ML20150A735

Rev 2 to Reg Guide 1.100,Task Ee 108.5, Seismic Qualification of Electric & Mechanical Equipment for Nuclear Power Plants

ML20150A735
Person / Time
Issue date:	06/30/1988
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
TASK-EE-108-5, TASK-RE REGGD-01.100, REGGD-1.100, NUDOCS 8807080179
Download: ML20150A735 (4)

Text

- -

Revision 2 l

[%s

• l e . U .S. NUCLEAR REGULATORY COMMISSION June 1988

!"/4 REGULATORY GUIDE

% .... OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1,100 (Task EE 108-5)

SEISMIC QUALIFICATION OF ELECTRIC AND MECHANICAL EQUIPMENT FOR NUCLEAR POWER PLANTS  !

A. INTRODUCTION combination with normal operating loads. The engineer-ing method used to ensure that the rqtiired safety The Commission's regulations in 10 CFR Part 50, fuoctions are maintained durmg and after the vibratory "Domestic ! ieensing of Production and Utilization ground motion associated with the safe shutdown earth-Facilities," require that certain structures, systems, and quake or the operating basis earthquake must invol e components in a nuclear power plant be designed to the use of either a suitable dynamic analysis or a suit-withstand the effects of natural phenomena such as able qualification test to demonstrate that struct' ires, earthquakes and that design control measures such as systems, and components can withstand the seismic and testing be used to check the adequacy of design. This other concurrent loads.

general requirement is contained in Appendix A, "Gen-eral Design Criteria for Nuclear Power Plants," to Part This regulatory guide describes a method acceptable 50; in Criterion Ill, "Design Control," and Criterion to the NRC staff for complying with NRC's regulations XVil, "Quality Assurance Records," of Appendix B, with respect to seismic qualification of electrie and "Quality Assurance Criteria for Nuclear Power Plants mechanical equipment, and Fuel Reprocessing Plan ts," to Part 50; and in Appendix A, "Seismic and Geologic Siting Cnteria for The Advisory Committee on Reactor Safeguards has Nuclear Power Plants," to Part 100, "Reactor Site been consulted concerning this pide and has concurred Criteria." in the regulatory position.

In Apptndix A to 10 CFR Part 100, Section VI, Any information collection activities mentioned in l

"Application to Engineering Design," requires that the this regulatory guide are contained as requirements in l 10 CFR Parts 50 or 100, which provide the regulatory nuclear power plant be designed so that, if the safe l

shutdown earthquake occurs, certain structures, systems, basis for this guide. The information collection require-and components will remain functional. These satety- ments in 10 CFR Pets 50 and 100 have been cleared related structures, systems, and components are those under OMB Clearance Nos. 3150-0011 and 3150-0093, necessary to ensure (1) the integrity of the reactor cool- respectively.

ant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe condition, or (3) B. DISCUSSION the capability to prevent or mitigate the consequences of accide nts that could result in offsite exposures IEEE Std 344-1987, "Recommended Practice for comparable to the Part 100 guidelines. In Appendix A Seismic Qualification of Class 1E Equipment for Nuclear l Power Generating Stations,"' was prepared by Working to Part 100, Section Vi(a)(2) requires that structures, systems, and components of the nuclear power plant Group 2.5 (Seismic Qualification) of Subcommittee 2 necessary for continued operation without undue risk to ti quipment Qualification) of the Institute af Ilectrical the health and safety of the public be designed to re-main functional and within applicable stress and defor- * "*

mation limits w hen subjected to the effects of the j$$'inIes i nrineers INI ervi [r$4 ffoe#s Lane, vibratory motion of an operstmg basis carthquake in P.O.15ax 1331, hscataway, NJ 08855.

j USNRC REGULATORY GUIDES The guides are issued 6n the following ten broad divisions:

( Regulatory Guides are issued to describe and make available to the 1, Power Reactors 6. Products public methods acceptable so the NRC staff of im plemen tin g 7. Transportat6on speciflc parts of the Commission's regulations, to delineate tech- 2. Research and Test Reactors 8. Occupational Heaff h niques used by the staff in evaluating specific problems or postu- a. Fuels and Materials F acshties tated accidents, of to provide guidante to appl 6 cants. Regulatory 4. E nvironmental and Siting 9. Antstrust and Financial Review Guides are not substitutes for regulations, and complisnce with S. Matsrials and Plant Protection IJ. General them is not required. Methods and setations dsf ferent f rom those set I

out in the guldes will be acceptable h they provide a basis for the Cop.es of issued guides may be purchased f rom the Government findings requisite to the issuance or sontinuance of a permit or Printing Of fice at the current GPO price, information on current license by the Commission. GPO prices may be obtained by contacting the Superintendent of This guide was issued af ter considerat6on of comments received from Doc u m ent s. U.S. Government Printing Of fice, Post O f fic e Boa the public. Comments and suggestions for improvements 6n these 3 7082, Washington, DC 20013-7082, 'eleonone (202)2 75-2060 or guides are encouraged at all times, and guides will be revised, as (202)275 2171.

appropriate, to accommodate comments and to reflect new informa-l tion or emperience, issued guides may also be purchased from the Nat6onal Technical Wr6tten Comments relay be submitted to the Rules and Proccdures i n f or matio n Se rvic e on a standing order basis. Detaals on thes l

Branch, DRR ADM, U .S . Nuclear R egulat ory Commiss#on, service may be obta6ned by writing N TIS, $26$ Port Royal Road, Washington, Od. 20555. Spr m9 field, V A 2 2161.

t I 8807080179 880630 ()qG PDR REGGD W Y ClL MoX0 FA PNU olsl

1 and Electronics Engineers (IEEE) Nuclear Power Engi- This method of qualification will be evaluated by the neering Committee, and was subsequendy approved by NRC staff on a case-by-case basis.

the IEEE Standards Board on June 11,1987.

IEEE Std 344-1987 references other standards that The IEEE standard includes principles, procedures, contain valuable information. Those referenced standards and methods of seismic qualification that, when satis- not endorsed by a regulatory guide or incorporated into fied, will confirm the adequacy of the equipment the regulations, if used, are to be used in a manner design for the performance of safety functions before, consistent with current regulations.

during, and after the time the safety-relate.! equipment is subjected to high stresses resulting from design basis even ts. I%r this guide, the design basis events are the C. REGULATORY POSITION loadings imposed by seismic events: the operating basis earthquake (OBE) and the safe shutdown earthquake The procedures described by IEEE Std 344-1987, (SSE). It is also necessary to combine other dynamic or "Recommended Practice for Seismic Qualification of vibratory loads as part of seismic qualification. It is Claw 1E Equipment for Nuclear Power Generating recognized that hydrodynamic loads have their primary Stations," are acceptable to the NRC staff for satisfying energy content in a frequency range greater than that of the Commission's regulations pertaining to seismic seismie vibrations; hwever, they are a part of the qualification of electric and mechanical equipment inplant equipment aging process, along with other non- subject to the following:

seismic vibration loads, and therefore should be con-sidered in seismic testing. For mechanical equipment, thermal distortion effects on operability should be considered, and loads imposed Revisioa I of this guide was issued in August 1977. by the attached piping should also be accounted for.

Since then, several new technical issues have arisen, such as treatment of hydrodynamic loads, the limits of If dynamic testing of a pump or a valve assembly is generic testing, the treatment of rattling, methods of impractitable, static testing of the assembly is acceptable quahfying line-mounted devices, and the use of actual provided that (1) the end loadings are applied and are seisraic ex perience data bases to qualify identical or equal to or greater than postulated event loads, (2) aD similar equipment. These issues are covered by IEEE dynamic amplification effects are accounted for, (3) the Std 344-1987, which reflects the state-of-the-art tech- component is in the operating mode during and after nology. Further, the NRC has extended the application the application of loads, and (4) an adequate analysis is of this standard to the qualification of mechanical made to show the validity of the static application of '

equipment on an interim basis, in extending the applica- loads.

tion of IEl E Std 3441987 to mechanical equipment, .

the NRC staff recognizes that there are differences in l qualification methods for electric and mechanical D. IMPLEMENTATION equipment. Specifically, qualification of mechanical equipmen. by analysis is permitted when such equip- The purpose of this section is to provide information ment can be modeled to adequately predict its response. to applicants and licensees regarding the NRC staff's lhe American Sotiety of Mechanical Engineers is cur- plans for using this regulatory guide.

rently developing a standard for seismic qualification of mechanical equipment. Upon publication of this stan. Except in those cases in which the applicant or dard, the NRC staff will review it for suitability for licensee proposes an acceptable alternative method for endorsement by a revision to this regulatory gui'le. complying with specified portions of the Commission's regulations, the methods described herein will be used in

~Ihis regulatory guide cosers two categories of equip- the evaluation of seismic qualification of electric and ment: (1) safety-related electric (Class IE) equipment mechanical equipment for the following nuclear power and safety-related mechanical equipment, and (2) non- plants:

safety-related equipment whose failure can prevent the satisfactory accomplishment of safety functions Exam- 1. Plants for which the construction permit is issued ples of n,echanical equipment within the scope of this after June 30,1988, guide are valves, valve operators, pumps, compressors, chillers, air handlers fans, blowers, fuel rod assemblies, 2. Plants for which the operating license application is and control rod drive mechanisms. docketed after December 30,1988, IEEE Std 3441987 recognizes the use of justified 3. Plants for which the applicant or licensee voluntarily expenence eta as a method for seismic qurlification. commits to the provisions of this guide.

1.100-2

r

.l% ,

J VALUE/ IMPACT STATEMENT l \

-\ / BACKGROUND categories of equipment: (1) safety-related electric (Gass IE) equipmen. and safety-related mechanical equipment, IEEE Std 344-1975, "Recommended Practice for and (2) non-safety related equipment whose failure can Seismic Qualification of Qass IE Equipment for Nuclear prevent the satisfactory accomplishment of safety func-Power Generating Stations," was approved by the IEEE tions. The regulatory position provides guidance for in Januny 1975. In August 1977, the NRC staff issued qualification of mechanical equipment that is consistent Revision I to Regulatory Guide 1.100, which endorsed with current NRC practice.

IEEE Std 344 1975, subject to four exceptions. Since then the staff has worked with the IEEE in developing Regulatory Positions C.1 to C.4 in Revision l'.tre not IEEE Std 344 1987. As a result of these efforts, the in.luded in Revision 2 because they have been hvorpo-exceptions to IEEE Std 344-1975 have been satisfacto- rated in IEEE Std 344-1987 as follows:

rily resdved.

Regulatory Position in IEEE Std 344 1987 IEEE Std 344 1987 also addresses several recent Rev.1 of this Guide Section Number technical issues, for example, treatment of hydrody-namic loads, the limits of generic testing the treatment C.1 6.3 of rattling, methods of qualifying line-mounted devices, C.2 7.6.2.1 and thtc use of actual seismic experience data bases to C.3 7.6.2.5 qualify identical or similar equipment. IEEE Std 344- C.4 10.3.2(6) 1987 thus reflects the state-of-the-art technology. - -- --- --

Issuance of Revision 2 is consistent with the NRC VALUE policy of evaluating the latest versions of national standards in terms of their suitability for endorsement This guide endorses the latest version of a national by regulatory guides. standard and reflects the current state-of-the-art tech-nology. The guide should also enhance the licensing process.

(n SUBSTANTIVE v) IEEE Std 344 1987 applies toCHANGES seismic and dynamic IMPACT qualification of Oass IE (safety-related electric) equip-ment. The nuclear industry has used this standard for Although the scope of this revision has been ex-seismic qualification of mechanical eqt.ipment as well. tended to include seismic qualification of mechanical The NRC staff recognizes this fact and intends to equipment, the requirements are consistent with NRC extend the application of this standard to seismic current licensing practice. Thus, this regulatory guide

-qualification of mechamcal equipment by this regulatory does not impose any new requirements or costs on guide. Specifically, this regulatory guide covers two licensees or applicants.

)

1.100-3

UNITED STATES nos,etas,u ,,,_

" '55tannie' tis Paio NUCLEAR REGULATORY COMMISSION "'*"*

WASHINGTON, D.C. 20555 PERMIT No. 0 $7 9

A USINESS PENAL p 1 1GP11S 120555064215 US NRC -0 ARM-I RM -

DIV OF INFO SUP SVCSCONT ROL 14R ANCH DOCUMENT CONTROL DESK 00CUMENT DC 20555 P1-1249 WASHINGTON I

I I

i O

l l

1 O(

- - - - -- _ - _ - _ _ _ _ _ _ _ _ _ _ _