Regulatory Guide 1.212: Difference between revisions

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{{Adams
{{Adams
| number = ML082740047
| number = ML23118A344
| issue date = 11/01/2008
| issue date = 06/30/2023
| title = Sizing of Large Lead-Acid Storage Batteries
| title = Rev 2, Sizing of Large Lead-Acid Storage Batteries
| author name =  
| author name = Ramadan L
| author affiliation = NRC/RES
| author affiliation = NRC/NRR/DEX/ELTB
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Bayssie Mekonen/RES 415-0703
| contact person =  
| case reference number = DG-1183
| case reference number = DG-1418
| document report number = RG-1.212
| document report number = RG-1.212, Rev. 2
| package number = ML082740044
| package number = ML23118A358
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 7
| page count = 10
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION  
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION  
November 2008
REGULATORY GUIDE 1.212, REVISION 2


REGULATORY GUIDE
Issue Date: June 2023 Technical Lead: Liliana Ramadan


OFFICE OF NUCLEAR REGULATORY RESEARCH 
Written suggestions regarding this guide may be submitted through the NRCs public Web site in the NRC Library at https://www.nrc.gov/reading-rm/doc-collections/reg-guides/index.html, under Document Collections, in Regulatory Guides, at https://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html, and will be considered in future updates and enhancements to the Regulatory Guide series. During the development process of new guides suggestions should be submitted within the comment period for immediate consideration. Suggestions received outside of the comment period will be considered if practical to do so or may be considered for future updates.


REGULATORY GUIDE 1.212 (Draft was issued as DG-1183, dated July 2008)
Electronic copies of this RG, previous versions of RGs, and other recently issued guides are also available through the NRCs public web site in the NRC Library at https://www.nrc.gov/reading-rm/doc-collections/reg-guides/index.html/ under Document Collections, in Regulatory Guides.
 
This RG is also available through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession Number (No.) ML23118A344. The regulatory analysis may be found in ADAMS under Accession No. ML22307A144. The associated draft guide DG-1418 may be found in ADAMS under Accession No.
 
ML22307A132, and the staff responses to the public comments on DG-1418 may be found under ADAMS Accession No. ML23118A345.


SIZING OF LARGE LEAD-ACID STORAGE BATTERIES  
SIZING OF LARGE LEAD-ACID STORAGE BATTERIES  


==A. INTRODUCTION==
==A. INTRODUCTION==
This guide describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for use in complying with requirements and regulations on the criteria for the sizing of large lead-acid storage batteries for use in nuclear power plants. Specifically, the method described in this regulatory guide relates to requirements set forth in Title 10, Section 50.55a, Codes and Standards, of the Code of Federal Regulations (10 CFR 50.55a), 10 CFR 50.63 (a)(2), Loss of all alternating current power, and General Design Criteria (GDC) 1 and 17, as set forth in Appendix A, General Design Criteria for Nuclear Power Plants, 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities. (Ref. 1):
Purpose 
 
This regulatory guide (RG) describes an approach that is acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) to meet regulatory requirements for sizing large lead-acid storage batteries for production and utilization facilities. It endorses, with some limitations and a clarification, Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 485-2020, IEEE
Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications (Ref. 1).
 
Applicability
 
This RG applies to licensees and applicants subject to Title 10 of the Code of Federal Regulations
(10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities (Ref. 2), and
10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants (Ref. 3). Under
10 CFR Part 50, this RG applies to licensees of or applicants for production and utilization facilities.
 
Under 10 CFR Part 52, this RG applies to applicants and holders of combined licenses, standard design certifications, standard design approvals, and manufacturing licenses.
 
Applicable Regulations
 
* 10 CFR Part 50 provides regulations for licensing production and utilization facilities.
 
o 10 CFR 50.55a, Codes and standards, requires, in part, that structures, systems, and components be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed.
 
o 10 CFR 50.63(a)(2) requires, in part, that the reactor core and associated coolant, control, and protection systems, including station batteries and any other necessary support systems, provide sufficient capacity and capability to ensure that the core is cooled, and appropriate containment integrity is maintained in the event of a station blackout for the specified duration.
 
RG 1.212, Rev. 2, Page 2 o 10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants, General Design Criterion (GDC) 1, Quality Standards and Records, requires, in part, that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed.
 
o 10 CFR Part 50, Appendix A, GDC 17, Electric Power Systems, requires, in part, that an onsite electric power system and an offsite electric power system be provided to permit functioning of structures, systems, and components important to safety.


*  
*  
10 CFR 50.55a(a)(1) requires that structures, systems, and components be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed.
10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. Part 52 specifies, among other things, that contents of some applications must satisfy the requirements of 10 CFR Part 50, Appendix A; 10 CFR 50.55a; and 10 CFR 50.63, Loss of all alternating current power.
 
Related Guidance


*  
*  
GDC 1, Quality Standards and Records, requires that structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed.
NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: Light-Water Reactor (LWR Edition) (Ref. 4), provides guidance to the NRC staff in performing safety reviews under 10 CFR Part 50 and 10 CFR Part 52. Specifically, Section
8.3.2, DC Power Systems (Onsite), contains review guidance related to direct current (dc)
systems, including batteries.


*  
*  
GDC 17, Electric Power Systems, requires that an onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety.
RG 1.129, Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants and Utilization Facilities (Ref. 5), endorses, with clarifications, IEEE
Std. 450, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications (Ref. 6), as an acceptable method to meet the regulations concerning the maintenance, testing, and replacement of vented lead-acid storage batteries in nuclear power plants.


*  
*  
10 CFR 50.63(a)(2) requires that the reactor core and associated coolant, control, and protection systems, including station batteries and any other necessary support systems, must provide The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in implementing specific parts of the agencys regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in reviewing applications for permits and licenses. Regulatory guides are not substitutes for regulations, and compliance with them is not required.  Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.
RG 1.128, Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants (Ref. 7), endorses, with clarifications, IEEE Std. 484, IEEE
Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications (Ref. 8), as an acceptable method to meet the regulations concerning the installation design and installation of vented lead-acid storage batteries in nuclear power plants.


This guide was issued after consideration of comments received from the public.
*
NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, issued February 1996 (Ref. 9), contains format and content guidance for non-power reactor applicants and licensees, as well as a standard review plan and acceptance criteria for the NRC staff.


Regulatory guides are issued in 10 broad divisionsC1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities; 4, Environmental and Siting; 5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health;
*
9, Antitrust and Financial Review; and 10, General.
Final Interim Staff Guidance Augmenting NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Parts 1 and 2, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors, issued October 2012 (Ref. 10), provides format and content guidance for non-power aqueous homogeneous reactor and radioisotope production facility applicants and licensees, as well as a standard review plan and acceptance criteria for the NRC staff.
 
*
Endorsement of Appendix A to Oak Ridge National Laboratory Report, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application, as Guidance for


Electronic copies of this guide and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRCs Electronic Reading Room at http://www.nrc.gov/reading-rm/doc- collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML082740047.
RG 1.212, Rev. 2, Page 3 Preparing Applications for the Licensing of Non-Power Liquid Fueled Molten Salt Reactors, dated November 18, 2020 (Ref. 11), endorses, with clarifications, Appendix A to ORNL/TM-2020/1478, Proposed Guidance for Preparing and Reviewing a Molten Salt Non- Power Reactor Application, issued July 2020 (Ref. 12), to support the review of non-power molten salt reactors.


RG 1.212, Page 2 sufficient capacity and capability to ensure that the core is cooled and appropriate containment integrity is maintained in the event of a station blackout for the specified duration.
Purpose of Regulatory Guides 


This regulatory guide endorses (with certain clarifying regulatory positions described in Section C of this guide) IEEE Std 485-1997, IEEE Recommended Practice for Sizing of Lead-Acid Batteries for Stationary Applications. (Ref. 2)
The NRC issues RGs to describe methods that are acceptable to the staff for implementing specific parts of the agencys regulations, to explain techniques that the staff uses in evaluating specific issues or postulated events, and to describe information that the staff needs in its review of applications for permits and licenses. RGs are not NRC regulations and compliance with them is not required. Methods and solutions that differ from those set forth in RGs are acceptable if supported by a basis for the issuance or continuance of a permit or license by the Commission.


The NRC issues regulatory guides to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agencys regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to applicants. Regulatory guides are not substitutes for regulations and compliance with them is not required.
Paperwork Reduction Act  


This regulatory guide contains information collection requirements covered by 10 CFR Part 50  
This RG provides voluntary guidance for implementing the mandatory information collections in
that the Office of Management and Budget (OMB) approved under OMB control number 3150-0011.
10 CFR Parts 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
These information collections were approved by the Office of Management and Budget (OMB), under control numbers 3150-0011 and 3150-0151, respectively. Send comments regarding this information collection to the FOIA, Library, and Information Collections Branch (T6-A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the OMB reviewer at: OMB Office of Information and Regulatory Affairs, (3150-0011 and 3150-
0151), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street, NW, Washington, DC, 20503; e-mail: oira_submissions@omb.eop.gov.


The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.
Public Protection Notification 
 
The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB  
control number.
 
RG 1.212, Rev. 2, Page 4


==B. DISCUSSION==
==B. DISCUSSION==
10 CFR 50.55a(h)(2) and (3) require compliance with the requirements for safety systems in IEEE Std 603-1991, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations (Ref. 3) and the correction sheet dated January 30, 1995. The IEEE Std 603-1991 states that specific criteria unique to the Class 1E power systems are given in IEEE Std 308-1980, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, (Ref. 4).  Furthermore, the IEEE
Reason for Revision  
Std 308-1980 states that each battery supply shall be capable of starting and operating its required steady-state and transient loads and refers the reader to IEEE Std 485-1978 for recommendations on sizing batteries.  The IEEE Std 485-1978 is no longer available from the IEEE.  However, wording of this section of the IEEE Std 308-2001, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, (Ref. 5) is identical to that of the IEEE Std 308-1980 except that it references the IEEE Std 485-1997.


While the NRC has not previously endorsed the IEEE Std 485, several previous positions relate directly or indirectly to various versions of this standard.  In addition to the references above to the IEEE
This revision of the RG (Revision 2) endorses, with some limitations and a clarification, IEEE  
Std 485-1978, the NRC staff has previously endorsed designs predicated on both the IEEE Std 485-1983 and the IEEE Std 485-1997.  For example, NUREG-1431, Standard Technical Specifications Westinghouse Plants (Ref. 6); NUREG-1433, Standard Technical Specifications General Electric Plants, BWR/4 (Ref. 7); and NUREG-1434, Standard Technical Specifications General Electric Plants, BWR/6, (Ref. 8) all reference the IEEE Std 485-1983.  On the other hand, NUREG-1793, Final Safety Evaluation Report Related to Certification of the AP1000 Standard Design, issued in September 2004, states that among the features of the AP1000, compared to currently operating reactors...[is]...increased battery capacity.  While NUREG-1793 notes that a regulatory guide had not previously endorsed the IEEE Std 485-1997, it proceeds to state that the battery sizing, which was performed in accordance with the IEEE Std 485-1997, is considered acceptable.  Additionally, Appendix A to NUREG/CR 6901, Current State of Reliability Modeling Methodologies for Digital Systems and Their Acceptance Criteria for Nuclear Power Plant Assessments, issued in February 2006, references the IEEE Std 485-1997.
Std. 485-2020 and applies to production and utilization facilities licensed under 10 CFR Part 50 and
10 CFR Part 52 within the scope of this RG. The previous version of this RG endorsed, with certain clarifications, IEEE Std. 485-2010. In 2020, the IEEE revised IEEE Std. 485 to refine the methods for defining dc load guidance and sizing large lead-acid batteries to ensure consistent performance. The revised IEEE standard provides a succinct document for the sizing of batteries with informative annexes.


More recently, Revision 3 to Section 8.3.2 of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, issued in March 2007, states that IEEE Std 485
The NRC staff determined that, based on the revised IEEE standard, a revision to this RG is needed to support applications for new reactor licenses, design certifications, and license amendments.


RG 1.212, Page 3 provides a method acceptable to the staff for sizing stationary lead-acid batteries and cites the IEEE Std
Background 
485-1997 as a reference.


The Battery Sizing Working Group of Standards Coordinating Committee 29 prepared the IEEE
This RG provides guidance to applicants and licensees for defining the dc load and sizing lead-acid batteries to supply the defined load for full-float stationary battery application
Std 485-1997, and the IEEE Standards Board approved it on March 20, 1997.  The IEEE reviewed and affirmed the standard in 2003.  The IEEE Std 485-1997 describes recommended methods for defining the direct current (dc) load and for sizing a lead-acid battery to supply that load.  The IEEE Std 485-1997 is applicable to full-float stationary applications in which a battery charger normally maintains the battery in a fully charged state and provides power to the dc load.  This standard is applicable to vented and valve- regulated lead-acid batteries, and also describes some factors relating to cell selection.  However, consideration of battery types other than lead-acid is beyond the scope of the standard.  Additionally, installation, maintenance, qualification, testing procedures, and design of the dc system and sizing of the battery charger(s) are also beyond the scope of this standard.


The IEEE Std 485-1978 is no longer available from the IEEE.  A comparison with the current standard is also not available.  The IEEE Std 485-1983, IEEE Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations (Ref. 12), addresses sizing of large lead storage batteries for generating stations and substations but does not mention valve-regulated lead-acid batteries.  Subsequently, the IEEE Std 485-1997 was generalized for the sizing of lead-acid batteries for stationary applications.  The later version explicitly states its applicability to both vented and valve- regulated lead-acid batteries.  In addition, requirements (indicated by the verb shall) in the previous version of the standard have been restated as recommendations (indicated by the verb should) in IEEE
====s. IEEE ====
Std 485-1997.  A comparison of IEEE Std 485-1983 and IEEE Std 485-1997 is available from the IEEE.
Std. 485-2020 describes the recommended methods for defining the dc load and for sizing lead-acid batteries to supply dc power to applications during the full range of operating and emergency conditions.


The IEEE Std 485-1997 also includes an additional instruction to consult with manufacturers on any limitations on paralleling two or more strings of cells.  The 1997 edition updates a previous reference to the IEEE Std 484-1981 in IEEE Std 485-1983 to reference the IEEE Std 484-1996, Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications. The 1981 edition of IEEE Std 484 is no longer in print, and the IEEE has since published a newer version of the standard, IEEE Std 484-2002 (Ref. 13) which the NRC endorsed in Revision 2 of Regulatory Guide 1.128, Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants (Ref. 14), issued in February 2007.
IEEE Std. 485-2020 is an updated national consensus standard that adds new recommendations and guidance, as well as informative annexes, for both vented and valve-regulated lead-acid batteries for stationary applications. The standard was developed by the IEEE Power Engineering Society Stationary Batteries Committee and approved by the IEEE Standards Association Standards Board on May 6, 2020.


The IEEE Std 450-2002, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications (Ref. 15), which the NRC
The standard is applicable to vented and valve-regulated lead-acid batteries and also describes some factors relating to cell selection. However, consideration of battery types other than lead acid is beyond the scope of this RG. Additionally, installation, maintenance, qualification, testing procedures, and design of the dc system and sizing of the battery charger(s) are beyond the scope of the IEEE standard and this RG.
endorsed in Regulatory Guide 1.129, Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants, (Ref. 16) repeatedly refers to IEEE Std 485-1997 in its discussion of considerations related to battery sizing as it affects many of the various testing criteria, including acceptance tests, performance tests, service tests, and battery replacement criteria.


The sizing methodology provided by IEEE Std 485-1997 is essentially identical to that provided by IEEE Std 485-1983. The approach consists of first defining the load that the batteries will be required to support. To this end, the standard provides guidance on general considerations that should be included in defining the duty cycle; load classifications, including continuous, non-continuous, and momentary loads; and the construction of a duty-cycle diagram. Annex B to IEEE Std 485-1997 provides a method for converting constant power and constant resistance loads to constant current loads so that they can be correctly considered using the sizing methodology provided in the standard.  The standard provides a brief summary of some factors that should be considered when selecting a cell design for a particular application. The IEEE Std 485-1997 refers the user to vendor literature and to the IEEE Std 1184-1994, IEEE Guide for Batteries for Uninterruptible Power Supply Systems, (Ref. 17) in its discussion of cell selection considerations.
It is important to recognize that IEEE Std. 485-2020 states it can be used as a standalone document. However, the NRC staff has found that using IEEE Std. 485-2020 in conjunction with IEEE
Std. 450 and IEEE Std. 484 provides the user with a general guide to the design, installation, and maintenance of vented lead-acid batteries. In addition, the staff notes that IEEE/American Society of Heating, Refrigerating and Air Conditioning Engineers (ASHRAE) 1635-2022, Guide for the Ventilation and Thermal Management of Batteries for Stationary Applications, (Ref. 13) provides helpful ventilation calculations that are associated with IEEE Standard 484. For the design, installation, and maintenance of valve-regulated lead-acid (VRLA) batteries, the NRC staff reviewed IEEE Std. 1187, IEEE Recommended Practice for Installation Design and Installation of Valve-Regulated Lead-Acid Storage Batteries for Stationary Applications (Ref. 14), and IEEE Std. 1188, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Valve-Regulated Lead-Acid (VRLA) Batteries for Stationary Applications (Ref. 15), and found that the standards provide additional information and criteria for VRLA battery users.


RG 1.212, Page 4 The standard provides a methodical and conservative procedure for determining the battery size required to deliver sufficient power to the previously determined load.  In addition to the defined duty cycle, the approach considers other factors, including maximum system voltage, minimum system voltage, and various correction factors.  The IEEE Std 485-1997 no longer includes a discussion on charging rate as a limiting factor in battery sizing and a qualification on total time span of the duty cycle, which appeared in the 1983 edition of the standard. The 1997 edition also slightly revised the consideration of minimum system voltage as a limiting factor to be more consistent with the cell-sizing worksheet incorporated by the method.
The sizing methodology in IEEE Std. 485-2020 is very similar to that in IEEE Std. 485-2010. The approach consists of defining the load that the batteries will be required to support and using the guidance in the IEEE standard to determine the best battery for the application. To this end, IEEE Std. 485-2020
provides guidance on general considerations that should be included in defining the duty cycle; load classifications, including continuous, noncontinuous, and momentary loads; and the construction of a duty cycle diagram. In calculating the number of cells and minimum voltage section, IEEE Std. 485-2020


In addition to Annex B described above, the IEEE Std 485-1997 was also augmented with the following additional information:
RG 1.212, Rev. 2, Page 5 cautions the user that the charging voltage needs to be recalculated and verified for adequacy if the numbers of cells are rounded off. It also discusses how to ensure all voltage drops are considered when calculating the allowable minimum voltage.


*
IEEE Std. 485-2020 discusses defining loads and other considerations but notes that for sizing purposes the loads can be treated as constant power or constant current. The updated annexes A, B, C, D,
Section 7 discusses the potential need for calculating cell or battery terminal voltages at various times throughout the duty cycle.
E, F, G, and H are informative, and applicants and licensees should review them to assist with the battery design.
 
IEEE Std. 485-2020, section 4.2.5, Duty Cycle Diagram, states that the total time span of the duty cycle is determined by the requirements of the installation. This duty cycle time depends on the type of production and utilization facility design and is typically discussed in a plant safety analysis report.


*
This guidance does not apply to the emergency diesel generators (EDGs) or onsite emergency power sources own battery if provided separately (which is exclusively sized based on the starting requirement of the EDG or onsite emergency power source, such as field flash).  
Annex C describes a method for calculating the cell/battery terminal voltage as a function of the duty cycle and provides two sample calculations, one using fan curves and one using S
curves to describe the discharge characteristics of a given battery.


*
Consideration of International Standards
Annex D provides a bibliography.


Annex A to IEEE Std 485-1997 provides battery- and cell-sizing examples.  Included are example calculations that demonstrate how to properly select the number of cells, how the number of cells affects the required cell capacity, and how to use the cell-sizing worksheet to calculate the required cell size. However, Figure A.1 contains three typographical errors. In Section 4 of the figure, the positive values and the negative value for the Section 4 subtotal, -800.2, are correct; however, the figure contains the following errors:  
The International Atomic Energy Agency (IAEA) works with member states and other partners to promote the safe, secure, and peaceful use of nuclear technologies. The IAEA develops safety requirements and safety guides for protecting people and the environment from harmful effects of ionizing radiation. This system of safety fundamentals, safety requirements, safety guides, and other relevant reports reflects an international perspective on what constitutes a high level of safety. Pursuant to the Commissions International Policy Statement (Ref. 16) and Management Directive 6.6, Regulatory Guides (Ref. 17), the NRC considered the following IAEA safety guide and safety requirement in the development of the RG:


*  
*  
The cell in Section 4, row 2, column 7 (Neg Values), is blank but should read -640.2.
IAEA Safety Guide NS-G-1.8, Design of Emergency Power Systems for Nuclear Power Plants, (Ref. 18)  


*  
*  
The cell in Section 4, row 3, column 7 (Neg Values), currently reads -40.2 but should read
IAEA Safety Standards Series No. SSG-34, Design of Electrical Power Systems for Nuclear Power Plants, (Ref. 19)  
0.0.
 
Although the NRC has an interest in facilitating the harmonization of standards used domestically and internationally, the agency does not specifically endorse the IAEA documents listed above and is only acknowledging that such documents may be a useful reference for general information.


*
Documents Discussed in Staff Regulatory Guidance
The cell in Section 4, row 4, column 7 (Neg Values), is blank but should read -160.0.


==C. REGULATORY POSITION==
This RG endorses, in part, the use of one or more codes or standards developed by external organizations, and other third-party guidance documents. These codes, standards and third-party guidance documents may contain references to other codes, standards, or third-party guidance documents (secondary references). If a secondary reference has itself been incorporated by reference into NRC  
Conformance with the procedures defined in IEEE-Std 485-1997 (reaffirmed in 2003) provides methods acceptable to the NRC staff for complying with the design requirements as set forth in (1) 10 CFR
regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation. If the secondary reference has been endorsed in a RG as an acceptable approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific RG. If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in a RG, then the secondary reference is neither a legally-binding requirement nor a generic NRC-approved acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in
50.55a(a)(1), (2) 10 CFR 50.55a(h)(2), (3) 10 CFR 50.55a(h)(3), (4) 10 CFR 50.63(a)(2), and (5) GDC 1 and 17 of Appendix A to 10 CFR Part 50 as they relate to the requirements for defining dc loads for all specified battery duty cycles and for sizing lead-acid batteries to supply that load for stationary battery applications in full-float operation for nuclear power plants, subject to the following stipulations:


1.
RG 1.212, Rev. 2, Page 6 the secondary reference, if appropriately justified, consistent with current regulatory practice, and consistent with applicable NRC requirements.


Section 2, References, which stipulates that this standard shall be used in conjunction with other IEEE standards, should be supplemented as follows:
RG 1.212, Rev. 2, Page 7 C.  STAFF REGULATORY GUIDANCE


For nuclear power generating stations, the recommended practice should also be used in conjunction with other pertinent publications.  The pertinent publications include the following IEEE standards:  
The staff finds that IEEE Std. 485-2020 provides methods acceptable to the NRC staff for complying with the design requirements for stationary battery applications in full-float operation for production and utilization facilities, subject to the following limitations and a clarification:  


*
1.
IEEE Std 308-2001, IEEE Standard  Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, as endorsed by Regulatory Guide 1.32
 
Annex A to IEEE Std. 485-2020 is informative and provides sample sizing demonstrations.


RG 1.212, Page 5
Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020
*
does not include endorsement of this annex.
IEEE Std 535-2006, " IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations"
*
IEEE Std 344-1987, IEEE Recommended Practice for Seismic Qualification of Class 1E
Equipment for Nuclear Power Generating Stations, as endorsed by Regulatory Guide 1.100
*
IEEE Std 384-1992, IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits, as endorsed by Regulatory Guide 1.75
*
IEEE Std 484-2002, IEEE Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications, as endorsed by Regulatory Guide 1.128
*
IEEE Std 450-2002, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Application, as endorsed by Regulatory Guide
1.129.


2.
2.


Annex A to IEEE Std 485-1997 is informative and provides sample sizing demonstrations.
Annex B to IEEE Std. 485-2020 is informative and provides a method for estimating battery terminal voltage at various points in the battery duty cycle using the manufacturers typical discharge characteristics. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.


Unless otherwise stated in a regulatory position, endorsement of the IEEE Std 485-1997 does not include this annex. Figure A.1 has the following three typographical errors: 
3.


3.
Annex C to IEEE Std. 485-2020 is informative and provides a method for considering other cell types when selecting a battery for its intended application. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.
 
4.


Annex B to IEEE Std 485-1997 is endorsed as an accepted method of converting constant power and constant resistance loads to constant current loads for purposes of defining the duty cycle for battery-sizing calculations.
Annex D to IEEE Std. 485-2020 is informative and provides a method for sizing a battery properly for a constant power application and for converting from either constant power loads or constant resistance loads to constant current. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.


a.
5.


The cell in Section 4, row 2, column 7 (Neg Values), is blank but should read -
Annex E to IEEE Std. 485-2020 is informative and provides a method for describing the construction and use of the battery discharge characteristics curve. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.
640.2.


b.
6.


The cell in Section 4, row 3, column 7 (Neg Values), currently reads -40.2 but should read 0.0.
Annex F to IEEE Std. 485-2020 is informative and provides a method for addressing random loads and their application in the battery sizing process. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.


c.
7.


The cell in Section 4, row 4, column 7 (Neg Values), is blank but should read -
Annex G to IEEE Std. 485-2020 is a full-size worksheet, Sizing Lead-Acid Batteries for Stationary Applications, and is endorsed as an accepted method for sizing lead-acid batteries.
160.0.


4.
8.


Annex C to IEEE Std 485-1997 is informative and provides a method for estimating battery terminal voltage at various points in the battery duty cycle using manufacturers typical discharge characteristics. Unless otherwise stated in a regulatory position, endorsement of the IEEE Std  
Annex H to IEEE Std. 485-2020 is informative and provides the bibliography. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.
485-1997 does not include this annex.


5.
9.


Annex D to IEEE Std 485-1997 is informative and provides the bibliography. Unless otherwise stated in a regulatory position, endorsement of the IEEE Std 485-1997 does not include this annex.
The safety analysis report should discuss the battery duty cycle span. For active designs, the battery duty cycle should cover both DBA and SBO scenarios (with a permitted load shedding scheme). The minimum duty cycle for active designs for DBAs should be 2 hours.


RG 1.212, Page 6
RG 1.212, Rev. 2, Page 8


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The purpose of this section is to provide information to applicants and licensees regarding the NRCs plans for using this regulatory guide. The NRC does not intend or approve any imposition or backfit in connection with its issuance.
The NRC staff may use this regulatory guide as a reference in its regulatory processes, such as licensing, inspection, or enforcement. However, the NRC staff does not intend to use the guidance in this RG to support NRC staff actions in a manner that would constitute backfitting as that term is defined in
10 CFR 50.109, Backfitting, and as described in NRC Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and


In some cases, applicants or licensees may propose an alternative method or use a previously established acceptable alternative method for complying with specified portions of the NRCs regulations.
===


Otherwise, the methods described in this guide will be used in evaluating compliance with the applicable regulations for license applications, license amendment applications, and amendment requests.
===Information Requests===
===
, (Ref. 20), nor does the NRC staff intend to use the guidance to affect the issue finality of an approval under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants. The staff also does not intend to use the guidance to support NRC staff actions in a manner that constitutes forward fitting as that term is defined and described in Management Directive 8.4. If a licensee believes that the NRC is using this regulatory guide in a manner inconsistent with the discussion in this Implementation section, then the licensee may file a backfitting or forward fitting appeal with the NRC in accordance with the process in Management Directive 8.4.


REFERENCES  
RG 1.212, Rev. 2, Page 9 REFERENCES 1


1.
1.


U.S. Code of Federal Regulations, Title 10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities, U.S. Nuclear Regulatory Commission, Washington, DC.
Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 485-2020, IEEE
Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications, Piscataway, New Jersey.2


2.
2.


IEEE Std 485-1997, IEEE Recommended Practice for Sizing of Lead-Acid Batteries for Stationary Applications, IEEE, Piscataway, NJ, September 1997.
U.S. Code of Federal Regulations (CFR), Domestic Licensing of Production and Utilization Facilities, Part 50, Chapter I, Title 10, Energy.


3.
3.


IEEE Std. 603-1991, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations, IEEE, Piscataway, NJ, December 1991.
CFR, Licenses, Certifications, and Approvals for Nuclear Power Plants, Part 52, Chapter I,  
Title 10, Energy.


4.
4.


IEEE Std 308-1980, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, IEEE, Piscataway, NJ, October 1980.
U.S. NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 8.3.2, DC Power Systems (Onsite),  
Washington, DC. (ADAMS Accession No. ML100740391)


5.
5.


IEEE Std 308-2001, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, IEEE, Piscataway, NJ, March 2002.
NRC, RG 1.129, Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities, Washington, DC.


6.
6.


NUREG-1431, Standard Technical Specifications Westinghouse Plants, U.S. Nuclear Regulatory Commission, Washington, DC, June 2004.
IEEE Std. 450, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications, Piscataway, New Jersey.


7.
7.


NUREG-1433, Standard Technical Specifications General Electric Plants, BWR/4, U.S.
NRC, RG 1.128, Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants, Washington, DC.
 
Nuclear Regulatory Commission, Washington, DC, June 2004.


8.
8.


NUREG-1434, Standard Technical Specifications General Electric Plants, BWR/6, U.S.
IEEE Std. 484, IEEE Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications, Piscataway, New Jersey.
 
Nuclear Regulatory Commission, Washington, DC, June 2004.


9.
9.


NUREG-1793, Final Safety Evaluation Report Related to Certification of the AP1000 Standard Design, U.S. Nuclear Regulatory Commission, Washington, DC, September 2004.
NRC, NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Washington, DC, February 1996. (ML12156A069 and ML12156A075, respectively)


10.
10.


NUREG/CR 6901, Current State of Reliability Modeling Methodologies for Digital Systems and Their Acceptance Criteria for Nuclear Power Plant Assessments, U.S. Nuclear Regulatory Commission, Washington, DC, February 2006.
NRC, Final Interim Staff Guidance Augmenting NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Parts 1 and 2, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors, Washington, DC,  
October 17, 2012. (ML12156A053)


11.
11.


NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC, March 2007.
NRC, Endorsement of Appendix A to Oak Ridge National Laboratory Report, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application, as
 
1 Publicly available NRC published documents are available electronically through the NRC Library on the NRCs public website at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html. For problems with ADAMS, contact the Public Document Room staff at 301-415-4737 or (800) 397-4209, or email pdr.resource@nrc.gov. The NRC Public Document Room (PDR), where you may also examine and order copies of publicly available documents, is open by appointment. To make an appointment to visit the PDR, please send an email to PDR.Resource@nrc.gov or call 1-800-397-
4209 or 301-415-4737, between 8 a.m. and 4 p.m. eastern time (ET), Monday through Friday, except Federal holidays.
 
2 Copies of Institute of Electrical and Electronics Engineers (IEEE) documents may be purchased from the Institute of Electrical and Electronics Engineers Service Center, 445 Hoes Lane, PO Box 1331, Piscataway, NJ 08855 or through the IEEEs public Web site at http://www.ieee.org/publications/index.html.
 
RG 1.212, Rev. 2, Page 10
Guidance for Preparing Applications for the Licensing of Non-Power Liquid Fueled Molten Salt Reactors, Washington, DC, November 18, 2020. (ML20251A008)


12.
12.


IEEE Std 485-1983, IEEE Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations, IEEE, Piscataway, NJ, June 1983.
Oak Ridge National Laboratory, ORNL/TM-2020/1478, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application, Oak Ridge, Tennessee, July 2020.


RG 1.212, Page 7
(ML20219A771)


13.
13.


IEEE Std 484-2002, IEEE Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications, IEEE, Piscataway, NJ, February 2003.
IEEE/American Society of Heating, Refrigerating and Air Conditioning Engineers (ASHRAE),
IEEE/ASHRAE 1635-2022, Guide for the Ventilation and Thermal Management of Batteries for Stationary Applications, Piscataway, New Jersey.


14.
14.


Regulatory Guide 1.128, Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC.
IEEE Std. 1187, IEEE Recommended Practice for Installation Design and Installation of Valve-Regulated Lead-Acid Storage Batteries for Stationary Applications, Piscataway, New Jersey.


15.
15.


IEEE Std 450-2002, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications, IEEE, Piscataway, NJ, April 2003.
IEEE Std. 1188, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Valve-Regulated Lead-Acid (VRLA) Batteries for Stationary Applications, Piscataway, New Jersey.


16.
16.


Regulatory Guide 1.129, Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC.
NRC, Nuclear Regulatory Commission International Policy Statement, Federal Register, Vol. 79, No. 132, July 10, 2014, pp. 39415-39418.


17.
17.


IEEE Std 1184-1994, IEEE Guide for Batteries for Uninterruptible Power Supply Systems, IEEE, Piscataway, NJ, June 1995.
NRC, Management Directive 6.6, Regulatory Guides, Washington, DC.


18.
18.


IEEE Std 535-2006, IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations, IEEE, Piscataway, NJ, June 2007.
International Atomic Energy Agency (IAEA) Safety Guide NS-G-1.8, Design of Emergency Power Systems for Nuclear Power Plants, IAEA, Vienna, Austria, 2004.3 


19.
19.


IEEE Std 344-1987, IEEE Recommended Practice for Seismic Qualification of Class 1E
IAEA, Safety Standards Series No. SSG-34, Design of Electrical Power Systems for Nuclear Power Plants, IAEA, Vienna, Austria, 2016.
Equipment for Nuclear Power Generating Stations, IEEE, Piscataway, NJ, August 1987.


20.
20.


IEEE Std 384-1992, IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits, IEEE, Piscataway, NJ, June 1992.}}
NRC, Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and  
 
===
 
===Information Requests===
===
, Washington, DC.
 
3 Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site:
www.IAEA.org/ or by writing the International Atomic Energy Agency, P.O. Box 100 Wagramer Strasse 5, A-1400 Vienna, Austria.}}


{{RG-Nav}}
{{RG-Nav}}

Latest revision as of 00:23, 7 February 2025

Rev 2, Sizing of Large Lead-Acid Storage Batteries
ML23118A344
Person / Time
Issue date: 06/30/2023
From: Liliana Ramadan
NRC/NRR/DEX/ELTB
To:
Shared Package
ML23118A358 List:
References
DG-1418 RG-1.212, Rev. 2
Download: ML23118A344 (10)
v • d • e


U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY GUIDE 1.212, REVISION 2

Issue Date: June 2023 Technical Lead: Liliana Ramadan

Written suggestions regarding this guide may be submitted through the NRCs public Web site in the NRC Library at https://www.nrc.gov/reading-rm/doc-collections/reg-guides/index.html, under Document Collections, in Regulatory Guides, at https://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html, and will be considered in future updates and enhancements to the Regulatory Guide series. During the development process of new guides suggestions should be submitted within the comment period for immediate consideration. Suggestions received outside of the comment period will be considered if practical to do so or may be considered for future updates.

Electronic copies of this RG, previous versions of RGs, and other recently issued guides are also available through the NRCs public web site in the NRC Library at https://www.nrc.gov/reading-rm/doc-collections/reg-guides/index.html/ under Document Collections, in Regulatory Guides.

This RG is also available through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession Number (No.) ML23118A344. The regulatory analysis may be found in ADAMS under Accession No. ML22307A144. The associated draft guide DG-1418 may be found in ADAMS under Accession No.

ML22307A132, and the staff responses to the public comments on DG-1418 may be found under ADAMS Accession No. ML23118A345.

SIZING OF LARGE LEAD-ACID STORAGE BATTERIES

A. INTRODUCTION

Purpose

This regulatory guide (RG) describes an approach that is acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) to meet regulatory requirements for sizing large lead-acid storage batteries for production and utilization facilities. It endorses, with some limitations and a clarification, Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 485-2020, IEEE

Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications (Ref. 1).

Applicability

This RG applies to licensees and applicants subject to Title 10 of the Code of Federal Regulations

(10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities (Ref. 2), and

10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants (Ref. 3). Under

10 CFR Part 50, this RG applies to licensees of or applicants for production and utilization facilities.

Under 10 CFR Part 52, this RG applies to applicants and holders of combined licenses, standard design certifications, standard design approvals, and manufacturing licenses.

Applicable Regulations

  • 10 CFR Part 50 provides regulations for licensing production and utilization facilities.

o 10 CFR 50.55a, Codes and standards, requires, in part, that structures, systems, and components be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed.

o 10 CFR 50.63(a)(2) requires, in part, that the reactor core and associated coolant, control, and protection systems, including station batteries and any other necessary support systems, provide sufficient capacity and capability to ensure that the core is cooled, and appropriate containment integrity is maintained in the event of a station blackout for the specified duration.

RG 1.212, Rev. 2, Page 2 o 10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants, General Design Criterion (GDC) 1, Quality Standards and Records, requires, in part, that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed.

o 10 CFR Part 50, Appendix A, GDC 17, Electric Power Systems, requires, in part, that an onsite electric power system and an offsite electric power system be provided to permit functioning of structures, systems, and components important to safety.

10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. Part 52 specifies, among other things, that contents of some applications must satisfy the requirements of 10 CFR Part 50, Appendix A; 10 CFR 50.55a; and 10 CFR 50.63, Loss of all alternating current power.

Related Guidance

NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: Light-Water Reactor (LWR Edition) (Ref. 4), provides guidance to the NRC staff in performing safety reviews under 10 CFR Part 50 and 10 CFR Part 52. Specifically, Section

8.3.2, DC Power Systems (Onsite), contains review guidance related to direct current (dc)

systems, including batteries.

RG 1.129, Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants and Utilization Facilities (Ref. 5), endorses, with clarifications, IEEE Std. 450, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications (Ref. 6), as an acceptable method to meet the regulations concerning the maintenance, testing, and replacement of vented lead-acid storage batteries in nuclear power plants.

RG 1.128, Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants (Ref. 7), endorses, with clarifications, IEEE Std. 484, IEEE

Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications (Ref. 8), as an acceptable method to meet the regulations concerning the installation design and installation of vented lead-acid storage batteries in nuclear power plants.

NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, issued February 1996 (Ref. 9), contains format and content guidance for non-power reactor applicants and licensees, as well as a standard review plan and acceptance criteria for the NRC staff.

Final Interim Staff Guidance Augmenting NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Parts 1 and 2, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors, issued October 2012 (Ref. 10), provides format and content guidance for non-power aqueous homogeneous reactor and radioisotope production facility applicants and licensees, as well as a standard review plan and acceptance criteria for the NRC staff.

Endorsement of Appendix A to Oak Ridge National Laboratory Report, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application, as Guidance for

RG 1.212, Rev. 2, Page 3 Preparing Applications for the Licensing of Non-Power Liquid Fueled Molten Salt Reactors, dated November 18, 2020 (Ref. 11), endorses, with clarifications, Appendix A to ORNL/TM-2020/1478, Proposed Guidance for Preparing and Reviewing a Molten Salt Non- Power Reactor Application, issued July 2020 (Ref. 12), to support the review of non-power molten salt reactors.

Purpose of Regulatory Guides

The NRC issues RGs to describe methods that are acceptable to the staff for implementing specific parts of the agencys regulations, to explain techniques that the staff uses in evaluating specific issues or postulated events, and to describe information that the staff needs in its review of applications for permits and licenses. RGs are not NRC regulations and compliance with them is not required. Methods and solutions that differ from those set forth in RGs are acceptable if supported by a basis for the issuance or continuance of a permit or license by the Commission.

Paperwork Reduction Act

This RG provides voluntary guidance for implementing the mandatory information collections in

10 CFR Parts 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).

These information collections were approved by the Office of Management and Budget (OMB), under control numbers 3150-0011 and 3150-0151, respectively. Send comments regarding this information collection to the FOIA, Library, and Information Collections Branch (T6-A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the OMB reviewer at: OMB Office of Information and Regulatory Affairs, (3150-0011 and 3150-

0151), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street, NW, Washington, DC, 20503; e-mail: oira_submissions@omb.eop.gov.

Public Protection Notification

The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB

control number.

RG 1.212, Rev. 2, Page 4

B. DISCUSSION

Reason for Revision

This revision of the RG (Revision 2) endorses, with some limitations and a clarification, IEEE Std. 485-2020 and applies to production and utilization facilities licensed under 10 CFR Part 50 and

10 CFR Part 52 within the scope of this RG. The previous version of this RG endorsed, with certain clarifications, IEEE Std. 485-2010. In 2020, the IEEE revised IEEE Std. 485 to refine the methods for defining dc load guidance and sizing large lead-acid batteries to ensure consistent performance. The revised IEEE standard provides a succinct document for the sizing of batteries with informative annexes.

The NRC staff determined that, based on the revised IEEE standard, a revision to this RG is needed to support applications for new reactor licenses, design certifications, and license amendments.

Background

This RG provides guidance to applicants and licensees for defining the dc load and sizing lead-acid batteries to supply the defined load for full-float stationary battery application

s. IEEE

Std. 485-2020 describes the recommended methods for defining the dc load and for sizing lead-acid batteries to supply dc power to applications during the full range of operating and emergency conditions.

IEEE Std. 485-2020 is an updated national consensus standard that adds new recommendations and guidance, as well as informative annexes, for both vented and valve-regulated lead-acid batteries for stationary applications. The standard was developed by the IEEE Power Engineering Society Stationary Batteries Committee and approved by the IEEE Standards Association Standards Board on May 6, 2020.

The standard is applicable to vented and valve-regulated lead-acid batteries and also describes some factors relating to cell selection. However, consideration of battery types other than lead acid is beyond the scope of this RG. Additionally, installation, maintenance, qualification, testing procedures, and design of the dc system and sizing of the battery charger(s) are beyond the scope of the IEEE standard and this RG.

It is important to recognize that IEEE Std. 485-2020 states it can be used as a standalone document. However, the NRC staff has found that using IEEE Std. 485-2020 in conjunction with IEEE Std. 450 and IEEE Std. 484 provides the user with a general guide to the design, installation, and maintenance of vented lead-acid batteries. In addition, the staff notes that IEEE/American Society of Heating, Refrigerating and Air Conditioning Engineers (ASHRAE) 1635-2022, Guide for the Ventilation and Thermal Management of Batteries for Stationary Applications, (Ref. 13) provides helpful ventilation calculations that are associated with IEEE Standard 484. For the design, installation, and maintenance of valve-regulated lead-acid (VRLA) batteries, the NRC staff reviewed IEEE Std. 1187, IEEE Recommended Practice for Installation Design and Installation of Valve-Regulated Lead-Acid Storage Batteries for Stationary Applications (Ref. 14), and IEEE Std. 1188, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Valve-Regulated Lead-Acid (VRLA) Batteries for Stationary Applications (Ref. 15), and found that the standards provide additional information and criteria for VRLA battery users.

The sizing methodology in IEEE Std. 485-2020 is very similar to that in IEEE Std. 485-2010. The approach consists of defining the load that the batteries will be required to support and using the guidance in the IEEE standard to determine the best battery for the application. To this end, IEEE Std. 485-2020

provides guidance on general considerations that should be included in defining the duty cycle; load classifications, including continuous, noncontinuous, and momentary loads; and the construction of a duty cycle diagram. In calculating the number of cells and minimum voltage section, IEEE Std. 485-2020

RG 1.212, Rev. 2, Page 5 cautions the user that the charging voltage needs to be recalculated and verified for adequacy if the numbers of cells are rounded off. It also discusses how to ensure all voltage drops are considered when calculating the allowable minimum voltage.

IEEE Std. 485-2020 discusses defining loads and other considerations but notes that for sizing purposes the loads can be treated as constant power or constant current. The updated annexes A, B, C, D,

E, F, G, and H are informative, and applicants and licensees should review them to assist with the battery design.

IEEE Std. 485-2020, section 4.2.5, Duty Cycle Diagram, states that the total time span of the duty cycle is determined by the requirements of the installation. This duty cycle time depends on the type of production and utilization facility design and is typically discussed in a plant safety analysis report.

This guidance does not apply to the emergency diesel generators (EDGs) or onsite emergency power sources own battery if provided separately (which is exclusively sized based on the starting requirement of the EDG or onsite emergency power source, such as field flash).

Consideration of International Standards

The International Atomic Energy Agency (IAEA) works with member states and other partners to promote the safe, secure, and peaceful use of nuclear technologies. The IAEA develops safety requirements and safety guides for protecting people and the environment from harmful effects of ionizing radiation. This system of safety fundamentals, safety requirements, safety guides, and other relevant reports reflects an international perspective on what constitutes a high level of safety. Pursuant to the Commissions International Policy Statement (Ref. 16) and Management Directive 6.6, Regulatory Guides (Ref. 17), the NRC considered the following IAEA safety guide and safety requirement in the development of the RG:

IAEA Safety Guide NS-G-1.8, Design of Emergency Power Systems for Nuclear Power Plants, (Ref. 18)

IAEA Safety Standards Series No. SSG-34, Design of Electrical Power Systems for Nuclear Power Plants, (Ref. 19)

Although the NRC has an interest in facilitating the harmonization of standards used domestically and internationally, the agency does not specifically endorse the IAEA documents listed above and is only acknowledging that such documents may be a useful reference for general information.

Documents Discussed in Staff Regulatory Guidance

This RG endorses, in part, the use of one or more codes or standards developed by external organizations, and other third-party guidance documents. These codes, standards and third-party guidance documents may contain references to other codes, standards, or third-party guidance documents (secondary references). If a secondary reference has itself been incorporated by reference into NRC

regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation. If the secondary reference has been endorsed in a RG as an acceptable approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific RG. If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in a RG, then the secondary reference is neither a legally-binding requirement nor a generic NRC-approved acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in

RG 1.212, Rev. 2, Page 6 the secondary reference, if appropriately justified, consistent with current regulatory practice, and consistent with applicable NRC requirements.

RG 1.212, Rev. 2, Page 7 C. STAFF REGULATORY GUIDANCE

The staff finds that IEEE Std. 485-2020 provides methods acceptable to the NRC staff for complying with the design requirements for stationary battery applications in full-float operation for production and utilization facilities, subject to the following limitations and a clarification:

1.

Annex A to IEEE Std. 485-2020 is informative and provides sample sizing demonstrations.

Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020

does not include endorsement of this annex.

2.

Annex B to IEEE Std. 485-2020 is informative and provides a method for estimating battery terminal voltage at various points in the battery duty cycle using the manufacturers typical discharge characteristics. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.

3.

Annex C to IEEE Std. 485-2020 is informative and provides a method for considering other cell types when selecting a battery for its intended application. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.

4.

Annex D to IEEE Std. 485-2020 is informative and provides a method for sizing a battery properly for a constant power application and for converting from either constant power loads or constant resistance loads to constant current. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.

5.

Annex E to IEEE Std. 485-2020 is informative and provides a method for describing the construction and use of the battery discharge characteristics curve. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.

6.

Annex F to IEEE Std. 485-2020 is informative and provides a method for addressing random loads and their application in the battery sizing process. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.

7.

Annex G to IEEE Std. 485-2020 is a full-size worksheet, Sizing Lead-Acid Batteries for Stationary Applications, and is endorsed as an accepted method for sizing lead-acid batteries.

8.

Annex H to IEEE Std. 485-2020 is informative and provides the bibliography. Unless otherwise stated in a separate regulatory position, endorsement of IEEE Std. 485-2020 does not include endorsement of this annex.

9.

The safety analysis report should discuss the battery duty cycle span. For active designs, the battery duty cycle should cover both DBA and SBO scenarios (with a permitted load shedding scheme). The minimum duty cycle for active designs for DBAs should be 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

RG 1.212, Rev. 2, Page 8

D. IMPLEMENTATION

The NRC staff may use this regulatory guide as a reference in its regulatory processes, such as licensing, inspection, or enforcement. However, the NRC staff does not intend to use the guidance in this RG to support NRC staff actions in a manner that would constitute backfitting as that term is defined in

10 CFR 50.109, Backfitting, and as described in NRC Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and

=

Information Requests

=

, (Ref. 20), nor does the NRC staff intend to use the guidance to affect the issue finality of an approval under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants. The staff also does not intend to use the guidance to support NRC staff actions in a manner that constitutes forward fitting as that term is defined and described in Management Directive 8.4. If a licensee believes that the NRC is using this regulatory guide in a manner inconsistent with the discussion in this Implementation section, then the licensee may file a backfitting or forward fitting appeal with the NRC in accordance with the process in Management Directive 8.4.

RG 1.212, Rev. 2, Page 9 REFERENCES 1

1.

Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 485-2020, IEEE

Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications, Piscataway, New Jersey.2

2.

U.S. Code of Federal Regulations (CFR), Domestic Licensing of Production and Utilization Facilities, Part 50, Chapter I, Title 10, Energy.

3.

CFR, Licenses, Certifications, and Approvals for Nuclear Power Plants, Part 52, Chapter I,

Title 10, Energy.

4.

U.S. NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 8.3.2, DC Power Systems (Onsite),

Washington, DC. (ADAMS Accession No. ML100740391)

5.

NRC, RG 1.129, Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities, Washington, DC.

6.

IEEE Std. 450, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications, Piscataway, New Jersey.

7.

NRC, RG 1.128, Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants, Washington, DC.

8.

IEEE Std. 484, IEEE Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications, Piscataway, New Jersey.

9.

NRC, NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Washington, DC, February 1996. (ML12156A069 and ML12156A075, respectively)

10.

NRC, Final Interim Staff Guidance Augmenting NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Parts 1 and 2, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors, Washington, DC,

October 17, 2012. (ML12156A053)

11.

NRC, Endorsement of Appendix A to Oak Ridge National Laboratory Report, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application, as

1 Publicly available NRC published documents are available electronically through the NRC Library on the NRCs public website at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html. For problems with ADAMS, contact the Public Document Room staff at 301-415-4737 or (800) 397-4209, or email pdr.resource@nrc.gov. The NRC Public Document Room (PDR), where you may also examine and order copies of publicly available documents, is open by appointment. To make an appointment to visit the PDR, please send an email to PDR.Resource@nrc.gov or call 1-800-397-

4209 or 301-415-4737, between 8 a.m. and 4 p.m. eastern time (ET), Monday through Friday, except Federal holidays.

2 Copies of Institute of Electrical and Electronics Engineers (IEEE) documents may be purchased from the Institute of Electrical and Electronics Engineers Service Center, 445 Hoes Lane, PO Box 1331, Piscataway, NJ 08855 or through the IEEEs public Web site at http://www.ieee.org/publications/index.html.

RG 1.212, Rev. 2, Page 10

Guidance for Preparing Applications for the Licensing of Non-Power Liquid Fueled Molten Salt Reactors, Washington, DC, November 18, 2020. (ML20251A008)

12.

Oak Ridge National Laboratory, ORNL/TM-2020/1478, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application, Oak Ridge, Tennessee, July 2020.

(ML20219A771)

13.

IEEE/American Society of Heating, Refrigerating and Air Conditioning Engineers (ASHRAE),

IEEE/ASHRAE 1635-2022, Guide for the Ventilation and Thermal Management of Batteries for Stationary Applications, Piscataway, New Jersey.

14.

IEEE Std. 1187, IEEE Recommended Practice for Installation Design and Installation of Valve-Regulated Lead-Acid Storage Batteries for Stationary Applications, Piscataway, New Jersey.

15.

IEEE Std. 1188, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Valve-Regulated Lead-Acid (VRLA) Batteries for Stationary Applications, Piscataway, New Jersey.

16.

NRC, Nuclear Regulatory Commission International Policy Statement, Federal Register, Vol. 79, No. 132, July 10, 2014, pp. 39415-39418.

17.

NRC, Management Directive 6.6, Regulatory Guides, Washington, DC.

18.

International Atomic Energy Agency (IAEA) Safety Guide NS-G-1.8, Design of Emergency Power Systems for Nuclear Power Plants, IAEA, Vienna, Austria, 2004.3

19.

IAEA, Safety Standards Series No. SSG-34, Design of Electrical Power Systems for Nuclear Power Plants, IAEA, Vienna, Austria, 2016.

20.

NRC, Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and

=

Information Requests

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, Washington, DC.

3 Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site:

www.IAEA.org/ or by writing the International Atomic Energy Agency, P.O. Box 100 Wagramer Strasse 5, A-1400 Vienna, Austria.


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