Nuclear Information and Resource Service All Nuclear Power Plants That Use Hemyc/MT Fire Barriers Notice of Issuance of Director's Decision Under 10 CFR 2.206, 3344-3345 [E6-625]
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Federal Register / Vol. 71, No. 13 / Friday, January 20, 2006 / Notices
20. Thus, the exemption is authorized
by law and will not result in an undue
hazard to life or property.
Nonradiological Impacts
The NRC determined that there are no
non-radiological impacts associated
with the proposed action.
Cumulative Impacts
The NRC determined that there are no
cumulative impacts associated with the
proposed action.
Alternatives to the Proposed Action
The NRC considered one alternative
to the proposed action, which was to
deny the amendment request. This
alternative was rejected because the
impacts of the proposed action on the
health and safety of the workers, the
public, and the environment were
determined to be insignificant. In
addition, the licensee will be able to
save time and resources using the
updated ICRP 68 models. The new
models will maintain doses within the
regulatory limit, while allowing the
licensee to remove unwarranted
protective measures required by the old
models.
Agencies and Persons Contacted
The NRC contacted the Virginia
Department of Environmental Quality
(VDEQ) concerning this request. There
were no comments, concerns or
objections from VDEQ.
Because the proposed action is
entirely within existing facilities, and
does not involve new or increased
effluents or accident scenarios, the NRC
has concluded that there is no potential
to affect endangered species or historic
resources, and therefore consultation
with the State Historic Preservation
Society and the U.S. Fish and Wildlife
Service was not performed.
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III. Finding of No Significant Impact
Based on the EA, the staff concludes
that the proposed action will not have
a significant effect on the quality of the
human environment. Accordingly, the
staff has determined that preparation of
an EIS is not warranted.
IV. Further Information
The following documents are related
to the proposed action:
1. C.F. Holman, Framatome ANP, Inc.,
letter to the U.S. Nuclear Regulatory
Commission, ‘‘Amendment Request to
Use of ICRP 68 for ALI and DAC
Values,’’ September 1, 2005
(ML052550120).
2. The NRC administrative review,
documented in a letter to Framatome
ANP, Inc. dated September 23, 2005
(ML052640365).
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16:16 Jan 19, 2006
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3. The U.S. Nuclear Regulatory
Commission, Special Nuclear Material
License SNM–1168 Amendment 7,
October 3, 2005 (ML052840071).
4. International Commission on
Radiological Protection, ‘‘Dose
Coefficients for Intake of Radionuclides
by Worker,’’ Publication 68, Elsevier
Science, 1995.
5. The U.S. Nuclear Regulatory
Commission, ‘‘SRM–SECY–99–0077—
To Request Commission Approval to
Grant Exemptions from Portions of 10
CFR Part 20,’’ April 21, 1999
(ML042750086).
6. The U.S. Nuclear Regulatory
Commission, ‘‘Environmental
Assessment for the Renewal Framatome
ANP, Inc., Lynchburg, Virginia,’’ April
2, 2003 (ML030940720).
7. U.S. Code of Federal Regulations,
‘‘Standards for Protection Against
Radiation,’’ Part 20, Chapter 1, Title 10,
Energy.
8. International Commission on
Radiological Protection,
‘‘Recommendations of the International
Commission on Radiological
Protection,’’ Publication 26, Elsevier
Science, 1977.
9. International Commission on
Radiological Protection, ‘‘Limits for the
Intake of Radionuclides by Workers,’’
Publication 30, Elsevier Science, 1978.
10. International Commission on
Radiological Protection, ‘‘1990
Recommendations of the International
Commission on Radiological
Protection,’’ Publication 60, Elsevier
Science, 1991.
The NRC documents related to this
action, including the application for
amendment and supporting
documentation, are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this site,
you can access the NRC’s Agencywide
Document Access and Management
System (ADAMS), which provides text
and image files of NRC’s public
documents. The accession numbers for
documents contained in ADAMS are
provided with the reference. If you do
not have access to ADAMS or if there
are problems in accessing the
documents located in ADAMS, contact
the NRC’s Public Document Room (PDR)
Reference staff at 1–800–397–4209, 301–
415–4737, or via e-mail to pdr@nrc.gov.
The documents in ADAMS may also
be viewed electronically on the public
computers located at the NRC’s PDR, O1
F21, One White Flint North, 11555
Rockville Pike, Rockville, MD 20852.
The PDR reproduction contractor will
copy documents for a fee.
Dated at Rockville, MD this 13th day of
January, 2006.
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For the Nuclear Regulatory Commission.
William C. Gleaves,
Project Manager, Fuel Cycle Facilities Branch,
Division of Fuel Cycle Safety and Safeguards,
Office of Nuclear Materials Safety and
Safeguards.
[FR Doc. E6–613 Filed 1–19–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Nuclear Information and Resource
Service All Nuclear Power Plants That
Use Hemyc/MT Fire Barriers Notice of
Issuance of Director’s Decision Under
10 CFR 2.206
Notice is hereby given that the
Director, Office of Nuclear Reactor
Regulation, has issued a Director’s
Decision with regard to a petition dated
May 12, 2005, filed by Paul Gunter on
behalf of the Nuclear Information and
Resource Service, Citizens Awareness
Network, Indian Point Safe Coalition,
North Carolina Waste Awareness and
Reduction Network, Alliance for
Affordable Energy, and Blue Ridge
Environmental Defense League,
hereinafter referred to as the
‘‘petitioners.’’ The petition was
supplemented on June 1, 2005. The
petition concerns the operation of all
nuclear power plants that use Hemyc/
MT fire barriers.
The petition requested that the U.S.
Nuclear Regulatory Commission (NRC)
engage in enforcement actions to modify
and/or suspend operating licenses for
Shearon Harris Nuclear Power Station
Unit 1, H. B. Robinson Unit 2, McGuire
Units 1 and 2, Catawba Units 1 and 2,
Ginna, James A. Fitzpatrick, Indian
Point Units 2 and 3, Vermont Yankee,
Waterford Unit 3, and Arkansas Nuclear
One Units 1 and 2.
As the basis for the requests, the
petitioners cited a meeting on April 29,
2005, held by NRC with all stakeholders
to discuss the performance of 1-hour
(Hemyc) and 3-hour (MT) fire barriers
for Electrical Raceways during full scale
fire testing. In that meeting the NRC
staff informed all stakeholders that the
Hemyc/MT electrical raceway fire
barrier system (ERFBS) failed to protect
electrical cables for 1 hour/3 hours in
fire tests that were performed to the
American Society of Testing and
Materials (ASTM) Standard E119. The
petitioners’ request was also based on
the following conclusions made by the
petitioners: (1) The same Hemyc/MT
fire barrier wrap systems as installed in
the above nuclear plants fail to assure
the protection of the control room
operations for achieving safe shutdown
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20JAN1
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Federal Register / Vol. 71, No. 13 / Friday, January 20, 2006 / Notices
of the reactor in the event of a
significant fire, (2) NRC has not
quantified the full extent of the amount
of Hemyc/MT fire barrier material in
terms of linear and/or square footage
deployed per fire protection regulation,
and NRC has not determined the safety
significance of this deployment for safe
shutdown systems that are not currently
protected by these fire barriers, and (3)
the petitioners believe that the above
listed nuclear power stations are
operating in violation of NRC fire
protection requirements and in an
unanalyzed condition resulting in a
degradation of defense-in-depth fire
protection and safe shut down in the
event of a significant fire.
The petitioners requested that the
NRC take the following actions:
(1) Collect information through
generic communications with nuclear
industry and specifically with the
named reactor sites to determine the
extent of condition of the inoperable fire
barriers; including the requirement that
the licensees conduct a full inventory of
the type Hemyc/MT to include the
amount in linear and square footage, its
specific applications, and the
identification of safe shutdown systems,
which are currently unprotected by the
noncompliance and an assessment of
the safety significance of each
application;
(2) The communication should
require, at minimum that the abovenamed sites provide justification for
operation in noncompliance with all
applicable fire protection regulations;
and
(3) With the determination that any
and/or all of the above-mentioned sites
are operating in unanalyzed condition
and/or that assurance of public health
and safety is degraded, promptly order
a suspension of the license or a power
reduction of the affected reactors until
such time as it can be demonstrated that
the licensees are operating in
conformance with all other applicable
fire protection regulations.
In a letter dated June 27, 2005, the
NRC informed the petitioners that the
issues in the petition were accepted for
review under Section 2.206 of the Code
of Federal Regulations (10 CFR) and had
been referred to the Office of Nuclear
Reactor Regulation for appropriate
action. A copy of the acknowledgment
letter is publicly available in the NRC’s
Agencywide Documents Access and
Management System (ADAMS) under
Accession No. ML051740562. A copy of
the petition is publicly available in
ADAMS under Accession No.
ML051440209.
The petitioners’ representatives held a
teleconference with the Petition Review
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16:16 Jan 19, 2006
Jkt 208001
Board to discuss the petition on June 1,
2005. The teleconference transcript was
treated as a supplement to the petition
and is publicly available in ADAMS
under Accession No. ML051640452.
The NRC sent a copy of the proposed
Director’s Decision to the petitioners for
comment on October 20, 2005
(Accession No. ML052630411). The
NRC staff did not receive any comments
on the proposed Director’s Decision.
The Director of the Office of Nuclear
Reactor Regulation has determined that,
with regard to Request Nos. 1 and 2, the
NRC staff has granted the petitioners’
request through the generic
communication process. Specifically,
the NRC staff is planning to issue a
Generic Letter (GL) to all licensees
asking them to provide detailed
information about the use of Hemyc/MT
in their nuclear power plants. In
response to Request No. 3, the NRC staff
is planning to review all affected plants
in detail and will take appropriate
actions to resolve the issues with the
use of Hemyc/MT material
commensurate with the safety
significance of the protected systems.
The GL will be issued after the NRC’s
internal review process to consider
comments received on the proposed GL
is completed.
The reasons for these decisions are
explained in the Director’s Decision
pursuant to 10 CFR 2.206 (DD–06–01),
the complete text of which is available
in ADAMS, and is available for
inspection at the Commission’s Public
Document Room (PDR), located at One
White Flint North, Public File Area O1
F21, 11555 Rockville Pike (first floor),
Rockville, Maryland, and from the
ADAMS Public Library component on
the NRC Web site, https://www.nrc.gov/
reading-rm/adams.html (the Public
Electronic Reading Room). 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 at
1–800–397–4209 or 301–415–4737, or
by e-mail to pdr@nrc.gov.
A copy of the Director’s Decision will
be filed with the Secretary of the
Commission for the Commission’s
review in accordance with 10 CFR 2.206
of the Commission’s regulations. As
provided for by this regulation, the
Director’s Decision will constitute the
final action of the Commission 25 days
after the date of the decision, unless the
Commission, on its own motion,
institutes a review of the Director’s
Decision in that time.
Dated at Rockville, Maryland, this 9th day
of January 2006.
PO 00000
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3345
For the Nuclear Regulatory Commission.
J.E. Dyer,
Director, Office of Nuclear Reactor
Regulation.
[FR Doc. E6–625 Filed 1–19–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Final Regulatory Guide; Issuance,
Availability
The U.S. Nuclear Regulatory
Commission (NRC) has issued a revision
to an existing guide in the agency’s
Regulatory Guide Series. This series has
been developed to describe and make
available to the public such information
as methods that are acceptable to the
NRC staff for implementing specific
parts of the NRC’s regulations,
techniques that the staff uses in
evaluating specific problems or
postulated accidents, and data that the
staff needs in its review of applications
for permits and licenses.
Revision 2 of Regulatory Guide 1.152,
entitled ‘‘Criteria for Use of Computers
in Safety Systems of Nuclear Power
Plants,’’ describes a method that the
staff of the U.S. Nuclear Regulatory
Commission (NRC) deems acceptable for
complying with the Commission’s
regulations for promoting high
functional reliability, design quality,
and cyber-security for the use of digital
computers in safety systems of nuclear
power plants. In this context, the term
‘‘computer’’ identifies a system that
includes computer hardware, software,
firmware, and interfaces.
The guidance provided in Revision 2
of Regulatory Guide 1.152 is consistent
with General Design Criterion (GDC) 21,
‘‘Protection System Reliability and
Testability,’’ of Appendix A, ‘‘General
Design Criteria for Nuclear Power
Plants,’’ to title 10, part 50, ‘‘Domestic
Licensing of Production and Utilization
Facilities,’’ of the Code of Federal
Regulations (10 CFR part 50). Among
other things, GDC 21 requires that
protection systems (or safety systems)
must be designed for high functional
reliability, commensurate with the
safety functions to be performed. In
addition, Criterion III, ‘‘Design Control,’’
of Appendix B, ‘‘Quality Assurance
Criteria for Nuclear Power Plants and
Fuel Reprocessing Plants,’’ to 10 CFR
part 50 requires, among other things,
that quality standards must be specified,
and design control measures must be
provided, for verifying or checking the
adequacy of design.
Revision 2 of Regulatory Guide 1.152
also contains the staff’s regulatory
E:\FR\FM\20JAN1.SGM
20JAN1
]]>Agencies
[Federal Register Volume 71, Number 13 (Friday, January 20, 2006)]
[Notices]
[Pages 3344-3345]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-625]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Nuclear Information and Resource Service All Nuclear Power Plants
That Use Hemyc/MT Fire Barriers Notice of Issuance of Director's
Decision Under 10 CFR 2.206
Notice is hereby given that the Director, Office of Nuclear Reactor
Regulation, has issued a Director's Decision with regard to a petition
dated May 12, 2005, filed by Paul Gunter on behalf of the Nuclear
Information and Resource Service, Citizens Awareness Network, Indian
Point Safe Coalition, North Carolina Waste Awareness and Reduction
Network, Alliance for Affordable Energy, and Blue Ridge Environmental
Defense League, hereinafter referred to as the ``petitioners.'' The
petition was supplemented on June 1, 2005. The petition concerns the
operation of all nuclear power plants that use Hemyc/MT fire barriers.
The petition requested that the U.S. Nuclear Regulatory Commission
(NRC) engage in enforcement actions to modify and/or suspend operating
licenses for Shearon Harris Nuclear Power Station Unit 1, H. B.
Robinson Unit 2, McGuire Units 1 and 2, Catawba Units 1 and 2, Ginna,
James A. Fitzpatrick, Indian Point Units 2 and 3, Vermont Yankee,
Waterford Unit 3, and Arkansas Nuclear One Units 1 and 2.
As the basis for the requests, the petitioners cited a meeting on
April 29, 2005, held by NRC with all stakeholders to discuss the
performance of 1-hour (Hemyc) and 3-hour (MT) fire barriers for
Electrical Raceways during full scale fire testing. In that meeting the
NRC staff informed all stakeholders that the Hemyc/MT electrical
raceway fire barrier system (ERFBS) failed to protect electrical cables
for 1 hour/3 hours in fire tests that were performed to the American
Society of Testing and Materials (ASTM) Standard E119. The petitioners'
request was also based on the following conclusions made by the
petitioners: (1) The same Hemyc/MT fire barrier wrap systems as
installed in the above nuclear plants fail to assure the protection of
the control room operations for achieving safe shutdown
[[Page 3345]]
of the reactor in the event of a significant fire, (2) NRC has not
quantified the full extent of the amount of Hemyc/MT fire barrier
material in terms of linear and/or square footage deployed per fire
protection regulation, and NRC has not determined the safety
significance of this deployment for safe shutdown systems that are not
currently protected by these fire barriers, and (3) the petitioners
believe that the above listed nuclear power stations are operating in
violation of NRC fire protection requirements and in an unanalyzed
condition resulting in a degradation of defense-in-depth fire
protection and safe shut down in the event of a significant fire.
The petitioners requested that the NRC take the following actions:
(1) Collect information through generic communications with nuclear
industry and specifically with the named reactor sites to determine the
extent of condition of the inoperable fire barriers; including the
requirement that the licensees conduct a full inventory of the type
Hemyc/MT to include the amount in linear and square footage, its
specific applications, and the identification of safe shutdown systems,
which are currently unprotected by the noncompliance and an assessment
of the safety significance of each application;
(2) The communication should require, at minimum that the above-
named sites provide justification for operation in noncompliance with
all applicable fire protection regulations; and
(3) With the determination that any and/or all of the above-
mentioned sites are operating in unanalyzed condition and/or that
assurance of public health and safety is degraded, promptly order a
suspension of the license or a power reduction of the affected reactors
until such time as it can be demonstrated that the licensees are
operating in conformance with all other applicable fire protection
regulations.
In a letter dated June 27, 2005, the NRC informed the petitioners
that the issues in the petition were accepted for review under Section
2.206 of the Code of Federal Regulations (10 CFR) and had been referred
to the Office of Nuclear Reactor Regulation for appropriate action. A
copy of the acknowledgment letter is publicly available in the NRC's
Agencywide Documents Access and Management System (ADAMS) under
Accession No. ML051740562. A copy of the petition is publicly available
in ADAMS under Accession No. ML051440209.
The petitioners' representatives held a teleconference with the
Petition Review Board to discuss the petition on June 1, 2005. The
teleconference transcript was treated as a supplement to the petition
and is publicly available in ADAMS under Accession No. ML051640452.
The NRC sent a copy of the proposed Director's Decision to the
petitioners for comment on October 20, 2005 (Accession No.
ML052630411). The NRC staff did not receive any comments on the
proposed Director's Decision.
The Director of the Office of Nuclear Reactor Regulation has
determined that, with regard to Request Nos. 1 and 2, the NRC staff has
granted the petitioners' request through the generic communication
process. Specifically, the NRC staff is planning to issue a Generic
Letter (GL) to all licensees asking them to provide detailed
information about the use of Hemyc/MT in their nuclear power plants. In
response to Request No. 3, the NRC staff is planning to review all
affected plants in detail and will take appropriate actions to resolve
the issues with the use of Hemyc/MT material commensurate with the
safety significance of the protected systems. The GL will be issued
after the NRC's internal review process to consider comments received
on the proposed GL is completed.
The reasons for these decisions are explained in the Director's
Decision pursuant to 10 CFR 2.206 (DD-06-01), the complete text of
which is available in ADAMS, and is available for inspection at the
Commission's Public Document Room (PDR), located at One White Flint
North, Public File Area O1 F21, 11555 Rockville Pike (first floor),
Rockville, Maryland, and from the ADAMS Public Library component on the
NRC Web site, https://www.nrc.gov/reading-rm/adams.html (the Public
Electronic Reading Room). 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 at 1-800-397-4209 or 301-
415-4737, or by e-mail to pdr@nrc.gov.
A copy of the Director's Decision will be filed with the Secretary
of the Commission for the Commission's review in accordance with 10 CFR
2.206 of the Commission's regulations. As provided for by this
regulation, the Director's Decision will constitute the final action of
the Commission 25 days after the date of the decision, unless the
Commission, on its own motion, institutes a review of the Director's
Decision in that time.
Dated at Rockville, Maryland, this 9th day of January 2006.
For the Nuclear Regulatory Commission.
J.E. Dyer,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. E6-625 Filed 1-19-06; 8:45 am]
BILLING CODE 7590-01-P
