License Renewal Interim Staff Guidance LR-ISG-2008-01: Staff Guidance Regarding the Station Blackout Rule (10 CFR 50.63) Associated With License Renewal Applications; Notice of Withdrawal, 33478-33479 [E9-16486]

Download as PDF 33478 Federal Register / Vol. 74, No. 132 / Monday, July 13, 2009 / Notices mstockstill on DSKH9S0YB1PROD with NOTICES Requirements (Design and Construction),’’ is temporarily identified by its task number, DG–1215, which should be mentioned in all related correspondence. DG–1215 is proposed Revision 4 of Regulatory Guide 1.28. DG–1215 describes methods that the NRC staff considers acceptable for complying with the provisions of Appendix B, ‘‘Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,’’ to Title 10, part 50, ‘‘Domestic Licensing of Production and Utilization Facilities,’’ of the Code of Federal Regulations (10 CFR part 50) for establishing and implementing a quality assurance (QA) program for the design and construction of nuclear power plants, fuel fabrication plants and fuel reprocessing plants. The methods described in this revision are similar to the methods described in Regulatory Guide (RG) 1.28, ‘‘Quality Assurance Program Requirements (Design and Construction),’’ Revision 3, which is the previously published version of this regulatory guide. RG 1.33, ‘‘Quality Assurance Program Requirements (Operation)’’ addresses additional guidance for the establishment and execution of QA programs for nuclear power plants during the operations phase, which is unaffected by the revision to RG 1.28. DG–1215 endorses methods defined in American Society of Mechanical Engineers (ASME) NQA–1, ‘‘Quality Assurance Requirements for Nuclear Facility Applications.’’ The NRC is aware that the ASME standards committee has proposed minor changes to NQA–1 in a draft of ASME NQA–1a– 2009, Addenda to ASME NQA–1–2008. If these addenda are issued in a timely manner, they will be considered for endorsement in RG 1.28, revision 4. II. Further Information The NRC staff is soliciting comments on DG–1215. Comments may be accompanied by relevant information or supporting data and should mention DG–1215 in the subject line. Comments submitted in writing or in electronic form will be made available to the public in their entirety through the NRC’s Agencywide Documents Access and Management System (ADAMS). Personal information will not be removed from your comments. You may submit comments by any of the following methods: 1. Mail comments to: Rulemaking and Directives Branch, Office of Administration, MS TWB–05–B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. 2. Federal e-Rulemaking Portal: Go to https://www.regulations.gov and search VerDate Nov<24>2008 18:36 Jul 10, 2009 Jkt 217001 for documents filed under Docket ID [NRC–2009–0308]. Address questions about NRC dockets to Carol Gallagher, 301–492–3668; e-mail Carol.Gallagher@nrc.gov. 3. Fax comments to: Rulemaking and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission at (301) 492–3446. Requests for technical information about DG–1215 may be directed to the NRC contact, Paul Prescott at (301) 415– 3026 or e-mail to Paul.Prescott@nrc.gov. Comments would be most helpful if received by September 8, 2009. Comments received after that date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this date. Although a time limit is given, comments and suggestions in connection with items for inclusion in guides currently being developed or improvements in all published guides are encouraged at any time. Electronic copies of DG–1215 are available through the NRC’s public Web site under Draft Regulatory Guides in the ‘‘Regulatory Guides’’ collection of the NRC’s Electronic Reading Room at https://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also available in ADAMS (https:// www.nrc.gov/reading-rm/adams.html), under Accession No. ML090150402. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland. The PDR’s mailing address is USNRC PDR, Washington, DC 20555–0001. The PDR can also be reached by telephone at (301) 415–4737 or (800) 397–4205, by fax at (301) 415– 3548, and by e-mail to pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them. Dated at Rockville, Maryland, this 6th day of July 2009. For the Nuclear Regulatory Commission. Mark P. Orr, Acting Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E9–16494 Filed 7–10–09; 8:45 am] BILLING CODE 7590–01–P PO 00000 Frm 00074 Fmt 4703 Sfmt 4703 NUCLEAR REGULATORY COMMISSION [NRC–2008–0147] License Renewal Interim Staff Guidance LR–ISG–2008–01: Staff Guidance Regarding the Station Blackout Rule (10 CFR 50.63) Associated With License Renewal Applications; Notice of Withdrawal AGENCY: Nuclear Regulatory Commission (NRC). ACTION: Notice of withdrawal. SUMMARY: The NRC is withdrawing its proposed License Renewal Interim Staff Guidance (LR–ISG) LR–ISG–2008–01, ‘‘Staff Guidance Regarding the Station Blackout Rule (10 CFR 50.63) Associated with License Renewal Applications.’’ The NRC staff issued the proposed guidance to clarify the acceptance criteria for the scoping of systems, structures, and components in accordance with section 54.4(a)(3) of Title 10 of the Code of Federal Regulations (10 CFR 54.4(a)(3)). However, after evaluating comments received on the proposed guidance, the NRC staff has determined that the current acceptance criteria, as provided in section 2.5.2.1.1 of NUREG–1800, Revision 1, ‘‘Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants’’ (SRP–LR), are adequate for the NRC staff’s review of license renewal applications. As such, the NRC staff is withdrawing the proposed LR–ISG– 2008–01. On March 12, 2008, the NRC requested public comments on the proposed LR–ISG in the Federal Register (73 FR 13258). The proposed LR–ISG and accompanying figures are available in the NRC’s Agencywide Documents Access and Management System (ADAMS) under Accession Nos. ML080520619 and ML080520620, respectively. The NRC staff drafted the proposed LR–ISG–2008–01 after finding that some license renewal applications did not include within the scope of license renewal all structures and components required by 10 CFR 54.4(a)(3) for demonstrating compliance with 10 CFR 50.63 (Station Blackout Rule). The proposed LR–ISG was intended to clarify the NRC staff’s acceptance criteria in SRP–LR section 2.5.2.1.1, ‘‘Components Within the Scope of SBO (10 CFR 50.63).’’ By letters dated May 9, 2008 (ML081400346), and May 12, 2008 (ML081350619), the NRC received comments on the proposed LR–ISG from the Strategic Teaming and Resource E:\FR\FM\13JYN1.SGM 13JYN1 mstockstill on DSKH9S0YB1PROD with NOTICES Federal Register / Vol. 74, No. 132 / Monday, July 13, 2009 / Notices Sharing alliance and the Nuclear Energy Institute (NEI), respectively. On July 18, 2008, the NRC staff discussed these comments during a public meeting with NEI and industry representatives, as documented in ‘‘Summary of the License Renewal Meeting Held between the U.S. Nuclear Regulatory Commission Staff and the Nuclear Energy Institute,’’ dated October 3, 2008 (ML082480547). Overall, the comments indicated that the NRC staff’s proposed guidance is too prescriptive and does not acknowledge the unique design aspects of each plant, as reflected in the plant’s current licensing basis. The NRC staff evaluated both the comments submitted in writing, and those provided during the July 18, 2008, meeting and subsequent public license renewal meetings, and determined that the proposed clarification in LR–ISG– 2008–01 is unnecessary because the NRC staff’s review of license renewal applications is based on the plantspecific current licensing bases, regulatory requirements, and offsite power design configurations. As such, the NRC staff will continue to review license renewal applications against the acceptance criteria in SRP–LR section 2.5.2.1.1 to ensure applicants include within the scope of license renewal the systems, structures, and components that perform functions to demonstrate compliance with the Station Blackout Rule, as required by 10 CFR 54.4(a)(3). Therefore, by this action, the NRC is withdrawing LR–ISG–2008–01. ADDRESSES: Documents created or received after November 1, 1999, are available electronically at the NRC’s Public Electronic Reading Room on the Internet at https://www.nrc.gov/readingrm/adams.html. From this site, the public can gain entry into ADAMS. If you do not have access to the Internet or if there are any problems in accessing the documents located in ADAMS, contact the NRC Public Document Room reference staff at 1–800–397–4209, 301– 415–4737, or by e-mail at PDR.Resource@nrc.gov. FOR FURTHER INFORMATION CONTACT: Mr. Matthew Homiack, Division of License Renewal, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone 301–415–1683; or e-mail Matthew.Homiack@nrc.gov. SUPPLEMENTARY INFORMATION: The NRC issues LR–ISGs to communicate insights and lessons learned, and to address emergent issues not addressed in certain license renewal guidance documents. The NRC staff and stakeholders can use approved LR–ISGs until their guidance is incorporated into a formal license VerDate Nov<24>2008 18:36 Jul 10, 2009 Jkt 217001 renewal guidance document revision. The NRC posts its issued LR–ISGs on the NRC Public Web page at https:// www.nrc.gov/reading-rm/doccollections/isg. Dated at Rockville, Maryland, this 7th day of July 2009. For the Nuclear Regulatory Commission. Brian E. Holian, Director, Division of License Renewal, Office of Nuclear Reactor Regulation. [FR Doc. E9–16486 Filed 7–10–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2009–0117] Notice of Revised Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Revised Regulatory Guide (RG) 1.200, Revision 2, ‘‘An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities.’’ FOR FURTHER INFORMATION CONTACT: Mary Drouin, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone (301) 251– 7574 or e-mail to Mary.Drouin@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The Nuclear Regulatory Commission (NRC) issued Revision 2 of RG 1.200 on March 17, 2009, which was published in the Federal Register, 74 FR 11381. RG 1.200, Revision 2 is a guide in the agency’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public information such as methods that are acceptable to the NRC staff for implementing specific parts of the agency’s regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in its review of applications for permits and licenses. A sentence was inadvertently omitted from the draft version that was issued for public comment and the final version that was published in March 2009. The current version of Regulatory Guide 1.200 on the NRC Web site includes the omitted sentence at the end of the first paragraph in Regulatory Position C.1.2.5. II. Further Information Electronic copies of Regulatory Guide 1.200, Revision 2 are available through PO 00000 Frm 00075 Fmt 4703 Sfmt 4703 33479 the NRC’s public Web site under ‘‘Regulatory Guides’’ at https:// www.nrc.gov/reading-rm/doccollections/. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR) located at Room O–1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852–2738. The PDR’s mailing address is USNRC PDR, Washington, DC 20555–0001. The PDR can also be reached by telephone at (301) 415–4737 or (800) 397–4209, by fax at (301) 415–3548, and by e-mail to pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. Dated at Rockville, Maryland, this 2nd day of July 2009. For the Nuclear Regulatory Commission. Mark P. Orr, Acting Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E9–16499 Filed 7–10–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–254 and 50–265; NRC– 2009–0309] Exelon Generation Company, LLC; Notice of Withdrawal of Application for Amendment to Facility Operating License The U.S. Nuclear Regulatory Commission (the Commission) has granted the request of Exelon Generation Company, LLC (the licensee) to withdraw its December 21, 2007, application for proposed amendment to Renewed Facility Operating License Nos. DPR–29 and DPR–30 for the Quad Cities Nuclear Power Station, Units 1 and 2, located in Rock Island County, Illinois. The proposed amendment would have revised the Technical Specifications Surveillance Requirements to establish an acceptance criterion to verify that total battery connector resistances for the 125 and 250 volt direct current batteries are within pre-established limits that ensure the batteries can perform their design function. The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on February 26, 2008 (73 FR 10298) and December 30, 2008 (73 FR 79932). However, by letter dated June 25, 2009, the licensee withdrew the proposed change. E:\FR\FM\13JYN1.SGM 13JYN1

Agencies

[Federal Register Volume 74, Number 132 (Monday, July 13, 2009)]
[Notices]
[Pages 33478-33479]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-16486]


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NUCLEAR REGULATORY COMMISSION

[NRC-2008-0147]


License Renewal Interim Staff Guidance LR-ISG-2008-01: Staff 
Guidance Regarding the Station Blackout Rule (10 CFR 50.63) Associated 
With License Renewal Applications; Notice of Withdrawal

AGENCY: Nuclear Regulatory Commission (NRC).

ACTION: Notice of withdrawal.

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

SUMMARY: The NRC is withdrawing its proposed License Renewal Interim 
Staff Guidance (LR-ISG) LR-ISG-2008-01, ``Staff Guidance Regarding the 
Station Blackout Rule (10 CFR 50.63) Associated with License Renewal 
Applications.'' The NRC staff issued the proposed guidance to clarify 
the acceptance criteria for the scoping of systems, structures, and 
components in accordance with section 54.4(a)(3) of Title 10 of the 
Code of Federal Regulations (10 CFR 54.4(a)(3)). However, after 
evaluating comments received on the proposed guidance, the NRC staff 
has determined that the current acceptance criteria, as provided in 
section 2.5.2.1.1 of NUREG-1800, Revision 1, ``Standard Review Plan for 
Review of License Renewal Applications for Nuclear Power Plants'' (SRP-
LR), are adequate for the NRC staff's review of license renewal 
applications. As such, the NRC staff is withdrawing the proposed LR-
ISG-2008-01.
    On March 12, 2008, the NRC requested public comments on the 
proposed LR-ISG in the Federal Register (73 FR 13258). The proposed LR-
ISG and accompanying figures are available in the NRC's Agencywide 
Documents Access and Management System (ADAMS) under Accession Nos. 
ML080520619 and ML080520620, respectively.
    The NRC staff drafted the proposed LR-ISG-2008-01 after finding 
that some license renewal applications did not include within the scope 
of license renewal all structures and components required by 10 CFR 
54.4(a)(3) for demonstrating compliance with 10 CFR 50.63 (Station 
Blackout Rule). The proposed LR-ISG was intended to clarify the NRC 
staff's acceptance criteria in SRP-LR section 2.5.2.1.1, ``Components 
Within the Scope of SBO (10 CFR 50.63).''
    By letters dated May 9, 2008 (ML081400346), and May 12, 2008 
(ML081350619), the NRC received comments on the proposed LR-ISG from 
the Strategic Teaming and Resource

[[Page 33479]]

Sharing alliance and the Nuclear Energy Institute (NEI), respectively. 
On July 18, 2008, the NRC staff discussed these comments during a 
public meeting with NEI and industry representatives, as documented in 
``Summary of the License Renewal Meeting Held between the U.S. Nuclear 
Regulatory Commission Staff and the Nuclear Energy Institute,'' dated 
October 3, 2008 (ML082480547). Overall, the comments indicated that the 
NRC staff's proposed guidance is too prescriptive and does not 
acknowledge the unique design aspects of each plant, as reflected in 
the plant's current licensing basis.
    The NRC staff evaluated both the comments submitted in writing, and 
those provided during the July 18, 2008, meeting and subsequent public 
license renewal meetings, and determined that the proposed 
clarification in LR-ISG-2008-01 is unnecessary because the NRC staff's 
review of license renewal applications is based on the plant-specific 
current licensing bases, regulatory requirements, and offsite power 
design configurations. As such, the NRC staff will continue to review 
license renewal applications against the acceptance criteria in SRP-LR 
section 2.5.2.1.1 to ensure applicants include within the scope of 
license renewal the systems, structures, and components that perform 
functions to demonstrate compliance with the Station Blackout Rule, as 
required by 10 CFR 54.4(a)(3).
    Therefore, by this action, the NRC is withdrawing LR-ISG-2008-01.

ADDRESSES: Documents created or received after November 1, 1999, are 
available electronically at the NRC's Public Electronic Reading Room on 
the Internet at https://www.nrc.gov/reading-rm/adams.html. From this 
site, the public can gain entry into ADAMS. If you do not have access 
to the Internet or if there are any problems in accessing the documents 
located in ADAMS, contact the NRC Public Document Room reference staff 
at 1-800-397-4209, 301-415-4737, or by e-mail at PDR.Resource@nrc.gov.

FOR FURTHER INFORMATION CONTACT: Mr. Matthew Homiack, Division of 
License Renewal, Office of Nuclear Reactor Regulation, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001; telephone 301-415-
1683; or e-mail Matthew.Homiack@nrc.gov.

SUPPLEMENTARY INFORMATION: The NRC issues LR-ISGs to communicate 
insights and lessons learned, and to address emergent issues not 
addressed in certain license renewal guidance documents. The NRC staff 
and stakeholders can use approved LR-ISGs until their guidance is 
incorporated into a formal license renewal guidance document revision. 
The NRC posts its issued LR-ISGs on the NRC Public Web page at https://www.nrc.gov/reading-rm/doc-collections/isg.

    Dated at Rockville, Maryland, this 7th day of July 2009.

    For the Nuclear Regulatory Commission.
Brian E. Holian,
Director, Division of License Renewal, Office of Nuclear Reactor 
Regulation.
[FR Doc. E9-16486 Filed 7-10-09; 8:45 am]
BILLING CODE 7590-01-P
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