83 FR 48471 - Regulatory Guidance and Technical Basis on the Alternate Pressurized Thermal Shock Rule
NUCLEAR REGULATORY COMMISSION Federal Register Volume 83, Issue 186 (September 25, 2018)
Federal Register Volume 83, Issue 186 (September 25, 2018)
| Page Range | 48471-48472 | |
| FR Document | 2018-20827 |
[Federal Register Volume 83, Number 186 (Tuesday, September 25, 2018)] [Notices] [Pages 48471-48472] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2018-20827] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION RIN 3150-AI01 [NRC-2014-0137] Regulatory Guidance and Technical Basis on the Alternate Pressurized Thermal Shock Rule AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 0 to Regulatory Guide (RG) 1.230, ``Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule'' and the associated technical basis, NUREG-2163, ``Technical Basis for Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule.'' This guidance describes a method that the NRC staff considers acceptable to permit use of the alternate fracture toughness requirements for protection against pressurized thermal shock events for pressurized water reactor pressure vessels. DATES: Revision 0 to RG 1.230 is available on September 25, 2018. ADDRESSES: Please refer to Docket ID NRC-2014-0137 when contacting the NRC about the availability of information regarding this document. You may obtain publically-available information related to this document, using the following methods:Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0137. Address questions about docket IDs in Regulations.gov to Jennifer Borges; telephone: 301-287-9127; email: [email protected]. For technical questions, contact the individuals 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 Document collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, 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 [email protected]. The ADAMS accession number for each document referenced in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced. Revision 0 to Regulatory Guide 1.230, and the regulatory analysis may be found in ADAMS under Accession No. ML15344A402 and ML14056A013 respectively. Revision 0 to NUREG-2163 may be found in ADAMS under Accession No. ML18255A118. 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. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. FOR FURTHER INFORMATION CONTACT: Mark Kirk, Office of Nuclear Regulatory Research, telephone: 301-415-2456, email: [email protected], and Stephen Burton, Office of Nuclear Regulatory Research, telephone: 301-415-7000, email: [email protected]. Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. SUPPLEMENTARY INFORMATION: I. Introduction The NRC is issuing a new guide in the NRC's ``Regulatory Guide'' series. This series was developed to describe and make available to the public information regarding methods that are acceptable to the NRC staff for implementing specific parts of the agency's regulations, techniques that the NRC staff uses in evaluating specific issues or postulated events, and data that the NRC staff needs in its review of applications for permits and licenses. Revision 0 of RG 1.230 was issued with a temporary identification of Draft Regulatory Guide, DG-1299. This RG is being issued to describe a method that the staff of the NRC considers acceptable to meet the alternate fracture toughness requirements for protection against pressurized thermal shock (PTS) events for pressurized water reactor (PWR) reactor pressure vessels (RPVs) in section 50.61a of title 10 of the Code of Federal Regulations (10 CFR), ``Alternate Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events.'' The alternate PTS requirements are based on updated analysis methods, whereas the requirements in 10 CFR 50.61, ``Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events,'' are based on overly conservative probabilistic fracture mechanics analyses. NUREG-2163 explains the basis for the requirements that establish the threshold conditions to permit use of 10 CFR 50.61a in lieu of 10 CFR 50.61 and describes methods by which the following four requirements can be met: (1) Criteria relating to the date of construction and design requirements, (2) criteria relating to evaluation of plant specific surveillance data, (3) criteria relating to inservice inspection data and non-destructive examination requirements, and (4) criteria relating to alternate limits on embrittlement. Revision 0 of RG 1.230 also describes these methods in a manner consistent with NUREG-2163. II. Additional Information The DG-1299 and draft NUREG-2163 were published in the Federal Register on March 13, 2015 (80 FR 13449) for a 60-day public comment period. The public comment period closed on May 12, 2015. Public comments on DG-1299 and draft NUREG-2163 and the NRC staff responses to the public comments are available in ADAMS under Accession No. ML15344A398. III. Congressional Review Act RG 1.230 is a rule as defined in the Congressional Review Act (5 U.S.C. 801-808). However, the Office of Management and Budget has not found it to be a major rule as defined in the Congressional Review Act. IV. Backfitting and Issue Finality The RG 1.230 provides guidance on the methods acceptable to the NRC for complying with the NRC's regulations associated with alternate fracture toughness requirements for protection against PTS events for PWR RPVs. NUREG-2163 provides technical bases that support the RG. The RG, like the alternate PTS requirements of 10 CFR 50.61a, applies to holders of operating licenses for a PWR whose construction permit was issued before February 3, 2010. Issuance of this RG and NUREG does not constitute backfitting under 10 CFR part 50. As discussed in the ``Implementation'' section of RG 1.230, the NRC has no current intention to impose the RG on current holders of 10 [[Page 48472]] CFR part 50 operating licenses. Also, this RG is the first guidance issued for the 10 CFR 50.61a final rule, which itself was an alternative to 10 CFR 50.61 and therefore not a backfit on current licensees (75 FR 1322; January 4, 2010). The first issuance of guidance on a newly-added rule does not constitute backfitting when, as here, the guidance is consistent with the regulatory requirements in the newly-added rule, and the backfitting considerations applicable to the newly-added rule apply to this guidance. Therefore, issuance of RG 1.230 does not constitute backfitting within the definition provided in 10 CFR 50.109(a)(1). Dated at Rockville, Maryland, this 20th day of September 2018. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2018-20827 Filed 9-24-18; 8:45 am] BILLING CODE 7590-01-P
![Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices 48471
Members of the public may request to (ADAMS): You may obtain publicly- Requirements for Protection against
receive this information electronically. available documents online in the Pressurized Thermal Shock Events.’’
If you would like to be added to the ADAMS Public Document collection at The alternate PTS requirements are
distribution, please contact the Nuclear http://www.nrc.gov/reading-rm/ based on updated analysis methods,
Regulatory Commission, Office of the adams.html. To begin the search, select whereas the requirements in 10 CFR
Secretary, Washington, DC 20555 (301– ‘‘Begin Web-based ADAMS Search.’’ For 50.61, ‘‘Fracture Toughness
415–1969), or you may email problems with ADAMS, please contact Requirements for Protection against
Patricia.Jimenez@nrc.gov or the NRC’s Public Document Room (PDR) Pressurized Thermal Shock Events,’’ are
Wendy.Moore@nrc.gov. reference staff at 1–800–397–4209, 301– based on overly conservative
Dated at Rockville, Maryland, this 20th day 415–4737, or by email to pdr.resource@ probabilistic fracture mechanics
of September, 2018. nrc.gov. The ADAMS accession number analyses.
For the Nuclear Regulatory Commission. for each document referenced in this NUREG–2163 explains the basis for
Denise L. McGovern, notice (if that document is available in the requirements that establish the
Policy Coordinator, Office of the Secretary. ADAMS) is provided the first time that threshold conditions to permit use of 10
a document is referenced. Revision 0 to CFR 50.61a in lieu of 10 CFR 50.61 and
[FR Doc. 2018–20888 Filed 9–21–18; 11:15 am]
Regulatory Guide 1.230, and the describes methods by which the
BILLING CODE 7590–01–P
regulatory analysis may be found in following four requirements can be met:
ADAMS under Accession No. (1) Criteria relating to the date of
NUCLEAR REGULATORY ML15344A402 and ML14056A013 construction and design requirements,
COMMISSION respectively. Revision 0 to NUREG– (2) criteria relating to evaluation of plant
2163 may be found in ADAMS under specific surveillance data, (3) criteria
RIN 3150–AI01 Accession No. ML18255A118. relating to inservice inspection data and
[NRC–2014–0137] • NRC’s PDR: You may examine and non-destructive examination
purchase copies of public documents at requirements, and (4) criteria relating to
Regulatory Guidance and Technical the NRC’s PDR, Room O1–F21, One alternate limits on embrittlement.
Basis on the Alternate Pressurized White Flint North, 11555 Rockville Revision 0 of RG 1.230 also describes
Thermal Shock Rule Pike, Rockville, Maryland 20852. these methods in a manner consistent
Regulatory guides are not with NUREG–2163.
AGENCY: Nuclear Regulatory copyrighted, and NRC approval is not
Commission. II. Additional Information
required to reproduce them.
ACTION: Regulatory guide; issuance. The DG–1299 and draft NUREG–2163
FOR FURTHER INFORMATION CONTACT:
Mark Kirk, Office of Nuclear Regulatory were published in the Federal Register
SUMMARY: The U.S. Nuclear Regulatory
Research, telephone: 301–415–2456, on March 13, 2015 (80 FR 13449) for a
Commission (NRC) is issuing Revision 0
email: Mark.Kirk@nrc.gov, and Stephen 60-day public comment period. The
to Regulatory Guide (RG) 1.230,
Burton, Office of Nuclear Regulatory public comment period closed on May
‘‘Regulatory Guidance on the Alternate
Research, telephone: 301–415–7000, 12, 2015. Public comments on DG–1299
Pressurized Thermal Shock Rule’’ and
email: Stephen.Burton@nrc.gov. Both and draft NUREG–2163 and the NRC
the associated technical basis, NUREG–
are staff of the U.S. Nuclear Regulatory staff responses to the public comments
2163, ‘‘Technical Basis for Regulatory
Commission, Washington, DC 20555– are available in ADAMS under
Guidance on the Alternate Pressurized
Thermal Shock Rule.’’ This guidance 0001. Accession No. ML15344A398.
describes a method that the NRC staff SUPPLEMENTARY INFORMATION: III. Congressional Review Act
considers acceptable to permit use of RG 1.230 is a rule as defined in the
the alternate fracture toughness I. Introduction
Congressional Review Act (5 U.S.C.
requirements for protection against The NRC is issuing a new guide in the 801–808). However, the Office of
pressurized thermal shock events for NRC’s ‘‘Regulatory Guide’’ series. This Management and Budget has not found
pressurized water reactor pressure series was developed to describe and it to be a major rule as defined in the
vessels. make available to the public information Congressional Review Act.
DATES: Revision 0 to RG 1.230 is regarding methods that are acceptable to
available on September 25, 2018. the NRC staff for implementing specific IV. Backfitting and Issue Finality
ADDRESSES: Please refer to Docket ID parts of the agency’s regulations, The RG 1.230 provides guidance on
NRC–2014–0137 when contacting the techniques that the NRC staff uses in the methods acceptable to the NRC for
NRC about the availability of evaluating specific issues or postulated complying with the NRC’s regulations
information regarding this document. events, and data that the NRC staff associated with alternate fracture
You may obtain publically-available needs in its review of applications for toughness requirements for protection
information related to this document, permits and licenses. against PTS events for PWR RPVs.
using the following methods: Revision 0 of RG 1.230 was issued NUREG–2163 provides technical bases
• Federal Rulemaking Website: Go to with a temporary identification of Draft that support the RG. The RG, like the
http://www.regulations.gov and search Regulatory Guide, DG–1299. This RG is alternate PTS requirements of 10 CFR
for Docket ID NRC–2014–0137. Address being issued to describe a method that 50.61a, applies to holders of operating
questions about docket IDs in the staff of the NRC considers licenses for a PWR whose construction
Regulations.gov to Jennifer Borges; acceptable to meet the alternate fracture permit was issued before February 3,
daltland on DSKBBV9HB2PROD with NOTICES
telephone: 301–287–9127; email: toughness requirements for protection 2010.
Jennifer.Borges@nrc.gov. For technical against pressurized thermal shock (PTS) Issuance of this RG and NUREG does
questions, contact the individuals listed events for pressurized water reactor not constitute backfitting under 10 CFR
in the FOR FURTHER INFORMATION (PWR) reactor pressure vessels (RPVs) in part 50. As discussed in the
CONTACT section of this document. section 50.61a of title 10 of the Code of ‘‘Implementation’’ section of RG 1.230,
• NRC’s Agencywide Documents Federal Regulations (10 CFR), the NRC has no current intention to
Access and Management System ‘‘Alternate Fracture Toughness impose the RG on current holders of 10
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![48472 Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices
CFR part 50 operating licenses. Also, telephone: 301–287–9127; email: charge by contacting NRC’s Clearance
this RG is the first guidance issued for Jennifer.Borges@nrc.gov. For technical Officer, David Cullison, Office of the
the 10 CFR 50.61a final rule, which questions, contact the individual listed Chief Information Officer, U.S. Nuclear
itself was an alternative to 10 CFR 50.61 in the FOR FURTHER INFORMATION Regulatory Commission, Washington,
and therefore not a backfit on current CONTACT section of this document. DC 20555–0001; telephone: 301–415–
licensees (75 FR 1322; January 4, 2010). • Mail comments to: David Cullison, 2084; email: Infocollects.Resource@
The first issuance of guidance on a Office of the Chief Information Officer, nrc.gov.
newly-added rule does not constitute Mail Stop: O–1 F13, U.S. Nuclear
Regulatory Commission, Washington, B. Submitting Comments
backfitting when, as here, the guidance
is consistent with the regulatory DC 20555–0001. Please include Docket ID NRC–2017–
requirements in the newly-added rule, For additional direction on obtaining 0060 in the subject line of your
and the backfitting considerations information and submitting comments, comment submission, in order to ensure
applicable to the newly-added rule see ‘‘Obtaining Information and that the NRC is able to make your
apply to this guidance. Therefore, Submitting Comments’’ in the comment submission available to the
issuance of RG 1.230 does not constitute SUPPLEMENTARY INFORMATION section of public in this docket.
backfitting within the definition this document. The NRC cautions you not to include
provided in 10 CFR 50.109(a)(1). FOR FURTHER INFORMATION CONTACT: identifying or contact information in
Dated at Rockville, Maryland, this 20th day David Cullison, Office of the Chief comment submissions that you do not
of September 2018. Information Officer, Mail Stop: O–1 F13, want to be publicly disclosed in your
For the Nuclear Regulatory Commission. U.S. Nuclear Regulatory Commission, comment submission. The NRC will
Thomas H. Boyce,
Washington, DC 20555–0001; telephone: post all comment submissions at http://
301–415–2084; email: www.regulations.gov as well as enter the
Chief, Regulatory Guidance and Generic
Issues Branch, Division of Engineering, Office
Infocollects.Resource@nrc.gov. comment submissions into ADAMS,
of Nuclear Regulatory Research. SUPPLEMENTARY INFORMATION: and the NRC does not routinely edit
[FR Doc. 2018–20827 Filed 9–24–18; 8:45 am]
comment submissions to remove
I. Obtaining Information and identifying or contact information.
BILLING CODE 7590–01–P Submitting Comments If you are requesting or aggregating
A. Obtaining Information comments from other persons for
NUCLEAR REGULATORY Please refer to Docket ID NRC–2017– submission to the NRC, then you should
COMMISSION 0060 when contacting the NRC about inform those persons not to include
the availability of information for this identifying or contact information that
[NRC–2017–0060] they do not want to be publicly
action. You may obtain publicly-
available information related to this disclosed in their comment submission.
Information Collection: NRC Form 361, Your request should state that the NRC
Reactor Plant Event Notification action by any of the following methods:
• Federal Rulemaking website: Go to does not routinely edit comment
Worksheet; NRC Form 361A, Fuel submissions to remove such information
Cycle and Materials Event Notification http://www.regulations.gov and search
Docket ID NRC–2017–0060. A copy of before making the comment
Worksheet; NRC Form 361N, Non- submissions available to the public or
Power Reactor Event Notification the collection of information and related
instructions may be obtained without entering the comment into ADAMS.
Worksheet
charge by accessing Docket ID NRC– II. Background
AGENCY: Nuclear Regulatory 2017–0060 on this website.
Commission. • NRC’s Agencywide Documents In accordance with the Paperwork
ACTION: Proposed information Access and Management System Reduction Act of 1995 (44 U.S.C.
collection; request for comment. (ADAMS): You may obtain publicly- Chapter 35), the NRC is requesting
available documents online in the public comment on its intention to
SUMMARY: The U.S. Nuclear Regulatory ADAMS Public Documents collection at request the OMB’s approval for the
Commission (NRC) invites public http://www.nrc.gov/reading-rm/ information collection summarized
comment on this proposed collection of adams.html. To begin the search, select below.
information. The information collection ‘‘Begin Web-based ADAMS Search.’’ For 1. The title of the information
is entitled, ‘‘NRC Form 361, Reactor problems with ADAMS, please contact collection: ‘‘NRC Form 361, Reactor
Plant Event Notification Worksheet; the NRC’s Public Document Room (PDR) Plant Event Notification Worksheet;
NRC Form 361A, Fuel Cycle and reference staff at 1–800–397–4209, 301– NRC Form 361A, Fuel Cycle and
Materials Event Notification Worksheet; 415–4737, or by email to pdr.resource@ Materials Event Notification Worksheet;
NRC Form 361N, Non-Power Reactor nrc.gov. A copy of the collection of NRC Form 361N, Non-Power Reactor
Event Notification Worksheet.’’ information and related instructions Event Notification Worksheet.’’
DATES: Submit comments by November may be obtained without charge by 2. OMB approval number: 3150–
26, 2018. Comments received after this accessing ADAMS Accession No. XXXX.
date will be considered if it is practical ML18038A512. The supporting 3. Type of submission: New.
to do so, but the Commission is able to statement is available in ADAMS under 4. The form number, if applicable:
ensure consideration only for comments Accession No. ML18038A511. NRC Form 361, NRC Form 361A, NRC
received on or before this date. • NRC’s PDR: You may examine and Form 361N.
daltland on DSKBBV9HB2PROD with NOTICES
ADDRESSES: You may submit comments purchase copies of public documents at 5. How often the collection is required
by any of the following methods: the NRC’s PDR, Room O1–F21, One or requested: On occasion, as defined
• Federal Rulemaking website: Go to White Flint North, 11555 Rockville NRC licensee events are reportable
http://www.regulations.gov and search Pike, Rockville, Maryland 20852. when they occur.
for Docket ID NRC–2017–0060. Address • NRC’s Clearance Officer: A copy of 6. Who will be required or asked to
questions about docket IDs in the collection of information and related respond: Holders of NRC licenses for
Regulations.gov to Jennifer Borges; instructions may be obtained without commercial nuclear power plants, fuel
VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 PO 00000 Frm 00064 Fmt 4703 Sfmt 4703 E:\FR\FM\25SEN1.SGM 25SEN1](https://thefederalregister.org/doc/83_FR_48657/page/2.svg)
Document Created: 2018-09-25 00:22:20
Document Modified: 2018-09-25 00:22:20
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Regulatory guide; issuance. | |
| Dates | Revision 0 to RG 1.230 is available on September 25, 2018. | |
| Contact | Mark Kirk, Office of Nuclear Regulatory Research, telephone: 301-415-2456, email: [email protected], and Stephen Burton, Office of Nuclear Regulatory Research, telephone: 301-415-7000, email: [email protected] Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. | |
| FR Citation | 83 FR 48471 | |
| RIN Number | 3150-AI01 |
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