[Federal Register Volume 79, Number 10 (Wednesday, January 15, 2014)]
[Notices]
[Pages 2700-2702]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2014-00644]
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NUCLEAR REGULATORY COMMISSION
[Project No. 753; NRC-2013-0173]
TSTF-523, ``Generic Letter 2008-01, Managing Gas Accumulation,''
Using the Consolidated Line Item Improvement Process
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of Availability.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is announcing the
availability of Technical Specifications (TS) Task Force (TSTF)
Traveler TSTF-523, Revision 2, ``Generic Letter 2008-01, Managing Gas
Accumulation,'' for plant-specific adoption using the Consolidated Line
Item Improvement Process (CLIIP). Additionally, the NRC staff finds the
proposed TS (Volume 1) and TS Bases (Volume 2) changes in Traveler
TSTF-523 acceptable for inclusion in the following Standard Technical
Specification (STS): NUREG-1430, ``Standard Technical
[[Page 2701]]
Specifications Babcock and Wilcox Plants,'' NUREG-1431, ``Standard
Technical Specifications Westinghouse Plants,'' NUREG-1432, ``Standard
Technical Specifications Combustion Engineering Plants,'' NUREG-1433,
``Standard Technical Specifications General Electric Plants BWR/4,''
and NUREG-1434, ``Standard Technical Specifications General Electric
Plants, BWR/6.''
ADDRESSES: Please refer to Docket ID NRC-2013-0173 when contacting the
NRC about the availability of information regarding this document. You
may access publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2013-0173. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: [email protected]. For technical questions, contact
the individuals listed in the FOR FURTHER INFORMATION CONTACT section
of this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to [email protected]. The ADAMS accession number
for each document referenced in this document (if that document is
available in ADAMS) is provided the first time that a document is
referenced.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Michelle C. Honcharik, telephone: 301-
415-1774, or email: [email protected]; or for technical
questions please contact Matthew Hamm, telephone: 301-415-1472, email:
[email protected]; both of the Office of Nuclear Reactor Regulation,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION: TSTF-523, Revision 2, is applicable to all
nuclear power plants. TSTF-523, Revision 2, includes a model
application and is available in ADAMS under Accession No. ML113260461.
The model safety evaluation for plant-specific adoption of TSTF 523,
Revision 2, is available in ADAMS under Accession No. ML13255A169.
Minor editorial comments were received from the Notice of Opportunity
for Public Comment announced in the Federal Register on August 2, 2013
(78 FR 47010). The disposition of comments received is available in
ADAMS under Accession No. ML13255A403. The proposed change captures the
on-going activities related to system Operability needed to address the
concerns in the Generic Letter 2008-01, ``Managing Gas Accumulation in
Emergency Core Cooling, Decay Heat Removal, and Containment Spray
Systems,'' dated January 11, 2008 (ADAMS Accession No. ML072910759).
The proposed change modifies the existing Surveillance Requirements
(SRs) related to gas accumulation for the emergency core cooling system
and adds new SRs on entrained gas to the specifications governing the
decay heat removal (also called the residual heat removal and shutdown
cooling systems) and the containment spray systems. Similar changes are
made to the existing SR on the reactor core isolation cooling system to
maintain consistency within the STS. Existing SRs are revised to
facilitate the performance of the proposed gas accumulation SR. The TS
Bases are revised to reflect the change to the SRs.
Specifically, the Traveler proposed changes to the following
sections for each of the six reactor types (corresponding to each of
the six NUREGs):
For Babcock and Wilcox Plants, changes were proposed for SRs
3.5.2.2, 3.5.2.3, and 3.6.6.1 as well as the addition of new SRs
3.4.6.3, 3.4.7.4, 3.4.8.3, 3.6.6.4, 3.9.4.2, and 3.9.5.3 to TS 3.4.6,
``RCS Loops--MODE 4,'' TS 3.4.7, ``RCS Loops--MODE 5, Loops Filled,''
TS 3.4.8, ``RCS Loops--MODE 5, Loops Not Filled,'' TS 3.5.2, ``ECCS--
Operating,'' TS 3.6.6, ``Containment Spray and Cooling Systems,'' TS
3.9.4, ``DHR and Coolant Circulation--High Water Level,'' and TS 3.9.5,
``DHR and Coolant Circulation--Low Water Level,'' respectively.
Associated Bases changes were proposed for the respective limiting
conditions for operation (LCO), SR changes and SR additions. Bases
changes for TS 3.5.3, ``ECCS--Shutdown,'' were also proposed because
they reference the SRs and Bases of TS 3.5.2.
For Westinghouse Plants, changes were proposed for SRs 3.5.2.2,
3.5.2.3, 3.6.6A.1, 3.6.6B.1, 3.6.6C.1, 3.6.6D.1, and 3.6.6E.4, as well
as the addition of new SRs 3.4.6.4, 3.4.7.4, 3.4.8.3, 3.6.6A.4,
3.6.6B.4, 3.6.6C.2, 3.6.6D.2, and 3.6.6E.5, 3.9.5.2, and 3.9.6.3 to TS
3.4.6, ``RCS Loops--MODE 4,'' TS 3.4.7, ``RCS Loops--MODE 5, Loops
Filled,'' TS 3.4.8, ``RCS Loops--MODE 5, Loops Not Filled,'' TS 3.5.2,
``ECCS--Operating,'' TS 3.6.6A, ``Containment Spray and Cooling Systems
(Atmospheric and Dual) (Credit taken for iodine removal by the
Containment Spray System),'' TS 3.6.6B, Containment Spray and Cooling
Systems (Atmospheric and Dual) (Credit not taken for iodine removal by
the Containment Spray System),'' TS 3.6.6C, ``Containment Spray System
(Ice Condenser),'' TS 3.6.6D, ``Quench Spray (QS) System
(Subatmospheric),'' TS 3.6.6E, ``Recirculation Spray System
(Subatmospheric),'' TS 3.9.5, ``RHR and Coolant Circulation--High Water
Level,'' and TS 3.9.6, ``RHR and Coolant Circulation--Low Water
Level,'' respectively. Associated Bases changes were proposed for the
respective LCOs, SR changes and SR additions. Bases changes for TS
3.5.3, ``ECCS--Shutdown'' were also proposed because they reference the
SRs and Bases of TS 3.5.2.
For Combustion Engineering Plants, Changes were proposed for SRs
3.5.2.2, 3.5.2.3, 3.6.6A.1, and 3.6.6 B.1, as well as the addition of
new SRs 3.4.6.4, 3.4.7.4, 3.4.8.3, 3.6.6A, 3.6.6B.5, 3.9.4.2, and
3.9.5.3 to TS 3.4.6, ``RCS Loops--MODE 4,'' TS 3.4.7, ``RCS Loops--MODE
5, Loops Filled,'' TS 3.4.8, ``RCS Loops--MODE 5, Loops Not Filled,''
TS 3.5.2, ``ECCS Operating,'' TS 3.6.6A, ``Containment Spray and
Cooling System (Atmospheric and Dual) (Credit taken for iodine removal
by the Containment Spray System),'' TS 3.6.6B, ``Containment Spray and
Cooling System (Atmospheric and Dual) (Credit not taken for iodine
removal by the Containment Spray System),'' TS 3.9.4, ``SDC and Coolant
Circulation--High Water Level,'' and TS 3.9.5, ``SDC and Coolant
Circulation--Low Water Level,'' respectively. Associated Bases changes
were proposed for the respective LCOs, SR changes and SR additions.
Bases changes for TS 3.5.3, ``ECCS--Shutdown,'' were also proposed
because they reference the SRs and Bases of TS 3.5.2.
For General Electric BWR/4 Plants, changes were proposed for SRs
3.5.1.1, 3.5.1.2, 3.5.2.3, 3.5.2.4, 3.5.3.1, and 3.5.3.2, as well as
the addition of new SRs 3.4.8.2, 3.4.9.2, 3.6.2.3.2, 3.6.2.4.2,
3.9.8.2, and 3.9.9.2 to TS 3.4.8, ``RHR Shutdown Cooling System--Hot
Shutdown,'' TS 3.4.9, ``RHR Shutdown Cooling System--Cold Shutdown,''
TS 3.5.1, ``ECCS--Operating,'' TS 3.5.2, ``ECCS--Shutdown,'' TS 3.5.3,
``RCIC System,'' TS 3.6.2.3, ``RHR Suppression
[[Page 2702]]
Pool Cooling,'' TS 3.6.2.4, ``RHR Suppression Pool Spray,'' TS 3.9.8,
``RHR--High Water Level,'' and TS 3.9.9, ``RHR--Low Water Level,''
respectively. Associated Bases changes were proposed for the respective
LCOs, SR changes, and SR additions.
For General Electric BWR/6 Plants, changes were proposed for SRs
3.5.1.1, 3.5.1.2, 3.5.2.3, 3.5.2.4, 3.5.3.1, 3.5.3.2, and 3.6.1.7.1, as
well as the addition of new SRs 3.4.9.2, 3.4.10.2, 3.6.1.7.2,
3.6.2.3.2, 3.9.8.2, and 3.9.9.2 to TS 3.4.9, ``RHR Shutdown Cooling
System--Hot Shutdown,'' TS 3.4.10, ``RHR Shutdown Cooling System--Cold
Shutdown,'' TS 3.5.1, ``ECCS Operating,'' TS 3.5.2, ``ECCS--Shutdown,''
TS 3.5.3, ``RCIC System,'' TS 3.6.1.7, ``RHR Containment Spray
System,'' TS 3.6.2.3, ``RHR Suppression Pool Cooling,'' TS 3.9.8, ``RHR
High Water Level,'' and TS 3.9.9, ``RHR--Low Water Level,''
respectively. Associated Bases changes were proposed for the respective
LCOs, SR changes, and SR additions.
The NRC staff has reviewed the model application for TSTF-523 and
has found it acceptable for use by licensees. Licensees opting to apply
for this TS change are responsible for reviewing the NRC's staff safety
evaluation and the applicable technical bases, providing any necessary
plant-specific information, and assessing the completeness and accuracy
of their license amendment request (LAR). The NRC will process each
amendment application responding to the Notice of Availability
according to applicable NRC rules and procedures.
The proposed changes do not prevent licensees from requesting an
alternate approach or proposing changes other than those proposed in
TSTF-523, Revision 2. However, significant deviations from the approach
recommended in this notice or the inclusion of additional changes to
the license require additional NRC staff review. This may increase the
time and resources needed for the review or result in NRC staff
rejection of the LAR. Licensees desiring significant deviations or
additional changes should instead submit an LAR that does not claim to
adopt TSTF-523, Revision 2.
Dated at Rockville, Maryland, this 23rd day of December, 2013.
For the Nuclear Regulatory Commission.
Anthony J. Mendiola,
Chief, Licensing Processes Branch, Division of Policy and Rulemaking,
Office of Nuclear Reactor Regulation.
[FR Doc. 2014-00644 Filed 1-14-14; 8:45 am]
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