ML20247F615

Reg Guide 1.158,Task Ee 006-5, Qualification of Safety- Related Lead Storage Batteries for Nuclear Power Plants

ML20247F615
Person / Time
Issue date:	02/28/1989
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
TASK-EE-006-5, TASK-EE-6-5, TASK-RE REGGD-01.158, REGGD-1.158, NUDOCS 8907270198
Download: ML20247F615 (3)

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cog U.S. NUCLEAR REGULATORY COMMISSION F bruary 1989.

g" h*****REGULATORY GU DE OFFICE OF NUCLEAR REGULATORY RESEARCH A

REGULATORY GUIDE 1.158 (Task EE 006-5)

QUALIFICATION OF SAFETY-RELATED LEAD STORAGE BATTERIES FOR NUCLEAR POWER PLANTS A. INTRODUCTION B. DISCUSSION The Commission's regulations in 10 CFR Part 50, The Station Design Subcommittee, a subcommit-

" Domestic Licensing of Production and Utilization tee of the Energy Development and Power Genera-Facilities," require that structures, systems, and com- tion Committee of the Institute of Electrical and Elec-ponents important to safety in a nuclear power plant tronics Engineers (IEEE), has prepared IEEE Std be designed to accommodate the effects of environ- 535-1986, "IEEE Standard for Qualification of Class mental conditions and that design control measures 1E Lead Storage Batteries for Nuclear Power Gener-such as testing be used to check the adequacy of ating Stations."' The IEEE Standards Board ap-design. These general requirements are contained in proved the standard on September 19,1985. This Gt.neral Design Criteria 1, 2, 4, and 23 of Appendix standard describes qualification methods for Class 1E A, " General Design Criteria for Nuclear Power lead storage batteries and racks to be used in nuclear Plants," to Part 50; and in Criterion III, " Design power plants outside of primary containment.

Control," and Criterion XVII, " Quality Assurance The safety-related batteries undergo a program of Records," of Appendix B, " Quality Assurance Crite- qualification as part of an overall quality assurance

[ j ria for Nuclear Pov tr Piants and Fuel Reprocessmg program that also includes requirements for design, (j Plants," to Part 50.

production, quality control, installation, maintenance, This regulatory guide describes a method accept- and periodic testing. This regulatory guide addresses able to the NRC staff for complying with Commis- only the qualification portion of the overall quality as-sion regulations with regard to qualification of safety- surance program.

related lead storage batteries for nuclear power Batteries qualified by test should be precondi-plants. tioned by natural or artificial (accelerated) aging The Advisory Committee on Reactor Safeguards to their end-of-installed-life condition, and has been consulted concerning this guide and has consideration must be given to all significant types of concurred in the regulatory position. degradation that can have an effect on the functional capability of the batteries. There are uncertainties re-Any information collection activities mentioned garding the processes and environmental factors that in this regulatoiy guide are contained as requirements c uld result m such degradation. Because of these in 10 CFR Part 50, which provides the regulatory ba-sis for this guide. The information co!!ection require-

• Copies may be obtained from the Institute of Electrical and Electron-ments .in 10 CFR Part 50 have been cleared under ics Engineers. lEEE Service Center, 44511oes lane, P.O. Ilox 1331, OMB Clearance No. 3150-0011. Piscataway, NJ 08855.

UsNFC REGtJLAToRY oUIDEs The guides are issued in the following ten broad divisions:

Regulatory ouides are issued lo describe and make available to the pua- j lic methods acceptable to the NRC staff of implementing specific parts of the Commission's regulatio9s. to dellneate techniques used by the 1. Power Reactors 6. Products i staff in evaluating specific problems or postulated accidents, or to pro- 2. Research and Test Reactors 7. Transportation >

3. FuMs and Materials FaciL1ses D. occupational Health {

vide guidance to appucants. Regutatory Guktes are not substitutes for 4. Environmental and Siting g. Antit*ust and Financial Review I regulations, and compliance with them is not required. Methods and S. Materials and Plant Protection 10. General J solutions different from those set out in the Guides will be acceptable if tney provide a basis for the fincings requ} site to the issuance or continu-ance of a permit or llcerse by the Commission. Copies of lesued guides may be purchased from the Government Printing This guide was issued after cor:sideretion of comments received from Office at the current GPO price. Information on current GPO prices may g [rw\ the pubilC. Comments and suggestions for improvements in these be obtairwxl by contacting the Superintendent of Documents, U.S. i f i guides are encouraged at a:t tirms, and guides will be revised. as ap. Governrnent Pnnting office. Post Office Bon 37C82. Washington, oC

\ ) propriate, to accommodate comrmnts and to reflect new information or 20013-7082. telephone (202)275-2060 or (202)275-2171.

%/ experience.

Written comments may be submitted to the Regulatory Pubhcations issued guidos may also be purchased from the National Technical Infor-

[ Dranch, DRPS, ARM, U S. Nuclear Regulatory Commission Washing- mation Serv 6ce on a standing order basis. Details on this service may be ton, DC 20555. obtained by wnting NTiS, 5285 Port Royal Road. Spnngfield. VA 22161.

- 8907270198 890228 PDR REGGD 01.158 R PDR _ _ _ _ _ _ - _ - _ _ _ __ - _ _ _ _ _ _ _---___--__ - __ _ _

I uncertainties, state-of-the-art preconditioning tech- (a) A purchase order for the identical batteries to niques as outlined in IEEE Std 535-1986 are not be used for replacement was issued prior to capable of simulating all significant types of degrada- February 28, 1989.

tion. As the state of the art advances and uncertain-ties are resolved, artificial preconditioning techniques (b) Replacement batteries qualified in accor- g may become more effective. Until such time, the dance with the provisions of IEEE Std ,

NRC staff prefers natural pre-aging of safety-related 535-1986 are not available to meet installa- {

batteries to the exten practicable, tion and operation schedules. However, in j such cases, the previously qualified batteries ~j 1EEE Std 535-1986 references other standards may be used no longer than the design life of that contain valuable information. Those referenced the batteries after the upgraded batteries be-standards not endorsed by a regulatory guide or in- come available from the manufacturer, corporated into the regulations, if used, are to be used in a manner consistent with current regulations.

D. IMPLEMENTATION The purpose of this section is to provide informa-C. REGULATORY POSITION tion to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.

Conformance with the requirements of IEEE Std Except in those cases in which the applicant or 535-1986, "IEEE Standard for Qualification of Class licensee proposes an acceptable alternative method j 1E Lead Storage Batteries for Nuclear Power Gener. f r complying with specified portions of the Commis-ating Stations," provides an acceptable method for sion's regulations, the methods described herein will ,

satisfying the Commission's regulations with respect to be used in the evaluation of the qualification of i qualification of safety-related lead storage batteries safety-related lead storage batteries for the following for nuclear power p; ants, subject to the following: nuclear power plants:

1. Plants for which the construction permit is issued Replacement batteries instal!ed subsequent to Feb- after February 28, 1989.

ruary 28,1989, should be qualified in accordance with the provisions of IEEE Std 535-1986 unless 2. Plants for which the operating license application j

there are sound reasons to the contrary. The is docketed after August 28, 1989. l NRC staff considers the following to be sound rea-sons for the use of previously qualified batteries in 3. All operating nuclear power plants that replace lieu of upgrading: batteries, i

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VALUE/ IMPACT STATEMENT g3 CACKGROllND dev* loping IEEE Std 535-1986, which is satisfactory (y) ' arge lead storage batteries are used in nuclear and delineates an acceptable methodology for meet-ing the Commission's regulations for qualification of power plants as a souNe of emergency po'ver for vital safety-related lead storage batteries. Issuing a regula-instrumentation and cor. trol systems such as electrical tory guide is consistent with the NRC policy of evalu-distribution breaker controls for engineered safety ating the latest versions of national standards in terms features, inverters for the reactor protection instru' of their sudbility for endorsement by regulatory ment channels, and certain other safety-related guides.

equipment. Since safety-related lead storage batteries must meet user specifications throughout the batter- This guide endorrr IEEE Std 535-1986 without les' installed life, the batteries under;;o a program of any exceptions, and conformance with the require-qualification as part of an overall quality assurance ments of IEEE Std 535-1986 constitutes an accept-program that also includes requirements for design, able method of compipag with the Commission's production, quality control, instal'atica, maintenance, regulations. The Regulatory Position provides regula-and periodic testing. This guide provides regulatory tory guidance for replacement batteries. This guide guidance for the qualification of safety-related lead should enhance the licensing process.

storage batteries used in nuclear power plants.

IMPACT VALUE This regulatory guide is consistent with current  !

NRC practice. It applies to future nuclear power There is no published NRC dacument that de-Pl ants and to operating nuclear power plants for re-scribes methods acceptable to the NRC staff for quali-

. placement batteries. All U.S. battery manufacturers fying safety-related Aead Storage batteries. As a conse-have already qualified their batteries to the provi-quence, license reviews of safety-related lead storage sions of IEEE Std 535 1979 or 1986. Also, the staff batterie are being done on a case-by-case basis.

has concluded that there is no significant difference  ;

IEEE Std 535-1979, "IEEE Standard for Qualifi- between the 1979 and 1986 versions of IEEE Std 535 l

[_} cation of Class 1E Lead Storage Batteries for Nuclearwith respect to the pre-aging part of the qualification 1

( / Power Generating Stations," was published in Sep- testing. Thus, this regulatory guide does not impose j tember 1979. This standard needed several improve- any new requirements or costs on current licensees ments. Since then the staff has worked with 1EEE in or applicants.

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