ML20205Q373
| ML20205Q373 | |
| Person / Time | |
|---|---|
| Issue date: | 10/02/1986 |
| From: | Beckjord E NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Sniezek J Committee To Review Generic Requirements |
| Shared Package | |
| ML20204J261 | List: |
| References | |
| FOIA-87-714, RTR-REGGD-1.156, TASK-EE-404-4, TASK-RE NUDOCS 8811090210 | |
| Download: ML20205Q373 (11) | |
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yf OCT 2 1986 R MEMORANDUM FOR: James H. Sniezek, Chainnan Committee to Review Generic Requirements FROM: Eric S. Beckjord, Director Office of Nuclear Regulatory Research
SUBJECT:
CRGR REVIEW - REGULATORY GUIDE. EE 404-4, ORAFT 2 "QUALIFICATION OF CONNECTION ASSEMBLIES FOR NUCLEAR POWER PLANTS" BACKGROUND: i IEEE Std 572-1985, "Qualification of Class 1E Connection Assemblies for l Nuclear Power Generating Stations," was )repared by Subcomittee 2 of the Nuclear Power Engineering Comittee of t1e Institute of Electrical and Electronics Engineers. Issuance of this regulatory guide which endorses IEEE Std 572-1985 is consistent with NRC policy of evaluating the latest versions of national standards in terms of their suitability for endorsement by regulatory guides.
CRGR approval to issue Regulatory Guide EE-404-4 for public coment is requested.
DISCUSSION:
This Regulatory Guide endorses IEEE Std 572-1985, without any exceptions.
IEEE Std 572-1985 prescribes specific methods for the qualification of safety-r) lated connection assemblies; for example, quick disconnect connection assemblies and environmental seals in corbination with cables as assembites.
All referenced standards not endorsed by NRC are expected to be used in a manner consistent with current regulatory practice.
l STAFF COMMENTS AND RESOLUTIONS:
Draft 1 of this Regulatory Guide was deve~,oned by RES and reviewed by NRR and l IE. All substantive coments have been resulved and, where appropriate, have been incorporated into the guide. Concurrences on this mernorandum have been obtained from the Directors of NRR, IE and OGC.
CONTACT:
S. K. Aggarwal, DES /RES 44-37840 l
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James H. Sniezek OCT 2 1986 VALUE AND IMPACT:
This guide does not impose any new requirements or costs on licensees or applicants. No impact will result from issuance of t.Ms guide with respect
- to the requirements in effect at this time.
Eric S. Beckjord Dtl ector Office of Nuclear R6qulatory Research ;
Enclosures (15copieseach):
- 1. Regulatory Guide EE 404-4, ,.
Draft 2, dated Scpt. 1986 ,.
- 2. CRGR Sumary
- 3. IEEE Std 572-1985 I
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S. X. Aggarwal (301) 443-7840 REGULATORY GUIDE TASK EE 404-4 ENVIRONMENTAL QUALIFICATION OF CONNECTION ASSEMBLIES FOR NUCLEAR POWER PLANTS A. INTRODUCTION Criterion III, "Design Control," of Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires, among other things, that, where a test program is used to verify the adequacy of specific design features, it include suitable qualifi ation testing of a prototype unit under the most adverse design conditions.
Section 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants," 10 CFR Part 50, requires that
< rertain electric equipnunt important to safety be qualified for its application and specified performance, and provides requirements for
, establishing environmental qualification methods and qualification parameters.
This regulatory guide describes a method acceptable to the NRC staff for complying with the Comission's regulations with regard to the environmental qualification of quick disconnect connection assemblies, and environmental seals in combination with cables or wires as assemblies, for service in nuclear power plants, to ensure that connection assemblies can perform their safety functions during and after a design basis event.
B. DISCUSSION IEEE Std 572-1985, "Qualification of Class IE Connection Assemblies for Nuclear Power Generating Stations," published September 1985, was prept. red by September 8,1986 Draft 2 GNCLOSURE\
Subcommittee 2, "Qualification," of the Nuclear Power Engineering Comittee of the Institute of Electrical and Electronics Engineers (IEEE) and was approved by the IEEE Standards Board on December 13, 1984. This standard describes basic procedures for qualifying connection assemblies (for example, quick disconnect connection assemblies and environn, ental seals in combination with cables as assemblies).
The guidance for seismic and dynamic qualification for this equipment is covered in Regulatory Guide 1.100 (Rev.1), "Seismic Qualification of Electric Equipment for Nuclear Power Plants."
650.49 of 10 CFR Part 50 defines three categories of electric equipment which are required to be environmentally qualified: (1) safety-related equipment, (2) non safety-related equipment whose failure could adversely affect safety-related equipment and (3) certain post accident monitoring equipment. This regulatory guide provides an acceptable method of qualifying quick disconnect connection assemblies, ano environmental seals in combination with cables or wires as assemblies, for all three categories of equipment.
IEEE Std 572-1985 contains references to other national standards. Thuse referenced standards not endorsed by NRC are expected to be used in a manner consistent with regulatory practice.
C. REGULATORY POSITION When used in conjunction with Regulatory Guide 1.89 (Rev.1),
"Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants," the procedures described by IEEE Std 572-1985 are l acceptable to the NRC staff for satisfying the Comission's regulations i pertaining to the environmental qualification of quick disconnect connection assemblies, and environmental seals in combination with cables or wires as
- assemblies, for service in nuclear power plants to ensure that the connection
- assemblies can perfonn their safety functions.
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D. IMPLEMENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.
Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Comission's regulations, the methods described herein will be used in the evaluation of the qualification of connection assemblies, within the scope of this guide, for nuclear power plants as follows:
- 1. Plants for which the construction pennit is issued after (issue date of guide).
- 2. Plants for which the operating license application is docketed 6 months or more after (issue date of guide).
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- 3. Plants for which the applicant or licensee voluntarily consnits to the provisions of this guide. '
VALUE/ IMPACT STATEMENT BACKGROUND:
Heretofore, no specific guidance for the qualification of connection assemblies has been published by NRC.* In September 1985, IEEE issued IEEE ,
Std 572-1985, which provides specific guidance for the qualification of !
connection assemblies for use in nuclear power plants. This regulatory guide ;
endorses IEEE Std 572-1985 without any exceptions. l l
- Draft Pegulatory Guide 1.131, "Qualification Tests of Electric Cables, Field l Splices and Connections for Light-Water-Cooled Nuclear Power Plants," was issued for public coment in August 1977 but never published as an effective guide, i
September 8, 1986 Draft 2
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4 VALUE/ IMPACT ASSESSMENT:
2.1 Value The standard endorsed by this regulatory guide represents a national consensus on qualification methods to assure the reliability and functionality of connection assemblies used in nuclear power plants.
It provides a standardized approach so that industry and the NRC staff may have a common understanding on connection assembly qualification and testing procedures, thus minimizing relevant engineering costs by the applicant and review costs for the staff.
2.2 Impact This regulatory guide does not impose any new costs or obligations on licensees or applicants. Thus, no impact will result from issuance of this guide. The guidance was developed through the national consensus standards process and reflects current NRC and industry practice.
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I September 8, 1986 Draft 2 f
SUMARY OF PROPOSED REGULATORY GUIDE FOR CRGR REVIEW OFFICE OF NUCLEAR REGULATORY RESEARCH DATE: September 8, 1986 RES TCF NO.: EE 404-4 RES PROGRAM MANAGER: S. K. Aggarwal Telephone: 443-7840 TITLE OF PROPOSED ACTION:
Proposed Regulatory Guide EE 404-4, "Qualification of Connection Asses 611es for Nuclear Power Plants," Draft 2 STATEMENT OF THE PROBLEM:
This Regulatory Guide endorses IEEE Std 572-1985. By this
- action, the staff has evaluated the latest version of a national standard in terms of its suitability for endorsement by a regulatory guide.
OBJECTIVE:
The objectives is to endorse a national consensus standard and, thereby, provide licensees and applicants with the NRC staff's position with regard to its use.
CONSEQUENCES:
This action is consistent with NRC policy of evaluating the latest versions of national standards in tenns of their suitability for endorsement by regulatory guides.
DECISION RATIONALE The guide should be issued to inform licensees and applicant of the current staff position on IEEE Std 572-1985 and to reduce staff effort during the licensing review process.
IMPLEMENTATION:
The guide will be used in the evaluation of the qualification ,
of connection assemblies for nuclear power plants as follows: -
- 1. Plants for which the construction permit is issued after (issuedateofguide).
- 2. Plants for which the operating license application is docketed 6 months or more af ter (issue date of guide).
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- 3. Plants for which the applicar.t or licensee voluntarily ccesits to the provisions of this guide, eMc LOSugg 2.
- g5,-& lc ffc) n Octob e 1985 Contac S. K. Aggarwal (301) 443-7840 REGULATORY GUIDE EF 606-5 0UALIFICATION OF S/M TY-RELATED LEAD STORAGE BATTERIES FOR MUCLEAR POWER PL ANTS A. INTR ^0UCTION The Comission's regulations in 10 CFR Part 50, "Domestic Lice ising of Production and Utilization Facilities," require that structures, systems, and components important to safety in a nuclear power plant be designed to accomodate the s 'fects of environmental conditiens and that design control measures such , isting be used to check the adecuacy of design. These gener.1 requirev ts are contained in General Design Criteria 1, 2, 4 and 23 of Apnendix A. "General Design Criteria for Nuclear Power Plants," to Part 50; in Criterion III, "Design XVII, "Cuality Assurance Records," of Appendix B."
Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to Part 50.
This regulatory guide describes a method acceptable to the NRC stafi for complying with Comission regulations with regard to qualification of ,
safety-related lead storage batteries for nuclear power plants.
B. DISCUSSION IEEE Std 535-1986, "!EEE Standard for Oualification of Class IE Lead Storage Batteries for Nuclear Power Generating Stations," was prepared by Station Design Subcomittee of the Institute of Electrical and Electronics Engineers (IEEE) and was approved by the IEEE Standards Board on September 19, 1985. The standard describes qualification methods for Class 1E lead storage batteries, and racks, to be used in nuclear power plants outside of primary containtrent . ,
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f Since safety-related lead storage batteries rust meet or exceed design i specificatiens throughout their installed life, the batteries undergo a [
program of eualification as a part of an overall quality ass *Jrance program that i also includes requirements for design, production, quality controle 3 installation, maintenance, and periodic testing. This regulatory guide t addresses only the qualification portion of the overall cuality assurance i program.
i IEEE Std 535-1986 references other standards that contain valuable ,
information. Those referenced standards not endorsed by a regulatory guide or i incorporated into the regulation, if used, are to be used in a manner con- ,
j sistent with current regulations.
C. REGULATORY POSITION i
, Conformance with the requirerents of IEEE Ste 535-1986, "! FEE Standard for '
Qualification of Class 1E Lead Storage Batteries i'or Nuclear Power Generating Stations," provides an acceptable method for satisfying the Cnmmissfr 's regulations with respect to qualification of safety-related lead ster ge batteries for nuclear power plants. 6 D. IMPLEF.ENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans foi using this regulatory guide.
Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified pertions of ?he Commission's regulations, the methods described !,erein will be used in the tviluation of the qualification of safety-related lead storage batteries for nc: lear power plants as follows:
I Draft 1 2 Oct 14,1966
f (1) Plants for which the construc(; ion pennit is issued after (issue date of this guide).
(2) Plants for which the operating license applicattor is docketed 6 months or rore after (issue date of this guide).
(3) Plants for which the applicant or licensee voluntarily comits to the provisions of this guide.
VALUE/ IMPACT STATFMENT BACKGROUND Large lead storage batteries are used in nuclear power plants as a source of emergency power for vital instrumentation and control systems such es electrical distribution breaker controls for engineered safety features, inverters for the reactor protection instrument channels, and certain other safety related equipment. Since safety related lead storage batteries must meet design specifications throughout the batteries' installed life, the batteries undergo a program of qualification as part of an overall quality assurance program that also includes requirements for design, production, quality control, installation, maintenance, and periodic testing. This guide provides specific, detailed regulatory guidance for the qualification of safety related lead storage batteries used in nuclear power plants.
Value 4
There is no NRC published document that describes methods acceptable to the NRC staff for qualifying safety-related lead storage batteries. As a consequence.
license reviews of safety-nlated lead storage batteries are being done on a case-by-case basis.
IEEE Std 535-1979, IEEE Standard for Qualification of Class IE Lead Storage Batteries for Nuclear Power Generating Stations," was published in September 1979. This standard needed several improvements. Since then the staff has worked with IEEE in development of IEEE 535-1986, which is satisfactory and meets the Comission's regulations for qualification of safety-related lead storage batteries. Issuance of the Regulatory Guide is consistent with the NRC policy of evaluating the latest versions of national stancards in terms of ,
their suitability for enc'orsement by regulatory guides, ,
Thus, this guide endoru s IEEE 535-1986 without any exceptior.s and concludes that conforrance with the requirements of IEEE 535-1986 constitutes an acceptable method of complying with the Cce ission's regulations. This guide should enhance the licensing process. ,
Draft 1 3 Oct 14, 1986
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Impact This regulatory guide is consistent with current NRC practice. It applies to '
future nuclear power plants and has no backfit provisions. Thus, this regulatory guide does not impose any new requirements or cos,ts on current
licensees or applicants. Use of the guide by the current licensees or applicants is voluntary.
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