81 FR 60029 - Instrumentation and Controls Guidance
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 169 (August 31, 2016)
Federal Register Volume 81, Issue 169 (August 31, 2016)
| Page Range | 60029-60030 | |
| FR Document | 2016-20873 |
[Federal Register Volume 81, Number 169 (Wednesday, August 31, 2016)] [Notices] [Pages 60029-60030] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-20873] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2015-0211] Instrumentation and Controls Guidance AGENCY: Nuclear Regulatory Commission. ACTION: Standard review plan-final section revision; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a final revision to Chapter 7, ``Instrumentation and Controls,'' of NUREG-0800, ``Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition.'' DATES: The effective date of this SRP update is September 30, 2016. ADDRESSES: Please refer to Docket ID NRC-2015-0211 when contacting the NRC about the availability of information regarding this document. You may access publicly-available information related to this document using any of the following methods:Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0211. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; 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 Documents collection at http://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 [email protected]. For the convenience of the reader, the ADAMS accession numbers are provided in a table in the ``Availability of Documents'' section of this document. 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. FOR FURTHER INFORMATION CONTACT: Carolyn Lauron, telephone: 301-415- 2736; email: [email protected] or Mark Notich, telephone: 301-415- 3053; email: [email protected]; both are staff of the Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555- 0001. SUPPLEMENTARY INFORMATION: I. Background On September 16, 2015 (80 FR 55654), the NRC published for public comment the proposed revisions to Chapter 7 of the SRP. The NRC made no changes to the proposed revisions after the consideration of comments received. A summary of the comments and the NRC staff's disposition of the comments are available in a separate document, ``Response to Public Comments on Draft SRP Sections in Chapter 7.'' The Office of New Reactors and the Office of Nuclear Reactor Regulation are revising these sections from their current versions. Details of specific changes in the proposed revisions are included at the end of each of the proposed sections. The changes to this SRP chapter reflect current NRC staff's review methods and practices based on lessons learned from the NRC's reviews of design certification and combined license applications completed since the last revision of this chapter. II. Backfitting and Finality Provisions Issuance of these revised SRP sections does not constitute backfitting as defined in Sec. 50.109 of title 10 of the Code of Federal Regulations (10 CFR), ``Backfitting,'' (the Backfit Rule) and is not inconsistent with the issue finality provisions in 10 CFR part 52. The NRC's position is based upon the following considerations: 1. The SRP positions do not constitute backfitting, inasmuch as the SRP is internal guidance directed at the NRC staff with respect to their regulatory responsibilities. The SRP provides guidance to the staff on how to review an application for the NRC's regulatory approval in the form of licensing. Changes in internal staff guidance are not matters for which either nuclear power plant applicants or licensees are protected under either the Backfit Rule or the issue finality provisions of 10 CFR part 52. 2. The NRC staff has no intention to impose the SRP positions on current licensees and regulatory approvals either now or in the future. The staff does not intend to impose or apply the positions described in the SRP to existing (already issued) licenses and regulatory approvals. Therefore, the issuance of a final SRP--even if considered guidance that is within the [[Page 60030]] purview of the issue finality provisions in 10 CFR part 52--need not be evaluated as if it were a backfit or as being inconsistent with issue finality provisions. If, in the future, the staff seeks to impose a position in the SRP on holders of already issued licenses in a manner which 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. 3. Backfitting and issue finality do not--with limited exceptions not applicable here--protect current or future applicants. Applicants and potential applicants are not, with certain exceptions, protected by either the Backfit Rule or any issue finality provisions under 10 CFR part 52. This is because neither the Backfit Rule nor the issue finality provisions under 10 CFR part 52--with certain exclusions discussed in the next paragraph--were intended to apply to every NRC action which substantially changes the expectations of current and future applicants. The exceptions to the general principle are applicable whenever an applicant references a 10 CFR part 52 license (e.g., an early site permit) and/or NRC regulatory approval (e.g., a design certification rule) with specified issue finality provisions. The staff does not, at this time, intend to impose the positions represented in the SRP in a manner that is inconsistent with any issue finality provisions. If, in the future, the staff seeks to impose a position in the SRP in a manner which 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. III. Congressional Review Act This action 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. Availability of Documents The documents identified in the following table are available to interested persons. ------------------------------------------------------------------------ ADAMS Document accession No. ------------------------------------------------------------------------ Summary of Comments and NRC Staff Disposition of ML16050A366 Comments--Response to Public Comments on Draft SRP Sections in Chapter 7.................................. SRP 7.0, ``Instrumentation and Controls--Overview of ML16020A049 Review Process,'' Revision 7........................... SRP 7.1, ``Instrumentation and Controls--Introduction,'' ML16020A050 Revision 6............................................. Table 7-1, ``Table 7-1 Regulatory Requirements, ML16020A103 Acceptance Criteria, and Guidelines for Instrumentation and Control Systems Important to Safety,'' Revision 6.. SRP 7.2, ``Reactor Trip System,'' Revision 6............ ML16020A059 SRP 7.3, ``Engineered Safety Features Systems,'' ML16020A082 Revision 6............................................. SRP 7.4, ``Safe Shutdown Systems,'' Revision 6.......... ML16020A086 SRP 7.5, ``Information Systems Important to Safety,'' ML16020A088 Revision 6............................................. SRP 7.6, ``Interlock Systems Important to Safety,'' ML16020A092 Revision 6............................................. SRP 7.7, ``Control Systems,'' Revision 6................ ML16020A095 SRP 7.8, ``Diverse Instrumentation and Control ML16020A096 Systems,'' Revision 6.................................. SRP 7.9, ``Data Communication Systems,'' Revision 6..... ML16020A097 App. 7.0-A, ``Review Process for Digital Instrumentation ML16019A085 and Control Systems,'' Revision 6...................... App. 7.1-A, ``Acceptance Criteria and Guidelines for ML16019A088 Instrumentation and Controls Systems Important to Safety,'' Revision 6................................... App. 7.1-B, ``Guidance for Evaluation of Conformance to ML16019A091 IEEE Std 279,'' Revision 6............................. App. 7.1-C, ``Guidance for Evaluation of Conformance to ML16019A107 IEEE Std 603,'' Revision 6............................. App. 7.1-D, ``Guidance for Evaluation of the Application ML16019A114 of IEEE Std 7-4.3.2,'' Revision 1...................... BTP 7-1, ``Guidance on Isolation of Low-Pressure Systems ML16019A127 from the High-Pressure Reactor Coolant System,'' Revision 6............................................. BTP 7-2, ``Guidance on Requirements of Motor-Operated ML16019A299 Valves in the Emergency Core Cooling System Accumulator Lines,'' Revision 6.................................... BTP 7-3, ``Guidance on Protection System Trip Point ML16019A358 Changes for Operation with Reactor Coolant Pumps Out of Service,'' Revision 6.................................. BTP 7-4, ``Guidance on Design Criteria for Auxiliary ML16020A028 Feedwater Systems,'' Revision 6........................ BTP 7-5, ``Guidance on Spurious Withdrawals of Single ML16020A033 Control Rods in Pressurized Water Reactors,'' Revision 6...................................................... BTP 7-6, ``Guidance on Design of Instrumentation and ML16011A106 Controls Provided to Accomplish Changeover from Injection to Recirculation Mode,'' Revision 6.......... BTP 7-8, ``Guidance for Application of Regulatory Guide ML16020A044 1.22,'' Revision 6..................................... BTP 7-9, ``Guidance on Requirements for Reactor ML16011A062 Protection System Anticipatory Trips,'' Revision 6..... BTP 7-10, ``Guidance on Application of Regulatory Guide ML16019A169 1.97,'' Revision 6..................................... BTP 7-11, ``Guidance on Application and Qualification of ML16019A184 Isolation Devices,'' Revision 6........................ BTP 7-12, ``Guidance on Establishing and Maintaining ML16019A200 Instrument Setpoints,'' Revision 6..................... BTP 7-13, ``Guidance on Cross-Calibration of Protection ML16019A240 System Resistance Temperature Detectors,'' Revision 6.. BTP 7-14, ``Guidance on Software Reviews for Digital ML16019A308 Computer-Based Instrumentation and Control Systems,'' Revision 6............................................. BTP 7-17, ``Guidance on Self-Test and Surveillance Test ML16019A316 Provisions,'' Revision 6............................... BTP 7-18, ``Guidance on the Use of Programmable Logic ML16019A327 Controllers in Digital Computer-Based Instrumentation and Control Systems,'' Revision 6...................... BTP 7-19, ``Guidance for Evaluation of Diversity and ML16019A344 Defense-in-Depth in Digital Computer-Based Instrumentation and Control Systems,'' Revision 7...... BTP 7-21, ``Guidance on Digital Computer Real-Time ML16020A036 Performance,'' Revision 6.............................. ------------------------------------------------------------------------ * No changes resulting from public comments. See documents in the package at ADAMS Accession No. ML16008B013 to see changes made since the last proposed revision. Dated at Rockville, Maryland, this 25th day of August, 2016. For the Nuclear Regulatory Commission. Joseph Colaccino, Chief, New Reactor Rulemaking and Guidance Branch, Division of Engineering Infrastructure and Advanced Reactors, Office of New Reactors. [FR Doc. 2016-20873 Filed 8-30-16; 8:45 am] BILLING CODE 7590-01-P
![Federal Register / Vol. 81, No. 169 / Wednesday, August 31, 2016 / Notices 60029
of the Chief Financial Officer). Similarly, it Meetings & Involvement’’ page at http:// 2736; email: Carolyn.Lauron@nrc.gov or
does not apply to ‘‘government-to- www.nrc.gov/public-involve.html. Mark Notich, telephone: 301–415–3053;
government’’ meetings: Meetings between [FR Doc. 2016–20946 Filed 8–30–16; 8:45 am] email: Mark.Notich@nrc.gov; both are
NRC staff and representatives of State staff of the Office of New Reactors, U.S.
BILLING CODE 7590–01–P
governments, including Agreement State Nuclear Regulatory Commission,
representatives, relating to NRC Agreement
Washington, DC 20555–0001.
State activities or to State regulatory actions
NUCLEAR REGULATORY SUPPLEMENTARY INFORMATION:
or to other matters of general interest to the
State or to the Commission, as well as COMMISSION
I. Background
meetings between NRC staff and [NRC–2015–0211]
representatives of local or Tribal On September 16, 2015 (80 FR 55654),
governments. Also, the policy does not apply Instrumentation and Controls the NRC published for public comment
to or supersede any existing law, rule or Guidance the proposed revisions to Chapter 7 of
regulation that addresses public attendance the SRP. The NRC made no changes to
at a specific type of meeting. For example, AGENCY: Nuclear Regulatory the proposed revisions after the
part 7 of Title 10 of the Code of Federal Commission. consideration of comments received. A
Regulations (10 CFR), ‘‘Advisory ACTION: Standard review plan-final summary of the comments and the NRC
Committees,’’ and 10 CFR part 9, ‘‘Public section revision; issuance. staff’s disposition of the comments are
Records,’’ will continue to be applicable to
advisory committee meetings and SUMMARY: The U.S. Nuclear Regulatory available in a separate document,
Commission meetings, respectively. Commission (NRC) is issuing a final ‘‘Response to Public Comments on Draft
5. This policy does not cover the hearings revision to Chapter 7, ‘‘Instrumentation SRP Sections in Chapter 7.’’
associated with adjudicatory proceedings The Office of New Reactors and the
and Controls,’’ of NUREG–0800,
under the Commission’s Rules of Practice Office of Nuclear Reactor Regulation are
‘‘Standard Review Plan (SRP) for the
and Procedure set forth in 10 CFR part 2. The revising these sections from their
term ‘‘hearings’’ relates primarily to
Review of Safety Analysis Reports for
current versions. Details of specific
Commission adjudicatory proceedings on Nuclear Power Plants: LWR Edition.’’
changes in the proposed revisions are
various types of license applications and DATES: The effective date of this SRP
included at the end of each of the
licensing actions (e.g., applications for initial update is September 30, 2016. proposed sections.
issuance of a license, amendment of an ADDRESSES: Please refer to Docket ID The changes to this SRP chapter
existing license, renewal of a license) or to NRC–2015–0211 when contacting the reflect current NRC staff’s review
enforcement actions involving the imposition NRC about the availability of
of civil penalties or orders to modify, methods and practices based on lessons
information regarding this document. learned from the NRC’s reviews of
suspend, or revoke a license or take other
appropriate action. Specific requirements
You may access publicly-available design certification and combined
regarding participation in and the conduct of information related to this document license applications completed since the
adjudicatory proceedings (including the using any of the following methods: last revision of this chapter.
settlement of such proceedings) are provided • Federal Rulemaking Web site: Go to
in the Commission’s Rules of Practice and http://www.regulations.gov and search II. Backfitting and Finality Provisions
Procedure set forth in 10 CFR part 2. This for Docket ID NRC–2015–0211. Address Issuance of these revised SRP sections
policy does not cover meetings concerning questions about NRC dockets to Carol does not constitute backfitting as
the settlement of enforcement matters. Gallagher; telephone: 301–415–3463; defined in § 50.109 of title 10 of the
6. Certain meetings that would normally be email: Carol.Gallagher@nrc.gov. For Code of Federal Regulations (10 CFR),
closed under section F.3.a. or F.3.b. above technical questions, contact the ‘‘Backfitting,’’ (the Backfit Rule) and is
may be opened to cleared members of the individuals listed in the FOR FURTHER
public who also have a need-to-know. A not inconsistent with the issue finality
INFORMATION CONTACT section of this provisions in 10 CFR part 52. The NRC’s
cleared member of the public is a person who
document. position is based upon the following
holds a U.S. Government security clearance
• NRC’s Agencywide Documents considerations:
or has been granted access to Safeguards
Information in accordance with 10 CFR Access and Management System 1. The SRP positions do not constitute
73.22(b). (ADAMS): You may obtain publicly- backfitting, inasmuch as the SRP is
7. This policy may be applicable to only available documents online in the internal guidance directed at the NRC
part of a meeting. For example, an NRC ADAMS Public Documents collection at staff with respect to their regulatory
meeting may have a portion that is open to http://www.nrc.gov/reading-rm/ responsibilities.
the public and a portion that is closed to the adams.html. To begin the search, select The SRP provides guidance to the
public due to any of the exceptions listed ‘‘ADAMS Public Documents’’ and then staff on how to review an application for
above. In these cases, this policy statement is select ‘‘Begin Web-based ADAMS the NRC’s regulatory approval in the
applicable to the public portion of the Search.’’ For problems with ADAMS,
meeting only. form of licensing. Changes in internal
please contact the NRC’s Public staff guidance are not matters for which
8. This policy is a matter of NRC
discretion; the NRC reserves the right to Document Room (PDR) reference staff at either nuclear power plant applicants or
depart from any stated conditions as 1–800–397–4209, 301–415–4737, or by licensees are protected under either the
circumstances may warrant. email to pdr.resource@nrc.gov. For the Backfit Rule or the issue finality
convenience of the reader, the ADAMS provisions of 10 CFR part 52.
G. Contact accession numbers are provided in a 2. The NRC staff has no intention to
The primary point of contact in the agency table in the ‘‘Availability of Documents’’ impose the SRP positions on current
for general issues related to this policy will section of this document. licensees and regulatory approvals
mstockstill on DSK3G9T082PROD with NOTICES
be the Deputy Assistant for Operations, • NRC’s PDR: You may examine and either now or in the future.
Office of the Executive Director for purchase copies of public documents at
Operations. The Office of Public Affairs is
The staff does not intend to impose or
the NRC’s PDR, Room O1–F21, One apply the positions described in the SRP
also available to receive questions and
suggestions. There are also opportunities for White Flint North, 11555 Rockville to existing (already issued) licenses and
comment on our public participation Pike, Rockville, Maryland 20852. regulatory approvals. Therefore, the
policies, or on many of our programs through FOR FURTHER INFORMATION CONTACT: issuance of a final SRP—even if
the NRC’s Web site under the ‘‘Public Carolyn Lauron, telephone: 301–415– considered guidance that is within the
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![60030 Federal Register / Vol. 81, No. 169 / Wednesday, August 31, 2016 / Notices
purview of the issue finality provisions ADAMS ADAMS
Document Document
in 10 CFR part 52—need not be accession No. accession No.
evaluated as if it were a backfit or as
Summary of Comments and BTP 7–5, ‘‘Guidance on Spu-
being inconsistent with issue finality NRC Staff Disposition of rious Withdrawals of Sin-
provisions. If, in the future, the staff Comments—Response to gle Control Rods in Pres-
seeks to impose a position in the SRP on Public Comments on Draft surized Water Reactors,’’
SRP Sections in Chapter 7 ML16050A366 Revision 6 ......................... ML16020A033
holders of already issued licenses in a SRP 7.0, ‘‘Instrumentation BTP 7–6, ‘‘Guidance on De-
manner which does not provide issue and Controls—Overview of sign of Instrumentation
finality as described in the applicable Review Process,’’ Revision and Controls Provided to
issue finality provision, then the staff 7 ........................................ ML16020A049 Accomplish Changeover
SRP 7.1, ‘‘Instrumentation from Injection to Recircula-
must make the showing as set forth in and Controls—Introduc- tion Mode,’’ Revision 6 ..... ML16011A106
the Backfit Rule or address the criteria tion,’’ Revision 6 ................ ML16020A050 BTP 7–8, ‘‘Guidance for Ap-
for avoiding issue finality as described Table 7–1, ‘‘Table 7–1 Regu- plication of Regulatory
in the applicable issue finality latory Requirements, Ac- Guide 1.22,’’ Revision 6 .... ML16020A044
ceptance Criteria, and BTP 7–9, ‘‘Guidance on Re-
provision. Guidelines for Instrumenta- quirements for Reactor
3. Backfitting and issue finality do tion and Control Systems Protection System Antici-
Important to Safety,’’ Revi- patory Trips,’’ Revision 6 .. ML16011A062
not—with limited exceptions not sion 6 ................................ ML16020A103 BTP 7–10, ‘‘Guidance on Ap-
applicable here—protect current or SRP 7.2, ‘‘Reactor Trip Sys- plication of Regulatory
future applicants. tem,’’ Revision 6 ............... ML16020A059 Guide 1.97,’’ Revision 6 .... ML16019A169
SRP 7.3, ‘‘Engineered Safety BTP 7–11, ‘‘Guidance on Ap-
Applicants and potential applicants Features Systems,’’ Revi- plication and Qualification
are not, with certain exceptions, sion 6 ................................ ML16020A082 of Isolation Devices,’’ Revi-
protected by either the Backfit Rule or SRP 7.4, ‘‘Safe Shutdown sion 6 ................................ ML16019A184
Systems,’’ Revision 6 ........ ML16020A086 BTP 7–12, ‘‘Guidance on Es-
any issue finality provisions under 10 SRP 7.5, ‘‘Information Sys- tablishing and Maintaining
CFR part 52. This is because neither the tems Important to Safety,’’ Instrument Setpoints,’’ Re-
Backfit Rule nor the issue finality Revision 6 ......................... ML16020A088 vision 6 .............................. ML16019A200
SRP 7.6, ‘‘Interlock Systems BTP 7–13, ‘‘Guidance on
provisions under 10 CFR part 52—with Important to Safety,’’ Revi- Cross-Calibration of Pro-
certain exclusions discussed in the next sion 6 ................................ ML16020A092 tection System Resistance
paragraph—were intended to apply to SRP 7.7, ‘‘Control Systems,’’ Temperature Detectors,’’
every NRC action which substantially Revision 6 ......................... ML16020A095 Revision 6 ......................... ML16019A240
SRP 7.8, ‘‘Diverse Instru- BTP 7–14, ‘‘Guidance on
changes the expectations of current and mentation and Control Software Reviews for Dig-
future applicants. Systems,’’ Revision 6 ........ ML16020A096 ital Computer-Based In-
SRP 7.9, ‘‘Data Communica- strumentation and Control
The exceptions to the general tion Systems,’’ Revision 6 ML16020A097 Systems,’’ Revision 6 ........ ML16019A308
principle are applicable whenever an App. 7.0–A, ‘‘Review Proc- BTP 7–17, ‘‘Guidance on
applicant references a 10 CFR part 52 ess for Digital Instrumenta- Self-Test and Surveillance
tion and Control Systems,’’
license (e.g., an early site permit) and/ Revision 6 ......................... ML16019A085
Test Provisions,’’ Revision
or NRC regulatory approval (e.g., a 6 ........................................ ML16019A316
App. 7.1–A, ‘‘Acceptance
BTP 7–18, ‘‘Guidance on the
design certification rule) with specified Criteria and Guidelines for
Use of Programmable
issue finality provisions. The staff does Instrumentation and Con-
trols Systems Important to Logic Controllers in Digital
not, at this time, intend to impose the Safety,’’ Revision 6 ........... ML16019A088 Computer-Based Instru-
positions represented in the SRP in a mentation and Control
App. 7.1–B, ‘‘Guidance for Systems,’’ Revision 6 ........ ML16019A327
manner that is inconsistent with any Evaluation of Conformance
to IEEE Std 279,’’ Revision BTP 7–19, ‘‘Guidance for
issue finality provisions. If, in the 6 ........................................ ML16019A091 Evaluation of Diversity and
future, the staff seeks to impose a App. 7.1–C, ‘‘Guidance for Defense-in-Depth in Digital
Evaluation of Conformance Computer-Based Instru-
position in the SRP in a manner which mentation and Control
does not provide issue finality as to IEEE Std 603,’’ Revision
6 ........................................ ML16019A107 Systems,’’ Revision 7 ........ ML16019A344
described in the applicable issue finality App. 7.1–D, ‘‘Guidance for BTP 7–21, ‘‘Guidance on
provision, then the staff must address Evaluation of the Applica- Digital Computer Real-
tion of IEEE Std 7–4.3.2,’’ Time Performance,’’ Revi-
the criteria for avoiding issue finality as sion 6 ................................ ML16020A036
Revision 1 ......................... ML16019A114
described in the applicable issue finality BTP 7–1, ‘‘Guidance on Iso-
provision. lation of Low-Pressure * No changes resulting from public com-
Systems from the High- ments. See documents in the package at
III. Congressional Review Act Pressure Reactor Coolant ADAMS Accession No. ML16008B013 to see
System,’’ Revision 6 ......... ML16019A127 changes made since the last proposed
This action is a rule as defined in the BTP 7–2, ‘‘Guidance on Re- revision.
Congressional Review Act (5 U.S.C. quirements of Motor-Oper-
ated Valves in the Emer- Dated at Rockville, Maryland, this 25th day
801–808). However, the Office of gency Core Cooling Sys- of August, 2016.
Management and Budget has not found tem Accumulator Lines,’’ For the Nuclear Regulatory Commission.
it to be a major rule as defined in the Revision 6 ......................... ML16019A299
BTP 7–3, ‘‘Guidance on Pro- Joseph Colaccino,
mstockstill on DSK3G9T082PROD with NOTICES
Congressional Review Act. tection System Trip Point
Changes for Operation Chief, New Reactor Rulemaking and
IV. Availability of Documents with Reactor Coolant Guidance Branch, Division of Engineering
Pumps Out of Service,’’ Infrastructure and Advanced Reactors, Office
The documents identified in the Revision 6 ......................... ML16019A358 of New Reactors.
following table are available to BTP 7–4, ‘‘Guidance on De- [FR Doc. 2016–20873 Filed 8–30–16; 8:45 am]
interested persons. sign Criteria for Auxiliary
Feedwater Systems,’’ Re- BILLING CODE 7590–01–P
vision 6 .............................. ML16020A028
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Document Created: 2018-02-02 12:14:58
Document Modified: 2018-02-02 12:14:58
| 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 | Standard review plan-final section revision; issuance. | |
| Dates | The effective date of this SRP update is September 30, 2016. | |
| Contact | Carolyn Lauron, telephone: 301-415- 2736; email: [email protected] or Mark Notich, telephone: 301-415- 3053; email: [email protected]; both are staff of the Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555- 0001. | |
| FR Citation | 81 FR 60029 |
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