Design of Structures, Components, Equipment, and Systems, 58512-58513 [2015-24654]

Download as PDF 58512 Federal Register / Vol. 80, No. 188 / Tuesday, September 29, 2015 / Notices Environmental Consideration The NRC staff also considered in the review of this exemption request whether there would be any significant environmental impacts associated with the exemption. For this proposed action, the NRC staff performed an environmental assessment pursuant to 10 CFR 51.30, ‘‘Environmental assessment.’’ The proposed action is the approval of an exemption from the requirements of 10 CFR 72.212(a)(2), 72.212(b)(3), 72.212(b)(5)(i), 72.214, and the portion of 72.212(b)(11) that states the licensee shall comply with the terms, conditions, and specifications of the CoC. This exemption would relieve the applicant from meeting Technical Specification (TS) 1.2.4a of Attachment A of CoC No. 1004, allowing for continued storage of DSCs numbers 93, 94, 100, 105, and 106 at the Oconee Nuclear Station ISFSI. The environmental assessment concluded that the proposed action would not significantly impact the quality of the human environment. The NRC staff concludes that the proposed action will not result in any changes in the types or amounts of any radiological effluents that may be released offsite, and there is no significant increase in occupational or public radiation exposure because of the proposed action. The proposed action only affects the requirements associated with Technical Specification (TS) 1.2.4a of Attachment A of CoC No. 1004, which limits the leak rate of the inner seal weld to 1.0 × 10¥7 ref cc/s at the highest DSC limiting pressure, and does not affect plant effluents, or any other aspects of the environment, for DSCs numbers 93, 94, 100, 105, and 106 at the Oconee Nuclear Station ISFSI. The Environmental Assessment and the Finding of No Significant Impact was published on September 3, 2015; 80 FR 53350. asabaliauskas on DSK5VPTVN1PROD with NOTICES 4.0 Conclusion Based on the foregoing considerations, the NRC staff has determined that, pursuant to 10 CFR 72.7, the exemption is authorized by law, will not endanger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the NRC grants the applicant an exemption from the requirements of 10 CFR 72.212(a)(2), 72.212(b)(3), 72.212(b)(5)(i), 72.214, and the portion of 72.212(b)(11) that states the licensee shall comply with the terms, conditions, and specifications of the CoC, only with regard to meeting Technical Specification (TS) 1.2.4a of Attachment A of CoC No. 1004. This exemption VerDate Sep<11>2014 18:28 Sep 28, 2015 Jkt 235001 approval is limited to authorizing continued storage of DSCs numbers 93, 94, 100, 105, and 106 in the TN Standardized NUHOMS® dry cask storage system at the Oconee Nuclear Station ISFSI. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 17 day September, 2015. For the Nuclear Regulatory Commission. Michele Sampson, Branch Chief, Spent Fuel Licensing Branch, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2015–24655 Filed 9–28–15; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION I. Obtaining Information and Submitting Comments [NRC–2015–0229] Design of Structures, Components, Equipment, and Systems Nuclear Regulatory Commission. ACTION: Standard review plan-draft section revision; request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on the following sections in Chapter 3, ‘‘Design of Structures, Components, Equipment, and Systems Reactor Coolant System and Connected Systems’’ of NUREG–0800, ‘‘Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,’’ Section 3.9.2, ‘‘Dynamic Testing and Analysis of Systems, Structures, and Components,’’ Section 3.9.4, ‘‘Control Rod Drive Systems,’’ Section 3.9.5, ‘‘Reactor Pressure Vessel Internals,’’ and Section 3.9.6, ‘‘Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints.’’ SUMMARY: Comments must be filed no later than November 30, 2015. ADDRESSES: You may submit comments by any of the following methods (unless this document describes a different method for submitting comments on a specific subject): • Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2015–0229. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individuals listed in the FOR FURTHER INFORMATION CONTACT section of this document. DATES: PO 00000 Frm 00051 Fmt 4703 Sfmt 4703 • Mail comments to: Cindy Bladey, Office of Administration, Mail Stop: OWFN–12–H08, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. For additional direction on obtaining information and submitting comments, see ‘‘Obtaining Information and Submitting Comments’’ in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Mark Notich, telephone: 301–415–3053; email: Mark.Notich@nrc.gov; or Nishka Devaser, telephone: 301–415–5196; email: Nishka.Devaser@nrc.gov. Both are staff of the Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: A. Obtaining Information Please refer to Docket ID NRC–2015– 0229 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document by any of the following methods: • Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2015–0229. • 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 available in ADAMS) is provided the first time that a document is referenced. For the convenience of the reader, instructions about obtaining materials referenced in this document are provided in the ‘‘Availability of Documents’’ section. • 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. B. Submitting Comments Please include Docket ID NRC–2015– 0229 in the subject line of your comment submission, in order to ensure that the NRC is able to make your E:\FR\FM\29SEN1.SGM 29SEN1 58513 Federal Register / Vol. 80, No. 188 / Tuesday, September 29, 2015 / Notices comment submission available to the public in this docket. The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in you comment submission. The NRC will post all comment submissions at https:// www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment submissions into ADAMS. II. Further Information The NRC seeks public comment on the proposed draft revisions of Standard Review Plan (SRP) Sections 3.9.2, 3.9.4, 3.9.5, and 3.9.6. These sections have been developed to assist the NRC staff review the design of structures, components, equipment, and systems under parts 50 and 52 of Title 10 of the Code of Federal Regulations (10 CFR). The revisions to these SRP sections reflect no changes in staff position; rather they clarify the original intent of these SRP sections using plain language throughout in accordance with the NRC’s Plain Writing Action Plan. Additionally, these revisions reflect operating experience, lessons learned, and updated guidance since the last revision, and address the applicability of regulatory treatment of non-safety systems where appropriate. Following the NRC staff’s evaluation of public comments, the NRC intends to finalize the proposed revisions of the subject SRP Sections in ADAMS and post them on the NRC’s public Web site at https://www.nrc.gov/reading-rm/doccollections/nuregs/staff/sr0800/. III. Availability of Documents SRP Section Current revision ADAMS accession No. Proposed revision ADAMS accession No. Section 3.9.2, ‘‘Dynamic Testing and Analysis of Systems, Structures, and Components’’. Section 3.9.4, ‘‘Control Rod Drive Systems’’ .......................... Section 3.9.5, ‘‘Reactor Pressure Vessel Internals’’ ............... Section 3.9.6, ‘‘Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints’’. Revision 3 (ML070230008) ... Revision 4 (ML15041A281) ... ML15041A367 Revision 3 (ML063190004) ... Revision 3 (ML070230009) ... Revision 3 (ML070720041) ... Revision 4 (ML15041A242) ... Revision 4 (ML15041A234) ... Revision 4 (ML15040A052) ... ML15041A334 ML15041A320 ML15041A287 asabaliauskas on DSK5VPTVN1PROD with NOTICES IV. Backfitting and Issue Finality Issuance of these draft SRP sections, if finalized, does not constitute backfitting as defined in 10 CFR 50.109, nor is it inconsistent with any of the issue finality provisions in 10 CFR part 52. These draft SRP sections do not contain any new requirements for COL applicants or holders under 10 CFR part 52, or for licensees of existing operating units licensed under 10 CFR part 50. Rather, it contains additional draft guidance and clarification on staff review of Preliminary Amendment Requests. The NRC staff does not intend to impose or apply the positions described in the draft SRP to existing licenses and regulatory approvals. Hence, the issuance of a final SRP—even if considered guidance within the purview of the issue finality provisions in 10 CFR part 52—would not need to be evaluated as if it were a backfit or as being inconsistent with issue finality provisions. If, in the future, the NRC staff seeks to impose a position in the SRP on holders of already issued licenses in a manner that does not provide issue finality as described in the applicable issue finality provision, then the staff must make the showing as set forth in the Backfit Rule or address the criteria for avoiding issue finality as described in the applicable issue finality provision. VerDate Sep<11>2014 17:54 Sep 28, 2015 Jkt 235001 The NRC staff does not, at this time, intend to impose the positions represented in the draft SRP sections in a manner that is inconsistent with any issue finality provisions. If, in the future, the staff seeks to impose a position in the draft SRP in a manner that does not provide issue finality as described in the applicable issue finality provision, then the staff must address the criteria for avoiding issue finality as described in the applicable issue finality provision. Dated at Rockville, Maryland, this 18th day of September, 2015. For the Nuclear Regulatory Commission. Kimyata Morgan Butler, Acting Chief, New Reactor Rulemaking and Guidance Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors. [FR Doc. 2015–24654 Filed 9–28–15; 8:45 am] BILLING CODE 7590–01–P PO 00000 Frm 00052 Fmt 4703 Sfmt 4703 Redline ADAMS accession No. NUCLEAR REGULATORY COMMISSION [NRC–2015–0227] Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations Nuclear Regulatory Commission. ACTION: Biweekly notice. AGENCY: Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular biweekly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued, and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued from September 1 to September 14, 2015. The last SUMMARY: E:\FR\FM\29SEN1.SGM 29SEN1

Agencies

[Federal Register Volume 80, Number 188 (Tuesday, September 29, 2015)]
[Notices]
[Pages 58512-58513]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-24654]


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

NUCLEAR REGULATORY COMMISSION

[NRC-2015-0229]


Design of Structures, Components, Equipment, and Systems

AGENCY: Nuclear Regulatory Commission.

ACTION: Standard review plan-draft section revision; request for 
comment.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting 
public comment on the following sections in Chapter 3, ``Design of 
Structures, Components, Equipment, and Systems Reactor Coolant System 
and Connected Systems'' of NUREG-0800, ``Standard Review Plan for the 
Review of Safety Analysis Reports for Nuclear Power Plants: LWR 
Edition,'' Section 3.9.2, ``Dynamic Testing and Analysis of Systems, 
Structures, and Components,'' Section 3.9.4, ``Control Rod Drive 
Systems,'' Section 3.9.5, ``Reactor Pressure Vessel Internals,'' and 
Section 3.9.6, ``Functional Design, Qualification, and Inservice 
Testing Programs for Pumps, Valves, and Dynamic Restraints.''

DATES: Comments must be filed no later than November 30, 2015.

ADDRESSES: You may submit comments by any of the following methods 
(unless this document describes a different method for submitting 
comments on a specific subject):
     Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2015-0229. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact 
the individuals listed in the FOR FURTHER INFORMATION CONTACT section 
of this document.
     Mail comments to: Cindy Bladey, Office of Administration, 
Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Mark Notich, telephone: 301-415-3053; 
email: Mark.Notich@nrc.gov; or Nishka Devaser, telephone: 301-415-5196; 
email: Nishka.Devaser@nrc.gov. Both are staff of the Office of New 
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2015-0229 when contacting the NRC 
about the availability of information regarding this document. You may 
obtain publicly-available information related to this document by any 
of the following methods:
     Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2015-0229.
     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 available in 
ADAMS) is provided the first time that a document is referenced. For 
the convenience of the reader, instructions about obtaining materials 
referenced in this document are provided in the ``Availability of 
Documents'' section.
     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.

B. Submitting Comments

    Please include Docket ID NRC-2015-0229 in the subject line of your 
comment submission, in order to ensure that the NRC is able to make 
your

[[Page 58513]]

comment submission available to the public in this docket.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in you 
comment submission. The NRC will post all comment submissions at https://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment submissions into ADAMS.

II. Further Information

    The NRC seeks public comment on the proposed draft revisions of 
Standard Review Plan (SRP) Sections 3.9.2, 3.9.4, 3.9.5, and 3.9.6. 
These sections have been developed to assist the NRC staff review the 
design of structures, components, equipment, and systems under parts 50 
and 52 of Title 10 of the Code of Federal Regulations (10 CFR). The 
revisions to these SRP sections reflect no changes in staff position; 
rather they clarify the original intent of these SRP sections using 
plain language throughout in accordance with the NRC's Plain Writing 
Action Plan. Additionally, these revisions reflect operating 
experience, lessons learned, and updated guidance since the last 
revision, and address the applicability of regulatory treatment of non-
safety systems where appropriate.
    Following the NRC staff's evaluation of public comments, the NRC 
intends to finalize the proposed revisions of the subject SRP Sections 
in ADAMS and post them on the NRC's public Web site at https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/.

III. Availability of Documents

----------------------------------------------------------------------------------------------------------------
                                     Current revision ADAMS     Proposed revision
            SRP Section                   accession No.        ADAMS accession No.   Redline ADAMS accession No.
----------------------------------------------------------------------------------------------------------------
Section 3.9.2, ``Dynamic Testing     Revision 3              Revision 4              ML15041A367
 and Analysis of Systems,             (ML070230008).          (ML15041A281).
 Structures, and Components''.
Section 3.9.4, ``Control Rod Drive   Revision 3              Revision 4              ML15041A334
 Systems''.                           (ML063190004).          (ML15041A242).
Section 3.9.5, ``Reactor Pressure    Revision 3              Revision 4              ML15041A320
 Vessel Internals''.                  (ML070230009).          (ML15041A234).
Section 3.9.6, ``Functional Design,  Revision 3              Revision 4              ML15041A287
 Qualification, and Inservice         (ML070720041).          (ML15040A052).
 Testing Programs for Pumps,
 Valves, and Dynamic Restraints''.
----------------------------------------------------------------------------------------------------------------

IV. Backfitting and Issue Finality

    Issuance of these draft SRP sections, if finalized, does not 
constitute backfitting as defined in 10 CFR 50.109, nor is it 
inconsistent with any of the issue finality provisions in 10 CFR part 
52. These draft SRP sections do not contain any new requirements for 
COL applicants or holders under 10 CFR part 52, or for licensees of 
existing operating units licensed under 10 CFR part 50. Rather, it 
contains additional draft guidance and clarification on staff review of 
Preliminary Amendment Requests.
    The NRC staff does not intend to impose or apply the positions 
described in the draft SRP to existing licenses and regulatory 
approvals. Hence, the issuance of a final SRP--even if considered 
guidance within the purview of the issue finality provisions in 10 CFR 
part 52--would not need to be evaluated as if it were a backfit or as 
being inconsistent with issue finality provisions. If, in the future, 
the NRC staff seeks to impose a position in the SRP on holders of 
already issued licenses in a manner that does not provide issue 
finality as described in the applicable issue finality provision, then 
the staff must make the showing as set forth in the Backfit Rule or 
address the criteria for avoiding issue finality as described in the 
applicable issue finality provision.
    The NRC staff does not, at this time, intend to impose the 
positions represented in the draft SRP sections in a manner that is 
inconsistent with any issue finality provisions. If, in the future, the 
staff seeks to impose a position in the draft SRP in a manner that does 
not provide issue finality as described in the applicable issue 
finality provision, then the staff must address the criteria for 
avoiding issue finality as described in the applicable issue finality 
provision.

    Dated at Rockville, Maryland, this 18th day of September, 2015.

    For the Nuclear Regulatory Commission.
Kimyata Morgan Butler,
Acting Chief, New Reactor Rulemaking and Guidance Branch, Division of 
Advanced Reactors and Rulemaking, Office of New Reactors.
[FR Doc. 2015-24654 Filed 9-28-15; 8:45 am]
BILLING CODE 7590-01-P
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