[Federal Register Volume 79, Number 10 (Wednesday, January 15, 2014)]
[Notices]
[Pages 2700-2702]
From the Federal Register Online via the Government Printing 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: Carol.Gallagher@nrc.gov. 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 pdr.resource@nrc.gov. 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: Michelle.Honcharik@nrc.gov; or for technical 
questions please contact Matthew Hamm, telephone: 301-415-1472, email: 
Matthew.Hamm@nrc.gov; 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

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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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