Draft NUREG-1824, “Verification & Validation of Selected Fire Models for Nuclear Power Plant Applications,” Draft for Comment, 5088-5089 [E6-1201]
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Federal Register / Vol. 71, No. 20 / Tuesday, January 31, 2006 / Notices
hsrobinson on PROD1PC70 with NOTICES
opinion which support the contention
and on which the petitioner intends to
rely in proving the contention at the
hearing. The petitioner 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.1
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.
Each contention shall be given a
separate numeric or alpha designation
within one of the following groups:
1. Technical—primarily concerns/
issues relating to technical and/or
health and safety matters discussed or
referenced in the applications.
2. Environmental—primarily
concerns/issues relating to matters
discussed or referenced in the
environmental analysis for the
applications.
3. Miscellaneous—does not fall into
one of the categories outlined above.
As specified in 10 CFR 2.309, if two
or more petitioners/requestors seek to
co-sponsor a contention, the petitioners/
requestors shall jointly designate a
representative who shall have the
authority to act for the petitioners/
requestors with respect to that
contention. If a petitioner/requestor
seeks to adopt the contention of another
sponsoring petitioner/requestor, the
petitioner/requestor who seeks to adopt
the contention must either agree that the
sponsoring petitioner/requestor shall act
as the representative with respect to that
contention, or jointly designate with the
sponsoring petitioner/requestor a
representative who shall have the
authority to act for the petitioners/
requestors with respect to that
contention.
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. Since the Commission has
1 To the extent that the applications contain
attachments and supporting documents that are not
publicly available because they are asserted to
contain safeguards or proprietary information,
petitioners desiring access to this information
should contact the applicant or applicant’s counsel
and discuss the need for a protective order.
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15:34 Jan 30, 2006
Jkt 208001
made a final determination that the
amendment involves no significant
hazards consideration, if a hearing is
requested, it will not stay the
effectiveness of the amendment. Any
hearing held would take place while the
amendment is in effect.
A request for a hearing or a petition
for leave to intervene must be filed 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; (2) courier, express
mail, and expedited delivery services:
Office of the Secretary, Sixteenth Floor,
One White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852,
Attention: Rulemaking and
Adjudications Staff; (3) E-mail
addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission,
HearingDocket@nrc.gov; or (4) facsimile
transmission addressed to the Office of
the Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC,
Attention: Rulemakings and
Adjudications Staff at (301) 415–1101,
verification number is (301) 415–1966.
A copy of the request for hearing and
petition for leave to intervene should
also be sent to the Office of the General
Counsel, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, and it is requested that copies be
transmitted either by means of facsimile
transmission to (301) 415–3725 or by email to OGCMailCenter@nrc.gov. A copy
of the request for hearing and petition
for leave to intervene should also be
sent to the attorney for the licensee.
Nontimely requests and/or petitions
and contentions will not be entertained
absent a determination by the
Commission or the presiding officer or
the Atomic Safety and Licensing Board
that the petition, request and/or the
contentions should be granted based on
a balancing of the factors specified in 10
CFR 2.309(a)(1)(i)–(viii).
Entergy Operations, Inc., Docket No.
50–313, Arkansas Nuclear One, Unit 1
(ANO–1), Pope County, Arkansas
Date of amendment request: January
3, 2006, as supplemented by letters
dated January 6 and 10, 2006.
Description of amendment request:
Entergy Operations, Inc. (Entergy)
requests an emergency Technical
Specification (TS) change to the Steam
Generator Level—Low allowable value
of Limiting Condition for Operation
3.3.11, ‘‘Emergency Feedwater [EFW]
Initiation and Control (EFIC) System
Instrumentation.’’ Operation at 100
percent power with the current
allowable value involves an increased
PO 00000
Frm 00040
Fmt 4703
Sfmt 4703
risk of spurious EFW initiation.
Therefore, Entergy requests a revised TS
allowable value of ≥ 9.34 inches and a
limiting trip setpoint value of ≥ 10.42
inches in order to achieve and maintain
100 percent power operation. An
actuation time delay of ≤ 10.4 seconds is
also proposed to minimize the
possibility of inadvertent actuations
during anticipated transients such as
main feedwater transients or main
turbine trips.
Date of issuance: January 13, 2006.
Effective date: As of the date of
issuance and shall be implemented
within 7 days from the date of issuance.
Amendment No.: 227.
Renewed Facility Operating License
No. DPR–51: Amendment revised the
Technical Specification.
Public comments requested as to
proposed no significant hazards
consideration (NSHC): No. The
Commission’s related evaluation of the
amendment, finding of emergency
circumstances, state consultation, and
final NSHC determination are contained
in a safety evaluation dated January 13,
2006.
Attorney for licensee: Nicholas S.
Reynolds, Esquire, Winston and Stawn,
1700 K Street, NW., Washington, DC
20006–3817.
NRC Branch Chief: David Terao.
Dated at Rockville, Maryland, this 20th day
of January 2006.
For the Nuclear Regulatory Commission.
Catherine Haney,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 06–744 Filed 1–30–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Draft NUREG–1824, ‘‘Verification &
Validation of Selected Fire Models for
Nuclear Power Plant Applications,’’
Draft for Comment
Nuclear Regulatory
Commission (NRC).
ACTION: Notice of availability of Draft
NUREG–1824, ‘‘Verification &
Validation of Selected Fire Models for
Nuclear Power Plant Applications’’ and
request for public comment.
AGENCY:
SUMMARY: The NRC is announcing the
availability of Draft NUREG–1824,
‘‘Verification & Validation of Selected
Fire Models for Nuclear Power Plant
Applications Volumes 1 through 7,’’ for
public comment.
DATES: Comments on this document
should be submitted by March 31, 2006.
E:\FR\FM\31JAN1.SGM
31JAN1
Federal Register / Vol. 71, No. 20 / Tuesday, January 31, 2006 / Notices
hsrobinson on PROD1PC70 with NOTICES
Comments received after that date will
be considered to the extent practicable.
To ensure efficient and complete
comment resolution, comments should
include references to the section, page,
and line numbers of the document to
which the comment applies, if possible.
ADDRESSES: Members of the public are
invited and encouraged to submit
written comments to Michael Lesar,
Chief, Rules and Directives Branch,
Office of Administration, Mail Stop T6–
D59, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001. Hand-deliver comments to
Michael Lesar, 11545 Rockville Pike,
Rockville, MD, between 7:30 a.m. and
4:15 p.m. on Federal workdays.
Comments may also be sent
electronically to NRCREP@nrc.gov.
This document is available at the
Agencywide Documents Access and
Management System (ADAMS) Public
Electronic Reading Room on the Internet
at the NRC Web site at https://
www.nrc.gov/reading-rm/adams.html
under Accession No. ML060060541; on
the NRC Web site at https://www.nrc.gov/
reading-rm/doc-collections/nuregs/
docs4comment.html; and at the NRC
Public Document Room, 11555
Rockville Pike, Rockville, MD. The
PDR’s mailing address is USNRC PDR,
Washington, DC 20555; telephone (301)
415–4737 or (800) 397–4205; fax (301)
415–3548; e-mail PDR@NRC.GOV.
FOR FURTHER INFORMATION CONTACT:
Mark H. Salley, Fire Research Team,
Probabilistic Risk Assessment Branch,
Office of Nuclear Regulatory Research,
telephone (301) 415–2840, e-mail
mxs3@nrc.gov.
SUPPLEMENTARY INFORMATION:
Verification & Validation of Selected
Fire Models for Nuclear Power Plant
Applications.
Draft NUREG–1824, ‘‘Verification &
Validation of Selected Fire Models for
Nuclear Power Plant Applications’’
The purpose of this document entitled
‘‘Verification & Validation of Selected
Fire Models for Nuclear Power Plant
Applications’’ Draft Report for Comment
(NUREG–1824), is to document the
verification and validation of five (5)
fire modeling tools commonly used in
nuclear power plant (NPP) applications.
This project was performed in
accordance with the guidelines
described in the American Society for
Testing and Materials (ASTM) Standard
E 1355–04, ‘‘Evaluating the Predictive
Capability of Deterministic Fire
Models.’’ Under a joint Memorandum of
Understanding (MOU), the NRC Office
of Nuclear Regulatory Research (RES)
and the Electric Power Research
VerDate Aug<31>2005
15:34 Jan 30, 2006
Jkt 208001
Institute (EPRI) have agreed to
collaboratively develop this technical
document to support the application of
these fire modeling tools in nuclear
power plants. A library of typical NPP
fire scenarios, and information on the
ability of specific fire models to predict
the consequences of typical NPP fire
scenarios are provided. Technical
review of fire models is necessary to
ensure that analysts can judge the
adequacy of the scientific and technical
basis for the models, select models
appropriate for a desired use, and
understand the levels of confidence that
can be placed in the results predicted by
the models. This work was performed
using state of the art fire dynamics
calculation methods/models and the
most applicable fire test data. Future
improvements in the fire dynamics
calculation methods/models and
additional fire test data may impact the
results of these reports.
The NRC is seeking public comment
in order to receive feedback from the
widest range of interested parties and to
ensure that all information relevant to
developing this document is available to
the NRC staff. This document is issued
for comment only and is not intended
for interim use. The NRC will review
public comments received on the
document, incorporate suggested
changes as necessary, and issue the final
NUREG–1824 for use.
Dated at Rockville, MD, this 18th day of
January 2006.
For the Nuclear Regulatory Commission.
Charles E. Ader,
Director, Division of Risk Analysis and
Applications, Office of Nuclear Regulatory
Research.
[FR Doc. E6–1201 Filed 1–30–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Draft Report for Comment: Office of
Nuclear Reactor Regulation Standard
Review Plan, Section 12.5,
‘‘Operational Radiation Protection
Program’’
Nuclear Regulatory
Commission.
ACTION: Notice of availability and
request for comments.
AGENCY:
SUMMARY: The U.S. Nuclear Regulatory
Commission’s (NRC) Office of Nuclear
Reactor Regulation (NRR) has issued
Section 12.5, Draft Revision 3,
‘‘Operational Radiation Protection
Program,’’ of NUREG–0800, ‘‘Standard
Review Plan for the Review of Safety
Analysis Reports for Nuclear Power
PO 00000
Frm 00041
Fmt 4703
Sfmt 4703
5089
Plants, LWR Edition’’ for public
comment.
Comments on this draft
document should be submitted by April
3, 2006. Comments received after that
date will be considered to the extent
practicable. To ensure efficient and
complete comment resolution,
comments should include references to
the section, page, and line numbers of
the document to which the comment
applies.
DATES:
NUREG–0800, including
Section 12.5, draft Revision 3, is
available for inspection and copying for
a fee at the Commission’s Public
Document Room, NRC’s Headquarters
Building, 11555 Rockville Pike (First
Floor), Rockville, Maryland. The Public
Document Room is open from 7:45 a.m.
to 4:15 p.m., Monday through Friday,
except on Federal holidays. NUREG–
0800, including Section 12.5, draft
Revision 3 is also available
electronically on the NRC Web site at:
https://www.nrc.gov/reading-rm/doccollections/nuregs/staff/sr0800/, and
from the ADAMS Electronic Reading
Room on the NRC Web site at: https://
www.nrc.gov/reading-rm/adams.html.
Members of the public are invited and
encouraged to submit written
comments. Comments may be
accompanied by additional relevant
information or supporting data. A
number of methods may be used to
submit comments. Written comments
should be mailed to Chief, Rules Review
and Directives Branch, U.S. Nuclear
Regulatory Commission, Mail Stop T6–
D59, Washington, DC 20555–0001.
Hand-deliver comments to: 11555
Rockville Pike, Rockville, MD, between
7:30 a.m. and 4:15 p.m., Federal
workdays. Comments may be submitted
electronically to: nrcrep@nrc.gov.
Comments also may be submitted
electronically through the comment
form available on the NRC Web site at:
https://www.nrc.gov/reading-rm/doccollections/nuregs/staff/sr0800/.
Please specify the report number
NUREG–0800, Section 12.5, draft
Revision 3, in your comments, and send
your comments by April 3, 2006.
FOR FURTHER INFORMATION, CONTACT:
Roger L. Pedersen, Mail Stop O–6F12,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001.
Telephone: (301) 415–3162; Internet:
rlp1@nrc.gov.
ADDRESSES:
The
Standard Review Plan (SRP) is prepared
for the guidance of staff reviewers in the
Office of Nuclear Reactor Regulation in
performing safety reviews of
applications to construct or operate
SUPPLEMENTARY INFORMATION:
E:\FR\FM\31JAN1.SGM
31JAN1
Agencies
[Federal Register Volume 71, Number 20 (Tuesday, January 31, 2006)]
[Notices]
[Pages 5088-5089]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-1201]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Draft NUREG-1824, ``Verification & Validation of Selected Fire
Models for Nuclear Power Plant Applications,'' Draft for Comment
AGENCY: Nuclear Regulatory Commission (NRC).
ACTION: Notice of availability of Draft NUREG-1824, ``Verification &
Validation of Selected Fire Models for Nuclear Power Plant
Applications'' and request for public comment.
-----------------------------------------------------------------------
SUMMARY: The NRC is announcing the availability of Draft NUREG-1824,
``Verification & Validation of Selected Fire Models for Nuclear Power
Plant Applications Volumes 1 through 7,'' for public comment.
DATES: Comments on this document should be submitted by March 31, 2006.
[[Page 5089]]
Comments received after that date will be considered to the extent
practicable. To ensure efficient and complete comment resolution,
comments should include references to the section, page, and line
numbers of the document to which the comment applies, if possible.
ADDRESSES: Members of the public are invited and encouraged to submit
written comments to Michael Lesar, Chief, Rules and Directives Branch,
Office of Administration, Mail Stop T6-D59, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001. Hand-deliver comments to Michael
Lesar, 11545 Rockville Pike, Rockville, MD, between 7:30 a.m. and 4:15
p.m. on Federal workdays. Comments may also be sent electronically to
NRCREP@nrc.gov.
This document is available at the Agencywide Documents Access and
Management System (ADAMS) Public Electronic Reading Room on the
Internet at the NRC Web site at https://www.nrc.gov/reading-rm/
adams.html under Accession No. ML060060541; on the NRC Web site at
https://www.nrc.gov/reading-rm/doc-collections/nuregs/
docs4comment.html; and at the NRC Public Document Room, 11555 Rockville
Pike, Rockville, MD. The PDR's mailing address is USNRC PDR,
Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4205; fax
(301) 415-3548; e-mail PDR@NRC.GOV.
FOR FURTHER INFORMATION CONTACT: Mark H. Salley, Fire Research Team,
Probabilistic Risk Assessment Branch, Office of Nuclear Regulatory
Research, telephone (301) 415-2840, e-mail mxs3@nrc.gov.
SUPPLEMENTARY INFORMATION: Verification & Validation of Selected Fire
Models for Nuclear Power Plant Applications.
Draft NUREG-1824, ``Verification & Validation of Selected Fire Models
for Nuclear Power Plant Applications''
The purpose of this document entitled ``Verification & Validation
of Selected Fire Models for Nuclear Power Plant Applications'' Draft
Report for Comment (NUREG-1824), is to document the verification and
validation of five (5) fire modeling tools commonly used in nuclear
power plant (NPP) applications. This project was performed in
accordance with the guidelines described in the American Society for
Testing and Materials (ASTM) Standard E 1355-04, ``Evaluating the
Predictive Capability of Deterministic Fire Models.'' Under a joint
Memorandum of Understanding (MOU), the NRC Office of Nuclear Regulatory
Research (RES) and the Electric Power Research Institute (EPRI) have
agreed to collaboratively develop this technical document to support
the application of these fire modeling tools in nuclear power plants. A
library of typical NPP fire scenarios, and information on the ability
of specific fire models to predict the consequences of typical NPP fire
scenarios are provided. Technical review of fire models is necessary to
ensure that analysts can judge the adequacy of the scientific and
technical basis for the models, select models appropriate for a desired
use, and understand the levels of confidence that can be placed in the
results predicted by the models. This work was performed using state of
the art fire dynamics calculation methods/models and the most
applicable fire test data. Future improvements in the fire dynamics
calculation methods/models and additional fire test data may impact the
results of these reports.
The NRC is seeking public comment in order to receive feedback from
the widest range of interested parties and to ensure that all
information relevant to developing this document is available to the
NRC staff. This document is issued for comment only and is not intended
for interim use. The NRC will review public comments received on the
document, incorporate suggested changes as necessary, and issue the
final NUREG-1824 for use.
Dated at Rockville, MD, this 18th day of January 2006.
For the Nuclear Regulatory Commission.
Charles E. Ader,
Director, Division of Risk Analysis and Applications, Office of
Nuclear Regulatory Research.
[FR Doc. E6-1201 Filed 1-30-06; 8:45 am]
BILLING CODE 7590-01-P