Text

Applicant Exhibit A-36,consisting of Rept Indicating IEEE Std for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
	ML20094P362
Person / Time
Site:	Farley
Issue date:	02/20/1992
From:	; INSTITUTE OF ELECTRICAL & ELECTRONICS ENGINEERS
To:	;
References
	CIVP-A-036, CIVP-A-36, NUDOCS 9204080063
	Download: ML20094P362 (25)
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0065939

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Foreword (This foreward is not part of tEEE Std 323 1974, Qualifying Clar.s IE Equipment for Nuclear Power Generating Stationa.s The following IEEE Standards establish basic requirements mat equipment within their acope roust be adeountely qualified:

IEEE Std 2791971 (ANSI N42.71972), Criteria for Protection Sys+emr for Nuclear Power Gen-erating Stations.

IEEE Std 3081974, Criteria for Class IE Power Systems for Nuclear Power Generating Stations.

The Institute of Electrical and Electronics Engineers has developed this document to provide guidance for demonstrating and documenting the adequacy of electnc equipment used in all Class IE and interface systems.

Adherence to this guide may not suffice for assuring public heahh and safety because it is the integrated performance of the structures, fluid systems, instrumentation systems, and electrical n systems of the station that limits the consequences of accidents. Each applicant has the responsi.

bility to assure himself and others that this guide,if used,is pemnent to his application and that the integrated performance of his station is adequate.

Representative in<ontainment design basis event conditions for the principal reactor types are included in the appendixes for guidance in environmental simulation.These conditions may not be acceptable for all specific applications and the user should cc:. firm the suitability of these data and modify them as appropriate for qualification in any given Nuclear Power Genetting Station.

Guidance for demonstrating the capability of :pecific electric equipment may be found in the following documents thich are in various stages of preparation or issue.

i Project P-351. Guide for Type Tests of Modules Used in Nuclear P wer Generating Station Pro-tection Systems.

IEEE Std 3341971, Tna5Use Guide for Type Tests of Continuous Duty Class 1 Motors Installed f Inside the Containment of Nuclear Power Generating Stations.

(m) IEEE Std 382-1972 (ANSI N41.61972), Trial.Use Guide for Type Test of Clus I Electric Valve

] Opera *. ors for Nuclear Power Generating Stations.

IEEE Std 353-1974 Guide for Type Test of Class IE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations.

LEEE Std 344 1971, Guide for Seismic Qualification of Class I Electric Equipment for Nuclear Power Generating Stations.

This standard was prepared by a working group of Subcommittee 2 (Qualification) of the Nuclear Power Engmeering Committee of the IEEE Power Enginee:ing Society. Members of this group were:

J. T. Bauer, Chairman W-- C. V. Fields, Past Chairman S. Carf agno A. Kaplan J. B. Gardner D. G. Woodward C. F. M:ller A. J. Simmora L D. Test J. T. Keiper At the time it approved this standard, Subcommittee 2 (Qualification) had the following member-ship:

A. J. Simmons, Chairman L. D. Test, Vice Chairman A. Eaplan, Secretary J. F. Ba:es D. J. Meraner D. G. Woodward J. T. Enuer F. W. Chandlei G. T. Dowd, Jr L J. Blaiak H. E. McConnell W. J. Denkowski J. T. Keiper C. E. Corley R. F. Edwards F. Campbell W. Dalos C. F. Miller W. J. Foley E. P. Donegan A. S. Hintze J. B. Ga drer W. D. Loftus W. G. Stiffler g T. H. Lir.g W. H. Steigelmann B. Gregory g i' T. R. Beans S. Carfagno A. Garshick G. W. Hammond W. A. Szelistowski E. E, Mc!he en O F. Trunzo V

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0065940 At the time it approved this standard, The Nuclear Power Engineering Committee had the follow.

'd hg membership:

J. C. Russ, Chairman T. J. Martin, Vice Chairman L. M. Johnson, Secretary J. T. Boettger, Coordinator R. E. Anen E. F. Chelotti E. S. Pattenon C. E. Stine J. F. Bates C. M. Chia ppetta D. G. Pitcher H. K. Stolt R. G. Benham R.J.Cooney W. F. Sailer D. F, Sullivs-K. J. Brockwell D. G. Fitzgerald R. A. Saya W. A. S2elistowski D. F. Brosman J. M. Gallagher A. J. Simmons L. D. Test O. K. Brown A. Kaplan J. H. Smith J. L Voyles S. G. Castake T. A. Ippolito A. J. Spurgin E. C. M'enzinger F. W. Chandler M.1. Olken L Stanley C. J. W ylie i

IEEE Std 323A 1975 (Supplement to i IEEE Std 30L1974)

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s Supplement to the Foreword of IEEE Std 323 1974 d IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations l

(Thu Supplement is prouded ) ampl:fy the information in the Foreword;it is not a part of IEEE Std 323 1974 )

The concept of aging was addressed explicitly for the first time in IEEE Std 3231974. The aging guidance therein reflects the requirement of IEEE Std 2791971 ( ANSI N42.7-1972) Section 4.4 It is based on an awareness by the IEEE that the abihty of Class IE equipment to perform its safety i

related function might be affected by changes due to natural, operational, and environmental phe-nomenn over time (agmg). . was not the intent that aging must be applied to all Class 1E equipment.

but rather that aging must be considered in the same manner as environmental parameters. The need for apng ot particular equipment should be determined based on an evaluation of the specific design and application. If agmg is needed a further determination must be made as to whether accelerated

, aging techniques can be applied to the equipment and yield valid results, that may be correlated to real time, ongoing qualification.

It is acknowledged that the state of the at*. regarding agmg for some Class IE equipment is more advanced than others It is expected that known technology will be utilized in any aang program.

Optionally tand particularly where the state of the art is limiting). agmg as part of the qualification program may be addressed by operaung experience, analysis, combined. or ongoing qualification as detailed in Section 5.2. 5.3, 5.4 and 5.5.

Further clarifwation of agmg as it applies to specific types of equipment will be provided in individual IEEE Class IE squipment qualification documents. For example, an IEEE Standard is

,h being prepared to establist. eriteria for Class 1E modules. IEEE Standards 3341974. 3S21972 i ANSI N41.6i, and 3831974 ( ANSI N41.101975) p asently provide ruidance for motors valve operators.

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0065941 -

Approved December 13,1973 IEFE Standards Board Robert D. Briskman. Chairman Sava 1. Sherr, Secretary Stephen J. Aneello Joseph L Koeprineer R.stph N1. Showers Saul Aronom William R. Kruesi Robert A Soderman James E. Beehler Benjamin J. Leon Frederick G. Timmet Richard Brereton Donald T, Michael Leendert van Rooij W.irren H. Cook Voss A. Moore Robert V. Wachter Louis Costrell J. David M. Phelp. Bruno O Wemschel

'l Jay Forster da ul W. Rosenthal William T. Wantrineham I Gentase Shapiro 4

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h Corrected copy June 1976 includes: 3/30/74 correction 11 r21l751EEE Std 322 A 197.*> Supplement to Fureword

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0065942 Contents SECTION PAGE

1. Scope.. .

....... .. . . .. .. . . . . .. .......... . . 7

2. Purpose . .. . ..... . . ... . .. .... ...... ....... .....7

. 3. Definitions . . . . . . . . ............... ......... ..

...................... ,. 7

4. Introduction . . . . . ...... ...... . . ... ............. .......... .... 8

5. Principles of Qualification . . . .. ....

.. .......... ... .... ....... ... . 9 5.1 Type Testing . . . . . . . . . . ... . .. . . ... . ..

5.2 Operating Expenence . . . . . . .

.... ....... ... ... 9

..... .. . .. ... ........... . ... .. .. S 5.3 Qualification by Analysis . . . ... ,, . .. ...... ... .. ... . ...... 9 5.4 Combined Qualification . . ......

5.5 On Going Qualification . . . . ..... .

. . .. . .... .................. . 10

..... ... ...... ... . . ...... 10

6. Qualification Procedures and Methods. . . ,., .. .

. .. . .. . .... . . . 10 6.1 Identification of the Class IE Equipment Bemg Qualified . . . . . ... .. . ... . . 10 6.2 Equipment Performance Specifications. . .

6.3 Type Test Procedures . . . . ..

... .. ., .... .. .... . 10 l

j 6.4 Operating Experience ...... .....

. .. .. ..... . .. .... . . . 11 1 6.5 Analysis . . ... ... ..

. .. .......... .. .... 13 6.6 On-Going Qualification . . . .

. .. ........ .. . .. ... 14

....... ......, ...... ... 15 6.7 Criteria of Failure . . . . . . . . . . ... , , .... . .... ................. . . 15 P

6.8 Modifications . . . . . . . . . . . . .. ... ..... .. ............. . . . . . 15 6.9 Documentation . . . . . .

.. . ....... ... . .... . ... ..... ... .. ..... 15

7. Simulated Servn Condition Test Profile. .. . . . .... .. ......... .. . .. 15

8. Documentation . .

. .. ................... ..... . . 16 8.1 Genera! . . . . . . .. .. , , .. ..

..... ....... ..... ......... 10 8.2 Documentation Fdes. . . . . ........ ..

. 16 8.3 Type Test Data .. ... .......... ..

8.4 Operating Experience Data

. ......... .... ..... . . . . 16

...... ... ... .. 16 8.5 Analysis . . .... ... . . . . ... .

8.6 Extrapolation . ... ............ ... ....... ... . 17

..... .. ................... 17 FIGl'RES Fig 1 Simulated Service Environment Test Profile i ...

...... .. ... ....... . . . . 16 i APPENDIXES Appendix A In-Containment Design Basis Event Environment Simulation for PWR and BWR. ,18 Al General. . . . . . . .

A2 Simulation Sequence . . . . . .. .. ............................... 18

.............................................. 20 Appendix B In Containment Design Basis Event Environment Simulation for a Hi Temperature Gas Cooled Reactor (HTGR). . . . . . . . . . . . . . ....... . . . . . . .gh 20 Appendix C Test Chamber Moisture Content . . . .

... ............................ 23 FIG URES Fig A1 Test Chamber Profile for Accident Environment Simulation . . . . . . . . . . . . . . . . . . . 18

/ Fig B1 Typical Temperature and Pressure History for Environment Simulation of HTGR Containment Atmosphere Respons* Following a Hot Helium Blowdown into Containment . . . . . . . . .

................................. .... .. .. 21 Fig B2 Typical Temperatare and Pressure History for Environment Simulation of HTGR h Containment Atmosphere Response Following a Ster.m Line Rupture Inside the Containment . . . . .. ........ .......

.... ..... .... ..... .... 22

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0065943 TABLES Table A1 Test Conditions for Pressunzed Water Reactors . . . . . . . . . . . . . . . . . . . . . . . . . .. 19 Table A2 Test Conditions for Boiling Water Reactors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 Table B1 Test Conditions for High Temperature Gas Cooled Reactors . . . . . . . . . . . . . . . . . 21 Ta ble B 2 HTG R Co nta_nmen t Bu ild in g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3 1

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0065944 g' IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations

1. Scope words in the context of their use in this guide.

Thts document describes the basic require-

. . analysis. A process of mathematical or other ments for qualifying Cass IE equipment and logical reasoning tha' is from ststed interfaces that are to be used in nuclear power premises to the conclusior .inceming specific generating stations. The requirements pre-capabilities of equip:nent and its adequacy for sented include the pnneiples, procedures, and a particular application.

methods of qualification. These qualification auditable data. Technical information which is requirements, when met, will confirm the ade- documented and organized in a readily under-quacy of the equipment design under normal, standable and :raceable manner that permits in-abno-mal, desiga basis event, post design basis dependent auditing cf the inferences or con-event, ard containment test conditions for the clusions based on the information.

performt ice of Cass IE functions.

I Cass IE. The safety classification M the elec-tric equipment and systems that are essential to

9. purpose emergency reactor shutdown, containment iso-lation, reactc.r core cooling, and containment The purpose of this document is to provide and reactor heat removal, or otherwise are es.

d' guidance for demonstrating the qualification of sential m preventm, g significan, release of radio-Cass IE equipment including components or ac e mat t the enWonmnt, equipment of any interface whose failure could components. Items from which the system is adversely affect the performance of Cass IE assembled (for example, resistors, capacitors, systems and electric equipment. Qualification wires, connectors, transistors, tubes, rwitches, required in IEEE Std 279 1971 (ANSI springs, etc).

N42.71972), Cnteria for Protection Systems for Nuclear Power Generating Stations and c ntainment. That portion of the engineered IEEE Std 308 1974, Criteria for Cass IE safety features designed to act as the principal Power Systems for Nuclear Power Generating barrier, after the reactor system pressure Stations can be demonstrsted by using the boundary, to prevent the release, even under guidance provided in this document, conditions of a reactor accident, of unac.

ceptable quantittes of radioactive material The qualification methods described shall be used for qualifying eeuipment and for updating beyond a controlled zone, qua'ification following modifications. Other demonstration. A course of reasoning showing qualification guides for specific electric equip- that a certain result is a consequence of as-ment or test methods (for example, IEEE Std sumed premises; an explanation or illustration, 344-1971, Guide for Seismic Qualification of as in teaching by use of examples.

Cass ! Electric Equipment for Nuclear Power Generating Stations) will present ::pecific re- design basis events. Postulated events,:;pecified

' quirements and should be used to supplement by the safety analysis of the station, used in this document, the dasign to establish the acceptable per-formance requirements of the structures and

, systems.

3. Definitions design life. The time during which satisfactory

[h These definitions establish the meanings of performance can be expected for a specific set of service conditions.

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en 0065945 IEEE Std T.31974 QUALIFYING CLASS IE EQUIPMENT FOR equipment qualification. The generation and '.nat such equipment will meet or exceed its m untenance of evidence to assure that the performance requirements throughout its in-stalled life. This is accomplished through a dis-equipment will operate on demand, to meet the system performance requirements, ciplined program of quality assurance that in-cludes but is not limited to design, qualifica-

.tnstalled life. The m . terval from .mstallation t tion, production quality control, installation.

removal, during which the equipment or com- maintenance, and periodic testing. This docu-ponent thereof may be subject to design senice trient willtreaLoniy .the. qualification portion condition, and system demands, of N3mm

' It is the phmary role e f qualification to as-NOTE: Equipment may have an installed life of 40 years sith certain components changed penodically: sure that for each type of Class IE equipment thus, the .nstalled life of the components would be leu the design and thf manufacturing processes are

'*" ~ " * such that there is a high degree of confidence interface. A junenen or junctions between a that future equipment of the same type will perform as required. The other steps in the

[l Cass IE ecuipment 3.nd ancther equipment or device Ixt=ples: connection boxes. splices, quality assurance program require strict control irrminal boards, eiecn. cal connections, grom- to assure that subsequent equipment of the

. nets. ;askets. cables, conduits, enclosures, etc.', same type matches that which was qualified and is suitsbiy applied, installed, maintamed, l nuciear generati ng station. A piant wherein and periodically tested. glargms used dunn; electne energy is produced from nuclear energv . type testing provide additional assurance that by means of suitable apparatus. The statio'n the equipment will perform as required.

i may consist of one or more units which may or Qualification may be accomplished in several may not share some common auxilianes. ways: type testtag, operstmg expenence, or

[, operating experience. Accumulation of venfi- analysis. These may be used indi"idua!1y er in able service data for conditions equivalent to any combination depending upon the particu-y those for which particular equipment is to be lar situation. In the first,it is expected that the 3

l qualified. equipment vrill be subjected to the environ-ments and operatmg conditions for which it qualified life. The pedod cf time for which was designed and its performance measured,in satisfactory performance can be deconstrated a test program, it is usually practical only to for a specific set of senice conditions. simulate emironmente, and operating condi-NOTE: The qualified life of a particular equiprt.ent tions. The limitations in such simulations. the tegrnay be enanged dunng its installed life where gg g ,

ing the severity of the environment, and the j j y j

sample e q uipment. Production equipment validity of data extrapolations must be taken tested to obtain data that are valid over a range into account n the design of the test. These 2

of ratings and for specific services. po nts will be covered in greater detail in this and other guides. A representative test profile senice conditions. Environmental power and is given in Section 7.!

signal conditions expected as a result of normal Operating expenence is a method oflimited operating requirements. expected extremes in use as a sole means of qualification but of great operating requirements, and postulated condi- use for the supplementation of testing in that it tions appropnate for the design basis events of rnay provide an insight into the change in be-the station. havior of materials and equipment with time type tests. Tests made on one or more sample equipments to venfy adequat.y of design and the manufactunng processes.

1 Representative uwontainment design basis event f h conditions for the pnncipal reactor types are it:cluded 4 in the appendixes for gridance in environrnentst .imu.

& lation. Thess conditions may not be applicabk for all I 4. Introduction spe ific applications and the user should confirm the suitability f these data and modify them as .ippropn-The manufacturers and users of Class IE ate for. qualification for any given Nuclear P-wer Gen-equipment are reuutred to provide assurance erating station.

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Nt* CLEAR POWER GENERA"'ING STATIONS 00G5946 itEE u 3::349N

/9 under actual service and maintenance condi- method to be used to auure proper qualifica-() tions. Operating experience is typically of tion. Each mecod (see halowi requires jusufi.

particular use in qualification of eqmpment cation to assure acceptability.

outside of the contamment.

Qualification by andysis must me!ude justi-5.1 Type Testing. Type testing of actual equio.

ment using simul:,ted service conditions is the ficat4on of methods, theories, and as umpnons

preferred method. This method should be used used. In general, electric equipment is too com-plex to be qualified by analysis alone, althougn for qualifying the greater pottion of equip-it may be effective m the extnpolation of test ment. However, a type test alone satisfies quali-fication only if the equipment to be tested is data and determinaticn of 23 effects or mmer aged. subjected :o all enytronmental ifluences.

design changes to eqmpment that was pre-viously tested. and operated under post-event conditions to With all qualification methods. the end re- provide assurance that all such equipment will N aMe 2 pen'orm Weir intended function for sult must be the documentation that must at '. east 2e recuired operating -ime. When sine demons: rate de equipment's adecuacy to per' form its required function. The cocumentat:ca or other oraciical rec'uirements limit or pre-dude ype tests, this p'ar; of te demonstration must be m a form that adows ven.ncanon ny ecmputent personnel other thsn de quahfiers man be comcieted by metheds desc toed in 3,ctions 5.2. 5.3. and 5.4.

and should contain th.e performance requ re-ments, the qualificat. ion method, results and 5.0 Operating Experience. Electr:c eqwment the justifications. that has operated successfully can be con-sidered qualified for equal or less severe service.

Operating experience can provide inforraation 3

5. Principles of QualifPation n limits of extre.polation, failure modes, and failures rates. The validity of operating expen.

The capability of all Class IE equipment,in- ence as a means of qualification shall be deter-cluding interfaces, of a nuclear power gen, mined from the type and amount of docu-erating station for performing its required func. :nentati n Supporting the service conditions il tion shall be demonstrated. It is prefe-red that and equipment performance, the demonstration be done by type tests on 5.3 Qualification by Analysis. Qualification by actual equipment. Operating experience and analysis shall require the construction of a valid analysis may be used to supplement type tests. mathematical model of the electric equipment Princ.ples and pmcedures for demonstratmg to be qudified,in which the performance char-the qualification of Class IE equipment in- acteristics of the equipment are the dependent clude:

vanables and the environmenta! influences are (1) Assn.ce that the severity of the qualifi- the independent variables. The validity of the cation methods equal or exceed the maximum mathematical model shall be justified by test anticipated service requirements and conditions data, operating experience, or physica' laws of (2) Assurance that any extrapolation or in- nature. Qualification shall consist of a quantita-ference be justified by allowances for known tive analysis of the mathematical mc. del of the potential failure modes and the mechanism

) leading to them electric equipment that shall logically prove dat the performance chanctenstics of the

. (3) On going qualification testing of installed equipment meet or exceed the equipmr ut de-equipment whose qualified life is less than se sign specifications when the equipment is sub-design life of the equipment jected to ie design basis event environment.

(4) Documentation files which provide the Qualified life shall be determined from the basis for qualification time dependent effects of the environmental (5) Qualification t est data as required for on- influences by quantitatively demonstrrdng that going qualification testing the performance charactenstics of the equip-(6.) Qualification of any interfaces associated ment meet or exceed the design specifications B with Class IE equipment of the equipment after a design basis event.

Several demonstration methods are accept- preceded by a time pened during which the 3 able. Service conditions, sine, and agmg are fac- equipment is subjectec, to its normal design en-d tors which d etermine the demonstration vironrnent. The max; mum time period of 9

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006590 IEEE Std 323 1974 QUALIFYING CLASS IE EQlTIPMENT FOR ,

normal environment for which the quantitative or components may continue during the quali.

ana'ysis is vahd shall be the maximum life for fled life period of the installed equipment which the equipment can be qualified by analy. (2) additional equipment could be installed sis, beside the required equipment, removed before in general, mathematical models which can the end of the qualified life pedod, and be type simultaneously quantify all the performance tested to determine its addithnal qualified life characteristics of electric equipment as func. Either of these methods would be considered tions of time and environment are unavailable, on-going qualification. Other methods with Because of this, analysis is generally itsed in the papet :ostification may be found equivalent.

quelification process to quantify electric equip-ment performance as a function of the magni-tude of a single environmental factor, such as S. Qualification Procedures and Method seismic excitation, with aging and all other in-dependent envircnment factors held constant The qualification of Clar, IE equiprnent2 or to quantify the performance of electric shallinclude the following, equipment as a function of the time history of 6.1 Identification of the Class IE Equipment a single environmer.r:1 ft: tor with all inde. Being Qualified.

pendent environmental mfluences held con-stant. This single vanable analysis is then used 6.2 Equipment Performar.ce Specifications.

for justification and augmentation of partial Electric equipment specifications shall define type tests and for providing tha necessary the equipment's Class IE requirements and logical link between the various factors of a shall include as applicable:

, test in which two or more environmenta] para- (1) Performance characteristics under de-meters are simulated. fined normal, abnormal, containment test, de-The data used to suppor*.the qualification of sign basis event, and post design basis event p equipment by analysis shall be pertinent to the conditions application and in an auditable form. The data (2) The range of voltage, frequency, load,

, shall be presented as a step-by step description electromagnetic interference, and other elec-

{ for one complete set of computations, so per. trical characteristL.

4 sons reasonably skilled in this type of analysis (3) The installation requirements including l can follow both the reasoning and the com. mounting method and configuration (s)

' putations. (4) Preventive maintenance schedule for the

) installed life of the equipment,(including lubri-

$ 5.4 Combined Qualification, Equipment may cants and seals) be qualified by type test, previous operating (5) The design life of the equiprnent and the experience, anMysis, or any combination of design life of any components which may have these three methods. Partial type test may be a life shorter than that of the complete equip-augmented by tests of components where size, ment applications, time, or other ter limitations pre- (6) Control, indicating, and other auxiliary clude the use of a full type test, devices contained in the equipment or extemal Partial type tests with extrapolation or to the equipment and required for proper op-an aly sis, operating experience with extra- eration polation or analysis, and type tests supple- (7) The range, type, and duration of environ-mented with te;,ts of compenents and analysis mental conditions including temperatute, pres-are exan.ples of the use of combined sure, humidity, radiation, chemicals, and qualification. seismic forces 5.5 On-Going Qualification. The qualification (8) Complete dascription and nunf.<r of methods described thus far may yield a quali- operating cycles ,meluding periodic testing fled life of equipment that is less than the anti- (9) Qualified life. (This Performance Speci-cipated installed life of the equipment. When fication entry may be established dunng the B this occurs, an on-going qualification program qualification testing)

A may be implemented.Two methods for achiev-ing this are: 2 Throughout this document the use of the term (1: aging and testing of identical equipment Class IE equipment also includes appropriate interfaces, i 10 l

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NUCLEAR POWER GENERATING STATIONS 0065948 rEEE sta 323 1974 taken into account in specifying the test f

x 6.3 Type Test Procedures 6.3.1 General The type test shall be de- mounting.

signed to demonstrate that the equipment per. 6.3.1.3 Connections. Equipn nc shall be formance meets or exceeds the requirements of connected in a manner that simulates N ex.

the equipment specifications for the plant.The pected installation when in actual use unlea an type test snall consist of a planned sequence of analysis can be performed and justified to show test conditions that meet or exceed the ex. that the equipment's performance would not pected or specified service conditions, includ. be altered by other means of connection. By ing performance margin, and shall take account manner is meant the means to be used in con-of both normal and abnormal operation. nection to equipment such as wiring, connec.

6.3.1.1 Test Plan. The first step in the test tors, cables, conduit, terminal blocks, service procedure is the preparation of the test plan. loops, piping, tubing, etc.

The plan should be compatible with the equip. 6.3.1.4 Afonitoring. The test shall be ment specification and should contain suf- monitored using equipment that provides reso.

Scient detail to describe the required tests and lution for detecting meaningful changes in tha provide an auditable link between the specifica- variables. The test equipment shall be cali.

tions and the test results. Auditable hnh means brated against auditable calibration standards that the plan should provide proof that the test and shall have documentation to support such method used was adequate, ns this is not a)- calibration.The time interval between measure-ways discernible from the test results. ments shall be such as to obtam the time de-The test plan should contain the following pendence of each variable. In describing test information: sequences, the measured variables may be (1) Equipasent descriptions classified into general categories as follows.

- (2) Number (quantity) of units to be tested 6.3.1.4.1 Category I - Environment.

(3) Mounting and connection requirements Temperature, pressure, moisture content,3 gas (4) Aging simulation procedure composition, vibration, and time.

, (5) The service conditions to be simulated 6.3.1.4.2 Category II-Input Electrical b (6) Performance and environmental variables Characteristics. Frequency. current, voltage.

to be measured power to the equipment, and time duration of (7) Test equipment requirements including the input.

accuracies 6.3.1.4.3 Category ill - Fluid Char.

(8) Environmental, operating, and measure- acteristics. Concentration of chemical con-ment sequence in step-by-step detail stituents in fluid injected into the test chamber (9) Performance limits or failure definition plus the flow rate and spray disposition and (10) Documentation (Section 8.3) temperature of such fluids.

(11) Statement of nonapplicable portions of 6.3.1.4. 4 Category IV - Radiological the 5,,eci5 cation Features. Nuclear radiation data including en-

= (12) A description of any conditions pecu. ergy type, energy level, exposure rate, and in.

liar to the equipment which are not covered tegrated dose.

above, but which would probably affect said 6.3.1.4.5 Category V-Ilectrical Char-equipment during testing acteristics. Insulation resistance of electrical 6.3.1.2 Afounting. Equipment shall be cornponents; voltage, current and power out-mounted in a manner and position that put; response time; frequency characteristics simulates Its expected inst ation when in and siinu sted load.

actual use unless an analysis can be performed 6.3.1.4.6 Category VI - Afech;nical and justified to show that the equipment's per- Characteristics. Thrust, torque, time, and load formance would not Ie altered by other mean profile.

of mounting. By manner is meant the means to 6.3.1.4.7 Category VII - Auxiliary be used such as bolts, rivets, welds, clamps, etc. Function Sfeasurements. Function measure-ments related to Class IE equipments which g By position is meant the spatial orientation with respect to the gravitational field of the

,m earth. The effect of any interposing structures which are required for installation, such as con- s Appendix c contains a pretened method to, as.

trol boards, stands, legs cedestals, etc, shall be suring i.atunted steam conditiona in a test ennronment.

11

. _ - . _ _ _ - _ _ _ - - _ _ - - ___ _ _ ._. n'

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0065949 TEEE Std 323 t974 QUALIFYING CLASS TE EQUIPMENT FOR are included in the equipment but not neces- 6.3.2 Test Sequence.The type tests shall be b sary for its own operation; that is items which run on the equipment in a specified order. For are required to provide a signal to control other most equipment and applications, the follow-Class IE equipment. Included under this head- ing constitutes the most severe sequence;how-ing would be auxiliary switches and position ever, the sequence used shall be justified as the feedback potentiometers. Measurements shall mcst severe for the item being tested, be taken which confirm the capability of the (1) Inspection may be performed to assure equipment to handle ratad or specified load that a test unit has not been damaged due to and to provide rated or specified accuracy. handling since manufacture and to determine Relevant measuremetas would include: current basic dimensions. This inspection shall not be carrying and current interrupting capability of directed to select a specific unit for type test-switches; contact resistance of limit switches ing with contacts closed; and potentiometer resist-(2) The equipment shall be operated under ance and linearity. -

normal conditions to provide a data base for l 6.3.15 Mergin. Margin is the differenc comparison with performance under more between the most severe specified service con- highly stressed conditions. Certain measure-ditions of the plant and the conditions used in ments such as drift (rate of change with time) type testing to account for normal variations in of a parameter may be made at this time commercial production of equipment and rea.

sonable errors in defining satisfactory per. (3) The equipment shall be operated to tha formam. The qualification type testing shall extremes of all performance and electrical char-include provisions to veri!y that adequate mar, acteristics given in the equipment specifications gm exists. In defining the type test, increasing excluding design basis event and post design

- levels of testing, number of test cycles, and test basis event conditions unless these data are duration shall be considered as methods of as. available from other tests on identical or e9

. suring adequate margin does exist. sentially similar equipment Suggested factors to be applied to service (4) Equipment shall be aged in accordance b conditions for typ testing are as follows: with Section 6.3.3 to put it in a condition (1) Temperature: + 15'F (8'C). When quali- which simulates its expected e n d -of-fication testmg is conducted under saturated qualified life condition including the effect of steam conditions, the temperature margm shall radiation (design basis event radiation may be be such that test pressure will not exceed satu- included). If the required radiation level can be

. nted steam pressure corresponding to peak ser. sho.vn to produce less effect than that which vice temperature by more than 10 lbr/in would cause loss of the equipment's Class IE (2) Pressure: + 10 percent of gauge,but not function, radiation need not be included as more than 10 lbr/in2 [7.03(104 ) kg/cm ] part of aging. Certain key measurements should (3) Radiation: + 10 percent (on accident be made following aging to determine if the dose) equipment is performing satisfactorily prior to (4) Voltage: 210 percent of rated value un- subsequent testing 1

less otherwise specified (5) The aged equipment shall be subjected to

. (5) Frequency: a 5 percent of rated value such mechanical vibration as will be. seen in ,-

unless otherwise specified service. This should include simulated seismic ->

(6) Time: + 10 percent of the period of time vibration (see IEEE Std 3441970,%If.

the equipment is required to be operatival fol. induced vibration (see IEEE Std 334 1971, lewing the design basis event Trial Use Guide for Type Tests of Continuous (7) Environmental Transients: The initial Duty Class I Motors Installed Inside the Con-transient and the dwell at peak temperature tainment of Nuclear Power Generating Stations i shall be applied at least twice ( ANSI N41.9)

(8) Vibration: + 10 percent added to the (6) The aged equipment shall next be g[ acceleration of the response spectrum at the operated while exposed to the simulated design mounting point of the equipment basis event (Section 7) [ radiation may be ex.

.copM b W abd. he hd NOTE: Nesative 1.: tors shall be applied when lowenng the value of the tvice conditions increases the functions which must be performed during the severity of the ter simulated design basis event shall be monitored 12 k l l

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I IEEE Std NUCLEAR POWER GENERATING STATIONS 006*v;950 323.t824

/~"N (7) The equipment shall then be operated plied as a part of the sequence of environments V while exposed to the simulated post accident conditions (following exposure to accident representative of service conditions. The equip.

ment shan be subjected to the significant type conditions). Those functions which must be of radiation equivalent to that expected in ser.

performed following the simulated design basis vice. However, if more than one type of radia-event shall be monitored during this simulation tion is significant, each type can be applied (8) Disassemble, to the extent necessary for separately. In determining the' total required the inspection of the status and condition of test radiation equivalent to that of servicelife, the equipment and record the findings consideration shaU be given to oxidation gas-6.3.3 Aging.The objective of aging is to put diffusion effects. To facilitate the use of a rea-samples in a condition equivalent to the end-of- sonable test time, an accelerated exposure rate life condition. If previous aging of various de- may be necessary. Thus, to allow margin for vices exists, it can be utilized provided these these effects, a greater total dose than the ser-data are applicable and justifiable in regard to vice lifetime dose should be applied. Formulas the service conditions that are required by the for approximating she test dose equivalent to performance speci5 cations of the device to be service are given in IEEE Std 2781967 (ANSI type tested. N4.119E7), Guide for Classifying Electrical In.

A short period of accelerated thermal aging sulating Materials Eroosed to Neutron and merely simulates service life; however, it pro- Gamma Radiation ar'd ASTM D 2953 71, Clas-duces some deterioration and, when followed sification System for Polymeric Materials for by vibrat!on may produce realistic failure Service in Ionizing Radiation.

v modes.' Radiation shall be added to other 6.3.5 Vibration. The aged equgment shaU known degrading influences where appropriate. be qualified for expected seismic events in ac.

I Margins over that expected in the qualified life cordance with IEEE Std 3441971. In addition, shall be provided in the application of each in- equipment subject to nonseismic vibration dur-fluence. Electromechanical equipment (motors, ing normal and abnormal use shall be subjected

(% relays, etc) shall be operated to simulate the to such typical vibration following the aring expected mechanical wear and electrical con- and seismic procedures. Vibration te be Ql tact degradation (for example, contact pitting) of the device to be type tested.

simulated shall include selfinduced vibration (su:h as the starting and running of a motor, An accelerated rate for the number of cycles vibration from nearby equipment, or vibration equal to the required number during the design from equipment) which produces the mounting life may be utilized provided the rate shau not support for the Class IE equipment being

be accelerated to any value which results in qualified (sach as pes, generators, motors,

, effects that would not be present at normal etc).

rates.

6.3.6 Operation UnderNormaland Accident For insulating materials, a regression line Conditions. Means shall be provided during the (see IEEE Std 101-1972, Guide for Statistical type test for electricaDy energizing the equip-Analysis of Thermal Life Test Data) may be ment, applying simulated loads, applying input used as a basis for selecting the aging time and signals, and exposing it to simulated emiron-temperature. Sample aging times of less than mental conditions (for example, temperature, 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months shau not be permitted. pressure, moisture, vibration, nuclear radia-6.3.4 Radiation. All materials or com- tions, chemical solutions, jet forces, and chem-ponents which may be degraded to a degree ical composition of the ambient environment).

which would adversely affect performance of 6.3.7 Inspection. Upon completion of type Class IE functions by the radiation exposure testing, the equipment shall be dismantled to expected to occur during normal service and permit all parts to be appropriately tested and postulated accidents shall be irradiated to visually inspected. The condition of electrical simulate this exposure. Radiation shall be ap. insulation, mechanical puts, bearings, lubri.

cants, electrical contacts, wiring, gear drive g trains, linkages, and other related components shall be recorded.

e 'See IEEE Std 11969. General Principles for

/[

d Temperature Lirnits m the Rating of Electric Equip.

me nt.

6.4 Operating Expertence 6.4.1 General Qualification of electric 13 i

_ _ _ _ - _ - _ _ _ _ . _ ._ I:

- "N 00659M IEEE Std 323 1974 QUALIFYING CLASS IE EQULPMENT FOR equipment by opvating experience shall con- 6.5 Analysis sist of determining the past history of per. 6.5.1 General. Qualification by analysis shall formance and service conditions of the equip- consist of a mathematical or logical proof that ment type to be qualified, correlating operating the Class IE performance of the equipment to service conditions with design service condi- be qualified meets or exceeds its specified per-tions, and proving that the Class IE per. formance when subjected 'to its specified formance characteristics of the equipment will normal and design basis event environments. In meet or exceed the equipment specification general, this proof must be based on estab-under design service conditions. lished principles, operating experience data, 6.4.2 Operating History. partial type test data, or combinations of these.

6.4.2.1 The operating environment of the All assumptions, including extrapolations that electric equipment to be qualified shall be are made in proof, thall be justified by estab-determined and shall be justified by analysis of lishing principles or verifiable tes; data; and the

': the effects of noncontinuous mecsurements. analysis shall be of a form that can be readily l The documentation of the operating environ- understood and verified by people qualified in l m ent shall include physical locations and the pertinent discipline of engineering or mounting arrangements of the equipments in science, the operating facilities. 6.5.2 Afathematical Afodeling.The first step 6.4.2.2 The performance of the electric in the qualification by analysis is generally the equipment type to be qualified shall be deter. construction of a valid mathematica1 model of mined from measured data or analysis of the electric equipment to be qualified. The failures that may have occurred or both. Docu. mathematical model shall be based upon estab-mentation of all Class IE performance shall in, lished pnneiples, veriCable test data, or operat-clude measurement or determination of all per. ing experience datn. The mathematical model fortnance characteristics in the equipment shall be such that the performance of the elec.

specifications, recording and analysis of all tric equipment is a function of time and the O[ , failures ud trends that occurred during the operating period, and a log all periodic main.

pertinent environmental parameters. All en-vironmental paramete:s listed in the equipment tenance (including adjustmms and calibra. specification must be accounted for in the con-

) tions) and inspections. struction of the mathematical model unless it I can be shown that the effects of the parameter 6.4.3 Determination of Qua!!/ication.It shell f interest are dependent on the effects of the

! be documented thr'. the equipment whose operational history becomes a basis for qualifi. remaining envir nmental para" . , Os.

cation is typical of equipment bearing the same 6.5.3 hpolata hpolation is an i

designation. analytical technique whien may be used to aug.

The electric equipment type shall be con- ment testing. However, in order to be con-sidered to be qualified by demonstrating that sidered valid for qtialifying Class E equipment the recorded operating envirotunent equals or certain guidelines must be met.

exceeds the design environment in severity, and 6.5.3.1 Failure Modes. The modes of that the performance of the in service equip. failure produced under intensified or ac-ment equaled or exceeded the specified user celerated envitonmental or other influences requirements. The period of time for which the shall be the same as those predicted under the above requirements can be shown to be met required service conditions. If not, the in-with reasonable margin shall be the qualified tensity of the accelerating variable shall be re-life. duced until faibre modes and mechanisms pw-It should be noted that if the design environ. duced are consistent with those known or pre-ment includes seismic accelerations followed dicted for required service conditions, by a design bs. sis event environment that is 6.5.3.2 Characterization of Effects. The g more severe than the recorded in service en.

vironment, then the installed equipment must, life (or other attribute) being extrapolated shall be characterized as a function of the environ-in general, be removed from service and sub. mental variable to provide a basis to forecast O jected to a partial type test to include the sei:mic and design basis event effects before changes of the equipment performance with tima (or other domains.

the equipmerit can be considereo fdly qualified. B.5.3.5 I.u.apolation Basis. To establish 14

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IEEE Std NUCLEAR POWER GENERATING STATIONS 00L 952 mum the basis for extrapolation, equipment or com- periodic replacement plan shall be instituted.

ponents shall be subjected to a comparable en.

vironment for a time or level necessary t 6.7 Criteria of Failun. In the evaluation of the Justify the extrapolation of the test results t qualification test results, any sample equip.

the total time or level to be qua'ified. ment is considered to have failed when the equipment does not perform the Class IE fune-6.5.4 Determination of Quell /icatw.n. The tions required by the equipment' specifications.

electric equipment type shall be considered to be qua!ified by demonstrating that the equip. 6.8 Mod 15cnions. Modifications should not be toent performance will meet or exceed its made to the equipment, or to the equ!pment or specified values for the mor.t severe environ- test specifications, after the start of the type ment or sequence of environments in the test or beginning of the operstmg experience equipment specification during its qualified reporting period since such modification wi'.1 life. The severity of thc environmental para- normally render the test and experience results meters shall be based upon knowledge of the inconclusive. Modifications may be made only faihtte modes and failure nwchanismr of the if full justification is documented t e M 'W5 0 equipment which may be determined by test, that such modifications have no be I z w ' e b The qualified bfe shall be baserl upon the validity of the test.

known limits of extapola+. ion of the time de- Each Lodification to 7 *t' A 11 <9 pendent environmental effects if an accelerated the equiptnent specificWr 4# N i \

aging test was used to determine the mathe- type test or beginning ; t / #Av . . .

matical model. pcrience reporting period :L 4 N .<d to 6.6 On-Going Quali5 cation. Some equipment determine its effect on the eq4usent qualifi-may have a qualified life less than the required cation. This evaluation shall indicate whether design life of a nuclear power genenting sta- or n t c mP ete l requalification is required. If tion. There are two recommended methods of not, the analysis or data and evaluation that O

V long term qualification (see Section 5.5):

(1) Equipment of the same type as that demonstrates the effect of the modi 5 cation on equ2pment performance shall be added to the

' riginal quali5 cation decumentation, which has been type tested rmnd installed in a station shall be placed in an environment that Components of the equiprnent which can be accelentes the aging under controlled condi- shown to be unaffected by the change need not tion.s. When it is determined that the equip- be type tested again, as previous operating ex-enent has reached the required design life of the perience and type test data along with com- ,

station, it shall be removed frorn the ac- plete qualifications for portions affected by the "

celerated life environment and type tested. The m dification shall constitute quali5cauon of installed equipment may be considered ade- '"** E**" .

quate for the design life of the station if the Any chr:ges m quali5 cation basis, materials equipment that was subjected to the ac- # "* "' "" ' "# "' *"**"'

celerati.d life environment passes the type test * *#*"# "' * * " " ' " E .E# **** ##

(2) Additional identical equipment shall be s, e , a en and b installed in a nuclear generating station in loca- e9uipment requali5ed if necessary. Necessity tions where service conditions equal or exceed a ased on effect of the change on the 3 those of the equipment to be qualified. This equipment shall be removed after a planned 6.9 Documentation. Files which provide docu-period less than the previously quali5ed life mentation of the qualificaticr. p ocedures, and subjected to a qualification test similar to methods, nd results shall be maintained to that performed prior to its installation. This provide a current basis for qualification and

est must include additional accelerated aging. permit comparisons if future tests are cou-Successful completion of this type test extends ducted.

the qualified life of the installed equipment.

R This procedure shall be repeated until the qualified life equals the required installed life t

7. Simulated Service Condition Test Profile of the equipment U Should the above methods demonstrate that The user shall fumish sufficient environ-the qualified life is le's than the required IL, z mental data to allo c the simulation of the 15

0065953 IEEE Sta 323 1974 QUAT.!FYING CLASS IE EQt!IPMENT FOR s

postulated design basis event profile. To this 8.3 Type Test Data. The type tut data shall shall be added performance margins (see Sec- contain:

tion 6.3.1.5) to derive the appropriate (1) The equipment performance specifica-simulated service condition test profile (Fig 1), tions (Section 6.2)

^

(2) Identification ol' the specific feature (s) to be demonstrated by the test _

(3) Test plan (Section 6.3.1.1)

(4) Report of test results

8. Documentation The report shall include: ?

(a) Objective S 8.1 General. The caalification documentation (b) Equ.ipment tested shall serify that each type of electric equip-ment is qualified for its appli:stion and meets (c) Description of test facility (test setup) {y and instrumentadon used including calibmtion e

its specified performance requirements. The records reference D basis of qualification shall be explained to (d) Test procedums show the relationship of all facets of proof [

(e) Test data and accuracy (results) i-needed to support adequacy of the complete (f) Summary, conclusions, and iecom- -

equipment. Data used to demonstrate the mendations qualification of the equipment shall be per- (g) Supporting data tinent to the application and organized in an (h) Approval signature and date auditable form.

8.4 Operating Experience Data. The operating 8.2 Documentation Files. The user shall main- experience data shall contain: r tain a qualification file (not necessarily at the (1) The equipment performance specifica.

plant site). The file shall contain the informa- tions (Section G.2) tion as listed in Sections 8.3, 8.4, 8.5, and 8.6 (2) The interface or boundary conditions of ;

depending upon the qualification method used, the equipment '

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i hi Q 2-l Q ;Q Q O G ,} s W .4 g NUCLEAR POWER GENERATING STATIONS 0065954 ter r sta 323 1974 (3) The specifications of equipment for (2) The interface or boundary conditions of which operating experience is available the equipment .

(4) Identification of the specific features to (3) The specific features, postulated failure be demonstrated by operating experience modes, or the failure effects to be analyzed (5) Comparison of past application and (4) The assumptions, empirienlly derived specifications with the new equipment specifi- values, and mathematical models used together cations for each feature identified above with appropriate justification for their use (6) Summary and source of operating ex- (5) Description of analytical methods or perience applicable to equipment qualification computer programs used

(7) The basis on which the data have been (6) A summary of analytica"y established L-determined to be suitable and the equin-ent performance characteristics and their accept-qualified ability (8) Approval signature and date (7) Approval signature and date

, , 8.6 Extrapolation. Where the test data or 6t 8.5 Analysis. The analysis data shc.ll contain: operating experience data have been extra.

C' (1) The equipment performance specifica- polated, the basis for the extrapolation shall be tions (Section 6.2) included.

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0065955 EEE Std 323 1974 QUALIFYD4G CLASS E EQUIPMENT FOR A

V Appendix A In Containment Design Basis Event Environment Simulation For Pressurized Water Reactors and Boiling Water Reactors (These appendizes are not part cf EEE Std 3231974. Qualifying Chun E Equipment for Nuclear Power Generating Stations.)

NOTE: All the conditions presented are npresentative other Guids. These environmental conditions and may need modincation to assun their suitabuity differ markedly among different types of re.

to any specine equipment application.

gg g Al General. The design basis event environ-to location in the plant. In most locations out.

ment conditions to be simulated for a Pres- side of the primary containment there will be surized Water Reactor (PWR) or Boiling Water no special environmental conditions resulting Reactor (BWR) resulting from a postulated from a design basis event.There are otherloca.

loss.of<oolant accident (LOCA) which are to tions, such as within the reactor building in be simulated generaDy consist of exposure to some BWR plants, where there will be special hot gases or vapots (for example, steam) and a environmental conditians, but these may be spray or jet of water, chemical solution, or less severe than those within the inmary con.

Fig Al Test Chamber Temperature Profile for Emironment Simulation (Combined PWR/BWR)

ADDITIONAL

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Table A1 Test Conditions for Pressurized Water Reactors *

(Typical In{ontainment Design Basis Event Teet Conditions)

-.A (1) Exposure to Nuclear Radiationt 4 megarada after 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 20 megarads after 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 24 megvads after i day 40 megarads after 10 days 55 megareds after 1 month 110 m:e trads after 6 montha 150 megarada after 1 year

- (2) Exposure to Steam and Q emicals (8 eam 2posure Temperature Pressure Time (* F) (*C) (Ibe/in s, gauge) (kPa) l O to 10 seconds 1"o to 300 48.9 to 148.9 0 to 70 0 to 482.6 10 seconds to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 300 148.9 70 482.6 to hours to 4 days 210 98.9 40 275.8 4 days to 1 year 167 75.0 5 34.5 (b) Spray Exposure. Continuously spray vertically downward for first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with a solution of the following composition at a rate of 0.15 (gal / min)/ft 2 (6.1 (ml/ min)/m 2) of area of the test chamber s projected on to a horisontal plane.

0.28 mola. n3 B0 3(3000 parts per million boron) 0.064 molar Na2S0 73 NaOH to make a pti of 10.5 at 77*F (about 0.59 percent)

Dissolve chemicals, on a one-liter basis, in the following order:

(i) 600 ml potable water (ii) H3B03 (iii) NaOH On I

(iv) Na2 S03 2 (v) Add remainder of water to volume of one liter (vi) Add NaOH to make a pH of 10.5 at 7P F, as required for the initial spray solution.

The valres given in this table may vary from plant to plant and may or may not contain adequate margin.

TConservativ< calculation of radistico dose to containment atmosphere resulting from beta and garnma radiation emitters rete * <d from the primary system and at a location within the primary containment.

Table A2 Test Cenditions for Boiling Water Reactors *

(Typical In-Conunment Dwign Basia Event Test Conditions)

9) Exposure to Nuclear Radiationst 26 megarads integrated over the accident (2) Exposure to Steam and Spray (a) Steam Exposure Temperature Pressure

. 'Ibe (*F) ('C) (Ibs/id. gsuge) (kPa)

O to 20 seconds 135 to 280 57.2 to 137.8 0 to 62 0 to 427.5 20 seconds to 5 min 280 to 340 137.8 to 171.1 62 427.5 5 min to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 340 171.1 40 275.8 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 320 160.0 40 275.8 6 iiours to 4 days 250 121.1 25 172.4 4 to 100 days 200 93.3 10 68.9 11 it is not practical to reprodace the specified pressure and temperature profiks combined, it la acceptable during the first four days to follow the temperature profile and allow the prenure to conforn. to saturated conditions (100 percent relative humidity). This procedure is justified by the fact that tem;:erature is the more important parameter and increasing the pressure (to maintal.s g saturated conditions) will increase the severity of the test,if anything.

(b) Spray Exposure. Continuously spr 7 vertically downward with domineralised water at a rate of 0.15 (gal / min)/fts (6.1 (rn!/ min)/m ) of trea of the test chamber projected onto a horiscntal plane.

'See 1st footnote to Tabte A1.

TSee 2nd footnote to Table A1.

19 m

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~~1' .WI,f44 usage,g IEEE Std 0065957 323 1974 QUALIFYING CLASS IE EQUIPMENT FOR O

V tainment, The equipment specification shall de- shown in the profiles (Fig A1).

fine the actual environment in detail.

The test profile to simulate the environ- A2 Simulation Sequence. Suggested sequences ment al c onditions anticipated within the include:

primary containtnent in current plants with (1) Expose sample equipment to simulated Pressuriaed Water Reactor (PWR) and Boiling (a) Aging Water Reactor (BWR) are shown in Tables A1 (b) Radiation (if size permits and if war-and A2. If it is desired to qualify equipment ranted by radiation tolerancelimits and effects for in containment service for both PWRs and on Class IE performance)

BWRs, the test conditions may be chosen to (c) Vibration encompass both test profiles, including the (2) Stabilize operation in normal environ-chemical spray specified for PWRs and the ment to establish reference conditions te m perature/ pressure profile specified for (3) Inject steam unct chemical sprays at rates BWRs Fig Al shows a representative test simulating service conditions, raising the chamber profile for a combined PWR/BWR temperature and pressure to tes; profile levels test. If tise actual conditfore are different from reged these curvas, the parameters may be adjusted (4) Maintain these conditiens for three accordingly. As noted above for out F hours. De-energize for static readings including containment service, the conditions may be insulation resistance to ground, Re-energize lets severe and generally are not different from one additional hour the normal operating conditions. (5) Reduce the environmental conditier.s to Although the equipment is expected to ex. the normal operating conditions within two perience at most only one severe environmental hours transient as a result of a LOCA event durmg its (6) Repeat first cycle; but at the end of installed life, it is recommended that it be ex- three hours, lower pressure in steps as required posed to two initial steam / chemical transients to simulate post-event profile for which equip-

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l'

. in the Accident Environment Simulation, as ment is to be qualified

o. !

Appendix B i

In Containment Desi;,n Basis Event Environment &mulation For A High Temperature Gas Cooled Reactor (HTGR)

NOTE: All the conditions presented are representative criteria he used in selecting this condition. If and may need modification to assure their suitabiUty to any specine equipment application. doubt exists in identifying which condition is The design basis event (DBE) environments to testing the equipment under both condi-to be simulated for a high temperature gas tions.

cooled reactor (HTGR) typically consist of ex- Various test profiles may be used to produce posure to helium or steam. Table B1 in con- the same equipment conditions provided this is junction with Figs B1 and B2 present the anti- adequately demonstrated by analysis or other cipated pressure and temperature history of the means. The helium blowdown DBE profile as-containment ttmosphere for design basis event sumes helium is used, however, nitrogen, air, or environments; hot helium blowdown and hot other gas can be used provided the exposure reheat steam line rupture. Shown with the profile is appropriately modified.

helium and steam exposure profiles is a repre. The qualification testing shd! assure ade.

O sentativa equipment surface temperature pro- quate margin of survival. Although the equip-

, f~ file. It is the responsibility of the equipment ment is expected to experience at most only

(' manufacturer to determine which of the con- one severe environmental transient as the result ditions will present the most severe environ- of a DBE during its installed life, it is suggested ment for his equipment and to specify the that it be exposed to at least two DBE 20

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NUCLEAR POWER GENERATING STATIONS QQhgr$ 3 IEEE Std 323 1974 c ._, c._. . . . , . .

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e; a i i 11-I n.ee.. g i i i

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-*=c ,,,~- e a

Fig B1 Typical Temperature and Pressure History for Erwironment Simulation of HTGR I Contammeat Atmosphere Response Following a Hot Helium Blowdown into Containment (T. = 100*F P. = 14.7 lb,/in e2 Note: For Long. Term Testing, Assume Equilibrium Conditions at T = 120*F and 35 lb,/in2.)

Table B1 Test Conditions for High. Temperature Gas. Cooled Reactors (TypicalIn Containment Design Basis Accident Conditiotti)

(1) Exposure to Nuclear Radiation 2 megarads after I hour 12 megarads after I day

'75 megarads after 1 year

$ (2) Exposure to Steam and Cases (a) Hot hehum exposure -see p}

s

(,)

Fig B1 (b) Superheated steam exposure -

see Fig B2

=

21

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OC65053 IEEE Std 323 1974 QUALIFYING CLASS IE EQUIPMENT b

N. transients as a method of demonstrating this As an aid in preparing for an environm<

margin. This method is shown in Figs B1 and simulation, the typical normal operating ec .

B 2. tions for an HTGR are presented in Tabh t

i Fig B2 Typical Temperature and Pressure History for Environment Simulation of HTGR Containment Atmosphere Response Following a Steam Line Rupture Inside the Containment (T. = 100* F, P. = 14.7 lb /in t. Note: For Long. Term Testing, Assume Equilibrium Conditions at T = 120'F and P = 16 lbr/in2.)

cw c, se.

_,..= . t

' i 1-.,w. 1-....

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l 14 u. aware . . . . 165 73 9

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4newsnoSe==en om 243 3 > 234 4 . .

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50 e

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.. e IEEE Std l NUCLEAR POFER GENERATING STATIONS 323 1974 Im I

'.) Table 32 HTGR Containment Building QO66900 (Normal Opera;.ing Conditions)

Top Head Area Bottom Support Area at.verage Ambient Maximum Average Ambient Maximum Temperature 70-100* F 1?0* F 70-130* F 160*F (54.4* C) f71.1*C)

Pressure -0.5 (21.1-37.8*C) to 0.5 lb /in 2, -0.5 to 0.5 lbg/int , (21.1-54.4*

-0.5 C) t, to 0.5 lbg/in 4.5 to 0.5 lb /in 2, gauge gauge gauge gauge

(-3.4 to 3.4 kPa) (-3.4 to 3.4 kPa) (-3.4 to 3.4 kPa) (-3.4 to 3.4 kPa)

jq

10-30 percent 80 percent 10-80 percent 80 percent d a 2.5 to 25 mrd/ hour < 100 mrd/ hour 2.5 to 25 mrd/ hour < 100 mrd/ hour l Radiat. ion

,,' 8.8 x 103 rd 8.5 x 108 rd I plant life

=====. a:r_ . .

I i Appendix C i

Test Chamber Meisture Content 1

The simulation of Design Basis Event (DBE) T = T... .. = T. ,,.

cor'litions in qualification tests sometimes re.

Q quires that a moistumeaturated environment For 100 percent relative humidity (RH), or 7# be maintained at temperatures exceeding the saturatO' conditions, it is necessary that the f highest temperatums at which commercially partial . team pressure be equal to the pressure available relative humidity and dewpoint of saturated steam (P,. ) at the temperature T.

sensors are capable of functioning. This ap* If one knew the partial pressure of steam in the l pendix suggests one way in which the existence

' muture, steam tables could be used to venfy of a saturated atmosphere can be assured in whether Pn..m and T correspond to saturated such cases.

steam condRions and, therefore, whether the Generally, the chamber that contains the RH of the mixture is 100 percent. However,

, equipment under test is initially full of air, and steam is injected into the chamber to execute the difficulty of measuring the partial pressure of steam makes this impractical. One way to the specified temperature profile. The analysis avoid this problem is to introduce moisture in-of moisture concentration inside the test to the test chamber in a way that assures chamber would be quite straight. forward if the saturation of the environment, as is described air initially in the chamber were to reusain below.

trapped inside it, or if the air were driven out The gas in a test chamber will be saturated completely by the introduction of steam. But with water vapor, that is, have a relative the situation is generally intermediate between humidity of 100 percent, if thennal equili-these extremes, and there is no convenient way of deter:rining-the exact state. This is il' brium exists between the water vapor and liquid water inside the chamber. Therefore, one lustrated by the following.

way to guarantee saturated conditions is to Consider a mixtum of air and steam at piace a container of water inside the chamber temperature 7 and pressure P. The pressere of and keep its temperature at a value e ,oal to the p) the mixture is equal to the sum of the partial temperature of the gas in the chmber. It is pressures of steam (P,,,,) and air (Po ,): also required that water vapor be evaporated (N) p.p ,+p,, from the heated water at a rate capable of

" saturating the chamber solume m a time that is and 9t mv*ium, we have short by comparison with the duration of con-

. 23

._ _____.m_ _ _ _ _ - - - - . _ - - . _

. . . .. . . . . . ... . w .~- - .- ~ , _ ,..- _ _ ,

l.

0065961 stant-temperature dwells in the test profile.To other means of mixing must be provided to facilitate this, the water should be heated to asrure uniformity of the chamber atmosphere, boiling prior to the start of the test. A further The method described above will provide a requirement is that the chamber atmosphere be saturated atmosphere essentially throughout stirred at a rate adequate to maintain uniform the test. The only exception is the short period

,l conditions. required to reestablish equilibrium following a i As an example, this can be done by sparging temperature rise. Since the amount of water steam through water in a vessel that is inside vapor needed to saturate an environment de-the test chamber. The temperature of the water creases with a drop in temperature, there must equal or exceed the temperature of the should be no lag in maintaining saturated con.

steam / air mixture in the test chamber. The ditions following temperature drops. Other steam flow rate must be adjusted to meet this methods t,f maintaining saturated conditions requirement as well as to satisfy the require- may be used provided their ad.:quacy is demon-ments of the preceding paragraph, and a fan or strated.

t i.i t 5l i

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1 i

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24

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ML20094P362

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