ML19220A236
| ML19220A236 | |
| Person / Time | |
|---|---|
| Site: | Perkins  |
| Issue date: | 09/30/1975 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19220A237 | List: |
| References | |
| REF-GTECI-A-43, REF-GTECI-ES, TASK-A-43, TASK-OR REGGD-01.079, REGGD-1.079, NUDOCS 7902090027 | |
| Download: ML19220A236 (4) | |
Text
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U.S. NUCLE AR REGULATORY COMMISSION Revision 1
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REG J a"?ORV G UBD)E OFFICE OF STANDARDS DEVELOPMENT REGUL ATORY GUIDE 1.79 PREOPERATIONAL TESTING OF EMERGENCY CORE COOLING SYSTEMS FOR PRESSURIZED WATER REACTORS
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A. INTRODUCTION B. DISCUSSION General Design Cnterion 1, " Quality Standards and The NRC staff has concluded as a result of recent RecordsJ of Appendix A," General Design Critena for inspections and reviews of safety analysis reports a:td Nuclear Power Plants / to 10 CFR Part 50, "Licensmg startup reports that additional guidance should be of Production and Utdization Facilities / requires that provided regarding the scope and reporting of ECCS structures, systems, and components of nuelcar power preoperational testmg identined in paragraph 9, "Em-plants important to safety be tested to quahty standards gency Core Cooling S,.'st e m s.'
of Appendix A to comm-nsurate with th importance of the safety fune-Regulatory Gaide 1.68.
tions to be performeu. Crnerion XI, " Test Control," of Appendix B, "Quaht y Assurance Criteria for Nuclear Power Plants and Fue! Reprocessing Plantsf' to 10 CFR C. REGULATORY POSITION Part 50 requires that a test program be estabbshed to ensure that a'l testing required to demonstrate that A comp.ehensise preoperational test program on structurec, systems, and compenents will perform entis.
the emergency core cooling system and its components factonly m service is identified and performed.
should be performed to provide asst.nnec that the ECCS wdl accomplish its intended function when required.
a l test-related actnities l
Regulatory Guide 1.6L "Preoperational and Imtial The program should cover Startup Test Programs for Water-Cooled Power Rea; including:
tors," describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to preoperational te> ing of nuclear power plant 1.
T sevelopment of test des.riptions, test structures, systems, and components that perform objectnes, ma specific acceptance criteria; safety-related functions.
2.
The preparation of test procedures; This guide describes a ereoperational test program 3.
Conduct of the tests and acquisition of system acceptable to the staff spe,.tfically fur emergency core coGmg systems (ECCS) :n pressu.ized water reactor and component performance data.and power plants. Although tais guide is appheable to all 4 Resolution of deficiencies and deviations from pressurized water reactors. certam aspects may rat be completely appheable to specific nuclear steam supply expected performance.
designs. The Advisory Con:mittee on Reactor Safeguards has been consulted concernmg this guide and has concurred m the regulatory position.
1.
System Testing The preoperational Msting of emergency core cool.
- Lines mdwa'e substantne chanees from rrevmus usue.
ing sy stems should include the tests desenbed below.
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Iligh-Preuure Safety injection :llPSI')
wdl be a thermal shock to the pipmg and reactor sessel a.
as a result of the hot injection test of the high-pressure The preoperational test program should proside saf ety ir!cetion system GIPSI). The statt has considered for testing of each train of the emergency core coohng the potentul for thermal shock hmay unJer these system under both cold and s:muhted hot operanrg conditions and has conduJed that the thermal c> chng condi6ons poor to fuelloadme.
can he tolerated it the test is termmated as soon as proper valve operation has been senfied and the pumps (1) Flow Test - Cold Conditions. The reacter bas e re iched rated flow.
vessel nuy be open and flooded and the reactor coolant system i RCSi pressure at essertu!!y atmosphene The ca pabih ty of IIPSI to Jehver. as (zero gauee pressure) condinons. No attempt is made to regired under accident conditions may also be senfied control the temperature of the w ater m the storage tank by analysis based on as-budt ilPSI pump and system or in the accumulators Thn test demonstrates sy stem head-capacity cunes without subjectmg the RCS to cold and component capabihty by inlectmg w ater
- from the water shak, how eser, the operabibty of the check water 3torage tank mto the reactor sessel throach s ah e s hould be demonstrated threugh testmg Any vanous combmations of mjection legs and pumps.
planned or unplanned actuation of the safety injection system (SIS) under hot operatmg conditions dunng the ihis test should be imtiated by the saf ety testing program should be documented in the preopera-inject:en signal with all affected auxthar) sy stems m tional testme summary dncussed in Section C3 Follow-taeir standard operating mode mg issuance of the operatmg heense, any plaane or unplanned actuation of the SIS that results in the it should be demonstrated that the flow inicetion of cold Guid irto the hot reacter coolant rates dehsered through each tnjection flow path using all systm may be classifiable as a reponable occurrence as pump comhmations are w:tlun the des.gn specifications.
defmed in Regulatory Guide 1.16. "Reportmg of Oper.
Venfication of proper system activation time should also atmg Information Appendix A Technical Specifia be obtained. The capabihty of the HPSI pumps to take tions.
suction from the low-pressurc safety miection pumps should be demonstrated in those plants that use this b
Low-Pressure Safety injection (LPSI) scheme to hud!e the small-break accident. The testing should venfy that pump motors wdl not inp out under (1) Flow Test - Cold Conditions. How tesung ranimum possible flow conditiors and that adequate of I PSI should be conducted m a manner similar to that margm exists between top points and maximum oper-for the llPSI(see regtdatcry oosition 1.all)above).
ating canditmns for all pump mmor inp-(2) Recirculation Test - Cold Conditions The objective of this test is to demonstrate the tapaNhty to The adequaev of the actne power supph reahgn valves and injection cumps to recirculate ceclant should be serified bs testme under maumum startup imm con a ent or m unp mto tb namr loadine conditiont co f ant sy stem. The testmg should induJe takmg Is - Hot Operating C.onditions.
suction f rom the sump to venfy sortex control and (26 H.ow ascept.hle pressure drops across screening and suction The o. tent of this tot is to demonstrate, by inlectino, a
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hnes and sabes. lo avoid Rb. contanunation, the sump mall amount of e ter in o the pnmary sy stem at water may be discharged to external drains or other operatmg pressure and tempera t u re conditions. that emergency core coohng water un be dehsered mto the SY * ""
reactor under conditions as cim > as possible to accident The testmg should senty that the available conditmns.
net Posttne suction head n greattr than that required at accident temperatures as discussed m Regulatory Guide The reactor sessel shou'.d be d ned and the 1.1 iSafety Guide 1.1 I O~'0). " Net Positive Suction RCS h"ed and mamtamed at the proper operattn?
llead for Lmerg ncy Core Coohng and Contamment pressure and temperature lesel The v ater lesel in the lleat Removal System Pumpc' Temporary arrangements pressunzer should be a.s low as practical. Sy stem may be made to provide adequate sump capacity for operanon shou!J be mittated by actuation of the safety pug >peration.
The temperature of the RCS will be I mjecnon signa!.
mt ch higher than that of the injection water. and there c Core Flooding (1) Flow Test - Cold Conditions The purpose on mp ps m
u on
'ltecaaw boated water is not made up unul the het function.d
.estm3 pregum is completed, the use of unborated water is and to senfy that the flow rate is as expected f or the aaertable for tha test test conditions lhe accumulators should be discharged l 1.79-2 126 028
one at a ame mto the reactor vessel af ter being til:cd to b.
Vah es their normallesel and pressunzed, usually with merogen.
Accumulator pressure is no'. cntical and the test may be II) P"'per operation of sy stem sabes meluding wnducted at any pressure up to normal precharge response times. This requires sisual sentication as w eli as pressure. The discharge flow rate may be calculated from proper control room indication.
measurements of the chance in aceumulator wate' level sersus ume. These tests apph to all passne mjection (2) Vahe eperanen unJa mmmum exputed sy st em s.
differential pressure conditions (consistent with sy stem
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test limitations)
(2) holation Vahe Test. At most nuclear pow er plant facihties the control circuit of the accumu.
(3) Operabthty at mmmum expected tem-lator isolation sahes recenes confirmatory open signal perature (consistent with sy stem test hmitat ons) wheneser the ufety irijec tion signal is actnated to ensure that mathertent vahe closures do not present c.
Pumps and Motors operation of the core floodmg sy stem if reqmred.
(1) Proper operatian of mjecnon pumps and At f acihties that hase this design feature,it motors m all design operatmg modes.
should be demonstrated that the valve wdl open under the maximum differential pressure condinons of tuo (2) A certable net routive se non head per-RCS pressure and maximum expected accumulator formance under maximum sy stem flow conditions.
precharge pressures This capabihty should be demon-strated with both normal and emercency power supphes.
(3) Adequacy of indnidual pump capacity and discharge head.
(3) Flow Test - Hot Operating Conditions.
The mient of this test is to senty that the check vahes (4) Pump response time (time to reach rated that see higher-tharrambient temperatures dunn; flow conditions).
power eperation will function at the hidier tempera-tures.
(5) Proper pump motor start sequence. oser-speed protection, and adequate marems between motor Ininally, the RCS and the accumulators running currents and protecthe breaker ratmgs.
should be at their normal operating temperature and O
accumulator pressure. Each accumulator injection tram pressure conditions, with the RCS Fressure higher than (6) Acceptable vibration levels.
should be tested indnidually or simultaneously by d.
Controls opemng the nolation sahe and then slowly decreasmg RCS pressure an ! temperature until the check valves (1) Proper operation of controls,includmg the operate as indicated by a decrease in the tiuid levcl of controls that effect transfer of pump suction.
each accumulatm. To minimve the thermal cytimg. the isolation salve should be closed as soon as check salve
(:) Proper operation of mterlocks and equip-operation is s critied.
ment protectne desices m pump and vahe controls if operabthty cf these valves at hgl1 e-Power Supplies temperature is demonstrated durine a different phase of the testmg program, this specific test may be ehminated.
(1) Propa operation of alternatne elec t ric power su pphes uwd for system vahes, pumps. end 2.
Component Testing motors The components of the systems msobed in the
. utomane and mar'ual
( ) r pn opaanon of syeem test desenbed in regulatory position I should power transfer switches.
be tested, either in conjunction with the system tests or in mdependent com piment tests. Performance data f.
System Piping nd Supports should be recorded and the following items serified:
Acceptabihty of system pipmg movemen ts a.
Instrumentation under system startup conditions and danng steady-state operation.
(1) Proper operation of mitiating instrumenta-tion in all combinations of logic and instrument channel g.
Auxiliary Feedwater System tup.
Confirmation that the a u ulia ry feed water (2) Proper functionmg of instrumentation and system actuates and supplies feedwater to th steam alarms used to monitor sy stem availabihty.
generator.
126 029 1.79 3
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- 3. Documentation Retention of the test procedures, data, and sum.
maries by the licensee should be consistent with para.
The preoperational testing program should be graph 9 of Appendtx C of Regulatory Guide 1.68, documented in a summary report and retamed as part of "Preoperational and Initial Startup Test Programs for the plant historical record. This summary report should Water-Cooled Power Reactors," and m accordance with include:
Cri:enon 1, "Quahty Standar ds and Records,' of Appendtx A and Cnteria XI, " Test Control," and XVII, A hstmg and description of the objectnes of "Quahty Assurance Records," of Appendix 11 to 10 CFR a.
each test; Part 50.
b.
Ilow each test was conducted; D. IMPLEMENTATION c.
The parameters morutored; The purpose of this section is to provide informa-tion to apphcants and hcensees regardmg the NRC staft's d.
Compansons and evaluations against design plans for utihzing this regulatory guide.
predictions or system performmee requirements for the high-pressure safety injection flow tests, the low-pressure This gtWde reflects current regulato.y practice.
safety injection flow and recirculation tests, and the core Therefore, except in those cases in which the applicant flooding tests; proposes an acceptable alternative method for comply-ing with specified portions of the Commission's regula-e.
Deficiencies noted; tions, the method described herein wdl be used in the evaluation of submittals for opentmg license or con-f.
System modifications and correcti e actions struction permit appheations for which the issue date of required; the Safety Esaluation Report (SER) is Apnl 1,1976, or a[Ier.
g.
Appropnate justification for acceptanee of systems or coraponents not in conformance with design Untd Arnl 1,1976, the staff wdl contmue to premetions or performance requirements;and evaluate applications on the basis of the regulatory position of the June 1974 version of Regulatery Guide h.
Conclusions.
1.79.
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