ML20207H390

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Discusses Review of Proposed Rev 2 to Reg Guide 1.89, Endorsing IEEE 323-1983.Review Concludes Rev Will Not Impose Backfitting Requirements Other than Those Resulting from Changes in Radiation Source Term.Copyrighted Matl Encl
ML20207H390
Person / Time
Issue date: 11/05/1984
From: Aggarwal S
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Noonan V
Office of Nuclear Reactor Regulation
Shared Package
ML20207H356 List:
References
FOIA-86-499, RTR-REGGD-01.089, RTR-REGGD-1.089 NUDOCS 8607240300
Download: ML20207H390 (14)
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s MEM0RAhDUl* FOR: Vincent S. Noonan, E0B, DE, NRR'

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Sa t i s h K. Agga rval, EE IC6, DET,

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PROPOSED REVISION 2 TO R.C. 1.89 - ENDORSENENT OF

SUBJECT:

IEEE-3?3-19C3 323-1983 ard coopered As requested by you, I have completed my review of IEEEThe changes are highlighted by it, paragraph by paragraph, with IEEE 323-1974.

a " yellow" marker on a copy of IEEE 323-1983, which is enclosed for your infomation and usc.

323-1974 was made to clarify its It is ny opinion that this revision to IEEE requiremants and imposes no additional requirements for qualifyingTherefore safety-related (Class 1E) equipocnt.will not inpose any backfitting 1.89, which endorses IEEE 323-1983, requirer.ents, exccpt those that may result from changes in the radiation source te rT:.

Satish K. Aggarvci, EEICB Division of Engineering Technologt Office of Nuclear Regulatory Research

Enclosure:

As stated above.

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IEEE Std 3231983 6

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..eitet Std 32319741 0FFICE OF MUCLEAR REGULATOPY RESEARCH 1 IEEE Standard for Qualifying Class 1E Equipment for.

NuclearPower Generating Stations ch Plans. recorrme. ids, and implements the programs of nuclear regulatory res basis for de E M W M M M n

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I IEEE Std 323-1983 a kes man e.f IE EE 5td 323-1974 s 1

IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations Sponsor Nuclear Power Engineering Committee of the IEEE Power Engineering Society

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[ Copynght 19o3 by The Institute of Electrical and Electronics Engineers, Inc 345 East lith Street, New Yorts. NY 10017 No part of thss pubiscorson may be reperduceti en any form h

an an riretronne rettsetal svstem or ot.cru ur u ntten permssswn of the publuher wndnout the prw e

Foreword

,]

(This Foreword is not a part of IEEE Std 323-1983. IEEE Standard for Quahrying Class IE Equipment for Nuclear Power Generating Stations i The requirements for qualification of Class IE equipment are included in the Code of Federal Regulations. Among them are the following:

(1) 10 CFR Part 50 Appendix B, Quality Assurance Criteria,III Design Control. This requires that design control measures be estabhshed and that such measures provide for venfying or checking the adequacy of design. One of the methods of design venfication is by the performance of a suitable testmg program.

(2) 10 CFR Part 50, Appendix B, Quality Assurance Cnteria, XI Test Control. This requires that a test program be established and that testing be performed under suitable environmental conditions. These requirements. at least in part, can be met by suitaole qualifications.

10 CFR Part 50.55 Codes and Standards Protection System. This requires t sat the protection i3) system meet the requirements set forth in ANSI /IEEE Std 279-1971 (R 1978i, Critena for Protection Systems for Nuclear Power Generating Stations, tsee section 4.41.

Information pertinent to developing designs and their quahfication requirements may be found in the above mentioned documents and in 10 CFR Part 50, Appendix A. General Design Critena 1,2,4, and 23.

Qualification is addressed by other IEEE standards for nuclear power generating stations, for example: ANSI /IEEE Std 497-1981, Standard Critena for Post Accident Monitonng Instrumentation for Nuclear Power Generating Stations, tsee section 6.1.81, ANSI /IEEE Std 308-1980, Cnteria for Class IE Power Systems for Nuclear Power Generating Stations,5.9, and IEEE Std 603-1980, Cntena for Safety Systems for Nuclear Power Generating Stations,(see section 4.4#.

This standard is written to serve as a general standard for qualification of all types of Class 1E equipment in nuclear power generating stations. Additional guidance for qualifying specific types of equipmerit may be found in vanous equipment qualification standards that are now available or being prepared. This standard gives generic requirements and methods for qualifying Class IE equipment.

Daughter standards may include unique test requirements or methods that are not specifically dis-

)

cussed in this standard, but that fall within the genene requirements of this standard. The unique requirements determined by applicable experience for the equipment covered by daughter standards.

should not be construed to apply to all equipment. For example, IEEE Project 572 for Class IE connection assemblies discusses qualification methods such as genene qualification, pacing, and on-going qualification. These methods are not specifically discussed m this standard. but do fall within its generic requirements.

Adherence to this standard may not assure public health and safety because it is the integrated performance of the structures, fluid systems, instrumentation systems. and electncal systems of the station that limits the consequence of accidents. Each user is responsible for assunng that this standard, if used. is pertinent to his application.

.gnen. M a w m M M aawar = " M n ~ mgw m m _., m u,

ftFnthi=%Gd M4-* "ME This is accomplished by a thorough program of quality assurance.

design, qualification, production, transportation, storage, installation, maintenance, periodic testmg, and surveillance. This standard is for the qualification portion of the program.

The user should note that while this standard covers Class IE equipment qualification, other documents such as ANSI /IEEE Std 279-1971 (R1978) and IEEE Std 603 1960 also require systcrt mtegrity. Therefore, attention needs to be given to equipment performance specifications and interfaces to ensure their adequate performance in a system.

The nuclear power generating station safety analysis. in part. considers the station and its safety system design in terms of postulated service conditions including events such as submersion, hydrogen burn, radiation plate-out, etc. Inherent to each such analysis are two nresumptions that must be evaluated. First, designs must be such that equipment can actually perform designated safety functions in postulated service environmentOum (JM 7pmsp agmg mT+Qot eernmes.epar,mw.my W a I:idisse m p ~, Q w,,

2h %+s5Wrm Production testing. normal service testing, and surveillance may not be able to determine whether the

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equipment is vulnerable to failure, either as a result of inadequate design or in service time and

l I.

At the time this standard was approved, Subcommittee 2 (Qualifications of the Nuclear Power Engineering Committee > had the following membership.

N. S. Porter. Chairman t

G. K. Ilenry, rice Chairman R. B.. Miller, Secretary S K Aagarwal G T Dowd.Jr J L Kligerman C F Seyer L. L Bonsor J B Gardner J. W Kroll M W. Sheeta N M Burstein A Gershock C. E. Kunkel G Shipway A. E Butt D R. Green T. H. Ling B P Skonberg S. P. Carfagno W Hadovski C F Miller G E Sliter D J Castro T P. Harrall M Pai E F Sproat R P. Daigle J T. Keeper J S Pirrong A P. Stakutis W J Denkowski P L. Kane R. R Reeves F LJnmaca At the time this standard was approved the Nuclear Power Engineenng Committee had the following membership:

R. E. Allen, Chairman B. 41. Rice, Vice Chairman J. T. Bauer, rice Chairman

  • G. R. Leidich. Serretary J. F. Bates L. Hanes H V. Redgate F. D Baxter
1. M Jacobs A. R Roby R. G Benham R F Karinek W F Sailer D F. Brosnan A Laird W G Schwart.:

W Buxton L C Madison A J Spurgin T

D G. Cain W E ONeal L Stanicy

)

F W Chandler R W Pack H. K. Stolt R. P. Daigle M Pai D F. Sullivan l

E F. Dowling E S Patterson P Szabados J J Ferenesik J R Penland L D Test E. P Fogarty C A Petnaro J E Thomas J. M Gallagher N S Porter T. R. Vardaro J B. Gardner W S Rautio R J Volpe "Standarcis Coordinator When the EEE Standards Board approved this standard on June 23. 1983. it had the following membership:

James II. Beall, Chairman Edward Chelotti, rice Chairman Sava 1. Sherr, Secretary J J Archambault Donald H Heirman John T, Boettger Irvin N Howell John P Ricanau J V. Bonucchi Joseph L Koepfinger*

Frank L. Rose Rene Castenschiold Irving Kolodny bbe-t W Seelbach Edward J Cohen George Konomos Jas A Stewart ten S Corey John E May Clifford O S anson Donald C Fleckenstein Donald T Michael

  • bbert E Weiler Jay Forster W B Wilkens Charles J Wylie
  • Member etneratus l

1 Contents SECTION PAGE

..9

1. Scope and Purpose 9

1.1 Scope 1.2 Purpose

.9 9

2. References

.9

3. Definitions 10
4. Introduction 11
5. Qualification hiethods.

5.1 Type Testing 11 5.2 Operating Experience

.11 I1 5.3 Analysis 5.4 Combined 51ethods I1 11

6. Qualification Procedures 6.1 Specification Requirements.

.11 3

6.2 Qualification Program Requirements.

.12 13 6.3 Type Testing 6.4 Operating Experience

. 16 6.5 Analysis

. 16 6.6 Combined Qualification 17

.17 6.7 Acceptance Criteria.

6.8 hiodifications

.18 6.9 Extension of Qualified Life 18

7. Simulated Test Profiles 18
8. Documentation

.20

.20 8.1 General 8.2 Documentation

.20

)

8.3 Type Test Data.

. 20

. 20

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8.4 Operating Experience Data.

8.5 Analysis 20 i

.20 I

8.6 Equipment for 31ild Environment.

20 t

8.7 Combined Qualification.

8.8 Extrapolation 20 L

FIGl'RES Fig 1 Typical LOCA:HELB Temperature and Pressure Dlustratmg Application of Time.

Temperature. and Pressurt Alargins

.19 Fig 2 Typical LOCA/HELB Temperature and Pressure Illustrating Additional Peak Transient to Account for 51argin 19

7 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations

1. Scope and Purpose (3) ANSI /EEE Std 308-1980. EEE Standard Cntena for Class 1E Power Systems for Nuclear 1.1 Scope. This standard describes the basic Power Generating Stations.

requirements for qualifying Class IE equipment

[4] ANSI /EEE Std 338-1977, EEE Standard i

with interfaces that are to be used in nuclear Critena for the Periodic Testing of Nuclear power generating stations. The requirements Power Generating Station Safety Systems presented include the pnnciples, procedures, and (S} ANSI /EEE Std 344-1975 (R1980), EEE methods of qualification. These qualification Recommended Practices for Seismic Qualifica-requirements, when met, will confirm the ade-tion of Class IE Equipment for Nuclear Power quacy of *.he cquipraent design under normal, abnormal. desip basis event, post design basis Generating Stations.

event, and in-service est conditions for the per-(6] ANSI /EEE Std 497-1981,IEEE Standard formance of safety function (s,.

Cnteria for Accident Momtoring Instrumenta-ti n f r Nucle r Power Generating Stations.

1.2 Purpose. The purpose of this standard is to identify requirements for the qualification of

[7] EEE Std 6031980, EEE Standard Cnte-

)

Class 1E equipment, including those interfaces ria for Safety Systems for Nuclear Power Gener-g whose failure could adversely affect the perform-ating Stations.2 ance of Class 1E equipment and systems (S) IEEE Std 627 1980. IEEE Standard for The methods described shall be used for Design Qualification of Safety Systems Equip-qualifying equipment, extending qualification, ment Used in Nuclear Power Generating Sta-and updatmg qualification if the equipment is tions.

modified. Other issued IEEE standards which i

present qualification methods for specific equip-ment or components, or both, and those that deal I

3. Definitions with parts of the quahfication program, may be used to supplement this standard, as applicable.

These definitions apply to key words as used in this standard only and which are not included m ANS!dEEE Std 100-1977(1)?

2. References aging. The effect of operational,environmenta..

[1] ANSIiEEE Std 1001977, EEE Standard and system conditions on equipment dunne a Dictionary of Electncal and Electronics Terms.'

penod of time up to. but not including deng process of simdatm he 3K mn L T 12] ANS!iEEE Std 279-1971 (R1978), EEE Standard Criteria for Protection Systems for Nuclear Power Generating Stations.

8 IEEE publi ions are available from the Institute of Electncal and Electronics Enrineers. Service Center 445 Hoes Lane. Pncataw sy. NJ Oo6M

  • ANSI publications are available from the Sales Depart.
  • The nurnbert in brackets correspond to tl.e reference
  • ment. Amencein National Standard institute.1430 Broad-hsted in Section 2 of this stand 5rd

= ay. New York. NY 10018 9

FOR NUC1. EAR POWER GENERATING STATIONS IEEE Std 323-1983 For all qualification programs, the end rerdt 5.4 Combined.Tlethods. Equipment may be must be documentation that demonstrates the quahfied by any combinationist of type test.oper-equipment's adequacy to perform its safety func-ating experience, and analysis. For example.

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tionist. The documentation must be in a form where size. application. tarae or other limitations that allows verification by competent personnel, preclude the use of a type test on the complete other thac the qualifiers, and shall contain, as equipment assembly. type testing of components appropriate. the equipment specification supplemented by analysis may be used in the requirements, the applicable qualification meth-qualification process.

ods. qualification plan. qualification data,justifi-cations, and acceptance criteria.

6. Qualification Procedures
5. Qualification.Tlethods 6.1 Specification Requirements. The basis for 51ethods for qualifying equipment are hsted qualification is a complete specification from below:

which a qualification program can be formulated and implemented. For the purpose of qualifica-5.1 Type Testing. Type testing of equipment tion, the equipment specification which contams satisfies qualification if it accounts for signifa.

the design performance requirements and pro-cant aging mechanisms (see 6.2.1), subjects the vides the technical basis for the equipment.shall equipment to specified service conditions, and identify the safety function (ss and the service demonstrates that such equipment can subse.

conditions during which the functionis is quentiv perform its intended safety functiontsi required. As a minimum, the following items for at l' east the required operating time.

shall be included:

6.1.1 Equipment identification. A technical 5.2 Operating Experience. Data from equi -

description of the equipment to be quahfied, P

ment of similar generic design that has success.

including apphcable performance and quahfica-fully operated under known service conditions tion standards, shall be provided.

may be used as the basis for qualifying other 6.1.2 Interfaces. Loadings at interfaces 'that

)

equipment to equal ~or less severe service condi-is, physical attachments. mountmg. auxthary tions. The validity of this qualification method devices, connectors to the equipment at the depends on the adequacy ofdocumentation estab-equipment boundary, shall be specified for each lishing the past senice conditions, equipment operatmg mode. Slotive power or control signal performance, maintenance, and similarity inputs and outputs, and the physical manner by between the equipment to be qualified and that which they are supplied s for example. connectors.

for which the operating experience exists. Oper-terminals blockse shall be specified. Control.

i ating experience can provide information on lim

  • indicating. and other auxiliary devices mounted its of extra polation. aging characteristics. failu re internal or externally to the equipment and modes, and failure rates.

required for proper operation shall be included 5.3 Analy sis. Qualificatio i by analysis NOTE Matenal incompaabdmes at intenaces snomo w

( ""d"'d 2nd *I u'd requires a logical assessment or a valid mathe-matical model of the equipment to be gaalified-6.1.3 Qualified Life Objective. Where Qualification shall consist of quantitative analy-applicable, the desired qualified life objective of sis supported by test data, operatmg experience the equipment shall be stated.

or physical laws of nature to demonstrate that ti.l.1 Safety Functionis t. The equ ' ment the equipment can perform its safety function'*'

specif cation shallidentify the equipment 9 safe-under specified service conditions. Agmg effects ty functionm which mcludes the required oper-shall be considered.

atmg times.

The analysis, including logical bases and data om "" "

used to support it, shall be presented in a step by fn$E "j r 'r th

'(Gcat o, n excI a

pr s

step manner for one complete set of computations it can be shoJn. through a documented rneans such a an analyus that assume t radures. includinc ipunous eperation-so a person reasonablv skilled m the typc of anal.

han na ads ersc efTect on the stated safets sunct:on v or. h t

ysis used can follow the reasoning and computa.

way of intertacet on the safety function.s. of other equip-tions.

ment

)

11

FOR NUCLEAR POWER GENERAENG STADONS IEEE SLd 3231983 equipment, and any limitations imposed by the test results. As a minimum. the following specified aging program. Any components with a requirements shall be met:

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design life shorter than the equipment's (1) Identification, description and quantity qualined life objective shall be identined.

of the samples to be tested including signiGcant

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information such as manufacturer, modelist and y ; _ u,,, u.x g

senal numbers to umquely identify the sample

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(2) Listmg of equipment safety functionisi to u....pq__

g_ g...z u g mag be demonstrated rNME@

(3) Mounting, connection, and other inter.

g,gg c y_rsrw mM==ne, maniE$m%EEDR (See ANSI /IEEE Std

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(4) Test sequence 33fis77 [4] for guidance on establishing and (5) Aging conditioning procedure,if required performing surveillance / maintenance.)

(6) The speciGed service conditions and mar.

6.2.3 Margin. Margm is required in qualifica-tion test programs to account for reasonable (7) Performance and environmental vari.

uncertamties in demonstrating satisfactory per.

ables to be measured includmg measurement formance and normal variations in commercial accuracy production, thereby providing assurance that the (8) Environmental, operating, and measure.

equipment can perform under the most adverse ment sequence in detail including monitoring service condition specified. Increasmg test parameter values, number of tests, transients, g

operability time, or test duration (but not neces.

(10) Mamtenance< replacement durmg aging, sarily all at the same times are acceptable meth.

f required ods of ensunng that adequate margin does exist.

(11) Provisions for control of modifications Ifit can be demonstrated that sufncient margin during tests exists in the equipment performance charactens.

i12) Required documentation tics or in the specified service conditions. then (13 A desenption of any condition > pecuhar k additional margin need not be added.

the equipment which are not listed but which

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6.2.4 Mamtenance. Penodic maintenance /

would probably affect said equipment during replacement required dunng the aging portion of testing' the qualineation program shall be identined.

6.2.5 Documentation. The quahfication of 6.3.1.2 Mounting. Equipment shall be the equipment shall be documented as speciGed mounted in a manner and a position that simu.

m Section 8.

lates its expected mstallation when in actual use 6.2.6 Qualification Method. The qualifica.

unless an analyns can be performed and justined tion method, selected from Section 5. shall be to show that the equipment's performance is not identifiad.

altered by other means of mountmg. By manner 6.2.7 Acceptance Criteria. The value's) of is meant tne means to be used such as bo!ts performance parameters to be used to demon.

nvets. welds, clamps, etc. By position is meant strate that the eqmpment can perform its safety the spatial onentation with respect to the grav.

function (si shall be identined for applicable ser.

itational Geld of the earth The effect of ar.y mter.

vice conditions.

posing structures which are required for installation, such as control boards, stands. legs pedestals, etc. shall be taken into account.n the 6.3 Type Testing test mountmg.

6.3.1 General. The type test shall demon.

6.3.1.3 Connections Eqmpment shall be strate that the equipment performance meets or connected in a manner that simulate < its expected exceeds its safety function requirements. The installation when in actual use unless an analyse type test conditions shall meet or exceed the spec.

can be performed to show that the equ:pmenn ified service conditions. Margin shall be added if ability to perform its safety functionisi would not not included in the speciGed service conditions.

be altered by other means of connection By man.

6.3.1.1 Test Plan. The test plan shall ner is meant the means such as winng. connectors.

desenbe the required tests and provide an cables, conduit termmal blocks, semce loops pip-auditable link between the specifications and the ing, tubmg. etc.

13

FOR NUCLEAR POWER GENERA 11NG STATIONS IEEE Std 323-1983 shown, by analysis or engineering judgement Natural aging may be supplemented by analy-that the safety function (s)is not affected during sis or age conditioning, or both, to account for

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the exposure to DBE radiation.

differences between the specified service and the (Si The test sample shall be subjected to spec-natural aging conditions to justify the qualified ified non-seismic mechanical vibration.

hfe of the sample.

t 61 The test sample shall be subjected to simu-6.3.3.2 Are Conditioning. If naturally-lated operating basis earthquake (OBEi and safe aged equipment is not available with proper doc-shutdown earthquake (SSE seismic vibration in umentation and significant aging mechanismiss accordance with ANSI /IEEE Std 344-1975 (R have been identtfied, the equipment shall be age 1980il5].

conditioned m the typetest program unless the (71 For equipment located in harsh environ-effects of the sigmficant aging mechanism can be ments, the test sample shall perform its required accounted for by in-service surveillanceImamte-safety functionts: while exposed to the simulated nance. Age conditionmg is a procc<, whereby the design basis accident. DBA radiation may be effects of sigmfican t aging mechamsms are simu-excluded if incorporated in (41. The functions lated in the test sample. For example, elec-which must be performed during the design basis tromechanical equipment shall be operated to accident shall be monitored.

simulate the expected mechanical wear and elec-t 8) The test sample shall perform its required trical contact degradation ithat is, contact pit-safety functiontsi while exposed to the simulated tings of the device to be type tested.

post DB A conditions as applicable.The functions An accelerated cycle rate for the number which must be performed followmg the simulat-required durmg the design life may be utilized ed design basis event shall be monitored during provided the rate is not accelerated to any value this post DBE simulation.

which results in effects that are not present at 49 Post-test inspection. Record findings.

normal rates.

Age conditioning generally involves applying NOTE The user of this standard should not infer that the sequence used amphes a couphng among the various DI3Es simulated m. service stresses tfor example, ther-postulated for any given plant-mal. radiation. wear, and vibrations at magni-tudes or rates that are greater than expected in-

)

6.3.3 Aging. The assessment of equipment service levels but less than the material property aging efTects is required to determine if aging has limitations. These stresses may be applied a significant efTect on operability. The types of sequentially.

aging include thermal, radiation, wear, and 6.3.1 Radiation. All material or components.

vibration. The assessment shall include an anal-which may be degraded to a degree which ysis of the equipment to determine any signifi adversely affects performance of the equipment's cant aging mechanisms for the DBEs under safety functiomsi by the radiation exposure consideration. Where these mechanisms are expected to occur during normal service and pos-identified, a suitable agmg subprogram shall be tulated accidents. shall be irradiated to simulate included in the type test unless excluded in 6.2.1.

this exposure. Radiation shall be applied as a When natural aging is used in the qualification part of the sequence of environments representa-program it is not necessary to identify significant tive of service conditions. The equipment shall be aging mechanisms.

subjected to the significant type of radiation 6.3.3.1 Natural Aging. Natural aging is the equivalent to or greater than that expected in most technically justified method. Naturally service. Ilowever,if more than one type of radia.

aged equipment may be used for type testmg tion is sigmficant, each type can be applied sepa-provided that:

rately. With an accelerated exposure rate, a eli The equipment has been aged in an greater total dose than the service hfetime dose environment at least as severe as the normal one may be needed to simulate long-term effects.

for the intended application If it can be shown that the combined normal (2) Operating and maintenance / replacement and accident radiation dose and dose rate do not records are available to verify the service condi-affect the safety functiontsi and there are no tions adverse affects if radiation is done sequentially.

(3i The aged equipment was operated under either before or after thermal or wear cychng, load at least as severe as that specified for the then radiation testing may be excluded. Ifit can

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equipment to be qualified.

be shown that the radiation effect is restricted to 15

1EEE FOR NUCLE.AR POWER GENERATING STATIONS Sid 3231983 to establish that the equipment to be qualified 6.5.3.5 Aging 31echanisms. The aging can perform ita safety function (s) when subjected mechar. isms that apply to the tested equipment g

to the specified service conditions. This assess-encompass those that apply to the similar equip-1 ment may be based exclusively on quantitative ment.

analysis; however, analytical techniques may be 6.5.3.6 Function. The safety functionisi as limited and analysis supplemented by test data evaluated shall be the same ifor example. acti-or operating experience may be needed in a quali-vate to operate or de activate to operates.

fication program. Justification is required for the 6.5.1 I)etermination of Qualification. The technique used.

equipment sha!! be considered quahfied through demonstration that its performance meets or 6.5.2 31athematical Stodeling. Quantitative exceeds that required under the specified service analysis may be used to qualify the equipment by conditions dunng its qualified hfe or that the construction of a valid mathematical model t operation limitations of periodic inspection or demonstrate that the equipment can perform its surveillance have been identi0ed.

safety functionts) under actual service condi.

tions. Such an analysis shall account for all time dependent environmental parameters originat-6.6 Combined Qualification. Equipment may ing from the qualification criteria, be qualified by a combination of test, analysis, or previous operating experience. Combined qual-6.5.3 Extrapolation and Interpolat. ion. Ex.

ification shall be developed on a case.by. case trapolation and interpolation are analytical basis applymg the procedures of the foregomg techniques which may be used to qualify equip-sections. The qualification shall provide audita-ment by extending the application of test data.

ble data by which the comb;ned methods can be Two types of extrapalation and interpolation are shown to constitute a complete qualification pro-possible:

gra m.

(1) Extrapolation or interpolation of success-ful performance at a specific service condition to a different service condition.

6.7 Acceptance Criteria. In the evaluation of (2) Extrapolation or interpolation of success-the qualification program results. the equip-

)

ful performance of a specific piece of equipmen t to ment is considered to have passed when it meets l

similar equipment.

the requirements of 6.2.7. Acceptance entena l

Extrapolation or inte polation of a service con.

shall be defined so that all failures to perform the dition requires analysis using established physi-specified safety functionts) for the service condi-cal pnneiples. Extrapolation or interpolation to tion; for w'hich the equipment is being quahfied other equipment by stmilarity can be used when can ce identi0ed. Any failure to meet the accep-the following critena are met:

tance entena shall be analyzed to determine the 6.5.7131sterial. Statenals of construction modification of the equipment or the limitation th@ (user be the same or equivalent. Any iden-that shall be imposed on its use. Failures shall be tided differences shall be shown not to adversdy documented as desenbed in S.I.

affect performance of the safety functionts).

Any failures or abnormalities occurnng dur-6.5.3.2 Size. Size may vary if the basic con-ing testing shall be documented according to figuration remains the same and dimensions are their cause and the overall effects on the equip-related by known scale factors. Consideration ment's qualification. If the failure or abnormali-shall be taken of such factors as thermal effects of ty is completely spunous tnot induced by the different surface areas and seismic effects of dif.

qualification testi or due to a deficiency in the ferent masses and modes.

test equipment e that is subsequently eliminatedi 6.5.S.3 Shape. The shape shall be the same corrective action is not required. However,if the or similar (subject to restnctions of size) and a iy failure is induced by the test er due to a cause differences shown shall not adversely affect the that affected or potentially could affect multiple performance of the safety function (s).

components operating in redundancy isuch as a 6.5.3.4 Stress. Operating and environmen-design deficiency), the document shal! mdicate tal stresses on the new equipment shall be equal the corrective actions required imaterial change to or less than those experienced on the qualified or replacement schedule) and all or portions of equipment under normal and abnormal condi-the test may have to be repeated. dependmg on tions.

the significance of the test deficiency.

)

17

FOR NUCLEAR POWER GENERATING STATION

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.%dditional l'eak Transient to Account for.Tlargin 19 l

IEEE

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Std Title 484 1981 Recommended Practice for installation Design and Installation of Large Lead Storage Battenes for Generating Stations and Substations (Revision of ANSI /IEEE Std 484 1975) 494 1974 Standard Method for identification of Documents Related to Class IE Equipment and Systems for Nuclear Power Generating Stations I ANS!!!EEE) 497 1981 Standard Cntena for Accident Monitonng Instrumentation for Nuclear Power Gen-erating Stations ( ANSI /IEEE) 498 1980 Standard Requirements for the Cahbration and Control of Measunne and Test Equip.

ment Used in the Construction and Maintenance of Nuclear Power Generatmc Stations 500-1977 Guide. to the Collection and Presentation of Electncal. Electrome and Sensmg Com-ponent Reliability Data for Nuclear-Power Generstmg Stations 535 1979 Standard for Qualification of Class 1E Lead Storage Battenes for Nuclear Power Gen-eratmg Stations ( ANSI /IEEE) 566-1977 Recommended Practice for the Design of Display and Control Facilities for Central Control Rooms of Nuclear Power Generating Stations 567 Trial Use Standard Critena for the Design of the Control Room Complex for a Nuclear Power Generating Station ( ANSillEEE) 577 1976 Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations ( ANSI /IEEE) 600 Trial-Use Standard Requtrements for Orgamzations that Conduct Qualification Testmg of Safety Systems Equipment for Use in Nuclear Power Generatmg Stations 603 1980 Standard Cntena for Safety Systems for Nuclear Power Generatine Stations (Revision of IEEE Std 603 1977) g 622 1979 Recommended Practice for the Design and Installation of Electric Pipe Heating Sys-

/

tems for Nuclear Power Generating Stations t ANS!'IEEE) 627 1980 Standard for Design Quahfication of Safety Systems Equipment Used m Nuclear Power Generating Stations 649-1980 Standard for Qualifymg Class IE Motor Control Centers for Nuclear Power Generatmc Stations 650 1979 Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations ( ANSI;IEEE) 749-1983 Standard Periodic Testing of Diesel Generator Units Applied as Standby Power Sup-plies in Nuclear Power Generating Stations 765-1983 Standard for Preferred Power Supply for Nuclear Power Generating Stations 7-4.3 2 1982 Application Cnteria for Programmable Digital Computer Systems m Safety Systems i

of Nuclear Power Generatmg Stations ANSllIEEE ANS)

ANSI N13.4-1971 Specifications of Portable X. or Gamma Radiation Survey Instruments (Reaff 1977) r_

ANSI N42.41971 High Voltage Connectors for Nuclear Instruments (Reaff 1973)

ANSI N42 5-1965 Bases for GM Counter Tubes (Reaffirmed 1977:

ANSI S42.61980 Interrelationship of Quartz Fiber Electroraeter Type Exposure Meters and Compamon Exposure Meter Charges ANSI N42121980 Calibration and Usage of Sodium lodide Detector Systems ANSI N42.15-1980 Performance Venfication of Liquid Semtillation Counting Systems ANSI N42181980 Specification and Performance of On S:te Instrumentation for Contmuously Monitoring Radioactivity in Effluents (Reaff and redesignation of ANSI N13.101974 )

ANSI N3171980 Performance Criteria for Instrumentation uscd for Inplant Plutomum Monitor-mg

)

ANSI N3201979 Performance Specifications for Reeactor Emergency Radiological Momtonng Instrumentation l

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