Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3, 53483-53484 [2013-21094]

Download as PDF Federal Register / Vol. 78, No. 168 / Thursday, August 29, 2013 / Notices (2) the pressure spike is also localized to the wetwell area which makes up roughly 10 percent of containment, (3) the number of containment penetrations in this area is limited. Therefore, the current Pa value of 7.6 psig meets the intent of 10 CFR part 50, appendix J by bounding the peak bulk containment pressure (3.6 psig) and assuring that leakage through the primary containment does not exceed allowable leakage rate values, (4) the calculated peak bulk containment pressure is 3.6 psig so the Technical Specification (TS) value of 7.6 is conservative for the use of determining containment leakage, and (5) this request is consistent with the determination that the NRC staff has reached for other licensees under similar conditions based on the same considerations. The application for exemption may be examined, and/or copied for a fee, at the NRC’s Public Document Room, located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. Publicly available records will be accessible electronically from the ADAMS Public Library component on the NRC’s Web site, http://www.nrc.gov (the Electronic Reading Room). Therefore, the NRC staff concludes that requesting exemption under the special circumstances of 10 CFR 50.12(a)(2)(ii) is appropriate and that the alternate definition of Pa may be used for the appendix J testing. sroberts on DSK5SPTVN1PROD with NOTICES Authorized by Law This exemption would allow Entergy to use a Pa value of 7.6 psig for appendix J testing at the RBS as discussed above. As stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR part 50, appendix J. The NRC staff has determined that granting of the licensee’s proposed exemption is in accordance with the Atomic Energy Act of 1954, as amended, or the Commission’s regulations. Therefore, the exemption is authorized by law. No Undue Risk to Public Health and Safety The underlying purposes of 10 CFR part 50, appendix J are stated in section (I) ‘‘Introduction.’’ The purpose is to conduct tests to assure that a) leakage through the primary reactor containment does not exceed allowable leakage rate values and b) to conduct periodic surveillance of reactor containment penetrations to support proper maintenance. No new accident precursors are created because the testing is conducted at a Pa value VerDate Mar<15>2010 18:34 Aug 28, 2013 Jkt 229001 calculated to be representative of peak conditions throughout containment during a design basis accident. No new accident precursors are created by use of a Pa of 7.6 psig instead of 9.3 psig, thus, the probability of postulated accidents is not increased. Therefore, there is no undue risk to public health and safety. Consistent With Common Defense and Security The exemption would permit exclusion of the short duration spike in wetwell pressure as Pa for Appendix J testing purposes. This change to the interpretation of Pa as defined in Appendix J has no relation to security issues. Therefore, the common defense and security is not impacted by this exemption. 4.0 Conclusion Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Also, special circumstances are present. Therefore, the Commission hereby grants Entergy Operations, Inc., an exemption from the definition for Pa in 10 CFR part 50, appendix J for River Bend Station, Unit 1 and alternatively to continue to use a Pa value of 7.6 psig. Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not have a significant effect on the quality of the human environment (78 FR 50454; August 19, 2013). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 20th day of August 2013. For the Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2013–21103 Filed 8–28–13; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 052–00025; NRC–2008–0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion. AGENCY: PO 00000 Frm 00062 Fmt 4703 Sfmt 4703 53483 The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the inspections, tests, and analyses have been successfully completed, and that the specified acceptance criteria are met for ITAAC E.2.5.04.05.05.02, for the Vogtle Electric Generating Plant, Unit 3. ADDRESSES: Please refer to Docket ID NRC–2008–0252 when contacting the NRC about the availability of information regarding this document. You may access publicly-available information related to this action by the following methods: • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2008–0252. 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/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: Ravindra Joshi, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–6191, email: Ravindra.Joshi@ nrc.gov. SUPPLEMENTARY INFORMATION: SUMMARY: Licensee Notification of Completion of ITAAC On May 31, 2013, Southern Nuclear Operating Company, Inc. (the licensee) submitted an ITAAC closure notification (ICN) under § 52.99(c)(1) of Title 10 of the Code of Federal Regulations (10 CFR), informing the NRC that the licensee has successfully performed the required inspections, tests, and analyses for ITAAC E.2.5.04.05.05.02, and that the specified acceptance criteria are met for Vogtle E:\FR\FM\29AUN1.SGM 29AUN1 53484 Federal Register / Vol. 78, No. 168 / Thursday, August 29, 2013 / Notices Electric Generating Plant, Unit 3 (ADAMS Accession No. ML13154A033). This ITAAC was approved as part of the issuance of the combined license, NPF– 91, for this facility. sroberts on DSK5SPTVN1PROD with NOTICES NRC Staff Determination of Completion of ITAAC The NRC staff has determined that the inspections, tests, and analyses have been successfully completed, and that the specified acceptance criteria are met for Vogtle Electric Generating Plant, Unit 3, ITAAC E.2.5.04.05.05.02. This notice fulfills the staff’s obligations under 10 CFR 52.99(c)(1) to publish a notice in the Federal Register of the NRC staff’s determination of the successful completion of inspections, tests and analyses. The documentation of the NRC staff’s determination is in the ITAAC Closure Verification Evaluation Form (VEF), dated July 10, 2013 (ADAMS Accession No. ML13191A249). The VEF is a form that represents the NRC staff’s structured process for reviewing ICNs. The ICN presents a narrative description of how the ITAAC was completed, and the NRC’s ICN review process involves a determination on whether, among other things, (1) The ICN provides sufficient information, including a summary of the methodology used to perform the ITAAC, to demonstrate that the inspections, tests, and analyses have been successfully completed; (2) the ICN provides sufficient information to demonstrate that the acceptance criteria are met; and (3) any inspections for the ITAAC have been completed and any ITAAC findings associated with the ITAAC have been closed. The NRC staff’s determination of the successful completion of this ITAAC is based on information available at this time and is subject to the licensee’s ability to maintain the condition that the acceptance criteria are met. If new information disputes the NRC staff’s determination, this ITAAC will be reopened as necessary. The NRC staff’s determination will be used to support a subsequent finding, pursuant to 10 CFR 52.103(g), at the end of construction that all acceptance criteria in the combined license are met. The ITAAC closure process is not finalized for this ITAAC until the NRC makes an affirmative finding under 10 CFR 52.103(g). Any future updates to the status of this ITAAC will be reflected on the NRC’s Web site at http://www.nrc.gov/reactors/ new-reactors/oversight/itaac.html. Dated at Rockville, Maryland, this 22nd day of August 2013. VerDate Mar<15>2010 18:34 Aug 28, 2013 Jkt 229001 For the Nuclear Regulatory Commission. Denise McGovern, Senior Project Manager, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. 2013–21094 Filed 8–28–13; 8:45 am] BILLING CODE 7590–01–P SUPPLEMENTARY INFORMATION: NUCLEAR REGULATORY COMMISSION [Docket No. 052–00026; NRC–2008–0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4 Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the inspections, tests, and analyses have been successfully completed, and that the specified acceptance criteria are met for ITAAC E.2.5.04.05.05.02, for the Vogtle Electric Generating Plant, Unit 4. ADDRESSES: Please refer to Docket ID NRC–2008–0252 when contacting the NRC about the availability of information regarding this document. You may access publicly-available information related to this action by the following methods: • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2008–0252. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3442; 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/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 SUMMARY: PO 00000 Frm 00063 Fmt 4703 Sfmt 4703 White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Ravindra Joshi, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–6191, email: Ravindra.Joshi@ nrc.gov. Licensee Notification of Completion of ITAAC On May 31, 2013, Southern Nuclear Operating Company, Inc. (the licensee) submitted an ITAAC closure notification (ICN) under § 52.99(c)(1) of Title 10 of the Code of Federal Regulations (10 CFR), informing the NRC that the licensee has successfully performed the required inspections, tests, and analyses for ITAAC E.2.5.04.05.05.02, and that the specified acceptance criteria are met for Vogtle Electric Generating Plant, Unit 4 (ADAMS Accession No. ML13154A032). This ITAAC was approved as part of the issuance of the combined license, NPF– 92, for this facility. NRC Staff Determination of Completion of ITAAC The NRC staff has determined that the inspections, tests, and analyses have been successfully completed, and that the specified acceptance criteria are met for Vogtle Electric Generating Plant, Unit 4, ITAAC E.2.5.04.05.05.02. This notice fulfills the staff’s obligations under 10 CFR 52.99(e)(1) to publish a notice in the Federal Register of the NRC staff’s determination of the successful completion of inspections, tests and analyses. The documentation of the NRC staff’s determination is in the ITAAC Closure Verification Evaluation Form (VEF), dated July 10, 2013 (ADAMS Accession No. ML13191A333). The VEF is a form that represents the NRC staff’s structured process for reviewing ICNs. The ICN presents a narrative description of how the ITAAC was completed, and the NRC’s ICN review process involves a determination on whether, among other things, (1) the ICN provides sufficient information, including a summary of the methodology used to perform the ITAAC, to demonstrate that the inspections, tests, and analyses have been successfully completed; (2) the ICN provides sufficient information to demonstrate that the acceptance criteria are met; and (3) any inspections for the ITAAC have been completed and any ITAAC findings associated with the ITAAC have been closed. The NRC staff’s determination of the successful completion of this ITAAC is E:\FR\FM\29AUN1.SGM 29AUN1

Agencies

[Federal Register Volume 78, Number 168 (Thursday, August 29, 2013)]
[Notices]
[Pages 53483-53484]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-21094]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 052-00025; NRC-2008-0252]


Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle 
Electric Generating Plant, Unit 3

AGENCY: Nuclear Regulatory Commission.

ACTION: Determination of inspections, tests, analyses, and acceptance 
criteria (ITAAC) completion.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) staff has 
determined that the inspections, tests, and analyses have been 
successfully completed, and that the specified acceptance criteria are 
met for ITAAC E.2.5.04.05.05.02, for the Vogtle Electric Generating 
Plant, Unit 3.

ADDRESSES: Please refer to Docket ID NRC-2008-0252 when contacting the 
NRC about the availability of information regarding this document. You 
may access publicly-available information related to this action by the 
following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2008-0252. 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: Ravindra Joshi, Office of New 
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-6191, email: Ravindra.Joshi@nrc.gov.

SUPPLEMENTARY INFORMATION: 

Licensee Notification of Completion of ITAAC

    On May 31, 2013, Southern Nuclear Operating Company, Inc. (the 
licensee) submitted an ITAAC closure notification (ICN) under Sec.  
52.99(c)(1) of Title 10 of the Code of Federal Regulations (10 CFR), 
informing the NRC that the licensee has successfully performed the 
required inspections, tests, and analyses for ITAAC E.2.5.04.05.05.02, 
and that the specified acceptance criteria are met for Vogtle

[[Page 53484]]

Electric Generating Plant, Unit 3 (ADAMS Accession No. ML13154A033). 
This ITAAC was approved as part of the issuance of the combined 
license, NPF-91, for this facility.

NRC Staff Determination of Completion of ITAAC

    The NRC staff has determined that the inspections, tests, and 
analyses have been successfully completed, and that the specified 
acceptance criteria are met for Vogtle Electric Generating Plant, Unit 
3, ITAAC E.2.5.04.05.05.02. This notice fulfills the staff's 
obligations under 10 CFR 52.99(c)(1) to publish a notice in the Federal 
Register of the NRC staff's determination of the successful completion 
of inspections, tests and analyses.
    The documentation of the NRC staff's determination is in the ITAAC 
Closure Verification Evaluation Form (VEF), dated July 10, 2013 (ADAMS 
Accession No. ML13191A249). The VEF is a form that represents the NRC 
staff's structured process for reviewing ICNs. The ICN presents a 
narrative description of how the ITAAC was completed, and the NRC's ICN 
review process involves a determination on whether, among other things, 
(1) The ICN provides sufficient information, including a summary of the 
methodology used to perform the ITAAC, to demonstrate that the 
inspections, tests, and analyses have been successfully completed; (2) 
the ICN provides sufficient information to demonstrate that the 
acceptance criteria are met; and (3) any inspections for the ITAAC have 
been completed and any ITAAC findings associated with the ITAAC have 
been closed.
    The NRC staff's determination of the successful completion of this 
ITAAC is based on information available at this time and is subject to 
the licensee's ability to maintain the condition that the acceptance 
criteria are met. If new information disputes the NRC staff's 
determination, this ITAAC will be reopened as necessary. The NRC 
staff's determination will be used to support a subsequent finding, 
pursuant to 10 CFR 52.103(g), at the end of construction that all 
acceptance criteria in the combined license are met. The ITAAC closure 
process is not finalized for this ITAAC until the NRC makes an 
affirmative finding under 10 CFR 52.103(g). Any future updates to the 
status of this ITAAC will be reflected on the NRC's Web site at http://www.nrc.gov/reactors/new-reactors/oversight/itaac.html.

    Dated at Rockville, Maryland, this 22nd day of August 2013.

    For the Nuclear Regulatory Commission.
Denise McGovern,
Senior Project Manager, Licensing Branch 4, Division of New Reactor 
Licensing, Office of New Reactors.
[FR Doc. 2013-21094 Filed 8-28-13; 8:45 am]
BILLING CODE 7590-01-P