ML062770301
| ML062770301 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/27/2006 |
| From: | Garrett T Wolf Creek |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ET 06-0038 | |
| Download: ML062770301 (12) | |
Text
Terry J. Garrett Vice President, Engineering
ET 06-0038
U. S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, DC 20555
Subject:
Docket No. 50-482: Application for Renewed Operating License
Gentlemen:
Pursuant to Code of Federal Regulations, Title 10, Parts 50, 51 and 54, Wolf Creek Nuclear Operating Corporation (WCNOC) hereby requests the renewal of Facility Operating License
Number NPF-42 for the Wolf Creek Generating Station (WCGS), Unit No. 1.
The current Operating License for WCGS expires at midnight, March 11, 2025. WCNOC requests that the WCGS Operating Licens e be extended for 20 years beyond the current expiration date to midnight, March 11, 2045.
The enclosed License Renewal Application contains the information required by 10 CFR Part 54 for filing an application and the application meets the timeliness requirements of 10 CFR
54.17(c) and 10 CFR 2.109(b).
As required by 10 CFR 54.21(b), current licensing basis changes which have a material effect on the content of this application, will be identified at least annually while the application is under NRC review and at least three months prior to the scheduled completion of the NRC
review.
Attachment II provides a summary of commitments made in this application. Implementation of new programs may require additional action items not included in this list. WCGS is committed
to including new program elements in the corrective action program.
The Enclosure provides the CD-ROM submittal of the WCGS License Renewal Application in
accordance with 10 CFR 2 Subpart A, 10 CFR 50.4, and 10 CFR 50.30.
ET 06-0038 Page 2 of 2If you have anyquestions concerning this matter, pleasecontact me at (620) 364
-4084,orMr.Kevin Moles at (620) 26.Very truly yours,
Attachment:
I-Oath-ListofRegulatory Commitments
Enclosure:
License Renewal Application cc: J.N.(NRC), wle G.E.Werner (NRC), B.S.(NRC),Senior Resident Inspector (NRC),
AttachmentIto ET 06-0038 Page 1 of 1 STATE OF KANSASCOUNTYOF COFFEY Terry J.Garrett,oflawful age, being first duly swornupon oath says that heis Vice President EngineeringofWolf Creek Nuclear Operating Corporation;that he has read the foregoing document and knows thecontents thereof; that he hasexecutedthesame for andonbehalfof said Corporation with full powerand authority todoso;andthat the facts therein stated are true and correct to the best of his knowledge,information and belief.
Vice Engineering SUBSCRIBEDand sworn to before me day 2006.MY COMMISSION EXPIRES January 11,2010 Notary Public I Expiration Date Attachment II to ET 06-0038 Page 1 of 8
LIST OF REGULATORY COMMITMENTS
The following table identifies a summary of those actions committed to by Wolf Creek Nuclear Operating Corporation (WCNOC) in this License Renewal Application (LRA). All commitments have a due date of March 11, 2025. Any other statements in this submittal are provided for information purposes and are not considered to be commitments. Please direct questions
regarding these commitments to Mr. Kevin Moles at (620) 364-4126.
COMMITMENT SUBJECT LRA, Appendix A, Section COMMITMENT DESCRIPTION Boric Acid Corrosion Program (RCMS 2006-198) A1.4 Prior to the period of extended operation, procedures will be
enhanced to state that susceptible
components adjacent to potential
leakage sources will include electrical
components and connectors.
Nickel-Alloy Penetration
Nozzles Welded To The Upper
Reactor Vessel Closure Heads
of Pressurized Water Reactors (RCMS 2006-199) A1.5 Prior to the period of extended operation, procedures will be
enhanced to indicate that detection of
leakage or evidence of cracking in the
vessel head penetration nozzles or
associated welds will cause an
immediate reclassification to the "High" susceptibility ranking, commencing from the same outage in
which the leakage or cracking is
detected.
Closed-Cycle Cooling Water
System (RCMS 2006-200) A1.10 Prior to the period of extended operation, a new periodic preventive
maintenance activity will be developed
to specify performing inspections of
the internal surfaces of valve bodies
and accessible piping while the valves
are disassembled for operational
readiness inspections to detect loss of
material and fouling.
Inspection of Overhead Heavy
Load and Light Load (Related
to Refueling) Handling Systems (RCMS 2006-201) A1.11 Prior to the period of extended operation, procedures will be
enhanced to: (1) identify industry
standards or Wolf Creek Generating
Station (WCGS) specifications that
are applicable to the component, and
(2) specifically inspect for loss of
material due to corrosion or rail wear.
Attachment II to ET 06-0038 Page 2 of 8
COMMITMENT SUBJECT LRA, Appendix A, Section COMMITMENT DESCRIPTION Fire Protection (RCMS 2006-202) A1.12 Prior to the period of extended operation: (1) fire damper inspection
and drop test procedures will be
enhanced to inspect damper housing
for signs of corrosion, (2) fire barrier
and fire door inspection procedures
will be enhanced to specify fire
barriers and doors described in USAR
Appendix 9.5A, "WCGS Fire
Protection Comparison to APCSB 9.5-
1 Appendix A", and WCGS Fire
Hazards Analysis, and (3) training for
technicians performing the fire door
and fire damper visual inspection will
be enhanced to include fire protection
inspection requirements and training
documentation.
Fuel Oil Chemistry (RCMS 2006-203 A1.14 Prior to the period of extended operation: (1) the emergency fuel oil
day tanks will be added to the ten
year drain, clean, and internal
inspection program, and (2)
procedures will be enhanced to
provide for supplemental ultrasonic
thickness measurements if there are
indications of reduced cross sectional
thickness found during the visual
inspection of the emergency fuel oil
storage tanks.
One-Time Inspection (RCMS 2006-204)
A1.16 The One-Time Inspection program conducts one-time inspections of
plant system piping and components
to verify the effectiveness of the Water
Chemistry program (A1.2), Fuel Oil
Chemistry program (A1.14), and
Lubricating Oil Analysis program (A1.23).This new program will be
implemented and completed within
the ten-year period prior to the period
of extended operation.
Selective Leaching of Materials (RCMS 2006-205) A1.17 The Selective Leaching of Materials program is a new program that will be
implemented prior to the period of
extended operation.
Attachment II to ET 06-0038 Page 3 of 8
COMMITMENT SUBJECT LRA, Appendix A, Section COMMITMENT DESCRIPTION Buried Piping and Tanks Inspection (RCMS 2006-206) A1.18 The Buried Piping and Tanks Inspection program is a new program
that will be implemented prior to the
period of extended operation. Within
the ten-year period prior to entering
the period of extended operation, an
opportunistic or planned inspection
will be performed. Upon entering the
period of extended operation a
planned inspection within ten years
will be required unless an
opportunistic inspection has occurred
within this ten-year period.
One-Time Inspection of ASME
Code Class 1 Small-Bore
Piping (RCMS 2006-207) A1.19 The fourth interval of the ISI program at WCGS will provide the results for
the one time inspection of ASME
Code Class 1 small-bore piping.
Inspection of Internal Surfaces
in Miscellaneous Piping and
Ducting Components (RCMS 2006-208) A1.22 The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting
Components program is a new
program that will be implemented prior
to the period of extended operation.
For those systems or components
where inspections of opportunity are
insufficient, an inspection will be
conducted prior to the period of
extended operation to provide
reasonable assurance that the
intended functions are maintained.
Electrical Cables and
Connections Not Subject to 10
CFR 50.49 Environmental
Qualification Requirements (RCMS 2006-209) A1.24 The Electrical Cables and Connections Not Subject to 10 CFR
50.49 Environmental Qualification
Requirements program is a new
program that will be implemented prior
to the period of extended operation.
Electrical Cables Not Subject
to 10 CFR 50.49
Environmental Qualification
Requirements Used in
Instrumentation Circuits (RCMS 2006-210) A1.25 A review of the calibration surveillance test results will be completed before
the period of extended operation and
every 10 years thereafter.
Attachment II to ET 06-0038 Page 4 of 8
COMMITMENT SUBJECT LRA, Appendix A, Section COMMITMENT DESCRIPTION Inaccessible Medium Voltage Cables Not Subject to 10 CFR
50.49 Environmental
Qualification Requirements (RCMS 2006-211) A1.26 The Inaccessible Medium Voltage Cables Not Subject to 10 CFR 50.49
Environmental Qualification
Requirements program is a new
program that will be implemented prior
to the period of extended operation. ASME Section XI, Subsection
IWL (RCMS 2006-212) A1.28 Prior to the period of extended operation, procedures will be
enhanced to include two new
provisions regarding inspection of
repair/replacement activities. The 2003 edition of ASME Section XI, Subsection IWL, Article IWL-2000, includes two provisions that are not
required by the 1998 edition. IWL-
2410(d) specifies additional
inspections for concrete surface areas
affected by a repair/replacement
activity, and IWL-2521.2 specifies
additional inspections for tendons
affected by a repair/replacement
activity. In accordance with 10 CFR
50.55a, WCGS will revise their CISI
program prior to the next inspection
interval to incorporate the ASME
Code edition and addenda
incorporated into 10 CFR 50.55a at
that time.
Masonry Wall Program (RCMS 2006-213) A1.31 Prior to the period of extended operation, procedures will be
enhanced to identify un-reinforced
masonry in the Radwaste Building
within the scope of license renewal
that requires aging management.
Structures Monitoring Program (RCMS 2006-214) A1.32 Prior to the period of extended operation, procedures will be
enhanced to add inspection
parameters for treated wood.
Attachment II to ET 06-0038 Page 5 of 8
COMMITMENT SUBJECT LRA, Appendix A, Section COMMITMENT DESCRIPTION RG 1.127, Inspection of Water-Control Structures Associated
with Nuclear Power Plants (RCMS 2006-215) A1.33 Prior to the period of extended operation, procedures will be
enhanced: (1) so that the main dam
service spillway and the auxiliary
spillway will be inspected in
accordance with the same
specification, (2) to clarify the scope
of inspections for the spillways, (3) to
add the 5 year inspection frequency
for the main dam service spillway, and
(4) to add cavitation to the list of
concrete aging effects for surfaces
other than spillways.
Supplement (RCMS 2006-216)
A1.35 WCNOC will:
A. Reactor Coolant System Nickel Alloy Pressure Boundary Components Implement applicable (1) NRC Orders, Bulletins and Generic Letters
associated with nickel alloys and (2)
staff-accepted industry guidelines, and B. Reactor Vessel Internals
(1) Participate in the industry programs for investigating and
managing aging effects on reactor
internals; (2) evaluate and implement
the results of the industry programs as
applicable to the reactor internals; and
(3) upon completion of these
programs, but not less than 24
months before entering the period of
extended operation, WCNOC will
submit an inspection plan for reactor
internals to the NRC for review and
approval. Electrical Cable Connections Not Subject To 10 CFR 50.49
Environmental Qualification
Requirements (RCMS 2006-217)
A1.36 Prior to the period of extended operation, the infrared thermography
testing procedure will be enhanced to
require an engineering evaluation
when test acceptance criteria are not
met. This engineering evaluation will
include identifying the extent of
condition, the potential root cause for
not meeting the test acceptance, and
the likelihood of recurrence.
Attachment II to ET 06-0038 Page 6 of 8
COMMITMENT SUBJECT LRA, Appendix A, Section COMMITMENT DESCRIPTION Metal Fatigue of Reactor Coolant Pressure Boundary (RCMS 2006-218) A2.1 Prior to the period of extended operation, the Metal Fatigue of
Reactor Coolant Pressure Boundary
program will be enhanced to include:
(1) Action levels to ensure that if the
fatigue usage factor calculated by the
code analysis is reached at any
monitored location, appropriate
evaluations and actions will be
invoked to maintain the analytical
basis of the leak-before-break (LBB)
analysis and of the high-energy line
break (HELB) locations, or to revise
them as required, (2) Action levels to
ensure that appropriate evaluations
and actions will be invoked to
maintain the bases of safety
determinations that depend upon
fatigue analyses, if the fatigue usage
factor at any monitored location
approaches 1.0, or if the fatigue
usage factor at any monitored
NUREG/CR6260 location approaches
1.0 when multiplied by the
environmental effect factor F EN , (3) Corrective actions, on approach to
these action levels, that will determine
whether the scope of the monitoring
program must be enlarged to include
additional affected reactor coolant
pressure boundary locations in order
to ensure that additional locations do
not approach the code limit without an
appropriate action, and to ensure that
analyses are maintained, (4) 10 CFR
50 Appendix B procedural and record
requirements. Prior to the period of
extended operation, changes in
available monitoring technology or in
the analyses themselves may permit
different action limits and action
statements, or may re-define the
program features and actions required
to address the fatigue time-limited
aging analyses (TLAAs).
Attachment II to ET 06-0038 Page 7 of 8
COMMITMENT SUBJECT LRA, Appendix A, Section COMMITMENT DESCRIPTION Environmental Qualification of Electrical Components (RCMS 2006-219) A2.2 Prior to the period of extended operation, program documents will be
enhanced to describe methods that
may be used for qualified life
evaluations for the period of extended
operation.
Concrete Containment Tendon
Prestress (RCMS 2006-220) A2.3 Prior to the period of extended operation, procedures will be revised
to: (1) extend the list of surveillance
tendons to include random samples
for the year 40, 45, 50, and 55 year
surveillances, (2) explicitly require a
regression analysis for each tendon
group after every surveillance, (3)
invoke and describe regression
analysis methods used to construct
the lift-off trend lines, (4) extend
surveillance program predicted force
lines for the vertical and hoop tendon
groups to 60 years, and (5) conform
procedure descriptions of acceptance
criteria action levels to the ASME
Code, Subsection IWL 3221
descriptions.
ASME III Subsection NG
Fatigue Analysis of Reactor
Pressure Vessel Internals (RCMS 2006-221) A3.2.2 WCNOC will obtain a design report amendment to either quantify the
increase in high-cycle fatigue effects, or to confirm that the increase will be
negligible. WCNOC will complete this
action before the end of the current
licensed operating period.
Assumed Thermal Cycle Count
for Allowable Secondary Stress
Range Reduction Factor in
B31.1 and ASME III Class 2
and 3 Piping (RCMS 2006-222) A3.2.4 WCNOC will complete the reanalysis of the reactor coolant sample lines
and any additional corrective actions
or modifications indicated by them, before the end of the current licensed
operating period.
USAR Supplement (RCMS 2006-223) A0 Following issuance of the renewed operating license in accordance with
10 CFR 50.71(e), WCNOC will
incorporate the USAR supplement
into the WCGS USAR as required by
54.21(d).
Pressure-Temperature (P-T)
Limits (RCMS 2006-224) A3.1.3 WCNOC will revise the Pressure and Temperature Limits Report for a 60-
year licensed operating life.
Attachment II to ET 06-0038 Page 8 of 8
COMMITMENT SUBJECT LRA, Appendix A, Section COMMITMENT DESCRIPTION Implementation of New Programs (RCMS 2006-225) N/A Implementation of new programs may require additional action items not
included in this list. WCGS is
committed to including new program
elements in the corrective action
program.
Enclosure to ET 06-0038 Page 1 of 1
Subject Enclosed is the CD-ROM submittal of the Wolf Creek License Renewal Application.
Contact Name Kevin Moles Mailing Address Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 E-Mail Address kemoles@wcnoc.com Phone Number 620-364-4126 Document Components:
The CD-ROM labeled "Wolf Creek License Renewal Application" contains the following files:
License Renewal Application Transmittal Letter; WCNOC_Xmttl.pdf (publicly available)
License Renewal Application; WCNOC_LRA.pdf (publicly available)
Environmental Report; WCNOC_AppE.pdf (publicly available)
License Renewal boundary drawings; WCNOC_Dwg.pdf (publicly available)