Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric & Gas Company, South Carolina Public Service Authority, Consolidation of Class 1E DC and Uninterruptible Power Supply System Spare Battery Termination Boxes, 35385-35386 [2016-12917]

Download as PDF Federal Register / Vol. 81, No. 106 / Thursday, June 2, 2016 / Notices III Accordingly, pursuant to Sections 161b, 161i, and 184 of the Act, 42 U.S.C. Sections 2201(b), 2201(i), and 2234; and 10 CFR 50.80, it is hereby ordered that the transfer of the license, as described herein, to LS is approved, subject to the following condition: asabaliauskas on DSK3SPTVN1PROD with NOTICES Prior to the closing of the license transfer from DPC to LS, LS shall provide the Directors of NRC’s Office of Nuclear Material Safety and Safeguards (NMSS) and Office of Nuclear Reactor Regulation (NRR) satisfactory documentary evidence that it has obtained the appropriate amount of insurance required of a licensee under 10 CFR 140.12 and 10 CFR 50.54(w) of the Commission’s regulations, consistent with the exemptions issued to LACBWR on June 26, 1986. It is further ordered that, consistent with 10 CFR 2.1315(b), the license amendment that makes changes, as indicated in Enclosure 2 to the cover letter forwarding this Order, to conform the license to reflect the subject direct license transfer is approved. The amendment shall be issued and made effective at the time the proposed direct license transfer is completed. It is further ordered that LS shall inform the Directors of NMSS and NRR in writing of the date of closing of the transfer of the DPC interests in LACBWR, at least 1 business day prior to closing. Should the transfer of the license not be completed within 1 year of this Order’s date of issuance, this Order shall become null and void; provided, however, that upon written application and for good cause shown, such date may be extended by order. This Order is effective upon issuance. For further details with respect to this Order, see the initial application dated October 8, 2015, as supplemented by letter dated December 15, 2015, and the associated NRC safety evaluation dated May 20, 2016, which are available for public inspection at the Commission’s Public Document Room (PDR), located at One White Flint North, Public File Area 01–F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available documents are accessible electronically through ADAMS in the NRC Library at https://www.nrc.gov/ reading-rm/adams.html. Persons who encounter problems with ADAMS should contact the NRC’s PDR reference staff by telephone at 1–800–397–4209 or 301–415–4737 or by email to pdr.resource@nrc.gov. Dated at Rockville, Maryland this 20th day of May 2016. VerDate Sep<11>2014 18:30 Jun 01, 2016 Jkt 238001 For the Nuclear Regulatory Commission. Scott Moore, Acting Director, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2016–13013 Filed 6–1–16; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 52–027 and 52–028; NRC– 2008–0441] Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric & Gas Company, South Carolina Public Service Authority, Consolidation of Class 1E DC and Uninterruptible Power Supply System Spare Battery Termination Boxes Nuclear Regulatory Commission. ACTION: Exemption and combined license amendment; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow changes to the certification information of Tier 1 of the AP1000 generic design control document (DCD) and issuing License Amendment No. 43 to Combined Licenses (COL), NPF–93 and NPF–94. The COLs were issued to South Carolina Electric & Gas Company (SCE&G), and South Carolina Public Service Authority (together called the licensee) in March 2012, for the construction and operation of the Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3, located in Fairfield County, South Carolina. DATES: June 2, 2016. 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 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 SUMMARY: PO 00000 Frm 00093 Fmt 4703 Sfmt 4703 35385 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 December 19, 2014 (ADAMS Accession No. ML14353A126). The licensee supplemented this request by letter dated February 25, 2015 (ADAMS Accession No. ML15056A429). • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. Specific information on NRC’s PDR is available at https:// www.nrc.gov/reading-rm/pdr.html. FOR FURTHER INFORMATION CONTACT: William (Billy) 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 Tier 1 information in the certified DCD incorporated by reference in part 52 of title 10 of the Code of Federal Regulations (10 CFR), appendix D, ‘‘Design Certification Rule for the AP1000 Design,’’ and issuing License Amendment No. 43 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 change Tier 1 information. The granting of the exemption allows the changes to Tier 1 information requested 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. Specifically, the amendments allow the implementation of changes to the Class 1E dc and Uninterruptible Power Supply System (IDS), replacing four spare termination boxes with a single spare battery termination box and minor cable raceway and cable routing changes. The exemptions allow the implementation of changes to the plant-specific Tier 1 UFSAR that are different from those in the generic Tier 1 information in the AP1000 Certified Design Control Document. E:\FR\FM\02JNN1.SGM 02JNN1 35386 Federal Register / Vol. 81, No. 106 / Thursday, June 2, 2016 / Notices asabaliauskas on DSK3SPTVN1PROD with NOTICES With the requested amendment, the licensee sought proposed changes related to the plant-specific Tier 1 tables related to the Class 1E dc and uninterruptible power supply system. The Tier 1 tables contain inspection, test, analysis, and acceptance criteria (ITAAC) and specifically, the licensee sought proposed changes to Tier 1 ITAAC Table 2.6.3–1 that contains lists Category I equipment and Tier 1 ITAAC Table 2.6.3–4 that contains component locations for this system. The proposed changes to plant-specific Tier 1 information also contain corresponding COL Appendix C and UFSAR Tier 2 information that would facilitate the replacement of four Class 1E DC and uninterruptible power supply system (IDS) spare termination boxes with a single spare battery termination box. 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 10 CFR 50.12, 10 CFR 52.7, and 10 CFR 52.63(b)(1). The license amendment was found to be acceptable as well. The combined safety evaluation is available in ADAMS under Accession No. ML16068A149. 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). These documents can be found in ADAMS under Accession Nos. ML16068A119 and ML16068A120, 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. ML16068A113 and ML16068A117, 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 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 December 19, 2014, supplemented February 25, 2015, the VerDate Sep<11>2014 18:30 Jun 01, 2016 Jkt 238001 South Carolina Electric & Gas Company (SC&G/licensee) requested from the Nuclear Regulatory Commission (NRC/ Commission) an exemption from the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Appendix D, ‘‘Design Certification Rule for AP1000 Design,’’ Section VIII.B.6.b, Item (4), to allow a departure from the certified information as part of license amendment request (LAR) 13–29, ‘‘Consolidation of Class 1E DC and Uninterruptible Power Supply System Spare Battery Termination Boxes.’’ For the reasons set forth in Section 3.1 of the NRC staff’s Safety Evaluation that supports this license amendment, which can be found at Agencywide Documents Access and Management System (ADAMS) Accession Number ML16068A149, 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; 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 AP1000 DCD Tier 1 information, as described in the licensee’s request dated December 19, 2014, supplemented February 25, 2015. This exemption is related to, and necessary for, the granting of License Amendment No. 43, which is being issued concurrently with this exemption. 3. As explained in Section 5 of the NRC staff’s Safety Evaluation that supports this license amendment (ADAMS Accession Number ML16068A149), 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 The request for the amendment and exemption was submitted by the letter dated December 19, 2014. The licensee supplemented this request by the letter PO 00000 Frm 00094 Fmt 4703 Sfmt 9990 dated February 25, 2015. The proposed amendment is described in Section I, above. 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 May 12, 2015 (80 FR 27200). No comments were received during the 30day comment period. The NRC staff has found that the amendment involves no significant hazards consideration. The Commission has determined that these amendments satisfy the criteria for categorical exclusion in accordance with 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for these amendments. The supplement dated February 25, 2015, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff’s original proposed no significant hazards consideration determination as published in the Federal Register. 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 December 19, 2014, and supplemented by the letter dated February 25, 2015. The exemption and amendment were issued on April 25, 2016, as part of a combined package to the licensee (ADAMS Accession No. ML16077A120). Dated at Rockville, Maryland, this 24th day of May 2016. For the Nuclear Regulatory Commission. John McKirgan, Acting Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. 2016–12917 Filed 6–1–16; 8:45 am] BILLING CODE 7590–01–P E:\FR\FM\02JNN1.SGM 02JNN1

Agencies

[Federal Register Volume 81, Number 106 (Thursday, June 2, 2016)]
[Notices]
[Pages 35385-35386]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-12917]


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NUCLEAR REGULATORY COMMISSION

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


Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina 
Electric & Gas Company, South Carolina Public Service Authority, 
Consolidation of Class 1E DC and Uninterruptible Power Supply System 
Spare Battery Termination Boxes

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 changes to the certification information of Tier 1 
of the AP1000 generic design control document (DCD) and issuing License 
Amendment No. 43 to Combined Licenses (COL), NPF-93 and NPF-94. The 
COLs were issued to South Carolina Electric & Gas Company (SCE&G), and 
South Carolina Public Service Authority (together called the licensee) 
in March 2012, for the construction and operation of the Virgil C. 
Summer Nuclear Station (VCSNS), Units 2 and 3, located in Fairfield 
County, South Carolina.

DATES: June 2, 2016.

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 December 19, 2014 (ADAMS Accession No. ML14353A126). The 
licensee supplemented this request by letter dated February 25, 2015 
(ADAMS Accession No. ML15056A429).
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, One White Flint North, 11555 Rockville 
Pike, Rockville, Maryland 20852. Specific information on NRC's PDR is 
available at https://www.nrc.gov/reading-rm/pdr.html.

FOR FURTHER INFORMATION CONTACT: William (Billy) 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 Tier 1 information in the 
certified DCD incorporated by reference in part 52 of title 10 of the 
Code of Federal Regulations (10 CFR), appendix D, ``Design 
Certification Rule for the AP1000 Design,'' and issuing License 
Amendment No. 43 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 change Tier 1 information.
    The granting of the exemption allows the changes to Tier 1 
information requested 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. 
Specifically, the amendments allow the implementation of changes to the 
Class 1E dc and Uninterruptible Power Supply System (IDS), replacing 
four spare termination boxes with a single spare battery termination 
box and minor cable raceway and cable routing changes. The exemptions 
allow the implementation of changes to the plant-specific Tier 1 UFSAR 
that are different from those in the generic Tier 1 information in the 
AP1000 Certified Design Control Document.

[[Page 35386]]

    With the requested amendment, the licensee sought proposed changes 
related to the plant-specific Tier 1 tables related to the Class 1E dc 
and uninterruptible power supply system. The Tier 1 tables contain 
inspection, test, analysis, and acceptance criteria (ITAAC) and 
specifically, the licensee sought proposed changes to Tier 1 ITAAC 
Table 2.6.3-1 that contains lists Category I equipment and Tier 1 ITAAC 
Table 2.6.3-4 that contains component locations for this system. The 
proposed changes to plant-specific Tier 1 information also contain 
corresponding COL Appendix C and UFSAR Tier 2 information that would 
facilitate the replacement of four Class 1E DC and uninterruptible 
power supply system (IDS) spare termination boxes with a single spare 
battery termination box.
    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 10 CFR 50.12, 10 CFR 52.7, and 10 CFR 52.63(b)(1). The license 
amendment was found to be acceptable as well. The combined safety 
evaluation is available in ADAMS under Accession No. ML16068A149.
    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). These documents can be found in ADAMS under 
Accession Nos. ML16068A119 and ML16068A120, 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. 
ML16068A113 and ML16068A117, 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 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 December 19, 2014, supplemented February 25, 
2015, the South Carolina Electric & Gas Company (SC&G/licensee) 
requested from the Nuclear Regulatory Commission (NRC/Commission) an 
exemption from the provisions of Title 10 of the Code of Federal 
Regulations (10 CFR) Part 52, Appendix D, ``Design Certification Rule 
for AP1000 Design,'' Section VIII.B.6.b, Item (4), to allow a departure 
from the certified information as part of license amendment request 
(LAR) 13-29, ``Consolidation of Class 1E DC and Uninterruptible Power 
Supply System Spare Battery Termination Boxes.''
    For the reasons set forth in Section 3.1 of the NRC staff's Safety 
Evaluation that supports this license amendment, which can be found at 
Agencywide Documents Access and Management System (ADAMS) Accession 
Number ML16068A149, 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;
    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 AP1000 DCD Tier 1 information, as described in the licensee's 
request dated December 19, 2014, supplemented February 25, 2015. This 
exemption is related to, and necessary for, the granting of License 
Amendment No. 43, which is being issued concurrently with this 
exemption.
    3. As explained in Section 5 of the NRC staff's Safety Evaluation 
that supports this license amendment (ADAMS Accession Number 
ML16068A149), 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

    The request for the amendment and exemption was submitted by the 
letter dated December 19, 2014. The licensee supplemented this request 
by the letter dated February 25, 2015. The proposed amendment is 
described in Section I, above.
    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 May 12, 2015 (80 FR 27200). No comments were received 
during the 30-day comment period.
    The NRC staff has found that the amendment involves no significant 
hazards consideration. The Commission has determined that these 
amendments satisfy the criteria for categorical exclusion in accordance 
with 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no 
environmental impact statement or environmental assessment need be 
prepared for these amendments. The supplement dated February 25, 2015, 
provided additional information that clarified the application, did not 
expand the scope of the application as originally noticed, and did not 
change the staff's original proposed no significant hazards 
consideration determination as published in the Federal Register.

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 December 19, 2014, and supplemented by the letter dated 
February 25, 2015. The exemption and amendment were issued on April 25, 
2016, as part of a combined package to the licensee (ADAMS Accession 
No. ML16077A120).

    Dated at Rockville, Maryland, this 24th day of May 2016.

    For the Nuclear Regulatory Commission.
John McKirgan,
Acting Chief, Licensing Branch 4, Division of New Reactor Licensing, 
Office of New Reactors.
[FR Doc. 2016-12917 Filed 6-1-16; 8:45 am]
 BILLING CODE 7590-01-P
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