winthrop Shaw Pittman LLP
2300 N Street, NW
Washington, DC 20037
Supervisor Licensing
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, KS 66839
Chief Engineer
Utilities Division
Kansas Corporation Commission
1500 SW Arrowhead Road
Topeka, KS 66604-4027
Office of the Governor
State of Kansas
Topeka, KS 66612-1590
Wolf Creek Nuclear Operating Corporation -3-
Attorney General
120 S.W. 10th Avenue, 2nd Floor
Topeka, KS 66612-1597
Chairman
Coffey County Courthouse
110 South 6th Street
Burlington, KS 66839
Chief, Radiation and Asbestos
Control Section
Bureau of Air and Radiation
Kansas Department of Health and
Environment
1000 SW Jackson, Suite 310
Topeka, KS 66612-1366
Chief, Technological Hazards
Branch
FEMA, Region VII
9221 Ward Parkway
Suite 300
Kansas City, MO 64114-3372
Wolf Creek Nuclear Operating Corporation -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)
DRS Deputy Director (Vacant)
Senior Resident Inspector (Chris.Long@nrc.gov)
Resident Inspector (Charles.Peabody@nrc.gov)
WC Administrative Assistant (Shirley.Allen@nrc.gov)
Acting Branch Chief, DRP/B (Don.Allen@nrc.gov)
Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov)
Project Engineer, DRP/B (Greg.Tutak@nrc.gov)
Project Engineer, DRP/B (Nestor.Makris@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
OEDO RIV Coordinator (James.Trapp@nrc.gov)
DRS/TSB STA (Dale.Powers@nrc.gov)
SUNSI Review Completed: ___Y___ ADAMS: 7 Yes No Initials: ___JFD_
7 Publicly Available Non-Publicly Available Sensitive 7 Non-Sensitive
C:PSB2 RI:PSB2 C:PSB2
G. Werner J. Drake G. Werner
/RA/ /RA/ /RA/ JFD for
1/26/2011 1/26/2011 1/27/2011
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: March 25, 2011, through April 1, 2011
Inspection Procedures: IP 71111.08, Inservice Inspection (ISI) Activities
TI 2515/172, Reactor Coolant System Dissimilar Metal Butt Welds
Inspectors: Jim Drake, Reactor Inspector (Lead Inspector - ISI)
Abin Fairbanks, 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 Drake, by February 28,
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 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 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 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)
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 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 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
commitments made in response to NRC Bulletin 2002-02 and
NRC Order EA-03-009. Also, include examination scope expansion criteria and
-2- Enclosure
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 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 shut down, 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 Steam Generator Tube (SGT) Inspections
a) A detailed schedule of:
i) Steam generator tube inspection, data analyses, and repair activities for
the upcoming outage
ii) Steam generator secondary side inspection activities for the upcoming
outage
b) Please provide a copy of your steam generator inservice 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 Technical Specification Task Force Traveler TSTF-449, Steam
Generator Tube Integrity, please provide copies of your correspondence with the
NRC regarding deviations from the standard technical specifications.
d) Copy of steam generator history documentation given to vendors performing
eddy current testing of the steam generators during the upcoming outage.
-3- Enclosure
e) Copy of steam generator eddy current data analyst guidelines and site validated
eddy current technique specification sheets. Additionally, please provide a copy
of EPRI Appendix H, Examination Technique Specification Sheets, qualification
records.
f) Identify and quantify any steam generator tube leakage experienced during the
previous operating cycle. Also provide documentation identifying which steam
generator 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) Provide copies of your most recent self-assessments of the steam generator
monitoring, loose parts monitoring, and secondary side water chemistry control
programs.
i) Indicate where the primary, secondary, and resolution analyses are scheduled to
take place.
j) Provide a summary of the scope of the steam generator tube 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 Materials Reliability Program: Primary System Piping Butt Weld Inspection and
Evaluation Guideline (MRP-139) Activities
a) A list, with verification, that the baseline inspections of all applicable dissimilar
metal butt welds have been completed by February 16, 2011.
b) Verification that baseline inspection of hot leg and cold leg temperature dissimilar
metal butt welds 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 dissimilar metal butt weld
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 dissimilar metal butt
welds in the upcoming outage. If no welding will be performed then records of
previous welding on dissimilar metal butt welds and postweld nondestructive
examination documentation.
-4- Enclosure
e) A list and schedule of any stress improvement activities planned for the
upcoming refueling outage. If none are scheduled then provide qualification
reports for any stress improvements previously performed.
f) Documentation and description of how the baseline and inservice inspection
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.
A.6 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 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 (examination, planning)
Containment exams
Reactor pressure vessel head exams
Snubbers and supports
Repair and replacement program
Licensing
Site welding engineer
Boric acid corrosion control program
Steam generator inspection activities (site lead and vendor contact)
B. Information to Be Provided Onsite to the Inspector(s) at the Entrance Meeting
(March 25, 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 inspector from the lists
provided from section A of this enclosure, please provide copies of the following
documentation for each subject weld:
-5- Enclosure
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
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
-6- Enclosure
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
NOTE: 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.
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).
-7- Enclosure
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 Steam Generator Tube Inspections
a) Copies of the examination technique specification sheets 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 steam generators.
c) Please provide a copy of the eddy current testing procedures used to perform the
steam generator tube inspections (specifically calibration and flaw
characterization/sizing 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 steam generator tube 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 steam generator 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 steam generator tube eddy current examination.
-8- Enclosure
Inspector Contact Information:
James Drake Abin Fairbanks
Senior Reactor Inspector Reactor Inspector
817-276-6558 817-860-8158
James.Drake@nrc.gov Abin.Fairbanks@nrc.gov
Mailing Address:
US NRC Region IV
Attn: James Drake
612 E. Lamar Blvd, Suite 400
Arlington, TX 76011
-9- Enclosure