South Carolina Electric & Gas Company; South Carolina Public Service Authority, Virgil C. Summer Nuclear Station, Units 2 and 3, Nuclear Instrumentation System Excore Detector Surface, Material Inspection Clarification, 21831-21832 [2017-09457]

Download as PDF Federal Register / Vol. 82, No. 89 / Wednesday, May 10, 2017 / Notices Authority: 40 U.S.C. 8721(e)(2) and 8722(a). Dated: May 5, 2017. Anne R. Schuyler, General Counsel. [FR Doc. 2017–09479 Filed 5–9–17; 8:45 am] BILLING CODE 7520–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 52–027 and 52–028; NRC– 2008–0441] South Carolina Electric & Gas Company; South Carolina Public Service Authority, Virgil C. Summer Nuclear Station, Units 2 and 3, Nuclear Instrumentation System Excore Detector Surface, Material Inspection Clarification Nuclear Regulatory Commission. ACTION: Exemption and combined license amendment; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment No. 72 to Combined Licenses (COL), NPF– 93 and NPF–94. The COLs were issued to South Carolina Electric & Gas Company, (the licensee); for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, located in Fairfield County, South Carolina. The granting of the exemption allows the changes to Tier 1 information asked for in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently. DATES: The exemption and amendment were issued on April 17, 2017. ADDRESSES: Please refer to Docket ID NRC–2008–0441 when contacting the NRC about the availability of information regarding this document. You may obtain 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–2008–0441. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. jstallworth on DSK7TPTVN1PROD with NOTICES SUMMARY: VerDate Sep<11>2014 15:21 May 09, 2017 Jkt 241001 21831 • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection 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 (if it is available in ADAMS) is provided the first time that it is mentioned in this document. The request for the amendment and exemption was submitted by letter dated November 16, 2016 (ADAMS Accession No. ML16323A020). • 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: Bill Gleaves, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–5848; email: Bill.Gleaves@ nrc.gov. SUPPLEMENTARY INFORMATION: exemption is necessary in order to issue the requested license amendment, the NRC granted the exemption and issued the amendment concurrently, rather than in sequence. This included issuing a combined safety evaluation containing the NRC staff’s review of both the exemption request and the license amendment. The exemption met all applicable regulatory criteria set forth in §§ 50.12, 52.7, and Section VIII.A.4 of appendix D to 10 CFR part 52. The license amendment was found to be acceptable as well. The combined safety evaluation is available in ADAMS under Accession No. ML17045A717. Identical exemption documents (except for referenced unit numbers and license numbers) were issued to the licensee for VCSNS Units 2 and 3 (COLs NPF–93 and NPF–94). The exemption documents for VCSNS Units 2 and 3 can be found in ADAMS under Accession Nos. ML17045A679 and ML17045A682, respectively. The exemption is reproduced (with the exception of abbreviated titles and additional citations) in Section II of this document. The amendment documents for COLs NPF–93 and NPF–94 are available in ADAMS under Accession Nos. ML17045A665 and ML17045A677, respectively. A summary of the amendment documents is provided in Section III of this document. I. Introduction The NRC is granting an exemption from Paragraph B of Section III, ‘‘Scope and Contents,’’ of appendix D, ‘‘Design Certification Rule for the AP1000,’’ to part 52 of title 10 of the Code of Federal Regulations (10 CFR), and issuing License Amendment No. 72 to COLs, NPF–93 and NPF–94, to the licensee. The exemption is required by Paragraph A.4 of Section VIII, ‘‘Processes for Changes and Departures,’’ appendix D, to 10 CFR part 52 to allow the licensee to depart from Tier 1 information. With the requested amendment, the licensee sought proposed changes to the VCSNS Units 2 and 3 Updated Final Safety Analysis Report (UFSAR) in the form of departures from the incorporated plantspecific DCD Tier 2 information. The proposed amendment also involves related changes to plant-specific Tier 1 information, with corresponding changes to the associated COL Appendix C information to clarify the Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) related to the inspection of excore (source range, intermediate range, and power range) detectors. Part of the justification for granting the exemption was provided by the review of the amendment. Because the II. Exemption Reproduced below is the exemption document issued to VCSNS Units 2 and Unit 3. It makes reference to the combined safety evaluation that provides the reasoning for the findings made by the NRC (and listed under Item 1) in order to grant the exemption: 1. In a letter dated November 16, 2016, the licensee requested from the Commission an exemption to allow departures from Tier 1 information in the certified DCD incorporated by reference in 10 CFR part 52, appendix D, as part of license amendment request 16–09, ‘‘Nuclear Instrumentation System Excore Detector Surface Material Inspection Clarification.’’ For the reasons set forth in Section 3.1 of the NRC staff’s Safety Evaluation, which can be found in ADAMS under Accession No. ML17045A717, the Commission finds that: A. The exemption is authorized by law; B. the exemption presents no undue risk to public health and safety; C. the exemption is consistent with the common defense and security; D. special circumstances are present in that the application of the rule in this circumstance is not necessary to serve the underlying purpose of the rule; PO 00000 Frm 00043 Fmt 4703 Sfmt 4703 E:\FR\FM\10MYN1.SGM 10MYN1 21832 Federal Register / Vol. 82, No. 89 / Wednesday, May 10, 2017 / Notices E. the special circumstances outweigh any decrease in safety that may result from the reduction in standardization caused by the exemption; and F. the exemption will not result in a significant decrease in the level of safety otherwise provided by the design. 2. Accordingly, the licensee is granted an exemption from the certified DCD Tier 1 information, with corresponding changes to Appendix C of the Facility Combined Licenses as described in the licensee’s request dated November 16, 2016. This exemption is related to, and necessary for, the granting of License Amendment No. 72, which is being issued concurrently with this exemption. 3. As explained in Section 5.0 of the NRC staff’s Safety Evaluation (ADAMS Accession No. ML17045A717), this exemption meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the exemption. 4. This exemption is effective as of the date of its issuance. jstallworth on DSK7TPTVN1PROD with NOTICES III. License Amendment Request By letter dated November 16, 2016 (ADAMS Accession No. ML16323A020), the licensee requested that the NRC amend the COLs for VCSNS, Units 2 and 3, COLs NPF–93 and NPF–94. The proposed amendment is described in Section I of this document. The Commission has determined for these amendments that the application complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission’s rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission’s rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment. A notice of consideration of issuance of amendment to facility operating license or combined license, as applicable, proposed no significant hazards consideration determination, and opportunity for a hearing in connection with these actions, was published in the Federal Register on February 14, 2017 (82 FR 10590). No comments were received during the 30day comment period. The Commission has determined that these amendments satisfy the criteria for categorical exclusion in accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental VerDate Sep<11>2014 15:21 May 09, 2017 Jkt 241001 assessment need be prepared for these amendments. IV. Conclusion Using the reasons set forth in the combined safety evaluation, the staff granted the exemption and issued the amendment that the licensee requested on November 16, 2016. The exemption and amendment were issued on April 17, 2017, as part of a combined package to the licensee (ADAMS Accession No. ML17045A616). Dated at Rockville, Maryland, this 1st day of May 2017. For the Nuclear Regulatory Commission. Jennifer Dixon-Herrity, Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. 2017–09457 Filed 5–9–17; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–409; NRC–2015–0279] LaCrosse Solutions, LLC; Dairyland Power Cooperative; La Crosse Boiling Water Reactor Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a January 16, 2017, request from LaCrosseSolutions, LLC (LS), for the La Crosse Boiling Water Reactor (LACBWR), from the requirement to investigate and report to the NRC when LS does not receive notification of receipt of a shipment, or part of a shipment, of low-level radioactive waste within 20 days after transfer by rail from the LACBWR facility. LaCrosseSolutions requested that the time period for it to receive acknowledgement that the shipment has been received by the intended recipient be extended from 20 to 45 days to avoid an excessive administrative burden because of operational experience that indicates that rail shipments may take more than 20 days to reach their destination. SUMMARY: May 10, 2017. Please refer to Docket ID NRC–2015–0279 when contacting the NRC about the availability of information regarding this document. You may obtain 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–2015–0279. Address DATES: ADDRESSES: PO 00000 Frm 00044 Fmt 4703 Sfmt 4703 questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection 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 notice (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: Marlayna G. Vaaler, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington DC 20555–0001; telephone: 301–415–3178, email: Marlayna.Vaaler@nrc.gov. SUPPLEMENTARY INFORMATION: I. Background The La Crosse Boiling Water Reactor was an Atomic Energy Commission (AEC) Demonstration Project Reactor that first went critical in 1967, commenced commercial operation in November 1969, and was capable of producing 50 megawatts electric. The LACBWR is located on the east bank of the Mississippi River in Vernon County, Wisconsin, and is co-located with the Genoa Generating Station, which is a coal-fired electrical power plant that is still in operation. The Allis-Chalmers Company was the original licensee; the AEC later sold the plant to the Dairyland Power Cooperative (DPC) and granted it Provisional Operating License No. DPR–45 on August 28, 1973 (ADAMS Accession No. ML17080A423). The LACBWR permanently ceased operations on April 30, 1987 (ADAMS Accession No. ML17080A422), and reactor defueling was completed on June 11, 1987 (ADAMS Accession No. ML17080A420). In a letter dated August 4, 1987 (ADAMS Accession No. ML17080A393), the NRC terminated E:\FR\FM\10MYN1.SGM 10MYN1

Agencies

[Federal Register Volume 82, Number 89 (Wednesday, May 10, 2017)]
[Notices]
[Pages 21831-21832]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-09457]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 52-027 and 52-028; NRC-2008-0441]


South Carolina Electric & Gas Company; South Carolina Public 
Service Authority, Virgil C. Summer Nuclear Station, Units 2 and 3, 
Nuclear Instrumentation System Excore Detector Surface, Material 
Inspection Clarification

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption and combined license amendment; issuance.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is granting an 
exemption to allow a departure from the certification information of 
Tier 1 of the generic design control document (DCD) and is issuing 
License Amendment No. 72 to Combined Licenses (COL), NPF-93 and NPF-94. 
The COLs were issued to South Carolina Electric & Gas Company, (the 
licensee); for construction and operation of the Virgil C. Summer 
Nuclear Station (VCSNS) Units 2 and 3, located in Fairfield County, 
South Carolina.
    The granting of the exemption allows the changes to Tier 1 
information asked for in the amendment. Because the acceptability of 
the exemption was determined in part by the acceptability of the 
amendment, the exemption and amendment are being issued concurrently.

DATES: The exemption and amendment were issued on April 17, 2017.

ADDRESSES: Please refer to Docket ID NRC-2008-0441 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain 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-2008-0441. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection 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 (if it is available 
in ADAMS) is provided the first time that it is mentioned in this 
document. The request for the amendment and exemption was submitted by 
letter dated November 16, 2016 (ADAMS Accession No. ML16323A020).
     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: Bill Gleaves, Office of New Reactors, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; 
telephone: 301-415-5848; email: Bill.Gleaves@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The NRC is granting an exemption from Paragraph B of Section III, 
``Scope and Contents,'' of appendix D, ``Design Certification Rule for 
the AP1000,'' to part 52 of title 10 of the Code of Federal Regulations 
(10 CFR), and issuing License Amendment No. 72 to COLs, NPF-93 and NPF-
94, to the licensee. The exemption is required by Paragraph A.4 of 
Section VIII, ``Processes for Changes and Departures,'' appendix D, to 
10 CFR part 52 to allow the licensee to depart from Tier 1 information. 
With the requested amendment, the licensee sought proposed changes to 
the VCSNS Units 2 and 3 Updated Final Safety Analysis Report (UFSAR) in 
the form of departures from the incorporated plant-specific DCD Tier 2 
information. The proposed amendment also involves related changes to 
plant-specific Tier 1 information, with corresponding changes to the 
associated COL Appendix C information to clarify the Inspections, 
Tests, Analyses and Acceptance Criteria (ITAAC) related to the 
inspection of excore (source range, intermediate range, and power 
range) detectors.
    Part of the justification for granting the exemption was provided 
by the review of the amendment. Because the exemption is necessary in 
order to issue the requested license amendment, the NRC granted the 
exemption and issued the amendment concurrently, rather than in 
sequence. This included issuing a combined safety evaluation containing 
the NRC staff's review of both the exemption request and the license 
amendment. The exemption met all applicable regulatory criteria set 
forth in Sec. Sec.  50.12, 52.7, and Section VIII.A.4 of appendix D to 
10 CFR part 52. The license amendment was found to be acceptable as 
well. The combined safety evaluation is available in ADAMS under 
Accession No. ML17045A717.
    Identical exemption documents (except for referenced unit numbers 
and license numbers) were issued to the licensee for VCSNS Units 2 and 
3 (COLs NPF-93 and NPF-94). The exemption documents for VCSNS Units 2 
and 3 can be found in ADAMS under Accession Nos. ML17045A679 and 
ML17045A682, respectively. The exemption is reproduced (with the 
exception of abbreviated titles and additional citations) in Section II 
of this document. The amendment documents for COLs NPF-93 and NPF-94 
are available in ADAMS under Accession Nos. ML17045A665 and 
ML17045A677, respectively. A summary of the amendment documents is 
provided in Section III of this document.

II. Exemption

    Reproduced below is the exemption document issued to VCSNS Units 2 
and Unit 3. It makes reference to the combined safety evaluation that 
provides the reasoning for the findings made by the NRC (and listed 
under Item 1) in order to grant the exemption:
    1. In a letter dated November 16, 2016, the licensee requested from 
the Commission an exemption to allow departures from Tier 1 information 
in the certified DCD incorporated by reference in 10 CFR part 52, 
appendix D, as part of license amendment request 16-09, ``Nuclear 
Instrumentation System Excore Detector Surface Material Inspection 
Clarification.''
    For the reasons set forth in Section 3.1 of the NRC staff's Safety 
Evaluation, which can be found in ADAMS under Accession No. 
ML17045A717, the Commission finds that:
    A. The exemption is authorized by law;
    B. the exemption presents no undue risk to public health and 
safety;
    C. the exemption is consistent with the common defense and 
security;
    D. special circumstances are present in that the application of the 
rule in this circumstance is not necessary to serve the underlying 
purpose of the rule;

[[Page 21832]]

    E. the special circumstances outweigh any decrease in safety that 
may result from the reduction in standardization caused by the 
exemption; and
    F. the exemption will not result in a significant decrease in the 
level of safety otherwise provided by the design.
    2. Accordingly, the licensee is granted an exemption from the 
certified DCD Tier 1 information, with corresponding changes to 
Appendix C of the Facility Combined Licenses as described in the 
licensee's request dated November 16, 2016. This exemption is related 
to, and necessary for, the granting of License Amendment No. 72, which 
is being issued concurrently with this exemption.
    3. As explained in Section 5.0 of the NRC staff's Safety Evaluation 
(ADAMS Accession No. ML17045A717), this exemption meets the eligibility 
criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). 
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact 
statement or environmental assessment needs to be prepared in 
connection with the issuance of the exemption.
    4. This exemption is effective as of the date of its issuance.

III. License Amendment Request

    By letter dated November 16, 2016 (ADAMS Accession No. 
ML16323A020), the licensee requested that the NRC amend the COLs for 
VCSNS, Units 2 and 3, COLs NPF-93 and NPF-94. The proposed amendment is 
described in Section I of this document.
    The Commission has determined for these amendments that the 
application complies with the standards and requirements of the Atomic 
Energy Act of 1954, as amended (the Act), and the Commission's rules 
and regulations. The Commission has made appropriate findings as 
required by the Act and the Commission's rules and regulations in 10 
CFR Chapter I, which are set forth in the license amendment.
    A notice of consideration of issuance of amendment to facility 
operating license or combined license, as applicable, proposed no 
significant hazards consideration determination, and opportunity for a 
hearing in connection with these actions, was published in the Federal 
Register on February 14, 2017 (82 FR 10590). No comments were received 
during the 30-day comment period.
    The Commission has determined that these amendments satisfy the 
criteria for categorical exclusion in accordance with 10 CFR 51.22. 
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact 
statement or environmental assessment need be prepared for these 
amendments.

IV. Conclusion

    Using the reasons set forth in the combined safety evaluation, the 
staff granted the exemption and issued the amendment that the licensee 
requested on November 16, 2016. The exemption and amendment were issued 
on April 17, 2017, as part of a combined package to the licensee (ADAMS 
Accession No. ML17045A616).

    Dated at Rockville, Maryland, this 1st day of May 2017.
    For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of 
New Reactors.
[FR Doc. 2017-09457 Filed 5-9-17; 8:45 am]
BILLING CODE 7590-01-P
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