[Federal Register Volume 75, Number 101 (Wednesday, May 26, 2010)]
[Notices]
[Pages 29587-29588]
From the Federal Register Online via the Government Publishing 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 http://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
[email protected].
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 [email protected].
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