Draft Regulatory Guide: Issuance, Availability, 47548-47549 [E6-13560]

Download as PDF 47548 Federal Register / Vol. 71, No. 159 / Thursday, August 17, 2006 / Notices the Licensee. Because of possible delays in delivery of mail to United States Government offices, it is requested that answers and requests for hearing be transmitted to the Secretary of the Commission either by means of facsimile transmission to 301–415–1101 or by e-mail to hearingdocket@nrc.gov and also to the Office of the General Counsel either by means of facsimile transmission to 301–415–3725 or by email to OGCMailCenter@nrc.gov. If a person other than the Licensee requests a hearing, that person shall set forth with particularity the manner in which his/her interest is adversely affected by this Order and shall address the criteria set forth in 10 CFR 2.309. If a hearing is requested by the Licensee or a person whose interest is adversely affected, the Commission will issue an Order designating the time and place of any hearing. If a hearing is held, the issue to be considered at such hearing shall be whether this Order should be sustained. Pursuant to 10 CFR 2.202(c)(2)(i), the Licensee may, in addition to demanding a hearing, at the time the answer is filed or sooner, move the presiding officer to set aside the immediate effectiveness of the Order on the ground that the Order, including the need for immediate effectiveness, is not based on adequate evidence but on mere suspicion, unfounded allegations, or error. In the absence of any request for hearing, or written approval of an extension of time in which to request a hearing, the provisions as specified above in Section III shall be final twenty (20) days from the date of this Order without further order or proceedings. If an extension of time for requesting a hearing has been approved, the provisions as specified above in Section III shall be final when the extension expires if a hearing request has not been received. An answer or a request for hearing shall not stay the immediate effectiveness of this order. Dated this 11th day of August 2006. For the Nuclear Regulatory Commission. Bruce A. Boger, Acting Director, Office of Nuclear Reactor Regulation. [FR Doc. E6–13562 Filed 8–16–06; 8:45 am] BILLING CODE 7590–01–P rwilkins on PROD1PC63 with NOTICES NUCLEAR REGULATORY COMMISSION Draft Regulatory Guide: Issuance, Availability The U.S. Nuclear Regulatory Commission (NRC) has issued for public comment a draft of a new guide in the VerDate Aug<31>2005 16:36 Aug 16, 2006 Jkt 208001 agency’s Regulatory Guide Series. This series has been developed to describe and make available to the public such information as methods that are acceptable to the NRC staff for implementing specific parts of the NRC’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. The draft regulatory guide, entitled ‘‘Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors,’’ is temporarily identified by its task number, DG–1144, which should be mentioned in all related correspondence. This proposed regulatory guide describes a method that the NRC staff considers acceptable for use in complying with the agency’s regulations in Title 10, part 50, of the Code of Federal Regulations (10 CFR Part 50), ‘‘Domestic Licensing of Production and Utilization Facilities.’’ Specifically, in Appendix A to10 CFR part 50, General Design Criterion (GDC) 1, ‘‘Quality Standards and Records,’’ requires, in part, that structures, systems, and components that are important to safety must be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety function performed. In addition, GDC 30, ‘‘Quality of Reactor Coolant Pressure Boundary,’’ requires, in part, that components that are part of the reactor coolant pressure boundary must be designed, fabricated, erected, and tested to the highest practical quality standards. Augmenting those design criteria, 10 CFR 50.55a, ‘‘Codes and Standards,’’ endorses the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code for design of safety-related systems and components. In particular, Section 50.55a(c), ‘‘Reactor Coolant Pressure Boundary,’’ requires, in part, that components of the reactor coolant pressure boundary must be meet the requirements for Class 1 components in Section III, ‘‘Rules for Construction of Nuclear Power Plant Components,’’ of the ASME Boiler and Pressure Vessel Code. Specifically, those Class 1 requirements contain provisions, including fatigue design curves, for determining a component’s suitability for cyclic service. These fatigue design curves are based on strain-controlled tests performed on small polished specimens, at room temperature, in air environments. Thus, these curves do not address the impact PO 00000 Frm 00070 Fmt 4703 Sfmt 4703 of the reactor coolant system environment. This draft regulatory guide provides guidance for use in determining the acceptable fatigue life of ASME pressure boundary components, with consideration of the light-water reactor (LWR) environment. In so doing, this guide describes a methodology that the NRC staff considers acceptable to support reviews of applications that the agency expects to receive for new nuclear reactor construction permits or operating licenses under 10 CFR part 50, design certifications under 10 CFR part 52, and combined licenses under 10 CFR part 52 that do not reference a standard design. Because of significant conservatism in quantifying other plantrelated variables (such as cyclic behavior, including stress and loading rates) involved in cumulative fatigue life calculations, the design of the current fleet of reactors is satisfactory, and the plants are safe to operate. The ASME Section III design curves, developed in the late 1960s and early 1970s, are based on tests conducted in laboratory air environments at ambient temperatures. The original code developers applied margins of 2 on strain and 20 on cyclic life to account for variations in materials, surface finish, data scatter, and environmental effects (including temperature differences between specimen test conditions and reactor operating experience). However, the developers lacked sufficient data to explicitly evaluate and account for the degradation attributable to exposure to aqueous coolants. More recent fatigue test data from the United States, Japan, and elsewhere show that the LWR environment can have a significant impact on the fatigue life of carbon and low-alloy steels, as well as austenitic stainless steel. Two distinct methods can be used to incorporate LWR environmental effects into the fatigue analysis of ASME Class 1 components. The first method involves developing new fatigue curves that are applicable to LWR environments. Given that the fatigue life of ASME Class 1 components in LWR environments is a function of several parameters, this method would necessitate developing several fatigue curves to address potential parameter variations. An alternative would be to develop a single bounding fatigue curve, which may be overly conservative for most applications. The second method involves using an environmental correction factor (Fen) to account for LWR environments by correcting the fatigue usage calculated with the ASME ‘‘air’’ curves. This method affords the E:\FR\FM\17AUN1.SGM 17AUN1 rwilkins on PROD1PC63 with NOTICES Federal Register / Vol. 71, No. 159 / Thursday, August 17, 2006 / Notices designer greater flexibility to calculate the appropriate impacts for specific environmental parameters. In addition, applicants have already used this method in their license renewal applications. The NRC staff has selected the Fen method, as described in NUREG/CR– 6909, ‘‘Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials.’’ In particular, Appendix A to that report, ‘‘Incorporating Environmental Effects into Fatigue Evaluations,’’ describes a methodology that the staff considers acceptable to incorporate the effects of reactor coolant environments on fatigue usage factor evaluations of metal components. In addition, NUREG/CR– 6909 provides a comprehensive review of, and technical basis for, the methodology proposed in this draft regulatory guide, including analysis of each parameter affecting the fatigue evaluations. The NRC staff is soliciting comments on both Draft Regulatory Guide DG– 1144 and NUREG/CR–6909. Comments may be accompanied by relevant information or supporting data. Please mention DG–1144 and/or NUREG/CR– 6909 in the subject line of your comments. 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. Mail comments to: Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. E-mail comments to: NRCREP@nrc.gov. You may also submit comments via the NRC’s rulemaking Web site at https://ruleforum.llnl.gov. Address questions about our rulemaking Web site to Carol A. Gallagher (301) 415–5905; e-mail CAG@nrc.gov. Hand-deliver comments to: Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on Federal workdays. Fax comments to: Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission at (301) 415–5144. Requests for technical information about Draft Regulatory Guide DG–1144 may be directed to Hipolito J. Gonzalez at (301) 415–0068 or by e-mail to HJG@nrc.gov. VerDate Aug<31>2005 16:36 Aug 16, 2006 Jkt 208001 Comments would be most helpful if received by September 25, 2006. 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 the draft regulatory guide are available through the NRC’s public Web site under Draft Regulatory Guides in the Regulatory Guides document 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 #ML060970173. Electronic copies of NUREG/CR–6909 are available through the NRC’s public Web site at https://www.nrc.gov/readingrm/doc-collections/nuregs/ docs4comment.html. NUREG/CR–6909 is also available through ADAMS (https://www.nrc.gov/reading-rm/ adams.html, under Accession No. ML061650347. In addition, regulatory guides and NUREG-series reports 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@nrc.gov. Requests for single copies of draft or final guides (which may be reproduced) or for placement on an automatic distribution list for single copies of future draft guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, Attention: Reproduction and Distribution Services Section; by e-mail to DISTRIBUTION@nrc.gov; or by fax to (301) 415–2289. Telephone requests cannot be accommodated. Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them. (5 U.S.C. 552(a)) Dated at Rockville, Maryland, this 17th day of July, 2006. PO 00000 Frm 00071 Fmt 4703 Sfmt 4703 47549 For the U.S. Nuclear Regulatory Commission. Mark A. Cunningham, Director, Division of Fuel, Engineering & Radiological Research, Office of Nuclear Regulatory Research. [FR Doc. E6–13560 Filed 8–16–06; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Proposed License Renewal Interim Staff Guidance LR–ISG–2006–03: Staff Guidance for Preparing Severe Accident Mitigation Alternatives (SAMA) Analyses; Solicitation of Public Comment Nuclear Regulatory Commission (NRC). ACTION: Solicitation of public comment. AGENCY: SUMMARY: NRC is soliciting public comment on its Proposed License Renewal Interim Staff Guidance LR– ISG–2006–03 (LR–ISG) for preparing Severe Accident Mitigation Alternatives (SAMA) analyses. This LR–ISG recommends that applicants for license renewal use the Guidance Document NEI 05–01, Rev. A (ADAMS Accession No. ML060530203) when preparing their SAMA analyses. The NRC staff issues LR–ISGs to facilitate timely implementation of the license renewal rule and to review activities associated with a license renewal application. Upon reviewing public comments, the NRC staff will evaluate the comments and make a determination to incorporate the comments, as appropriate. Once the NRC completes the LR–ISG, it will issue the LR–ISG for NRC and industry use. The NRC staff will also incorporate the approved LR– ISG into the next revision of Supplement 1 to Regulatory Guide 4.2, ‘‘Preparation of Supplemental Environmental Reports for Applications to Renew Nuclear Power Plant Operating Licenses.’’ DATES: Comments may be submitted by September 18, 2006. Comments received after this date will be considered, if it is practical to do so, but the Commission is to ensure consideration only for comments received on or before this date. ADDRESSES: Comments may be submitted to: Chief, Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. Comments should be delivered to: 11545 Rockville Pike (first floor), Rockville, Maryland, Room T–6D59, E:\FR\FM\17AUN1.SGM 17AUN1

Agencies

NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 71, Number 159 (Thursday, August 17, 2006)]
[Notices]
[Pages 47548-47549]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-13560]


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

NUCLEAR REGULATORY COMMISSION


Draft Regulatory Guide: Issuance, Availability

    The U.S. Nuclear Regulatory Commission (NRC) has issued for public 
comment a draft of a new guide in the agency's Regulatory Guide Series. 
This series has been developed to describe and make available to the 
public such information as methods that are acceptable to the NRC staff 
for implementing specific parts of the NRC'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.
    The draft regulatory guide, entitled ``Guidelines for Evaluating 
Fatigue Analyses Incorporating the Life Reduction of Metal Components 
Due to the Effects of the Light-Water Reactor Environment for New 
Reactors,'' is temporarily identified by its task number, DG-1144, 
which should be mentioned in all related correspondence. This proposed 
regulatory guide describes a method that the NRC staff considers 
acceptable for use in complying with the agency's regulations in Title 
10, part 50, of the Code of Federal Regulations (10 CFR Part 50), 
``Domestic Licensing of Production and Utilization Facilities.'' 
Specifically, in Appendix A to10 CFR part 50, General Design Criterion 
(GDC) 1, ``Quality Standards and Records,'' requires, in part, that 
structures, systems, and components that are important to safety must 
be designed, fabricated, erected, and tested to quality standards 
commensurate with the importance of the safety function performed. In 
addition, GDC 30, ``Quality of Reactor Coolant Pressure Boundary,'' 
requires, in part, that components that are part of the reactor coolant 
pressure boundary must be designed, fabricated, erected, and tested to 
the highest practical quality standards.
    Augmenting those design criteria, 10 CFR 50.55a, ``Codes and 
Standards,'' endorses the American Society of Mechanical Engineers 
(ASME) Boiler and Pressure Vessel Code for design of safety-related 
systems and components. In particular, Section 50.55a(c), ``Reactor 
Coolant Pressure Boundary,'' requires, in part, that components of the 
reactor coolant pressure boundary must be meet the requirements for 
Class 1 components in Section III, ``Rules for Construction of Nuclear 
Power Plant Components,'' of the ASME Boiler and Pressure Vessel Code. 
Specifically, those Class 1 requirements contain provisions, including 
fatigue design curves, for determining a component's suitability for 
cyclic service. These fatigue design curves are based on strain-
controlled tests performed on small polished specimens, at room 
temperature, in air environments. Thus, these curves do not address the 
impact of the reactor coolant system environment.
    This draft regulatory guide provides guidance for use in 
determining the acceptable fatigue life of ASME pressure boundary 
components, with consideration of the light-water reactor (LWR) 
environment. In so doing, this guide describes a methodology that the 
NRC staff considers acceptable to support reviews of applications that 
the agency expects to receive for new nuclear reactor construction 
permits or operating licenses under 10 CFR part 50, design 
certifications under 10 CFR part 52, and combined licenses under 10 CFR 
part 52 that do not reference a standard design. Because of significant 
conservatism in quantifying other plant-related variables (such as 
cyclic behavior, including stress and loading rates) involved in 
cumulative fatigue life calculations, the design of the current fleet 
of reactors is satisfactory, and the plants are safe to operate.
    The ASME Section III design curves, developed in the late 1960s and 
early 1970s, are based on tests conducted in laboratory air 
environments at ambient temperatures. The original code developers 
applied margins of 2 on strain and 20 on cyclic life to account for 
variations in materials, surface finish, data scatter, and 
environmental effects (including temperature differences between 
specimen test conditions and reactor operating experience). However, 
the developers lacked sufficient data to explicitly evaluate and 
account for the degradation attributable to exposure to aqueous 
coolants. More recent fatigue test data from the United States, Japan, 
and elsewhere show that the LWR environment can have a significant 
impact on the fatigue life of carbon and low-alloy steels, as well as 
austenitic stainless steel.
    Two distinct methods can be used to incorporate LWR environmental 
effects into the fatigue analysis of ASME Class 1 components. The first 
method involves developing new fatigue curves that are applicable to 
LWR environments. Given that the fatigue life of ASME Class 1 
components in LWR environments is a function of several parameters, 
this method would necessitate developing several fatigue curves to 
address potential parameter variations. An alternative would be to 
develop a single bounding fatigue curve, which may be overly 
conservative for most applications. The second method involves using an 
environmental correction factor (Fen) to account for LWR 
environments by correcting the fatigue usage calculated with the ASME 
``air'' curves. This method affords the

[[Page 47549]]

designer greater flexibility to calculate the appropriate impacts for 
specific environmental parameters. In addition, applicants have already 
used this method in their license renewal applications.
    The NRC staff has selected the Fen method, as described 
in NUREG/CR-6909, ``Effect of LWR Coolant Environments on the Fatigue 
Life of Reactor Materials.'' In particular, Appendix A to that report, 
``Incorporating Environmental Effects into Fatigue Evaluations,'' 
describes a methodology that the staff considers acceptable to 
incorporate the effects of reactor coolant environments on fatigue 
usage factor evaluations of metal components. In addition, NUREG/CR-
6909 provides a comprehensive review of, and technical basis for, the 
methodology proposed in this draft regulatory guide, including analysis 
of each parameter affecting the fatigue evaluations.
    The NRC staff is soliciting comments on both Draft Regulatory Guide 
DG-1144 and NUREG/CR-6909. Comments may be accompanied by relevant 
information or supporting data. Please mention DG-1144 and/or NUREG/CR-
6909 in the subject line of your comments. 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.
    Mail comments to: Rules and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.
    E-mail comments to: NRCREP@nrc.gov. You may also submit comments 
via the NRC's rulemaking Web site at https://ruleforum.llnl.gov. Address 
questions about our rulemaking Web site to Carol A. Gallagher (301) 
415-5905; e-mail CAG@nrc.gov.
    Hand-deliver comments to: Rules and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission, 11555 Rockville 
Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on 
Federal workdays.
    Fax comments to: Rules and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission at (301) 415-5144.
    Requests for technical information about Draft Regulatory Guide DG-
1144 may be directed to Hipolito J. Gonzalez at (301) 415-0068 or by e-
mail to HJG@nrc.gov.
    Comments would be most helpful if received by September 25, 2006. 
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 the draft regulatory guide are available 
through the NRC's public Web site under Draft Regulatory Guides in the 
Regulatory Guides document collection of the NRC's Electronic Reading 
Room at https://www.nrc.gov/reading-rm/doc-collections/. Electronic 
copies are also available in ADAMS (https://www.nrc.gov/reading-rm/
adams.html), under Accession ML060970173.
    Electronic copies of NUREG/CR-6909 are available through the NRC's 
public Web site at https://www.nrc.gov/reading-rm/doc-collections/
nuregs/docs4comment.html. NUREG/CR-6909 is also available through 
ADAMS (https://www.nrc.gov/reading-rm/adams.html, under Accession No. 
ML061650347.
    In addition, regulatory guides and NUREG-series reports 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@nrc.gov. Requests for 
single copies of draft or final guides (which may be reproduced) or for 
placement on an automatic distribution list for single copies of future 
draft guides in specific divisions should be made in writing to the 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, 
Attention: Reproduction and Distribution Services Section; by e-mail to 
DISTRIBUTION@nrc.gov; or by fax to (301) 415-2289. Telephone requests 
cannot be accommodated.
    Regulatory guides are not copyrighted, and Commission approval is 
not required to reproduce them.

(5 U.S.C. 552(a))

    Dated at Rockville, Maryland, this 17th day of July, 2006.

    For the U.S. Nuclear Regulatory Commission.
Mark A. Cunningham,
Director, Division of Fuel, Engineering & Radiological Research, Office 
of Nuclear Regulatory Research.
 [FR Doc. E6-13560 Filed 8-16-06; 8:45 am]
BILLING CODE 7590-01-P

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