NRC-2009-0309, Federal Register Notice of Issuance of Regulatory Guide 1.200 Rev 2, 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
| ML13109A115 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/13/2009 |
| From: | Orr M P Office of Nuclear Regulatory Research |
| To: | |
| References | |
| LRISG200801, NRC-2009-0309, RG-1.200, Rev 2 | |
| Download: ML13109A115 (2) | |
Text
33478 Federal Register/Vol. 74, No. 132/Monday, July 13, 2009/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 http://www.regulations.gov and search 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
http://www.nrc.gov/reading-rm/doc-
collections/. Electronic copies are also available in ADAMS (http:// 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 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
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 VerDate Nov<24>2008 18:36 Jul 10, 2009Jkt 217001PO 00000Frm 00074Fmt 4703Sfmt 4703E:\FR\FM\13JYN1.SGM13JYN1 mstockstill on DSKH9S0YB1PROD with NOTICES 33479 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 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 http://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. FORFURTHERINFORMATIONCONTACT
- 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. SUPPLEMENTARYINFORMATION
- 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 http:// 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 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. FORFURTHERINFORMATIONCONTACT
- 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. SUPPLEMENTARYINFORMATION
- 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 the NRC's public Web site under
Regulatory Guides at http:// www.nrc.gov/reading-rm/doc-
collections/. 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. VerDate Nov<24>2008 18:36 Jul 10, 2009Jkt 217001PO 00000Frm 00075Fmt 4703Sfmt 4703E:\FR\FM\13JYN1.SGM13JYN1 mstockstill on DSKH9S0YB1PROD with NOTICES