Notice of Issuance of Regulatory Guide, 40943-40944 [2011-17441]
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Federal Register / Vol. 76, No. 133 / Tuesday, July 12, 2011 / Notices
the NRC staff’s original proposed no
significant hazards determination.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated June 28, 2011.
No significant hazards consideration
comments received: No.
emcdonald on DSK2BSOYB1PROD with NOTICES
Florida Power and Light Company,
Docket Nos. 50–250 and 50–251, Turkey
Point Plant, Units 3 and 4, Miami-Dade
County, Florida
Date of application for amendments:
June 25, 2009, as supplemented by
letters dated July 21, July 30, August 26,
2009, February 10, March 15, April 14,
April 28, May 21, June 11, June 23, June
25, September 2, September 15, October
13, December 14, 2010, and May 11,
2011.
Brief description of amendments: The
amendments revised the licensing bases
to adopt the alternative source term as
allowed in Title 10 of the Code of
Federal Regulations (10 CFR) 50.67.
Date of issuance: June 23, 2011.
Effective date: As of the date of
issuance and shall be implemented by
the completion of the Cycle 26 refueling
outage for Unit 3 and Cycle 27 refueling
outage for Unit 4.
Amendment Nos.: Unit 3–244 and
Unit 4–240.
Renewed Facility Operating License
Nos. DPR–31 and DPR–41: Amendments
revised the Operating Licenses and the
Technical Specifications.
Date of initial notice in Federal
Register: December 29, 2009 (74 FR
68870). The supplements dated July 21,
July 30, August 26, 2009, February 10,
March 15, April 14, April 28, June 11,
June 23, June 25, September 2,
September 15, October 13, December 14,
2010, and May 11, 2011, provided
additional information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the staff’s original
proposed no significant hazards
consideration determination as
published in the Federal Register. The
supplement dated May 21, 2010,
changed the scope of the application as
originally noticed. Due to the changes,
the application was renoticed and
published in the Federal Register on
July 13, 2010 (75 FR 39978).
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated June 23, 2011.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this 30th day
of June 2011.
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16:14 Jul 11, 2011
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For the Nuclear Regulatory Commission.
Allen G. Howe,
Deputy Director, Division of Operating
Reactor Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2011–17439 Filed 7–11–11; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2010–0216]
Notice of Issuance of Regulatory Guide
Nuclear Regulatory
Commission.
ACTION: Notice of Issuance and
Availability of Regulatory Guide 1.152,
Revision 3, ‘‘Criteria for Use of
Computers in Safety Systems of Nuclear
Power Plants.’’
AGENCY:
FOR FURTHER INFORMATION CONTACT:
Mark P. Orr, Regulatory Guide
Development Branch, Division of
Engineering, Office of Nuclear
Regulatory Research, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–251–
7495 or e-mail: Mark.Orr@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a revision
to an existing guide in the agency’s
‘‘Regulatory Guide’’ series. This series
was developed to describe and make
available to the public information such
as methods that are acceptable to the
NRC staff for implementing specific
parts of the agency’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 3 of Regulatory Guide 1.152,
‘‘Criteria for Use of Computers in Safety
Systems of Nuclear Power Plants,’’ was
issued with a temporary identification
as Draft Regulatory Guide, DG–1249, for
public comments on June 22, 2010 (75
FR 35508). The public comment period
closed on August 20, 2010. All
comments that were received were
considered and, where appropriate, the
final guide was revised to address the
comments. Editorial changes and
clarifications were made to Regulatory
Guide 1.152 as a result of the public
comments. These include minor
changes to the discussion section to
improve consistency with other NRC
regulations and guidance, clarification
of the regulatory criteria to more clearly
indicate that licensees are responsible
for demonstrating establishment of a
PO 00000
Frm 00072
Fmt 4703
Sfmt 4703
40943
secure development and operational
environment, and clarification of
regulatory criteria to precisely state the
expectations of actions taken to protect
developmental activities. This guide
describes a method that the staff of the
NRC considers acceptable to implement
Title 10, of the Code of Federal
Regulations, part 50, ‘‘Domestic
Licensing of Production and Utilization
Facilities’’ (10 CFR part 50); 10 CFR
50.55a(h); General Design Criterion
(GDC) 21, ‘‘Protection System Reliability
and Testability,’’ of Appendix A,
‘‘General Design Criteria for Nuclear
Power Plants,’’ to 10 CFR part 50; and
Criterion III, ‘‘Design Control,’’ of
Appendix B, ‘‘Quality Assurance
Criteria for Nuclear Power Plants and
Fuel Reprocessing Plants,’’ to 10 CFR
part 50 with regard to the use of
computers in safety systems of nuclear
power plants. This guide applies to all
types of commercial nuclear power
plants. Regulatory Guide 1.152 was not
uniquely developed for non-power
reactors; therefore, the applicability of
this guide for those facilities should be
determined on a case-by-case basis.
This regulatory guide describes a
method that the NRC staff deems
acceptable for complying with the
Commission’s regulations for promoting
high functional reliability, design
quality, and a secure development and
operational environment for the use of
digital computers in the safety systems
of nuclear power plants. In this context,
the term ‘‘computer’’ identifies a system
that includes computer hardware,
software, firmware, and interfaces.
II. Further Information
Electronic copies of Regulatory Guide
1.152, Revision 3 are available through
the NRC’s public Web site under
‘‘Regulatory Guides’’ at https://
www.nrc.gov/reading-rm/doccollections/. The regulatory analysis
may be found through the NRC’s
Agencywide Documents Access and
Management System (ADAMS) under
Accession No. ML101320317.
In addition, regulatory guides are
available for inspection at the NRC’s
Public Document Room (PDR) located at
Room O–1F21, One White Flint North,
11555 Rockville Pike, Rockville,
Maryland 20852–2738. The PDR’s
mailing address is USNRC PDR,
Washington, DC 20555–0001. The PDR
can also be reached by telephone at
301–415–4737 or 800–397–4209, by fax
at 301–415–3548, and by e-mail to
pdr.resources@nrc.gov.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
E:\FR\FM\12JYN1.SGM
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40944
Federal Register / Vol. 76, No. 133 / Tuesday, July 12, 2011 / Notices
Dated at Rockville, Maryland, this 5th day
of July, 2011.
For the Nuclear Regulatory Commission.
Harriet Karagiannis,
Acting Chief, Regulatory Guide Development
Branch, Division of Engineering, Office of
Nuclear Regulatory Research.
[FR Doc. 2011–17441 Filed 7–11–11; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2011–0006]
Sunshine Federal Register Notice
Nuclear
Regulatory Commission.
DATE: Weeks of July 11, 18, 25, August
1, 8, 15, 2011.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
AGENCY HOLDING THE MEETINGS:
Week of July 11, 2011
Tuesday, July 12, 2011
9:30 a.m. Briefing on the NRC Actions
for Addressing the Integrated
Regulatory Review Service (IRRS)
Report (Public Meeting (Contact:
Jon Hopkins, 301–415–3027).
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
Week of July 18, 2011—Tentative
Tuesday, July 19, 2011
9:30 a.m. Briefing on the Task Force
Review of NRC Processes and
Regulations Following Events in
Japan (Public Meeting) (Contact:
Nathan Sanfilippo, 301–415–3951).
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
Week of July 25, 2011—Tentative
Dated: July 7, 2011.
Rochelle C. Bavol,
Policy Coordinator, Office of the Secretary.
[FR Doc. 2011–17574 Filed 7–8–11; 11:15 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Thursday, July 28, 2011
emcdonald on DSK2BSOYB1PROD with NOTICES
Week of August 15, 2011—Tentative
There are no meetings scheduled for
the week of August 15, 2011.
*
*
*
*
*
* The schedule for Commission
meetings is subject to change on short
notice. To verify the status of meetings,
call (recording)—(301) 415–1292.
Contact person for more information:
Rochelle Bavol, (301) 415–1651.
*
*
*
*
*
The NRC Commission Meeting
Schedule can be found on the Internet
at: https://www.nrc.gov/public-involve/
public-meetings/schedule.html.
*
*
*
*
*
The NRC provides reasonable
accommodation to individuals with
disabilities where appropriate. If you
need a reasonable accommodation to
participate in these public meetings, or
need this meeting notice or the
transcript or other information from the
public meetings in another format (e.g.
braille, large print), please notify Bill
Dosch, Chief, Work Life and Benefits
Branch, at 301–415–6200, TDD: 301–
415–2100, or by e-mail at
william.dosch@nrc.gov. Determinations
on requests for reasonable
accommodation will be made on a caseby-case basis.
*
*
*
*
*
This notice is distributed
electronically to subscribers. If you no
longer wish to receive it, or would like
to be added to the distribution, please
contact the Office of the Secretary,
Washington, DC 20555 (301–415–1969),
or send an e-mail to
darlene.wright@nrc.gov.
9 a.m. Briefing on Severe Accidents and
Options for Proceeding with Level 3
Probabilistic Risk Assessment
Activities (Public Meeting)
(Contact: Daniel Hudson, 301–251–
7919).
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
[Docket Nos. 50–272 and 50–311; NRC–
2009–0390]
Week of August 1, 2011—Tentative
Notice is hereby given that the U.S.
Nuclear Regulatory Commission (the
Commission) has issued Renewed
Facility Operating License Nos. DPR–70
and DPR–75 to PSEG Nuclear LLC (the
licensee), the operator of the Salem
Nuclear Generating Station, Units 1 and
There are no meetings scheduled for
the week of August 1, 2011.
Week of August 8, 2011—Tentative
There are no meetings scheduled for
the week of August 8, 2011.
VerDate Mar<15>2010
16:14 Jul 11, 2011
Jkt 223001
PSEG Nuclear, LLC, Salem Nuclear
Generating Station, Units 1 and 2;
Notice of Issuance of Renewed Facility
Operating License Nos. DPR–70 and
DPR–75 for an Additional 20-Year
Period
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Frm 00073
Fmt 4703
Sfmt 4703
2 (Salem). Renewed Facility Operating
License Nos. DPR–70 and DPR–75
authorize the licensee to operate Salem
at reactor core power levels not in
excess of 3,459 megawatts thermal in
accordance with the provisions of the
Salem renewed license and its technical
specifications.
The notice also serves as the record of
decision for the renewal of Facility
Operating License Nos. DPR–70 and
DPR–75, consistent with Title 10 of the
Code of Federal Regulations (10 CFR)
51.103, ‘‘Record of Decision—General.’’
As discussed in the final supplemental
environmental impact statement for
Salem (NUREG–1437, Supplement 45,
‘‘Generic Environmental Impact
Statement for License Renewal of
Nuclear Plants, Supplement 45,
Regarding Hope Creek Generating
Station and Salem Nuclear Generating
Station, Units 1 and 2, Final Report,’’
issued March 2011), the Commission
has considered a range of reasonable
alternatives that included generation
from coal-fired generation, natural gas
combined-cycle generation, a combined
alternative, and the no-action
alternative. The factors considered in
the record of decision can be found in
the supplemental environmental impact
statement for Salem.
Salem’s units are pressurized-water
reactors located in Lower Alloways
Creek Township, Salem County, NJ. The
application for the renewed license
complied with the standards and
requirements of the Atomic Energy Act
of 1954, as amended (the Act), and the
Commission’s regulations. As required
by the Act and the Commission’s
regulations in 10 CFR Chapter I,
‘‘Nuclear Regulatory Commission,’’ the
Commission has made appropriate
findings, which are set forth in the
license. Prior public notice of the action
involving the proposed issuance of the
renewed license and of an opportunity
for a hearing regarding the proposed
issuance of the renewed license was
published in the Federal Register on
October 23, 2009 (74 FR 54854).
For further details with respect to this
action, see (1) PSEG Nuclear LLC’s
license renewal application for Salem
Nuclear Generating Station, Units 1 and
2, dated August 18, 2009, as
supplemented by letters dated through
May 18, 2011, (2) the Commission’s
safety evaluation report (NUREG–2101,
‘‘Safety Evaluation Report Related to the
License Renewal of the Salem Nuclear
Generating Station,’’ issued June 2011),
(3) the licensee’s updated safety analysis
report, and (4) the Commission’s final
environmental impact statement
(NUREG–1437, Supplement 45), for
Salem, published in March 2011. These
E:\FR\FM\12JYN1.SGM
12JYN1
Agencies
[Federal Register Volume 76, Number 133 (Tuesday, July 12, 2011)]
[Notices]
[Pages 40943-40944]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-17441]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2010-0216]
Notice of Issuance of Regulatory Guide
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of Issuance and Availability of Regulatory Guide 1.152,
Revision 3, ``Criteria for Use of Computers in Safety Systems of
Nuclear Power Plants.''
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Mark P. Orr, Regulatory Guide
Development Branch, Division of Engineering, Office of Nuclear
Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone: 301-251-7495 or e-mail: Mark.Orr@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision
to an existing guide in the agency's ``Regulatory Guide'' series. This
series was developed to describe and make available to the public
information such as methods that are acceptable to the NRC staff for
implementing specific parts of the agency'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 3 of Regulatory Guide 1.152, ``Criteria for Use of
Computers in Safety Systems of Nuclear Power Plants,'' was issued with
a temporary identification as Draft Regulatory Guide, DG-1249, for
public comments on June 22, 2010 (75 FR 35508). The public comment
period closed on August 20, 2010. All comments that were received were
considered and, where appropriate, the final guide was revised to
address the comments. Editorial changes and clarifications were made to
Regulatory Guide 1.152 as a result of the public comments. These
include minor changes to the discussion section to improve consistency
with other NRC regulations and guidance, clarification of the
regulatory criteria to more clearly indicate that licensees are
responsible for demonstrating establishment of a secure development and
operational environment, and clarification of regulatory criteria to
precisely state the expectations of actions taken to protect
developmental activities. This guide describes a method that the staff
of the NRC considers acceptable to implement Title 10, of the Code of
Federal Regulations, part 50, ``Domestic Licensing of Production and
Utilization Facilities'' (10 CFR part 50); 10 CFR 50.55a(h); General
Design Criterion (GDC) 21, ``Protection System Reliability and
Testability,'' of Appendix A, ``General Design Criteria for Nuclear
Power Plants,'' to 10 CFR part 50; and Criterion III, ``Design
Control,'' of Appendix B, ``Quality Assurance Criteria for Nuclear
Power Plants and Fuel Reprocessing Plants,'' to 10 CFR part 50 with
regard to the use of computers in safety systems of nuclear power
plants. This guide applies to all types of commercial nuclear power
plants. Regulatory Guide 1.152 was not uniquely developed for non-power
reactors; therefore, the applicability of this guide for those
facilities should be determined on a case-by-case basis.
This regulatory guide describes a method that the NRC staff deems
acceptable for complying with the Commission's regulations for
promoting high functional reliability, design quality, and a secure
development and operational environment for the use of digital
computers in the safety systems of nuclear power plants. In this
context, the term ``computer'' identifies a system that includes
computer hardware, software, firmware, and interfaces.
II. Further Information
Electronic copies of Regulatory Guide 1.152, Revision 3 are
available through the NRC's public Web site under ``Regulatory Guides''
at https://www.nrc.gov/reading-rm/doc-collections/. The regulatory
analysis may be found through the NRC's Agencywide Documents Access and
Management System (ADAMS) under Accession No. ML101320317.
In addition, regulatory guides are available for inspection at the
NRC's Public Document Room (PDR) located at Room O-1F21, One White
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852-2738. The
PDR's mailing address is USNRC PDR, Washington, DC 20555-0001. The PDR
can also be reached by telephone at 301-415-4737 or 800-397-4209, by
fax at 301-415-3548, and by e-mail to pdr.resources@nrc.gov.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
[[Page 40944]]
Dated at Rockville, Maryland, this 5th day of July, 2011.
For the Nuclear Regulatory Commission.
Harriet Karagiannis,
Acting Chief, Regulatory Guide Development Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2011-17441 Filed 7-11-11; 8:45 am]
BILLING CODE 7590-01-P