Notice of Availability of Revised Model Proposed No Significant Hazards Consideration Determination for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-475, Revision 1, “Control Rod Notch Testing Frequency and SRM Insert Control Rod Action”, 29587-29588 [2010-12708]
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<![CDATA[
Federal Register / Vol. 75, No. 101 / Wednesday, May 26, 2010 / Notices
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC, 20555–
0001; telephone 301–415–4117 or e-mail
at Barry.Miller@nrc.gov.
NUCLEAR REGULATORY
COMMISSION
[NRC–2010–0185]
Notice of Availability of Revised Model
Proposed No Significant Hazards
Consideration Determination for PlantSpecific Adoption of Technical
Specifications Task Force Traveler
TSTF–475, Revision 1, ‘‘Control Rod
Notch Testing Frequency and SRM
Insert Control Rod Action’’
Nuclear Regulatory
Commission (NRC).
ACTION: Notice of Availability.
wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1
AGENCY:
SUMMARY: The Notice of Availability
(NOA) for adoption of TSTF–475,
Revision 1, using the Consolidated Line
Item Improvement Process (CLIIP), was
published in the Federal Register on
November 13, 2007 (72 FR 63935). The
prior NOA followed the CLIIP and
contained a model safety evaluation, a
model license amendment application,
and a model proposed no significant
hazards consideration determination
(NSHCD). The purpose of this NOA is
to revise the model proposed NSHCD.
Technical Specifications Task Force
(TSTF) Traveler TSTF–475, Revision 1,
‘‘Control Rod Notch Testing Frequency
and SRM Insert Control Rod Action,’’ is
available in the Agencywide Documents
Access and Management System
(ADAMS) under Accession Number
ML071420428.
Documents: You can access publicly
available documents related to this
notice using the following methods:
NRC’s Public Document Room (PDR):
The public may examine and for a fee
have copied publicly available
documents at the NRC’s PDR, Room O1
F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland.
NRC’s Agencywide Documents Access
and Management System (ADAMS):
Publicly available documents created or
received at the NRC are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this page,
the public can gain entry into ADAMS,
which provides text and image files of
NRC’s public documents. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC’s
PDR reference staff at 1–800–397–4209,
301–415–4737, or by e-mail to
pdr.resource@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
Barry W. Miller, Senior Project Manager,
Licensing Processes Branch, Mail Stop:
O–12 D3, Division of Policy and
Rulemaking, Office of Nuclear Reactor
VerDate Mar<15>2010
15:16 May 25, 2010
Jkt 220001
Dated at Rockville, Maryland, this 17th day
of May 2010.
For the Nuclear Regulatory Commission.
Michael D. McCoppin,
Acting Chief, Licensing Processes Branch,
Division of Policy and Rulemaking, Office
of Nuclear Reactor Regulation.
Revised Model Proposed No Significant
Hazards Consideration Determination
for Plant-Specific Adoption of
Technical Specifications Task Force
Traveler TSTF–475, Revision 1,
‘‘Control Rod Notch Testing Frequency
and SRM Insert Control Rod Action’’
Description of amendment request:
[(1) The proposed amendment would
change the frequency of control rod
notch testing, as specified in technical
specification (TS) surveillance
requirement (SR) [3.1.3.2], from at least
once per 7 days to at least once per 31
days. The purpose of this SR is to
confirm control rod insertion capability
which is demonstrated by inserting each
partially or fully withdrawn control rod
at least one notch and observing that the
control rod moves. This ensures that the
control rod is not stuck and is free to
insert on a scram signal. (2) The
proposed amendment would add the
word ‘‘fully’’ to the Action for TS
Limiting Condition for Operation (LCO)
[3.3.1.2] Required Action E.2 to clarify
the requirement to insert fully all
insertable control rods in core cells
containing one or more fuel assemblies
when the required source range monitor
(SRM) instrumentation is inoperable.
(3)] The proposed amendment would
revise Example 1.4–3 in Section 1.4
‘‘Frequency’’ to clarify that the 1.25
surveillance test interval extension in
SR [3.0.2] is applicable to time periods
discussed in NOTES in the
‘‘SURVEILLANCE’’ column in addition
to the time periods in the
‘‘FREQUENCY’’ column. The licensee
stated that the proposed amendment is
based on Nuclear Regulatory
Commission (NRC)-approved Technical
Specifications Task Force (TSTF)
change Traveler TSTF–475, Revision 1,
‘‘Control Rod Notch Testing Frequency
and SRM Insert Control Rod Action.’’
The availability of this change to the
Standard Technical Specifications (STS)
was announced in the Federal Register
on November 13, 2007 (72 FR 63935), as
part of the consolidated line item
improvement process.
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), an
PO 00000
Frm 00081
Fmt 4703
Sfmt 4703
29587
analysis of the issue of no significant
hazards consideration is presented
below.
1. Does the proposed amendment involve
a significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
The proposed change to SR [3.1.3.2]
reduces the frequency of control rod notch
testing. Changing the frequency of testing is
not expected to have any significant impact
on the reliability of the control rods to insert
as required on a scram signal. The proposed
change to the Required Action E.2 for LCO
[3.3.1.2] merely clarifies the intent of the
action. The proposed change to revise
Example 1.4–3 in Section 1.4 ‘‘Frequency’’
clarifies the applicability of the 1.25
surveillance test interval extension. There are
no physical plant modifications associated
with this change. The proposed amendment
would not alter the way any structure,
system, or component (SSC) functions and
would not alter the way the plant is operated.
As such, the proposed amendment would
have no impact on the ability of the affected
SSCs to either preclude or mitigate an
accident. Therefore, the proposed change
does not involve a significant increase in the
probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create
the possibility of a new or different kind of
accident from any accident previously
evaluated?
Response: No.
The proposed amendment would not
change the design function or operation of
the SSCs involved and would not impact the
way the plant is operated. As such, the
proposed change would not introduce any
new failure mechanisms, malfunctions, or
accident initiators not already considered in
the design and licensing bases. Therefore, the
proposed change does not create the
possibility of a new or different kind of
accident from any previously evaluated.
3. Does the proposed amendment involve
a significant reduction in a margin of safety?
Response: No.
The margin of safety is associated with the
confidence in the ability of the fission
product barriers (i.e., fuel cladding, reactor
coolant pressure boundary, and containment
structure) to limit the level of radiation to the
public. There are no physical plant
modifications associated with the proposed
amendment. The proposed amendment
would not alter the way any SSC functions
and would not alter the way the plant is
operated. The proposed amendment would
not introduce any new uncertainties or
change any existing uncertainties associated
with any safety limit. The proposed
amendment would have no impact on the
structural integrity of the fuel cladding,
reactor coolant pressure boundary, or
containment structure. Based on the above
considerations, the NRC staff concludes that
the proposed amendment would not degrade
the confidence in the ability of the fission
product barriers to limit the level of radiation
to the public. Therefore, the proposed change
does not involve a significant reduction in a
margin of safety.
E:\FR\FM\26MYN1.SGM
26MYN1
29588
Federal Register / Vol. 75, No. 101 / Wednesday, May 26, 2010 / Notices
Based on this review, it appears that
the three standards of 10 CFR 50.92(c)
are satisfied and the requested
amendment involves no significant
hazards consideration.
[FR Doc. 2010–12708 Filed 5–25–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2010–0186]
Notice of Availability of the Models for
Plant-Specific Adoption of Technical
Specifications Task Force Traveler
TSTF–501, Revision 1, ‘‘Relocate
Stored Fuel Oil and Lube Oil Volume
Values to Licensee Control’’
AGENCY: Nuclear Regulatory
Commission (NRC).
ACTION: Notice of availability.
As part of the consolidated
line item improvement process (CLIIP),
the NRC is announcing the availability
of the enclosed model application (with
model no significant hazards
consideration determination) and model
safety evaluation (SE) for the plantspecific adoption of Technical
Specifications Task Force (TSTF)
Traveler TSTF–501, Revision 1,
‘‘Relocate Stored Fuel Oil and Lube Oil
Volume Values to Licensee Control.’’
TSTF–501, Revision 1, is available in
the Agencywide Documents Access and
Management System (ADAMS) under
Accession Number ML090510686. The
proposed changes would revise
Technical Specifications (TS) 3.8.3,
‘‘Diesel Fuel Oil, Lube Oil, and Starting
Air,’’ by relocating the current stored
diesel fuel oil and lube oil numerical
volume requirements from the TS to the
TS Bases so that it may be modified
under licensee control. This CLIIP
model SE will facilitate expedited
approval of plant-specific adoption of
TSTF–501, Revision 1.
Documents: You can access publicly
available documents related to this
notice using the following methods:
NRC’s Public Document Room (PDR):
The public may examine and have
copied for a fee publicly available
documents at the NRC’s PDR, Public
File Area O1 F21, One White Flint
North, 11555 Rockville Pike, Rockville,
Maryland.
NRC’s Agencywide Documents Access
and Management System (ADAMS):
Publicly available documents created or
received at the NRC are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this page,
the public can gain entry into ADAMS,
wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1
SUMMARY:
VerDate Mar<15>2010
15:16 May 25, 2010
Jkt 220001
which provides text and image files of
NRC’s public documents. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC’s
PDR reference staff at 1–800–397–4209,
301–415–4737, or by e-mail to
pdr.resource@nrc.gov.
The model application (with model
no significant hazards consideration
determination) and model SE for the
plant-specific adoption of TSTF–501,
Revision 1, are available electronically
under ADAMS Package Accession
Number ML100850069. The NRC staff
disposition of comments received to the
Notice of Opportunity for Comment
announced in the Federal Register on
August 20, 2009 (74 FR 42131–42138),
is available electronically under
ADAMS Accession Number
ML100920563.
FOR FURTHER INFORMATION CONTACT:
Barry W. Miller, Senior Project Manager,
Licensing Processes Branch, Mail Stop:
O–12 D1, Division of Policy and
Rulemaking, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC, 20555–
0001; telephone 301–415–4117 or e-mail
at Barry.Miller@nrc.gov.
SUPPLEMENTARY INFORMATION: TSTF–
501, Revision 1, is applicable to all
nuclear power reactors. Licensees
opting to apply for this TS change are
responsible for reviewing the NRC
staff’s model SE, referencing the
applicable technical justifications, and
providing any necessary plant-specific
information. The NRC will process each
amendment application responding to
this notice of availability according to
applicable NRC rules and procedures.
The model does not prevent licensees
from requesting an alternate approach or
proposing changes other than those
proposed in TSTF–501, Revision 1.
However, significant deviations from
the approach recommended in this
notice or the inclusion of additional
changes to the license require additional
NRC staff review and would not be
reviewed as a part of the CLIIP. This
may increase the time and resources
needed for the review or result in NRC
staff rejection of the license amendment
request (LAR). Licensees desiring
significant deviations or additional
changes should instead submit an LAR
that does not claim to adopt TSTF–501,
Revision 1.
The NRC staff requests that each
licensee applying for the changes
proposed in TSTF–501, Revision 1,
include their current licensing basis for
fuel and lube oil storage requirements in
their LAR.
PO 00000
Frm 00082
Fmt 4703
Sfmt 4703
Dated at Rockville, Maryland, this 14th day
of May 2010.
For the Nuclear Regulatory Commission.
Michael D. McCoppin,
Acting Chief, Licensing Processes Branch,
Division of Policy and Rulemaking, Office
of Nuclear Reactor Regulation.
[FR Doc. 2010–12716 Filed 5–25–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2010–0184]
Office of New Reactors: Proposed
NUREG–0800; Standard Review Plan
Section 13.6.6, Draft Revision 0 on
Cyber Security Plan
AGENCY: Nuclear Regulatory
Commission (NRC).
ACTION: Solicitation of public comment.
SUMMARY: The NRC staff is soliciting
public comment on NUREG–0800,
‘‘Standard Review Plan for the Review of
Safety Analysis Reports for Nuclear
Power Plants,’’ on a proposed Standard
Review Plan (SRP) Section 13.6.6 on
‘‘Cyber Security Plan’’ (Agencywide
Documents Access and Management
System (ADAMS) Accession No.
ML093560837). The Office of Nuclear
Security and Incident Response is
issuing the SRP Section 13.6.6
(Enclosure 1) for the purpose of
soliciting comments from the entities
that we understand have a need to
comment on the proposed draft
guidance.
The NRC staff issues notices to
facilitate timely implementation of the
current staff guidance, to facilitate
activities associated with the review of
amendment applications, and to
facilitate activities associated with
review of applications for design
certification and combined license by
the Office of New Reactors. The NRC
staff intends to incorporate the final
approved guidance into the next
revision of NUREG–0800, SRP Section
13.6.6 and Regulatory Guide 1.206,
‘‘Combined License Applications for
Nuclear Power Plants (LWR Edition),’’
June 2007.
DATES: Comments must be filed no later
than 30 days from the date of
publication of this notice in the Federal
Register. Comments received after this
date will be considered practical to do
so, but the Commission is able to ensure
consideration only for comments
received on or before this date.
ADDRESSES: You may submit comments
by any one of the following methods.
Please include Docket ID NRC–2010–
E:\FR\FM\26MYN1.SGM
26MYN1
]]>Agencies
[Federal Register Volume 75, Number 101 (Wednesday, May 26, 2010)]
[Notices]
[Pages 29587-29588]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-12708]
[[Page 29587]]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2010-0185]
Notice of Availability of Revised Model Proposed No Significant
Hazards Consideration Determination for Plant-Specific Adoption of
Technical Specifications Task Force Traveler TSTF-475, Revision 1,
``Control Rod Notch Testing Frequency and SRM Insert Control Rod
Action''
AGENCY: Nuclear Regulatory Commission (NRC).
ACTION: Notice of Availability.
-----------------------------------------------------------------------
SUMMARY: The Notice of Availability (NOA) for adoption of TSTF-475,
Revision 1, using the Consolidated Line Item Improvement Process
(CLIIP), was published in the Federal Register on November 13, 2007 (72
FR 63935). The prior NOA followed the CLIIP and contained a model
safety evaluation, a model license amendment application, and a model
proposed no significant hazards consideration determination (NSHCD).
The purpose of this NOA is to revise the model proposed NSHCD.
Technical Specifications Task Force (TSTF) Traveler TSTF-475, Revision
1, ``Control Rod Notch Testing Frequency and SRM Insert Control Rod
Action,'' is available in the Agencywide Documents Access and
Management System (ADAMS) under Accession Number ML071420428.
Documents: You can access publicly available documents related to
this notice using the following methods:
NRC's Public Document Room (PDR): The public may examine and for a
fee have copied publicly available documents at the NRC's PDR, Room O1
F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland.
NRC's Agencywide Documents Access and Management System (ADAMS):
Publicly available documents created or received at the NRC are
available electronically at the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain
entry into ADAMS, which provides text and image files of NRC's public
documents. If you do not have access to ADAMS or if there are problems
in accessing the documents located in ADAMS, contact the NRC's PDR
reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to
pdr.resource@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Barry W. Miller, Senior Project
Manager, Licensing Processes Branch, Mail Stop: O-12 D3, Division of
Policy and Rulemaking, Office of Nuclear Reactor Regulation, U.S.
Nuclear Regulatory Commission, Washington, DC, 20555-0001; telephone
301-415-4117 or e-mail at Barry.Miller@nrc.gov.
Dated at Rockville, Maryland, this 17th day of May 2010.
For the Nuclear Regulatory Commission.
Michael D. McCoppin,
Acting Chief, Licensing Processes Branch, Division of Policy and
Rulemaking, Office of Nuclear Reactor Regulation.
Revised Model Proposed No Significant Hazards Consideration
Determination for Plant-Specific Adoption of Technical Specifications
Task Force Traveler TSTF-475, Revision 1, ``Control Rod Notch Testing
Frequency and SRM Insert Control Rod Action''
Description of amendment request: [(1) The proposed amendment would
change the frequency of control rod notch testing, as specified in
technical specification (TS) surveillance requirement (SR) [3.1.3.2],
from at least once per 7 days to at least once per 31 days. The purpose
of this SR is to confirm control rod insertion capability which is
demonstrated by inserting each partially or fully withdrawn control rod
at least one notch and observing that the control rod moves. This
ensures that the control rod is not stuck and is free to insert on a
scram signal. (2) The proposed amendment would add the word ``fully''
to the Action for TS Limiting Condition for Operation (LCO) [3.3.1.2]
Required Action E.2 to clarify the requirement to insert fully all
insertable control rods in core cells containing one or more fuel
assemblies when the required source range monitor (SRM) instrumentation
is inoperable. (3)] The proposed amendment would revise Example 1.4-3
in Section 1.4 ``Frequency'' to clarify that the 1.25 surveillance test
interval extension in SR [3.0.2] is applicable to time periods
discussed in NOTES in the ``SURVEILLANCE'' column in addition to the
time periods in the ``FREQUENCY'' column. The licensee stated that the
proposed amendment is based on Nuclear Regulatory Commission (NRC)-
approved Technical Specifications Task Force (TSTF) change Traveler
TSTF-475, Revision 1, ``Control Rod Notch Testing Frequency and SRM
Insert Control Rod Action.'' The availability of this change to the
Standard Technical Specifications (STS) was announced in the Federal
Register on November 13, 2007 (72 FR 63935), as part of the
consolidated line item improvement process.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of no significant hazards consideration is presented below.
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change to SR [3.1.3.2] reduces the frequency of
control rod notch testing. Changing the frequency of testing is not
expected to have any significant impact on the reliability of the
control rods to insert as required on a scram signal. The proposed
change to the Required Action E.2 for LCO [3.3.1.2] merely clarifies
the intent of the action. The proposed change to revise Example 1.4-
3 in Section 1.4 ``Frequency'' clarifies the applicability of the
1.25 surveillance test interval extension. There are no physical
plant modifications associated with this change. The proposed
amendment would not alter the way any structure, system, or
component (SSC) functions and would not alter the way the plant is
operated. As such, the proposed amendment would have no impact on
the ability of the affected SSCs to either preclude or mitigate an
accident. Therefore, the proposed change does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed amendment would not change the design function or
operation of the SSCs involved and would not impact the way the
plant is operated. As such, the proposed change would not introduce
any new failure mechanisms, malfunctions, or accident initiators not
already considered in the design and licensing bases. Therefore, the
proposed change does not create the possibility of a new or
different kind of accident from any previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The margin of safety is associated with the confidence in the
ability of the fission product barriers (i.e., fuel cladding,
reactor coolant pressure boundary, and containment structure) to
limit the level of radiation to the public. There are no physical
plant modifications associated with the proposed amendment. The
proposed amendment would not alter the way any SSC functions and
would not alter the way the plant is operated. The proposed
amendment would not introduce any new uncertainties or change any
existing uncertainties associated with any safety limit. The
proposed amendment would have no impact on the structural integrity
of the fuel cladding, reactor coolant pressure boundary, or
containment structure. Based on the above considerations, the NRC
staff concludes that the proposed amendment would not degrade the
confidence in the ability of the fission product barriers to limit
the level of radiation to the public. Therefore, the proposed change
does not involve a significant reduction in a margin of safety.
[[Page 29588]]
Based on this review, it appears that the three standards of 10 CFR
50.92(c) are satisfied and the requested amendment involves no
significant hazards consideration.
[FR Doc. 2010-12708 Filed 5-25-10; 8:45 am]
BILLING CODE 7590-01-P
