Regulatory Guide 1.128
| ML003740099 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1978 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| RG-1.128, Revision 1 | |
| Download: ML003740099 (3) | |
Revision 1 October 1978 U.S. NUCLEAR REGULATORY COMMISSION
) REGULATORY GUIDE
OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE 1.128 INSTALLATION DESIGN AND INSTALLATION OF LARGE LEAD
STORAGE BATTERIES FOR NUCLEAR POWER PLANTS
A.
INTRODUCTION
General Design Criterion 1, "Quality Stand ards and Records," of Appendix A,
"General Design Criteria for Nuclear Power Plants," to
"Domestic Licensing of Pro duction and Utilization Facilities,"
requires that structures, systems, and components im portant to safety be designed, fabricated, erected, and tested to quality standards com mensurate with the importance of the safety functions to be performed.
Criterion
17,
"Electric Power Systems,"
of Appendix A
requires an onsite electric power system and an offsite electric power system to be provided to permit functioning of structures, systems, and components important to safety. Criterion III,
"Design Control,"
of Appendix B,
"Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part
50
requires that design
- control measures include provisions to ensure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled.
This guide describes a method acceptable to the NRC staff for performing the installation design and installation of large lead storage batteries for all types of nuclear power plants.
The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
B.
DISCUSSION
"IEEE
Recommended Practice for Installation Design and Installation of Large Lead Storage Batteries for Generating Stations and Substations," dated January 27, Lines indicate substantive changes from previous issues.
'Copies may be obtained from the Institute of Electrical and Electronics Engineers, United Engineering Center, 345 East 47th Street, New York, New York 10017.
USNRC REGULATORY GUIDES
Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evalu ating specific problems or postulated accidents, or to piovide guidance to applicants. Regulatory Guides are not substitutes for regulations, and conm pliance with them is not required. Methods and solutions different from those set out in the guides will be accepta if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.
Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as app rate, to accommodate comments and to reflect new information or experience This guide was revised as a result of substantive comments received from the public and additional staff review.
1975, was prepared by the Working Group on Batteries, Station Design Subcommittee of the Power Generation Committee, add was approved by the IEEE Standards Board on September 5,
1974. It was subsequently approved and des ignated N41.24-1976 by the American National Standards Institute on January 15, 1976.
Immediately following the Browns Ferry fire on March 22,
1975, NRC appointed a Special Review Group to identify the lessons learned from this event and make recommendations for the future in light of these lessons. The Re view Group published its report in February
1976.2 Among other recommendations, the Re view Group recommended that greater attention be given to fire prevention measures in nuclear power plants. The lessons learned and brought out in the report are appropriate for applica tion to batteries and battery installations. Por tions of IEEE Std 484-1975 are directed toward preventing battery-related fires and explo sions.
These portions of the standard have been supplemented in the regulatory position of this guide with additional information that takes into consideration the recommendations on fire prevention of the Special Review Group. In addition to the requirements of the standard, the recommendations were evaluated with respect to importance to safety. Certain recommendations were considered to be of sufficient importance to safety to be endorsed along with the requirements given in the standard.
The provisions of the standard include design practices and procedures for storage, location, mounting, ventilation, instrumenta tion, preassembly, and assembly of large lead
2 NUREG-0050,
"Recommendations Related to Browns Ferry Fire," Special Review Group, USNRC, February 1976. Copies may be obtained from the National Technical Information Serv ice, Springfield, Virginia 22161.
Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 2056M, Attention: Docketing and Service Branch.
The guides are issued in the following ten broad divisions:
1. 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
10. General Requests for single copies-of issued guides (which may be reproduced) or for placement on an automatic distributioni list for single copies of future guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, D.C.
20566.
Attention: Director, Division of Technical Information and Document Control.
sealed-cell storage batteries. Safety practices are also included.
C.
REGULATORY POSITION
Conformance with the requirements (indi cated by the verb "shall") specified by IEEE Std 484-1975 for installation design and instal lation of large lead storage batteries for nuclear power plants provides an adequate basis for complying with the design, fabrica tion, erection, and testing requirements of Criteria 1 and 17 of Appendix A and Criterion III of Appendix B to
10 CFR Part 50 with respect to quality standards applied to installa tion design and installation of large lead storage batteries, subject to the following:
1. In Subsection 4.1.4, "Ventilation,"
in stead of the second sentence, the following should be used:
"The ventilation system shall limit hydro gen concentration to less than two percent by volume at any location within the bat tery area."
2. In Subsection 4.2.1, "Location," item 1 The general requirement that the battery be protected against fire should be supplemented with the applicable recommendations in Regula tory Guide 1.120, "Fire Protection Guidelines for Nuclear Power Plants."
3. Items 1 through 5 of Subsection 4.2.2,
"Mounting," should be supplemented with the following:
"6. Restraining channel beams and tie rods shall be electrically insulated from the cell case and shall also be in conformance with item 2 above regarding moisture and acid resistance."
In addition, the general requirement in item 5 to use IEEE
Standard
344-1975 should be supplemented by Regulatory Guide
1. 100,
"Seismic Qualification of Electric Equipment for Nuclear Power Plants."
4. In Subsection 5.3.2, "Acceptance Test,"
instead of IEEE Std 450-1972, IEEE Std 450
1975 should be followed.
5. Section 7, "References," of IEEE Std 484
1975, lists reference documents. The specific applicability or acceptability of these referenced documents has been or will be covered separately in other regulatory guides where appropriate.
6. In addition to the requirements of the standard, the recommendations (indicated by the verb "should") contained in the sections of IEEE Std 484-1975 noted below (including supplementary material) have sufficient safety importance to be treated the same as the re quirements of the standard.
a. Subsection 4.1.1,
"Location," item 2 The recommendations that address the need for a well-ventilated location with adequate aisle space and space above cells.
b. Subsection 4.1.1, "Location," item 4 The recommendations that address temperature differential between cells at a given time and the avoidance of localized heat sources.
c. Subsection 4.1.1, "Location," item 5 The recommendation set forth in item 5 that addresses the provisions for containing or safely dispersing spillage from water facilities, supplemented with the following:
"Where stationary water facilities are provided within the battery room, their design should be such as to preclude any inadvertent spilling of water from these facilities on the battery installation itself."
d. Subsection 4.1.2, "Mounting," item 2 The recommendation that addresses the number of tiers or steps for mounting batteries.
e. Subsection 4.1.5, "Instrumentation and Alarms"-The three items liste
d. Instead of the
"NOTE"
following the last paragraph of Subsection
4.1.5, the following should be used:
"NOTE: The preceding recommendations for instrumentation and alarms could be satisfied by equipment in the d.c. system, with the exception of items 4 and 5."
In addition, the three listed items should be supplemented with the following items:
"4. Ventilation air flow sensor(s)
and alarm(s) in the control room.
"5. Fire detection sensor(s), instrumenta tion, and alarm(s)."
f. Subsection 5.1.2, "Unpacking," item 3 The recommendation that any cell that exhibits an electrolyte level 1/2 inch or more below the top of the plates be replaced.
g. Subsection 5.1.3, "Storage," item 1 The recommendation that cells not be exposed to extremely low ambient temperatures or local ized sources of heat during storage.
h. Subsection
5.2.3,
"Preoperational Care," with "IEEE Std 450-1975" used in lieu of
i. The eight items listed in Subsection
5.3.1,
"Freshening Charge,"
supplemented with the following item:
"9. At the completion of Item 7 above, a hydrogen survey should be performed to verify that the design criteria required by Position 1 are met (see Section 6,
"Re cords")."
1.128-2 t
j. The five items listed in Section 6, "Re cords," supplemented with the following item:
"6. Initial hydrogen survey data for future reference."
D.
IMPLEMENTATION
The purpose of this section is to provide information to applicants regarding the NRC
staff's plans for using this regulatory guide.
Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used in the evaluation of submittals for construction permit applications docketed after December 1, 1977.
If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or before December 1,
1977.
the pertinent portions of the application will be evaluated on the basis of this guide.
1.128-3