TSTF-523, “Generic Letter 2008-01, Managing Gas Accumulation,” Using the Consolidated Line Item Improvement Process, 2700-2702 [2014-00644]

Download as PDF 2700 Federal Register / Vol. 79, No. 10 / Wednesday, January 15, 2014 / Notices §§ 380.4(b), 382.15(b),1 and 384.6(b). Prior to conducting an audit, SoundExchange must file with the Judges a notice of intent to audit a licensee and serve the notice on the licensee to be audited. Id. at §§ 380.6(c), 382.15(c), and 384.6(c). On December 20, 2013, SoundExchange filed with the Judges five separate notices of intent to audit IMUC, Inc. (IMUC), Crystal Media Networks (CMN), Pandora Media, Inc. (Pandora) and LoudCity LLC (LoudCity) for their webcasting services, and Sirius XM Radio, Inc. (Sirius XM) for its various services: webcasting service, preexisting satellite digital audio radio service, new subscription service, and business establishment service for the years 2010, 2011, and 2012. Sections 380.6(c), 382.15(c), and 384.6(c) require the Judges to publish a notice in the Federal Register within 30 days of receipt of the notice announcing the Collective’s intent to conduct an audit. Today’s notice fulfills this requirement with respect to SoundExchange’s notices of intent to audit IMUC, CMN, Pandora, LoudCity and Sirius XM, filed December 20, 2013. Dated: January 10, 2014. Suzanne M. Barnett, Chief Copyright Royalty Judge. [FR Doc. 2014–00654 Filed 1–14–14; 8:45 am] BILLING CODE 1410–72–P NUCLEAR REGULATORY COMMISSION [Docket No. NRC–2013–0085] Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB) Review; Comment Request Nuclear Regulatory Commission. ACTION: Notice of the OMB review of information collection and solicitation of public comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). The NRC hereby informs potential respondents that an wreier-aviles on DSK5TPTVN1PROD with NOTICES SUMMARY: 1 SoundExchange’s authority to audit new subscription services falls under § 383.4(a), which states in pertinent part that ‘‘terms governing . . . audit and verification of royalty payments and distributions, cost of audit and verification . . . shall be those adopted by the [Judges] for subscription transmissions and the reproduction of ephemeral recordings by preexisting satellite digital audio radio services in 37 CFR part 382, subpart B.’’ VerDate Mar<15>2010 14:04 Jan 14, 2014 Jkt 232001 agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. The NRC published a Federal Register notice with a 60-day comment period on this information collection on May 14, 2013 (78 FR 28244). 1. Type of submission, new, revision, or extension: Extension. 2. The title of the information collection: 10 CFR part 50, ‘‘Domestic Licensing of Production and Utilization Facilities.’’ 3. Current OMB approval number: 3150–0011. 4. The form number if applicable: N/ A. 5. How often the collection is required: As necessary in order for NRC to meet its responsibilities to conduct a detailed review of applications for licenses and amendments thereto to construct and operate nuclear power plants, preliminary or final design approvals, design certifications, research and test facilities, reprocessing plants and other utilization and production facilities, licensed pursuant to the Atomic Energy Act of 1954, as amended (the Act) and to monitor their activities. Reports are submitted daily, monthly, quarterly, annually, semiannually, and on occasion. 6. Who will be required or asked to report: Licensees and applicants for nuclear power plants and research and test facilities, and approximately 100 materials licensees responding to generic communications. 7. An estimate of the number of annual responses: 46,098. 8. The estimated number of annual respondents: 251. 9. An estimate of the total number of hours needed annually to complete the requirement or request: 4.88M hours; 1.93M hours reporting (an average of 41.8 hrs/response) + 2.96M hours recordkeeping (an average of 19.5K hrs/ recordkeeper). 10. Abstract: Part 50 of Title 10 of the Code of Federal Regulations (10 CFR), ‘‘Domestic Licensing of Production and Utilization Facilities,’’ specifies technical information and data to be provided to the NRC or maintained by applicants and licensees so that the NRC may take determinations necessary to protect the health and safety of the public, in accordance with the Act. The reporting and recordkeeping requirements contained in 10 CFR part 50 are mandatory for the affected licensees and applicants. The public may examine and have copied for a fee publicly available documents, including the final supporting statement, at the NRC’s PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 Public Document Room, Room O–1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. The OMB clearance requests are available at the NRC’s Web site: https://www.nrc.gov/ public-involve/doc-comment/omb/. The document will be available on the NRC’s home page site for 60 days after the signature date of this notice. Comments and questions should be directed to the OMB reviewer listed below by February 14, 2014. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. Chad Whiteman, Desk Officer, Office of Information and Regulatory Affairs (3150–0011), NEOB–10202, Office of Management and Budget, Washington, DC 20503. Comments can also be emailed to Chad_S_Whiteman@omb.eop.gov or submitted by telephone at 202–395– 4718. The NRC Clearance Officer is Tremaine Donnell, telephone: 301–415– 6258. Dated at Rockville, Maryland, this 9th day of January, 2014. For the Nuclear Regulatory Commission. Tremaine Donnell, NRC Clearance Officer, Office of Information Services. [FR Doc. 2014–00569 Filed 1–14–14; 8:45 am] BILLING CODE 7590–01–P 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 Nuclear Regulatory Commission. ACTION: Notice of Availability. AGENCY: 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 SUMMARY: E:\FR\FM\15JAN1.SGM 15JAN1 wreier-aviles on DSK5TPTVN1PROD with NOTICES Federal Register / Vol. 79, No. 10 / Wednesday, January 15, 2014 / Notices 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 https://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 https://www.nrc.gov/readingrm/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. VerDate Mar<15>2010 14:04 Jan 14, 2014 Jkt 232001 The model safety evaluation for plantspecific 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, PO 00000 Frm 00070 Fmt 4703 Sfmt 4703 2701 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 E:\FR\FM\15JAN1.SGM 15JAN1 2702 Federal Register / Vol. 79, No. 10 / Wednesday, January 15, 2014 / Notices wreier-aviles on DSK5TPTVN1PROD with NOTICES 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] BILLING CODE 7590–01–P VerDate Mar<15>2010 14:04 Jan 14, 2014 Jkt 232001 PRESIDIO TRUST Notice of Public Meeting of Fort Scott Council The Presidio Trust. Notice of public meeting of Fort Scott Council. AGENCY: ACTION: Pursuant to the Federal Advisory Committee Act, as amended (5 U.S.C. Appendix 2), notice is hereby given that a public meeting of the Fort Scott Council (Council) will be held from 1:00 p.m. to 4:30 p.m. on Tuesday, January 28, 2014. The meeting is open to the public, and oral public comment will be received at the meeting. The Council was formed to advise the Executive Director of the Presidio Trust (Trust) on matters pertaining to the rehabilitation and reuse of Fort Winfield Scott as a new national center focused on service and leadership development. SUPPLEMENTARY INFORMATION: The Trust’s Executive Director, in consultation with the Chair of the Board of Directors, has determined that the Council is in the public interest and supports the Trust in performing its duties and responsibilities under the Presidio Trust Act, 16 U.S.C. 460bb appendix. The Council will advise on the establishment of a new national center (Center) focused on service and leadership development, with specific emphasis on: (a) Assessing the role and key opportunities of a national center dedicated to service and leadership at Fort Scott in the Presidio of San Francisco; (b) providing recommendations related to the Center’s programmatic goals, target audiences, content, implementation and evaluation; (c) providing guidance on a phased development approach that leverages a combination of funding sources including philanthropy; and (d) making recommendations on how to structure the Center’s business model to best achieve the Center’s mission and ensure long-term financial selfsufficiency. Meeting Agenda: In this meeting of the Council, the Acting Director will provide an update on the Cross Sector Leadership Fellows program. There will be a discussion about a strategic plan for the Presidio Institute. The period from 4:00 p.m. to 4:30 p.m. will be reserved for public comments. Public Comment: Individuals who would like to offer comments are invited to sign-up at the meeting and speaking times will be assigned on a first-come, first-served basis. Written comments may be submitted on cards that will be provided at the meeting, via SUMMARY: PO 00000 Frm 00071 Fmt 4703 Sfmt 4703 mail to Linh Tran, Presidio Trust, 1201 Ralston Avenue, San Francisco, CA 94129–0052, or via email to institute@ presidiotrust.gov. If individuals submitting written comments request that their address or other contact information be withheld from public disclosure, it will be honored to the extent allowable by law. Such requests must be stated prominently at the beginning of the comments. The Trust will make available for public inspection all submissions from organizations or businesses and from persons identifying themselves as representatives or officials of organizations and businesses. Time: The meeting will be held from 1:00 p.m. to 4:30 p.m. on Tuesday, January 28, 2014. Location: The meeting will be held at 1202 Ralston Avenue, The Presidio of San Francisco, San Francisco, CA 94129. FOR FURTHER INFORMATION CONTACT: Additional information is available online at https://www.presidio.gov/ explore/Pages/presidio-institute.aspx. Dated: January 7, 2014. Karen A. Cook, General Counsel. [FR Doc. 2014–00492 Filed 1–14–14; 8:45 am] BILLING CODE 4310–4R–P SECURITIES AND EXCHANGE COMMISSION [Release No. 34–71273; File No. SR–NYSE– 2013–83] Self-Regulatory Organizations; New York Stock Exchange LLC; Notice of Filing and Immediate Effectiveness of Proposed Rule Change Making Effective as of January 1, 2014 Recently Approved Changes to NYSE Rules 451 and 465, and the Related Provisions of Section 402.10 of the NYSE Listed Company Manual Concerning Charges by Member Organizations for Processing and Forwarding Proxy and Other Issuer Communications to Beneficial Owners, and Establishing a Fee Under Certain Conditions for an Enhanced Brokers’ Internet Platform January 9, 2014. Pursuant to Section 19(b)(1) 1 of the Securities Exchange Act of 1934 (the ‘‘Act’’) 2 and Rule 19b–4 thereunder,3 notice is hereby given that, on December 31, 2013, New York Stock Exchange LLC (‘‘NYSE’’ or the ‘‘Exchange’’) filed 1 15 U.S.C.78s(b)(1). U.S.C. 78a. 3 17 CFR 240.19b–4. 2 15 E:\FR\FM\15JAN1.SGM 15JAN1

Agencies

[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]


-----------------------------------------------------------------------

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.

-----------------------------------------------------------------------

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 https://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 https://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

[[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]
BILLING CODE 7590-01-P
This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.