[Federal Register Volume 73, Number 35 (Thursday, February 21, 2008)]
[Notices]
[Pages 9602-9604]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E8-3284]
[[Page 9602]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-482]
Wolf Creek Nuclear Operating Corporation; Notice of Consideration
of Issuance of Amendment to Facility Operating License, Proposed No
Significant Hazards Consideration Determination, and Opportunity for a
Hearing
The U.S. Nuclear Regulatory Commission (the Commission, or the NRC)
is considering issuance of an amendment to Facility Operating License
No. NPF-42 to Wolf Creek Nuclear Operating Corporation (the licensee)
for operation of the Wolf Creek Generating Station (WCGS), which is
located in Coffey County, Kansas.
The proposed amendment in the licensee's application dated February
8, 2008, would revise Technical Specification (TS) 5.5.9, ``Steam
Generator (SG) Program,'' and TS 5.6.10, ``Steam Generator Tube
Inspection Report.'' For TS 5.5.9, the amendment would replace the
existing alternate repair criteria (ARC) in TS 5.5.9.c.1 for SG tube
inspections that was approved in Amendment No. 169 issued October 10,
2006, for refueling outage 15 (the outage for the fall of 2006) and the
subsequent operating cycle. The new interim ARC would be for the
upcoming refueling outage 16 (the outage for the spring of 2008) and
the subsequent 18-month and 36-month eddy current inspection intervals,
and would apply to service-induced crack-like flaws found below 17
inches from the top of the tubesheet. For TS 5.6.10, three new
reporting requirements are proposed to be added to the existing seven
requirements.
Before issuance of the proposed license amendment, the Commission
will have made findings required by the Atomic Energy Act of 1954, as
amended (the Act), and the Commission's regulations.
The Commission has made a proposed determination that the amendment
request involves no significant hazards consideration. Under the
Commission's regulations in Title 10 of the Code of Federal Regulations
(10 CFR), Sec. 50.92, this means that operation of the facility in
accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. As required
by 10 CFR 50.91(a), the licensee has provided its analysis of the issue
of no significant hazards consideration, which is presented below:
(1) Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No
Of the various accidents previously evaluated, the proposed
changes only affect the steam generator tube rupture (SGTR) event
evaluation and the postulated steam line break (SLB), locked rotor
and control rod ejection accident evaluations. Loss-of-coolant
accident (LOCA) conditions cause a compressive axial load to act on
the tube. Therefore, since the LOCA tends to force the tube into the
tubesheet rather than pull it out, it is not a factor in this
amendment request. Another faulted load consideration is a safe
shutdown earthquake (SSE); however, the seismic analysis of Model F
steam generators [the steam generators at WCGS] has shown that axial
loading of the tubes is negligible during an SSE.
At normal operating pressures, leakage from primary water stress
corrosion cracking (PWSCC) below 17 inches from the top of the
tubesheet is limited by both the tube-to-tubesheet crevice and the
limited crack opening permitted by the tubesheet constraint.
Consequently, negligible normal operating leakage is expected from
cracks within the tubesheet region.
For the SGTR event, the required structural margins of the steam
generator tubes is maintained by limiting the allowable ligament
size for a circumferential crack to remain in service to 214 degrees
below 17 inches from the top of the tubesheet for the 18-month SG
tubing eddy current inspection interval and to remain in service 183
degrees below 17 inches from the top of the tubesheet for the 36-
month SG tubing eddy current inspection interval. Tube rupture is
precluded for cracks in the hydraulic expansion region due to the
constraint provided by the tubesheet. The potential for tube pullout
is mitigated by limiting the allowable crack size to 214 degrees for
the 18-month SG tubing eddy current inspection interval and to 183
degrees for the 18-month SG tubing eddy current inspection interval.
These allowable crack sizes take into account eddy current
uncertainty and crack growth rate. It has been shown that a
circumferential crack with an azimuthal extent of 214 degrees for
the 18-month SG tubing eddy current inspection interval and an
azimuthal extent of 183 degrees for the 36-month SG tubing eddy
current inspection interval meet the performance criteria of NEI
[Nuclear Energy Institute] 97-06, Rev. 2, ``Steam Generator Program
Guidelines'' and [NRC] Regulatory Guide (RG) 1.121, ``Bases for
Plugging Degraded PWR Steam Generator Tubes.'' Likewise, a visual
inspection will be conducted to confirm that a circumferential crack
of greater than 294 degrees for the 18-month SG tubing eddy current
inspection interval and a circumferential crack of greater than 263
degrees for the 36-month SG tubing eddy current inspection interval
do not remain in service in the tube-to-tubesheet weld metal in any
tube mitigating the potential for tube pullout. Therefore, the
margin against tube burst/pullout is maintained during normal and
postulated accident conditions and the proposed change does not
result in a significant increase in the probability or consequence
of a SGTR.
The probability of a SLB is unaffected by the potential failure
of an SG tube as the failure of a tube is not an initiator for an
SLB event. SLB leakage is limited by leakage flow restrictions
resulting from the leakage path above potential cracks through the
tube-to-tubesheet crevice. The leak rate during postulated accident
conditions (including locked rotor and control rod ejection) has
been shown to remain within the accident analysis assumptions for
all axial or circumferentially oriented cracks occurring 17 inches
below the top of the tubesheet. Since normal operating leakage is
limited to 0.10 gpm (150 gpd), the attendant accident condition leak
rate, assuming all leakage to be from indications below 17 inches
from the top of the tubesheet would be bounded by 0.25 gpm. This
value is within the accident analysis assumptions for the limiting
design basis accident for WCGS, which is the postulated SLB event.
Based on the above, the performance criteria of NEI-97-06, Rev.
2 and draft Regulatory Guide (RG) 1.121 continue to be met and the
proposed change does not involve a significant increase in the
probability or consequences of an accident previously evaluated.
(2) Does the proposed change create the possibility of a new or
different accident from any accident previously evaluated?
Response: No
The proposed change does not introduce any changes or mechanisms
that create the possibility of a new or different kind of accident.
Tube bundle integrity is expected to be maintained for all plant
conditions upon implementation of the interim alternate repair
criteria. The proposed change does not introduce any new equipment
or any change to existing equipment. No new effects on existing
equipment are created nor are any new malfunctions introduced.
Therefore, based on the above evaluation, the proposed changes
do not create the possibility of a new or different kind of accident
from any accident previously evaluated.
(3) Does the proposed change involve a significant reduction in
a margin of safety?
Response: No
The proposed change maintains the required structural margins of
the steam generator tubes for both normal and accident conditions.
NEI 97-06, Rev. 2 and RG 1.121 are used as the basis in the
development of the limited tubesheet inspection depth methodology
for determining that steam generator tube integrity considerations
are maintained within acceptable limits. RG 1.121 describes a method
acceptable to the NRC staff for meeting GDC [General Design
Criteria, of Appendix A to 10 CFR Part 50], 14, 15, 31, and 32 by
reducing the probability and consequences of an SGTR. RG 1.121
concludes that by determining the limiting safe conditions of tube
wall degradation beyond which tubes with unacceptable
[[Page 9603]]
cracking, as established by inservice inspection, should be removed
from service or repaired, the probability and consequences of a SGTR
are reduced. This RG uses safety factors on loads for tube burst
that are consistent with the requirements of Section III of the ASME
Code.
For axially oriented cracking located within the tubesheet, tube
burst is precluded due to the presence of the tubesheet. For
circumferentially oriented cracking in a tube or the tube-to-
tubesheet weld, Reference 6 [Westinghouse Electric Company
proprietary report LTR-CDME-08-11-P submitted in the licensee's
application] defines a length of remaining tube ligament that
provides the necessary resistance to tube pullout due to the
pressure induced forces (with applicable safety factors applied).
Additionally, it is shown that application of the limited tubesheet
inspection depth criteria will not result in unacceptable primary-
to-secondary leakage during all plant conditions.
Based on the above, it is concluded that the proposed changes do
not result in any reduction of margin with respect to plant safety
as defined in the Updated Safety Analysis Report or bases of the
plant Technical Specifications.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day
comment period such that failure to act in a timely way would result,
for example, in derating or shutdown of the facility. Should the
Commission take action prior to the expiration of either the comment
period or the notice period, it will publish in the Federal Register a
notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
Written comments may be submitted by mail to the Chief, Rulemaking,
Directives and Editing Branch, Division of Administrative Services,
Office of Administration, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, and should cite the publication date and
page number of this Federal Register notice. Written comments may also
be delivered to Room 6D59, Two White Flint North, 11545 Rockville Pike,
Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays.
Documents may be examined, and/or copied for a fee, at the NRC's Public
Document Room (PDR), located at One White Flint North, Public File Area
O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
The filing of requests for hearing and petitions for leave to
intervene is discussed below.
Within 60 days after the date of publication of this notice, the
person's) may file a request for a hearing with respect to issuance of
the amendment to the subject facility operating license and any
person's) whose interest may be affected by this proceeding and who
wishes to participate as a party in the proceeding must file a written
request via electronic submission through the NRC E-filing system for a
hearing and a petition for leave to intervene. Requests for a hearing
and a petition for leave to intervene shall be filed in accordance with
the Commission's ``Rules of Practice for Domestic Licensing
Proceedings'' in 10 CFR Part 2. Interested person's) should consult a
current copy of 10 CFR 2.309, which is available at the Commission's
PDR, located at One White Flint North, Public File Area O1F21, 11555
Rockville Pike (first floor), Rockville, Maryland. Publicly available
records will be accessible from the Agencywide Documents Access and
Management System's (ADAMS) Public Electronic Reading Room on the
Internet at the NRC Web site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to
intervene is filed by the above date, the Commission or a presiding
officer designated by the Commission or by the Chief Administrative
Judge of the Atomic Safety and Licensing Board Panel, will rule on the
request and/or petition; and the Secretary or the Chief Administrative
Judge of the Atomic Safety and Licensing Board will issue a notice of a
hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and (4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The petition must
also identify the specific contentions which the petitioner/requestor
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
petitioner/requestor shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner/requestor must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
petitioner intends to rely to establish those facts or expert opinion.
The petition must include sufficient information to show that a genuine
dispute exists with the applicant on a material issue of law or fact.
Contentions shall be limited to matters within the scope of the
amendment under consideration. The contention must be one which, if
proven, would entitle the petitioner to relief. A petitioner/requestor
who fails to satisfy these requirements with respect to at least one
contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing
[[Page 9604]]
held would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, any hearing held would take place before the
issuance of any amendment.
A request for hearing or a petition for leave to intervene must be
filed in accordance with the NRC E-Filing rule, which the NRC
promulgated on August 28, 2007 (72 FR 49139). The E-Filing process
requires participants to submit and serve documents over the internet
or in some cases to mail copies on electronic storage media.
Participants may not submit paper copies of their filings unless they
seek a waiver in accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least
five (5) days prior to the filing deadline, the petitioner/requestor
must contact the Office of the Secretary by e-mail at
[email protected], or by calling (301) 415-1677, to request (1) a
digital ID certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and/or (2)
creation of an electronic docket for the proceeding (even in instances
in which the petitioner/requestor (or its counsel or representative)
already holds an NRC-issued digital ID certificate). Each petitioner/
requestor will need to download the Workplace Forms ViewerTM
to access the Electronic Information Exchange (EIE), a component of the
E-Filing system. The Workplace Forms ViewerTM is free and is
available at http://www.nrc.gov/site-help/e-submittals/install-viewer.html. Information about applying for a digital ID certificate is
available on NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. Once a petitioner/requestor has
obtained a digital ID certificate, had a docket created, and downloaded
the EIE viewer, it can then submit a request for hearing or petition
for leave to intervene. Submissions should be in Portable Document
Format (PDF) in accordance with NRC guidance available on the NRC
public Web site at http://www.nrc.gov/site-help/e-submittals.html. A
filing is considered complete at the time the filer submits its
documents through EIE. To be timely, an electronic filing must be
submitted to the EIE system no later than 11:59 p.m. Eastern Time on
the due date. Upon receipt of a transmission, the E-Filing system time-
stamps the document and sends the submitter an e-mail notice confirming
receipt of the document. The EIE system also distributes an e-mail
notice that provides access to the document to the NRC Office of the
General Counsel and any others who have advised the Office of the
Secretary that they wish to participate in the proceeding, so that the
filer need not serve the documents on those participants separately.
Therefore, applicants and other participants (or their counsel or
representative) must apply for and receive a digital ID certificate
before a hearing request/petition to intervene is filed so that they
can obtain access to the document via the E-Filing system.
A person filing electronically may seek assistance through the
``Contact Us'' link located on the NRC Web site at http://www.nrc.gov/site-help/e-submittals.html or by calling the NRC technical help line,
which is available between 8:30 a.m. and 4:15 p.m., Eastern Time,
Monday through Friday. The help line number is (800) 397-4209 or
locally, (301) 415-4737. Participants who believe that they have a good
cause for not submitting documents electronically must file a motion,
in accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North, 11555 Rockville, Pike, Rockville,
Maryland 20852, Attention: Rulemaking and Adjudications Staff.
Participants filing a document in this manner are responsible for
serving the document on all other participants. Filing is considered
complete by first-class mail as of the time of deposit in the mail, or
by courier, express mail, or expedited delivery service upon depositing
the document with the provider of the service.
Non-timely requests and/or petitions and contentions will not be
entertained absent a determination by the Commission, the presiding
officer, or the Atomic Safety and Licensing Board that the petition
and/or request should be granted and/or the contentions should be
admitted, based on a balancing of the factors specified in 10 CFR
2.309(c)(1)(i)-(viii). To be timely, filings must be submitted no later
than 11:59 p.m. Eastern Time on the due date.
Documents submitted in adjudicatory proceedings will appear in
NRC's electronic hearing docket which is available to the public at
http://ehd.nrc.gov/EHD_Proceeding/home.asp, unless excluded pursuant
to an order of the Commission, an Atomic Safety and Licensing Board, or
a Presiding Officer. Participants are requested not to include personal
privacy information, such as social security numbers, home addresses,
or home phone numbers in their filings. With respect to copyrighted
works, except for limited excerpts that serve the purpose of the
adjudicatory filings and would constitute a Fair Use application,
Participants are requested not to include copyrighted materials in
their submissions.
For further details with respect to this license amendment
application, see the letter dated February 8, 2008, from the Wolf Creek
Nuclear Operating Corporation, which is available for public inspection
at the Commission's PDR, located at One White Flint North, File Public
Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
Publicly available records will be accessible electronically from the
Agencywide Documents Access and Management System's (ADAMS) Public
Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to
ADAMS or who encounter problems in accessing the documents located in
ADAMS, should contact the NRC PDR Reference staff by telephone at 1-
800-397-4209, 301-415-4737, or by e-mail to [email protected].
Dated at Rockville, Maryland, this 14th day of February 2008.
For the Nuclear Regulatory Commission.
Balwant K. Singal,
Senior Project Manager, Plant Licensing Branch IV, Division of
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E8-3284 Filed 2-20-08; 8:45 am]
BILLING CODE 7590-01-P