Regulatory Guide 1.158

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(Task Ee 006-5) Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants
ML003740047
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Issue date: 02/28/1989
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Office of Nuclear Regulatory Research
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RG-1.158
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February 1989 U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY (3UIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 1.158 (Task EE 006-5)

QUALIFICATION OF SAFETY-RELATED LEAD

STORAGE BATTERIES FOR NUCLEAR POWER PLANTS

B. DISCUSSION

A. INTRODUCTION

The Station Design Subcommittee, a subcommit The Commission's regulations in 10 CFR Part 50, tee of the Energy Development and Power Genera

"Domestic Licensing of Production and Utilization tion Committee of the Institute of Electrical and Elec Facilities," require that structures, systems, and com tronics Engineers (IEEE), has prepared IEEE Std ponents important to safety in a nuclear power plant 535-1986, "IEEE Standard for Qualification of Class be designed to accommodate the effects of environ 1E Lead Storage Batteries for Nuclear Power Gener mental conditions and that design control measures ating Stations."* The IEEE Standards Board ap such as testing be used to check the adequacy of proved the standard on September 19, 1985. This design. These general requirements are contained in standard describes qualification methods for Class 1E

General Design Criteria 1, 2, 4, and 23 of Appendix lead storage batteries and racks to be used in nuclear A, "General Design Criteria for Nuclear Power power plants outside of primary containment.

Plants," to Part 50; and in Criterion III, "Design 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 ria for Nuclear Power Plants and Fuel Reprocessing program that also includes requirements for design, Plants," to Part 50. production, quality control, installation, maintenance, and periodic testing. This regulatory guide addresses This regulatory guide describes a method accept only the qualification portion of the overall quality as able to the NRC staff for complying with Commis surance program.

sion regulations with regard to qualification of safety related lead storage batteries for nuclear power Batteries qualified by test should be precondi plants. tioned by natural or artificial (accelerated) aging to their end-of-installed-life condition, and The Advisory Committee on Reactor Safeguards consideration must be given to all significant types of has been consulted concerning this guide and has degradation that can have an effect on the functional concurred in the regulatory position. capability of the batteries. There are uncertainties re Any information collection activities mentioned garding the processes and environmental factors that in this regulatory guide are contained as requirements could result in such degradation. Because of these in 10 CFR Part 50, which provides the regulatory ba sis for this guide. The information collection require *Copies maybe obtained from the Institute of Electrical and Electron ments in 10 CFR Part 50 have been cleared under ics Engineers, IEEE Service Center, 445 Hoes Lane, P.O. Box 1331, Piscataway, NJ 08855.

OMB Clearance No. 3150-0011.

The guides are issued in the following ten broad divisions:

USNRC REGULATORY GUIDES The guides are issued in the following ten broad divisions:

pub Regulatory Guides are issued to describe and make available to the lic methods acceptable to the NRC staff of implementing specific parts 1, Power ReactorsTest Reactors 6.

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ton, DC 20555.

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 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 extent practicable. tion and operation schedules. However, in such cases, the previously qualified batteries IEEE 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

1E Lead Storage Batteries for Nuclear Power Gener for 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 qualification of safety-related lead storage batteries safety-related lead storage batteries for the following for nuclear power plants, subject to the following: nuclear power plants:

1. Plants for which the construction permit is issued Replacement batteries installed 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 there are sound reasons to the contrary. The is docketed after August 28, 1989.

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.

1.158-2

VALUE/IMPACT STATEMENT

BACKGROUND developing IEEE Std 535-1986, which is satisfactory and delineates an acceptable methodology for meet Large lead storage batteries are used in nuclear ing the Commission's regulations for qualification of power plants as a source of emergency power for vital safety-related lead storage batteries. Issuing a regula instrumentation and control 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 suitability for endorsement by regulatory ment channels, and certain other safety-related guides.

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

guidance for the qualification of safety-related lead 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 document that de plants 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 lead 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 batteries 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 cation of Class 1E Lead Storage Batteries for Nuclear with respect to the pre-aging part of the qualification Power Generating Stations," was published in Sep testing. Thus, this regulatory guide does not impose tember 1979. This standard needed several improve any new requirements or costs on current licensees ments. Since then the staff has worked with IEEE in or applicants.

1.158-3

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