ML20096E635
| ML20096E635 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 05/13/1992 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C NRC |
| References | |
| NUDOCS 9205190282 | |
| Download: ML20096E635 (28) | |
Text
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IqV13'92 02:32Pf1 G E ttCLEr4R DLtG J P.340 14.2.2.3 General Electric Company INSERT A for equipment and systems within the GE scope of supply; INSERT 8
[ Note: The official designation of this group may differ for the plant owner / operator referencing the ABWR Standard Plant design and SCG is used throughout this discussion for illustrative p posos only) 14.2.3 Test Procedures INSERT C Specifically, GE will proAde the plant owner / operator referencing the ABWR Standard Plant design with scoping documents (i.e. prooperational and startup test specifications) containing testing objectives and acceptance criteria applicable to its scope of design responsibility. Such documents shall also include, as appropriate, delineation of specific plant operational conditions at which tests are to be conducted, testing methodologies to be utilized, specific data to be collected, and acceptable data reduction techniques, INSERT D for preoperational tests and 60 days prior to scheduled fuelloading for power ascension tests.
as well as any reconciliation methods needed to account for test conditions, methods or results where testing is performed at conditions other than representative design operating conditions.
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t%Y 13 '92 02tE2PfiGEtOCLEARDLfGJ P.4/20
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iM MA6100A,N Etandard Plant nry a 14.2.10.1 Pre ruel14ad Checks Once the plant has been declared ready to
-load fuel, there are a number of specific checks
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tha M be made prior to proceeding. Thes
' c ude a final review of the preoperational test results and.Je status of any design
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- changes, work packages, and/or retests that were initiated as a result of enceptions noted during this phase. Also, the technical specifications surveillance program requirements, as described ychad
,ln Chapter 16 shall be instituted at this time L
to assure the operability of systems required for fuel loading. Just prior to the initiation
>>Un @ - he proper vessel water lesel l.
and chemistr M be verified and the calibration and response of nuclear instruments
-- I
%, hee 4d be checked.
14.2.10.2 initial fuel Loading
_ Fuel loading regulres the movement of the full core complement of-assemblies from the fuel Amendmeet la -
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,,... (19Y 13 ' 92 02:32Pt1 G E fLCLEM DLM J P.5/28 2sasmc4s ABM 8'
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Standard Plant NN[
ding that of the autou.ite depressuri-to be performe and the i p cf a p pJic ajile egeanicrperi lo each(
2at;on system (ADS);
ith ne j pryopet4tiot) 341 at in apords cc
/ dEtalle'd system sp les ions d
ulp ent (c) proper operation of MSIVs and main e m/.
steamliue drain valves,includiog sert.
-( spefificationylor e<,;uipag}nt i thoie sy'tal)6d fication of closure time in ahe isola.
Jh'e iry tion mode, and test mode,if applicable;
> T 6 e/c's t s/d c m/nsir de t1pf equ4mentind sfstemy' perform within (he ihnits bese' specifications.
(d) verification of SRV and MSIV accumulator
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.## p The preoperational tests antic. pated for the capacity; ABWR Standard Plant are listed and described in(c) proper operation of SRV air piston the following paragraphs. Testing of systems actuators and discharge line vacuvin outside the scope of the ABWR Standard Plant, but breakers; that sqay have related design and therefore testing requirements, are discussed in Subsection (f) verification of the acceptable leak 14.2.13, along with other interface requirements tightnets and overall integrity of the related to the initial test prograrn, reactor coolant pressure boundary via the leakage rate and/or hydratatic 14.2.12.1.1 Nuclear ltollcr System testing as described in Section Preoperational Test 5.2.4.6.1 and 5.2.4.6,2 respectively; and (1) Purpose (g) proper system lustrumentation and )
370 To verify that all pumps, valves, actuators.
equipment operation while powered from instrumentation, trip logic, alarms, annun-kyl ciatcrs, and indications associated with the primary and alternate sources, including transfers, and in degraded i:. odes for
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"8 nuclear boiler system function as specified.
which the system and/or components are Jl to remain operational.
""j expec (2) Prerequisites I
Other checks obedd be performed, as appro-The construction tests have been success.
priate, to demonstrate that design requirements, 3 g.
fully completed and the SCG hu resiewed the such as those for sizing or installation, are a
'5 '
test procedure and has approved the initia.
tion of testiog, All required interfacing met via as built calculations, visual inspec-
.E..j tions, review of qualification documentation or systems shall be availabic, as needed, to i support the specified testing and the Miher methods. For inst
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c appropriate system configurations, or bench tests to be consistent with applicable I
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) ff n i requirements. Additionally, proper installation j j {' \\)(3) GeneralTe 4ethods and Acceptance Criteria and setting of supports and restraints for SRV l
be observed and recorded discharge piping will be verified as part of the sbl u&
Performance g5 during a series of individual component and testing described in 14.2.12.1.51, integrated system tests to demonstrate the o
P[S 14.2.12.1.2 seactor necirculation system 5.
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follo*las:
Preoperational Test
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]w (a) verification that all sensing devices gf respond to actual process variables and s ) Purpow s
provide alarms and trips at specified To verify the proper operation of the values-reactor recirculation system at conditions approaching rated volumetric flow, including (b) proper operation of system Instrumen-the reactor internal pumps (RIPS)'and tation and any associated logie, inclu.
motors, and the equipment associated with the motor cooling, se al purge, and inflatable shaft seal 'i b s y s t e m s,
14 2M Arneaemcas 18 FF"M 4 %- M l( M M-l?-M 74: M FM PcE
... N.Y 13 '92 02 33Pr1 G C f'ICLEAR BLM J P. U29 14.2.12.1 Preoperational Test Procedures INSERT F 4
Speci!!c testing to be performed and the applicable acceptance criteria for each preoperational test see will be docum2nted in detailed test crocedures to be m@
available to the NRQ,anorosimatejy.,30 davs erlor to their Intended use.
Precoerational testing will he in accordanco with the detailed system specifications and associated equipment specifications for equipment in those systems (croudod p I
cart of scooing documents to be sormlied by GE and others as describedlfle,nhsaetlen 14.23). The tests demonstrate that the installed equipment and systems perform within the limits of these specifications, To hee,hin
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neenrdance with establisbod methods and nootopdate nerantance criteria. the plant f
and system oreocerational test tDeciications will also be made availabl.a to the NBC.
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allow for verification that that the detailed lost proceduros woro developed l
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tlW 13 '92 02:33Pii G E f ELEM l! LEG J P. WEB 1BWR
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s-m3 Standard _ Plant teristics, from the testing described above, meet (d) proper operation of control systems in the applicable design specifications.
s11 design operating modes and all le.
sels of controls; 14.2.12.1.3 Recirculation Flow Control Sptem (e) proper operation of the adjustable speed Preoperatiot al Test drises; (1) Purpose (f) ability of the control system to comm.
2 To verify that the operation of tl.e recir-unicate properly with equipment and culation flow control system. including that controllers in other systems; of the adjustable speed drises RIP trip and runback logic, and the core flow,acasurement (g) proper conttol of pump motor start subsystem, is as specified, sequence; s
s (2) Prerequisites (b) proper operstion of interlocks and equipment protective devices; The construction tests have been success.
' lly complettd and the SCO has reviewed the (i) proper operation of peratissive, prohi-test procedure n.d has approved the initia-bit and trypass functions; and tion of testin; All required interf acing systetas shall be available, es aceded, to (j) proper system operation while powered support the specified testing and the from primary and alternate sources, corresponding system configuraticus.
locluding transfers, and in degraded modes for which the system is especte.i (3) f t4t Methods and Ac e
teria to remain operational.
(ess.f.Wd {t.tw Q
- ant H 4 Sptem operation is considered acceptable Somc portionGNii{A rect arion ow con-o trol system testing be performed in when the observed / measured performance charac.
l conjuriction with that of the recirculation teristics, from the testing described above.
sys h described in Subsection meet the applicable design specifications.
4 J l4.2.12.1.g2. glose coordination of the L
g
%j testing specilled for the two systems is 14.2.12.1.4 Feedwater Cnntrol System required in order to demonstrate the proper PreoperationalTest integrated system res onse and operation.
wil (1) Purpose Performance e observed and recorded daring a series of in/ividual component and To verify proper operation of the feedwater integratc6 system tests to demonstrate the control system, including individual compo-cents such as controllers, indicators, and following:
controller software. settings such as gains (a) proper operation ofinstrumentation and and function generator curves, equipment in all combinations of logic and instrument channel trip including (2) Prerequisites recirculation pump trip (RPT) and runback circuitry, (RPT testing will The construction tests have been success-specifically include its related ATWS fully completed and the SCG has redewed the test procedures and has approved the initi-l function);
ation of testing. Preoperational testt must (b) proper functioning of instrumentation be completed on lower lesel controllers that do not strictly belong to the feedwater con-and alarms used to monitor system operation and availability; trol sptem but that may affect syst;m re-sponse. All feedwater control sprem com-(.) proper 'unctioning of the core flow measurement subsystem; L@
j An.tru! ment 18 F 7 MJ.; " ' - c m e ; s n-
1 fW 13 '92 02:3&M G C itCLEM BLIG J P. 8 '20 j
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-(e) proper operation of the tank beaters and be installed and ready to be stroked proper alsing of the neutron absorbe:
and scrammed. Reactor building cooling l
solution; water, instrument air, and other requ: red interfacing systems shall be available, as (T) proper systeta now paths and now rates needed, to supposi the specified testing and including pump capacity and discharge the corresponding sptem coofigurations.
head (with demineralized water substi.
suced for (.be neutron absorber mix-Additionally, the rod control and t ur e);
information sptem shall be functional when needed, with the applicable portio:s of its (g) proper pump motor start sequence and specified preoperational testing comphte.
margin to actuarloa of protective de.
vtces; (3) Genera] Test Met Acceptance Criteria shel (b) prvper operation of inrotocks and equi-Performance Ep o served and recorded mec' pro:ecuve dedces in pump and during a series of individual compocent and vaWe cuerch; integrated system tests to demonstiate the following:
(i) Proper operation of permissive, pro.
hibit, and bypass functions; (a) proper functioning of instrumentation and alarms used to monitor system opera-(j) proper system operation while powered tion and status; from primary and alternate sources, in-cluding transfers, and in degraded modes (b) proper communication with, and response for which the system is expected to re.
to demands from, the rod control and main operatiocal; red information system and the reactc< pro-tection system, including that associa-(k) acceptability of pump / motor vibration ted with alterna utRiisilgttion (ATWS),
levels and sptem piping movements dur alternate rod-(post scrprn), and select ing both transient and steady state control tod un intuactlens; operation.
(c) proper fun 5 ng of system vahes, in.
System op: ration is comidered acceptable when cluding purge water pressure control the observed / measured cerformance characteris-valves, under expected operating condi-tics, from the testing described above, meet the tions; applicable design specifications.
(d) proper operation of CRD bydraulic sub-102.12.i.6 Control Rod Drhe System system pumps and motors in all design Freoperational Test operating modes; (1) Purpose (c) acceptable pump NPSH under the most lim-iting design Co.v conditions; To serify that the control rod (CRD) system, includiog the CRD hydraulic and fine (f) proper pump motor start sequence and mar-motion control subsystems, functions as de-gin to actuation of protective devi:es; signed.
(g) propee system Cow paths and now rates (2) Prerequisites including sufficient pump capacity and discharg: bead; The construe: ion tests have been success-fully completed and the SCO has reviewed the (b) proper operation of interlocks and test procedure and has approved the equipment protective devices in pump, initiation of ta. sting. The control blades motor, and valve controls; AmCndment 18 14[Il
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t,W 13 92 02:34Pt1 G E tocttm ettc y p,9,29 ABWR Standard Plant pry a g $:
(3) GeneralTest Methods cceptance criteria tesels and system piping movereents dur.
shti ing both transient and steady state opy
$25 Performance skrid o served and recorded cration; and 0E o l
during a series of fadividual component and
,32 integrated system tests that includes all (m) proper operation of pump discharge lin ' $3 D
3 )) modes of RHR system op gtiggingd keep fill system (s) and its ability I j$jj l
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demonstrate the follo ' _
prevent damaging water hammer durin
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system trsAtients, gg g,_
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p-3 (a) proper operation of instr %cEiabo an 1
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- jj equipment in all combinations of logic System ope ation is considered acceptabl[ Uye y,g and instrument channel trip; when the observed / measured performance chara E
y, I
y s4E teristics, from the testing described above st-5 j g 3, (b) proper functioning of system instrumen-meet the applicable design spenfications.
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=4a tation and alarms used to monitor system 3
operation and availability %
14112,1.9 Reactor Cort Isolation Cooling I
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-d Sptem Preoperational Test hf 3E b
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,, { { ' (c) p oper operation of system valves, in.
g['d3 j}ya ciudNg timi.j, unde.r expected operating (1) Purpose g$?9
.ej conditions;(-,._,,
Verify that the operation of the reacto g 3
.6 f, 5 g ju (d) proper operation of pumps and motors in core isolation cooling (RCIC) system, in-y y3g
? N g g-i 3 o-3 all design operating modes; ciuding the turbine, pump, valves, instru 8-gg mentation, and control,is as specified.
gT2 l (c) acceptable pump NPSH under the most I
Pjj limiting design flow conditions; (2) Prerequisites 32 N
j (j (f) proper system flow paths and flow rates The construction tests have been success-3
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including pump capacity and discharge Elly completed and the SCG has resiewed the 2'j
'v head and time to rated flow, test procedure and has approved the initia.
2j tion of testing. A temporary steam supply i
t (g) proper operation of containment spray shall be available for drivin5 the RCIC tur j Eg; l
modes including verfication that spray bine. The turbine instruction manual shall ) e I nozzles, he is and piping argr e of be reviewej in detailin order that precau.
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tions relative to turbine operation are foi-g(
debris; Q]
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lowed. Ail required interfacing systems ;
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) proper pump motor start sequence and mar-shall be evatlabic, as needed, to support [
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sin to actuation of protecthc devices; the specified testing and the cortesponding 5g system configurations, g
3gigi (i) proper operation of laterlocks and 1,
l equipment protective devices in purnp and (3) GeneralTest Methods and Acceptance Criteria
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The RCIC turbine sh Id first be tested 3j i
(j) proper operation of permissive, pro-while disconnected f m and then while ji 3 g; l hibits and bypass functions; coupled to the pump, ace preoperational 3a testing is rkrmed utilizing a temporary g8 gg t y{.y j,y (k) proper system operation while powered steam su the attainable RCIC pump flow s cc
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'Performan;e be c.ticeved and recorded
}gg main operational; during a series of individual component and integrateG system tests to demonstrate the e,.2 U 6g@
(1) acceptability of pump /rnotor vibration following
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Should this provent any specified testing from being completed suCCeS$ fully, $bch case $ will be documented and Scheduled for v
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mpletion during t!'e power ascension test phase.
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' ) proper operation of instrumentation and (1) proper operation of the barometric con-(a equipment in all combinations of logic denser condensate pump and vacuum pump; and instrument charinet uip; (m)the ability of the system to swap pump (b) proper functioning of instrumentation and stetion source from the condensate stor-alarms used to monitor system operation age pool to the suppression pool without and avaihbility; interrupting system operation; and (c) proper operation of system valves,includ-(n) proper operation of the pump discharge ing timing, under expected operating line keep fill system and its ability to conditions; prevent damaging water hammer during sptem transleets, (d) proper operation of turbiae and pump in all design operating modes; System operation is considered acceptable when the obser.ed/ measured performance charac-(c) acceptable pump NPSH under the most teristics, from the testing descelbed above, limiting design flow conditions; intet the applicable design specifications (while accounting for the limitations imposed by the (f) proper system flow paths and flow rates temporary steam stpply),
including pump capacity, discharge head and time to rated flow; 14.2.12.1.10 H6sh Pressurt Curt Flooder Sptem Pitoperational Test (g) proper manual and automatic system ope-ration and margin to actuation of pro-(1) Purpose tectly dedces:
To verify the operation of the high pressuye (h) proper operation of interlocks and core flooder (HPCF) syttem, including relat-equipment protective devices in turbine, ed auxiliary equipment, pumps, valve <, ire pump, and valve controls; strumentation and control,is as spectfied.
(i) proper operation of p:rmissive, probi.
(2) Prerequisites bit, and bypass functions; The construction tests have been success-(j) prope system operation while powered lully completed and the SCG has r,cdewed the from priraary and alternate sources,in-test procedure and has approved the initia-ciuding transfers, and in degraded modes tion of testing. The su pression pool and for which the system is expected to r -
noensate storage thee4d be available l
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main operational, included simwed ea as HPCF pump suction and tbc reactor
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demonstration of RCIC system ability to 4 vesse 4 $44 be suffielent ntact to re-start without the aid of AC power, ex j ceive HPCF injection flow. T required
_ interfacingys,tempim4d be avai le, as
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cept ior RCIC DC/AC inverters; an eval M t
untion of RCIC operat on beycad its needed, to support the specified testing d
i design basis during an extended loss of the approprhre system configurations.
M AC power to it angitosuppctrtassems and verification'6f hCIC DC compoM5Q eneralTest Methods and Accepunce Criteria batteries we disconceesg (ses.emch IA.T.h)N operabil}tf when the non RCIC station Perfor nee ebook! be observed and recorded l
d duringt series of individual component and (k) acceptab 1(ty of pump / turbine vibration intep ed system tests to demonstrate the levels and systqQping movements lur pieU6 wing:
i in g bot h t r a n sie ntTud m edyTriTe operation; (a) proper operation of instrumentation and equipment in all combinations of logic Id W Arntedment 2 l
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integrated system tests to demonstrate gaskets or bellows; the following:
(m) proper functioning of Ibc system in (a) proper operation of instrumentation and conjunction with the Ri{rt sptem in the equipment in all combinations of logic supplemental fuel pool cooling mode; and and instrument ~ channel trip, including isolation and bypass of the nontafety (n) proper operation of filter /demineralizer related fuel pool cleanup filter / demi.
units and their associated support neralizers; f a cilitie s.
(b) proper functioning of instrumentation Integrated systern testing with flow to and and alarcas used to monitor system opera.
froca tbc fuel pool cleanup subsystem will be tion and availability, including those performed in conjunction with the appropriate associated with pool water level; potit as of the suppression pool cleanup sptem p;eo; described in Subsection 14.2.12.1.20.
(c) proper operation of system valves, in.
cluding tirning, under expected operat.
System operation is considered acceptable ing conditions; when the observed / measured perfonnance charac-teristics, from the testing described above, (d) proper operation of purops and motors in meet tbc applicable design specificat!ons.
all design operating modes; 14.2.12.1.22 Plant Process Sampling System
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(e) uceptable pump NFSH uoder the caost PreoperationalTest limiting design flow conditions; (inc!uding that required to show (1) Purpose compliance with Reg Gwde L56)
I (O proper system flow paths and flow ratcs
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including pump capacity and discharge To verify the proper operation and the head; accuracy of equipment and techniques to be used for on line and periodic sampling and (g) proper pump motor start sequence and analysis of overall reactor water chemistryc margin to actuation of protective as well as that of indvidual plant process devices; streams, including the post accident sampling system (PASS).
(h) proper operation of interlocks and equipment protective devices in pump, (2) Prerequisites motor, arid valve controls:
Construction tests have been successfully (i) proper operation of permissive, prohi-completed and tt.e SCO has reviewed the test bit, and bypass functiens; procedure and has approved the initiation of testing. Adequate laboratory facilities and (j) proper system operation while powered appropriate analytical procedures shall be from primary and alternate sources, in place.
including transfers, and in degraded modes for whleh the systera is expected (3) GeneralTest Meth -
d cceptance Ciiteria to remain operational; A ti Performance sheirtd. o serve'd and recorded
(
(k) acceptability of putsp/ motor vibration during a series of tists to demonstrate the I levels and system piping movements dur-following:
9-ing both transient and steady state operation; (a) proper operation o n lin samplin and j
1 monitoring equipi ent c sideringMali-
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(1) proper functioning of pool antisiphon brttion, indicatio and rm/ functions, devices and acceptable nonicakage from including reactor er conductisity pool drains, sectionaliting devices, and inst r um e nt atiorQ-
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and other eqwpment or instrumentat=on required to show compliance wdh Reg Gwde 1,56 j
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4411:adWah:.h ad : Jean exhausts, and plant and process effluents.
The offgn system and the main steam lines (b) the capability of obtaining grab samples are also monitored.
of designated process streams at the 5%
desired locations:
Performance c'3 served and recorded
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during a series of disidual component and (c) proper functioning of personnel protec-integrated subsystem tests to demonstrate tise deuces at local sampling stations; the followir:g.
y and (a) proper calibration of detector assem.
(d) the adequacy and accuracy of sample blies and associated equipment using a analysis methods.
standard radiation source or portable calibration unit; The above tests should be performed using actual process strearrs where practicable. System (b) proper functioning of ludicators, re.
operation is considered acceptable when the ob-corders, annunciators, and alartas; served /rneasured performance characteristics rncet the applicable design specifications.
(c) proper system trips in response to high radiation and downseale/ inoperative 14.2.12.1J3 Process Radiation Monitoring conditions; System Preoperational Test (d) proper operation of permissive, probi.
(1) Purpose bit, interloct, and bypass functions; and To verify the ability of the process radia.
tion monitoring system (PRMS) to indicate and (e) proper operation of primary and backup alarm notmal and abnormal radiation levels, sampling functions.
and to !nitiate, if appropriate, isolation and/or cleanup sptems upon detection of high System operation is considered acceptable radiatio levels in any of the process when the observed / measured performance charae.
streams that are monitored.
teristics, from the testing described above, meet the applicable design specincation.t (2) Prerequisites 14.2.12.lJ4 Area Radiation Monitoring System The construction tests have been successfully Prtoperational Test completed and the SCG has resiewed the test procedure and has approved the initiation of (1) Purpose testing. The various process radiation inoni.
toring subsystems, including preamplifiers, To verify the ability of the area radiation power supplies, indicator and trip units, and monitoring (ARM) system to indicate and sensors and converters, have been calibrated alarm normal and abnormal general area according to vendor instructions. The re-radiation tevels throughour the plant.
quired interfacing systems shall be a" ail-able, as needed, to support the specified (2) Prerequhites testing.
The construction tests have been successful-(3) General Test Methoda and Acceptance Criteria ly completed and the SCG has reviewed the test procedure and has approved the initia-The PRMS consists of a number of subsntems tion of testing. Indicator and trip units, that monitor various liquid and gaseous pro-power supplies, and sensor / converters hue cess streams, building and area ventilation been calibrated according to vendor instruc-tions.
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cIompleted and the SCG has reviewed the test (d) proper operation of fans and motors in procedure (s) and has approsed the initiation all design operating modrs; of testing. Additionally, the normal and backup electrical power sources, the applic.
(e) proper system flow paths and flow rates able beating, cooling, and chilled water sp.
Including individual consponent and total tems, and any other required systern inter.
system capacities and overall system faces shall be available, as needed, to flow balancing; support the speci med testing.
(1) proper operation uf interlocks and l (3) GeneralTest Methods and Acceptance Critesia equipmcat proteetive devicesi There are numerous HVAC systems in ibn plant, (g) proper operation of permissive, pro-located throughout the various buildingt, bibit, and bypass functions; Each system typically consists of some combi-nation of supply and cabaust air handling (b) proper system operation while powered units and local cooling units, and the asso-frorn primary and alternate sources, ciated f ans, dampers, valves, filters, heat.
including transfers, and in degraded ing and cooling colh, and control and instru.
modes for which the system is expected mentation. Tbc HVAC systerns to be tested to remain operational; e
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+herhi include the following: those support-ing the reactor building rooms containing the (i) the ability to maintain the speelfled emergency diesel generators and the ECCS positive or negative pressure (s) in the pumps and heat exchangers; those serving the designated rooms and areas and to direct electrical equipment rooms of the control local and total air flow, including any building; those supporting the divisional potential leakage, relative to the cooling water rooms; those supporting the anticipated contamination levels; turbine / generator auxiliaries, those serving the secondary containment and the general (j) the ability of exhaust, supply, and areas of the control building, reactor recirculation filter units to rasintain building and turbine building; and.:le the spr,cified dust and contamination dedicated systems of the drywell and the main free environment (s);
control room (including the control room habitability function),
(k) the ability of the control room s
habljshHitTIunction io diItict de
/pr(sence of smoke and/or toxic gas anh Since the various HVAC sptems are similar in to ternove or prevent in leakage of sucif design of equipment and function, they are h AthMt "A NMt h%
subject to the same basic testing require.
(1) proper operation of HEPA filters and M
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ments.
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Performance shedd bc observed and recorded during a series of Individual cornponen in. place Asting equirements of g
Integrated system tests to demons te Regul y Gulder,140 regarding visual Wt-pections ifd airflow distribution, following:
- "b DOP yon tion and bypass leakege (a) proper operation of instrum ntation aidlogir~p4esng; equiprnent in all combinati and instrument channel trip; (m)the ability of the heating and cooling l coils to mnintain the specified thermal (b) proper functioning of instrumentation environment (s) while considering the and alarens used to monitor system heat loads present during the peop test operation and availability; phase; and (c) proper operation of system valves and (n) the ability of primary and secondary l dampers, including isolation functions, containment HVAC systems to provide under expected operating conditions; "W
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f*AY 13 '92 02:3Ft1 G E TOCLEM ILM J P.1 M 8 ABWR axu m Sandard Plant RILD tightness of charcoal adsorber section 14.2.12.1.a0.1 Containment Integrated 1akage l
per Regulatory Guide 1.5; Rate Test (f) stoper system and component flow paths Description of and criteria i e containment and flow rates including oserall system integrated leakage rate tests are so in Sub.
flow balance; section 6.2.6.1.
(g) ability 1 maintain the specified nega-14.2.12.1.40.2 Contalamtnt Strmtural tive pres. te in the secondary Integrity Test containmentt Description of and criteria for the required (h) proper operation of interlocks and containment structural integrity test is given equipment protective devices; in Subsection ;,.6.1.7.1.
(i) proper operation of permissivu, 14.2.12.1.41 Pressure Suppression Contalnment prohibit, and bypass function; llypass Leakage Tests d) proper operation of heaters, demister.
Test procedures ire identical to those used and moisture seperator equipment; and for other penetrations under isolation condi, tions as discussed in Subsection 6.2.6.2.
(k) proper systern operation while powered from primary and alternate sources, 14.2.12.1.42 Contalument isolation Valve including transfers, and in degraded Functional and Closure Timing Tests
[
modes for which the system is expected to temain operational, re perat')n nayan clo)4rp tisping -
ests f c at oc;re nt o[ati a sfis t s ly dis.
Refer also to Subseetinn 6.5.1.4.1.
cuss d.iysj.lsio 6.2.,t.--
(.s Systern operation is considered acceptable when 14.2.111.43 Wetwell to-Drpell Vacuum Breaker the observed / measured performance characteris.
Systenr PrmperationalTest F@ @,,_ h ties, from the testing described above, meet the applicabk dcs!;n specifications.
(1) Purpose
(.M e d )p 1/.2.12.lJ7 Contalantent isolation Valse To verify proper fur.ctioning of the wetwell.
f.eakage Rate Tests to drywell vacuum breakers.
Deteriptic n of and criteria for preopera.
(2) Prerequisites tioealleakage rate tests of containment isola.
tion valves are given in Subsection 6.2.6.3.
The construction tests have been success.
fully completed and the SCG has reviewed the 11.2.12.1.38 Contalament Fenetration LeaLare test procedure and has approved the initta.
Rate Tests tion of testing.
De:cription of and criteria for preoperational (3) GeneralTest Methods Acceptance Criteria leakage rate tests of containment penetrations skt t!-
are given in Subsection 6.2.6.2.
Performance M. Fserved and recorded during a series of individual component and 14.2.12.1.39 Contain.nent Airlock Leakage Rate integrated system tests to demonstrate the Tests following:
Description of and criteria for preoperational (a) proper operation of vacuum breaker leakage rate tests of containment airlocks are salves and system logic incluJing given in Subsection 6.2.6.2.
verification of opening and closing setpoints and timing; 14 F D ArntMmer t 18 I
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14.2.12.1.'42 Containment isolation Valve Function and Closure Timing Tests
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INSERT G The containment liolation system it diteutted }D Subsection S 2.4 with cht ggleritths of and roaultements for individual vafvet listed in Table 8.2-7.
Preoperational functional snd closure timing tests <+
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44,4 of valves cerforming_ containment is_olal!0D functions wl!! ce rbre as cart of the testino of the sygigma to which such valves bg!gng fgge Table 6.2 7 for system affiliation of Individual valves). OveI2'Lf0Dtainment isolation Inillation loch is a function Of the ten,: dalCCit0D l
gndjattalion_svetem the testing of which is dC$CDD0d_iu Subs.ggtlen : 14.2 12 1.13.
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closure devices. including verification y~
-N of adequate valse leak tightness; and (a) properfacking of drywell pressure b)N fa1Iinstrument channels during con sin-(d) proper functioning of vacuum breaker ment integrated leak rate testin e
test features.
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(b) proper respon:e of agl su.t.rssknr pool Sptem operation is considered acceptabir shen level 4estrumem1Fion during actual the observed / measured performance characteostics changes in pool level; meet the applicable des:gn specific.ations.
(c) proper tracking by all suppression pool 14.2.12.1.44 Primary Containment Monitoring teinperature instrument channels of an Instrumentation Preoperatienal Test actual change in pcol temperature; 3
(1) Purpose (d) proper functioning of associated indica-tors, recorders, annunciators. and i
To serify 'he proper operation of instru-alarms including those monitoring mentation used for long term mocitoring of instrument son status; and the drywell and wetwell atmcspheres and suppression pool temperature and level during (e) proper system trips in response to tbc both normal operations and accident appropriate high and/or low seapoints condit'ons in the primary :ontainment.
and inoperative conditicas.
(2) Prerequisites System operation is considered acceptsble when the observed /mec.uted performance character-The construction tests have been c.uccess-istics, from the tcsting described at,ose, :nect fuliy completed and the SCO has re iewed the the applicable design specifications, test procedure and has approved the initia-tion of testing. The suppression pool shall 14.2.121A! Electrical Systems Preoperational be filled and expected to undergo measurable Test level and temperature changes at some point during the scheduled testing. The required The total plant electrical distribution net-interfacing systems and components are work is described in Chapter 8 and is comprised available, as needed, to support the speci-of the following systems:
fied testing, Additionally, any parallel testing to be performed in caujunction with (1) unit auxiMary AC power system; the testing of this subsection is appropri-(2) unit Class LE AC power sy; tem; ately scheduled.
(3) safety sptem logic and control system power system; l (3) GeneralTest Methods and Acceptance Criteria (4) inst.rument power system; (5) uninterruptible power :.ystem; A description of the instrumentation eequit.
(6) unit auxillary DC power s>Memt and ed for contalement monitcring is presented in (7) unit class 1E DC powtr system.
Subsection ti 2.1.7. Preoperational testing of these instruments will be performed in Because of the similarities in their design conjunction with the testing of the applic-and function, the testing requirements for these 4
able systems. Only that instrumentation systems, and their respective components, can be requiring special considerations is discus-divided into the four general categories as sed below.
described below. The specific testing required for each system is described in the applicable
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Performan:e Aedd be observed and re:Orded design and testing specifications.
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I'he specifics' of the startup tests relating to plant operatirig records, regular routine test methodology, plant prerequisites, laitial coolant analysis, radiochemical measurements conditions, acceptance criteria, analysis tech-of specific nuclides, and special chemical niques, and the likes,.will come from the appro-
- tests,
-priate design and engineering organizations in the form of plant, system and component perfor.
Prior to fuel loading a complete set of mance and testing specifications.
chemical and radiochemical samples will be taken to ensure that all samp!c stations are
_14.2.12.2.1 _ Chemical and Radiochemical functioning properly, if not demonstrated Measurements during the preoperational testiog, and to determine initial concentrations. Subse.
(1) Purpose quent to fuel loading, during reactor heat-up, and at each major power lesel change,.
- To secure information on the che vistry and samples will be taken and measurements will radiochemistry of the reactor coolant while be made t) determine the chemical and radio-
. verifying that the sampling equipment, procc-chemical quality of reactor water'and in.
dures and analytic feenniques are adequate to coming feedwater, amount of radiolytic gas supply the data re uireLeah nstrate that in the steam, gaseous activities leaving the the' ry of all parts of t tire air ejectors, decay times in the offgas actor system meet specifications and pro-lines, and performance of filters and demin-l cess reqdrements blA %c. ret,armuds ralizers.
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I (2)' Prerequisites Calibrations will be made of monitors in effluent release paths, waste handling The preoperational tests have been completed systems, and process lines. ' Proper
-mo n t o r s will be and plant management has reviewed the test funettoning offs i
procedures and has approved the initiation of verified, as apropriate. including via testing. For each scheduled testing itera-comparison w'th independe9t laboratory or.
Irf articu ar, the proper c her analy s.
tion the plant shall be in the appropriate o
operational configuration with all prete.
t.,.eration f failed fuel d ection functions quisite testing complete, Instrumentation of the ma n stearnli and offgas pre-has ' ten checked or calibrated as appro-treatmer.t p ce 1.setflation monitors will be
( priate.
verified. In this regard, sufficient data will,bc taken to assure proper setting of, (3) Description or to make needed adjustments to, the alarm
-and trip settings of the applicable
~
Specific'ocjectives of the test progra'm in.
instrumentation.
clude evaluation of fuel performance, eval-untions of demineralizer operations by direct (4) Criteria
-and indirect methods, measurements of filter performance, confirmation of condenser inte -
Chemleal factors defined in the Technical grity, demonstration of proper steam separa.
Specifications must be maintained within the tor dryer operation, measurement and calibra-limits specified.
tion of the offgas system, and evaluation and The activity of gaseous and liquM effluents calibration of certain process instru a.
tion (including that used to monito eacto must conform to license limitations, water conductivitQ. An additional objective of this test is he demonstration, and Water quality should be known at all times
. adjustment if' ecessary, of the proper and shall remain within the guidelines of functioning of ti e hydrogen water chemistry the water quality specifications and the system, the oxyg en injection system, the zine requirements of the Fuel Warranty document.
inje: tion passivation system and the iron ion injection system Data for these purposes is jg secured from a variety of sources such as Amendment 18 Ai t'epked h kej C l' b
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( 3 ) Description Concrete temperature data will be collected, around selected high temperature penatrations, at various power levels and system configurations in order to verify acceptable performance under expected plant operational conditions.
Penetrations and measure nt locations selected for monitoring, as well as the test conditions at h'
data is oye colle':ted, shall be sufficiently comprehensiv o as to include the qxpected limiting thermal loading conditions on critical e crete walg and struct tes within the plant.
(4) Criteria The temperature (s) of the concrete at the monitored locations should be consistent with design predictions and shall not exceed design basis requirements or assumptions critical to associated design basis analyses.
14.2.12.2.38 Radioactive Waste Systems Performance
( 1 ) Purpose To demonstrate acceptable performance of gaseous and liquid radioactive waste processing, storage and release systems under normal plant operational conditions.
( 2 ) Prerequisites The preoperational tests are complete and plant management has reviewed the test procedure and has approved the initiation of testing. The plant shall be in the appropriate operational configuration for the scheduled testing. The necessary instrumentation shall be checkec or calibrated. Appropriate precautions shall be taken relative to activities conducted in the vicinity of radioactive material or potential radiation areas.
/ 3) Description Radioactive waste systems operation will be monitored, and appropriate data collected, during the power ascension test chase to demonstrate system operation is an accordance with design reytrements. Operation and testing of liquid and gaseous radioactive waste systems is discussed in detailin Secticns 11.2 and 11.3, respectively. Testing specific to the main condenser offgas i
system is also discussed separately in subsection 14.2.12.2.35.
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'14.2.13 Interfaces (continuation)
The applicant referencing the ABWR Standard Plant shall also provide a list of those tests to be performed as part of the power ascension test phase that are proposed to be vemntyrom operating license conditions requiring NRC prior approval for maior test y
changes /Su31 tesis me hvav when are nol essemiaiio iis Ucmen30siton or m
/
/confptriiance withYte n requireme$t for structuh*, pstems, ponents, 'id desigg
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Thosbthat'will be u(seMor safe shut own,Md[cooldo of thef$$cto vnder norntal featurb6 which m,0c a of thpfollow g critoriat i
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Reg Guide 1.68 specif>es criteria (see Regulatory Position C.1) for determining what structures, systems, components and design features are requjred to be tested dunng the power ascension test phase in accordance with the requirements tnerein. Testing of such structures, systems.
A components and design features is then subject to license condit: ens requiring NRC prior approval l for major test changes. For compteteness, the testing descrked in 14.2.12.2 includes testing of a hmited number of ABWR structures, systems, components and design features that do not moot the referenced Reg Guice 'o68 critena, and are thus exempt from swh licenso conditions
_- - -_-__-_- m d.
Those,anakare classified s' ngineereo satei tuin vi wm ue used to support or en (fre the - ration o)- gin red safety s within cesi;glirrQts:
I e.
Th a that are ae med to functio rf hich cre ~ is tak in the a efit analyllis,. for e'facilityN as described the FSAR: or
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Those th will be used to process, store, control, of limit the release of radioactive materials.
Of the tests described in Secten 14.2.12.2 for the ABWR Standaro Plant the following tests, or designated portions thereof, mcct :he sbcvc cd::P 4
- 1) 14.2.12.2.13 Recirculaticn Flow Control enfmt for those features intended to limit maximum core flow;
- 2) 14.2.12.2.21 Reactor Water Cleanup System Performanco;
- 3) 14.2.12.2.23 Plant Cooling / Service Water System Performance - those portions pertaining to the turbine building cooling and service water systems;
- 4) 14.2.12.2.24 HVAC System Performance those portions pertaining to the Normal HVAC system and its associated nonessential chilled water systom;
- 5) 14.2.12.2.29 Foedwater Pump Trip; and
- 6) 14.2.12.2.39 Steam and Power Conversion Systems Performance.
The cot. applicant shall provide the final list of tests proposed to be exempt from such license conditions, including adoption or augmentation of the above list, as appropriate.
-p-
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are thus candid 6tes for proposed exemptions from cperating heenso conditions requiring NRC prior approval for major test changes:
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Pf. 2 - d. I et m ::c-gn: tc e-: - :
e pp r:
Table 14.21 POWERASCENSIONTESTMAmiX Pago1
.5
~
W w
TF5IING PLEIYAU -
- n N
110 l LP l MP IIP NOIES POWER ASCENSION TFSF OV O
\\
\\
f.?
Chennical and Radiochemical Meanusenwnts
,I n
Santpfmg System Funcuonlag V
V V
V
}'
$ 8 g g,gi Q
Process Rad Monicoting Functioning V
V V
V V
- Es b?
3 3,.
M
--)
Steady State Performance Measurements V
V V.
V V
1subdes weiric 6 a.4 won <pusu, j
%S*b*
5
+
- 5ga g ri "d
V At low p,wr,14gh finw.orner i,1 power s = m.g.
Steann Separausr/ Dryer Performance Eo -
3' o Q
3 y g g a Q-g Radiation Measurements a:e oe
-gt EE" F"
5 g
Steady State Measurements v
V V
.V V
o 9 a 6 5' sa 3
gg g a I
y V
V i
Shielding Adequacy Assessenent
&ggEh
-x oE-Fuct loadia.g
( o * *S-5' F5e Core imiting V
l
( 4ee e m E 'o Y%5 l
Parual Core S/D Margin V
--a
- n. 3 )
$ g 5-K w f Fult Core Verification V
e o c) E z 5 8 5 * "k.
Full Core S..utcown Marpn Demonstration V
l ORg 3 5 y "=. a
- .s r
R.e Control Systern Performance m
7 o
I gE g
b o
I CRD Fi.nctional Testing V
V i
o e o a
f5E e l i
no-o J
Fric6on Testing V
V "3~nE l
Rod Paer krain Testisig V
V I'
o o
pg..g
- g is v
w.a.
Fun core s.rma 43e 2
eind e4
- i<a so.L I:r pr.or 3.L..wd sell-p *3 8
ce As k:>
g-
}
.imep/d RIP et ps g
C-SCRRE Furntiornng vy u
er urn
,n
~
r@disu.t[&.(>= gps i nt u.p
{
e' I
er er er Alternate Rod Hun-in Furwooning 3
i m
/
N
. =
\\
o a a N
N (D
OV = OporiVessesk i10 = Nucloor llisaiup LP tcw Poer MP = W3 Power iip - t i gh pm j \\~
a_
~
Tat >le 14.2-1 POWER ASCE_NSIONTESTMATRIX PMe2
' L' Y- -
-)
.. g
~s
.a.> -
r
'IFSMNGPIATEAU r
POWER ASCENSION TEST OV '11U LP MP 11P N(y1'ES u.
Neutron Monitoring Speemn Performanec I
. SRNM Calibration /_h.se e/
er o..
7 F1 r
V-V V-e 3
ifRM Calasauon/ Response e
r V
of e/-
e h
AI'dM Calibradon/Re-se '
r-r er O=3r m orede I m < om:4rse ecm -t~.aurea = 1118 -
qb-TIP System Alignment / Response e
=o r.,
[
Proccas Cmuner System ()peration t-.g' r
/
V.
e/
e NSS/ BOP Monitoring Programe 4
/
/
V e/
Autommuon Pri. grams
/'
w' or RWM/RC&lS Functioning e/
e V.
er r
Cose Peskununce Nintear Boiler Prwess Moniwwwig er e/ ' e/
As Mi* k IIP da.ng mena weic
=t stir u., erum.
r Reactor CoulantTemperature Measurcament r
er Reutor Water Lewi Measurement-of e/
V w
f r
V r
er w
Core Flow Calibradon/ Measurement e
'l,
,1 System Eapansion '
er er er omiy as aceded us==> icius. m 4.At we.in.;..,*s..o.,s Support inapecnon/Inserference Check des pt nced steesdusas suturqu.sie su IIH e/
w or.
e/
r' Dapixctnent Measurements
,3 System %bradon q
V or er 'or Steely State Measurements n
or e/
V Transient Response Reutor Internals %biation Of Required)
/
/
er of C=84.
- era i=~'t. tru. if 'rs' ued, wm < aone we.
stry trod em 4: mag i10 y
.l. '
v s-rg; F
EM bwbED MAb hee- %. :)
s P
OV = Open Vessel IRJ = Nudesar Hoamp LP = Low Powest MP. MJ Pcwor HP = Hegti Power w
K t' e
Table 14.2 I POWER ASCENSION TEST MATRIX Page 3
-5<
ww h
T1511NG PLATEAU POWER ASCENSION TEST OV 11U I.P h MP llP NO~I ES h
Retucubtion How Control h
Conuel System Adjartment/Conrsanat2on V
V V
3 a
i f
Feedwater tbntrol g
Control Sv?um Adjustrnent/Confirrnation V
V V
V p
4 n
r-
[
Pressure Control ri fu Control Systeni Adjustroent/ Confirmation V
V V
V
(
3 Phnt Auiornation and Control 6
Phnt Starsup/ Shutdown V-V V
V 4
/
trad Folkeneing Reactor 1:nircuhaien Systern Performance V
V V
V Sacady Staic Perfomiance V
V RIPS Out e4 Service
/
V Purnp Hestarts Feedwater Systen Perforrnance
/
Sicady State Performance V
V V
V
/
Manemoen Runout Was Desctrnination V
Main Saram Sysicm Perforniance
/
V V
/
Swady State Perforinance Residual Heat Remo+41 Sysicin t'crformante n
/
Ah **"' "8 * ' *
- 8"*' ' d " " l'I * * * **" 8".
Suppicsmon Poci Conding pv May e se be sutl.secas taae as tows }auwe Lewis N""'k#"'*"""*****'*"1*~"'
Shuidown Cooling V
V Y
h levels so dcoruminrate lla twat seemsval sq.4%iety E3 LEr SAD (acc ke 1)J j L;es-T bMW rh e
Y m
OV = Open Vesset HU = Nuclear Heatup 1P = 1.ow Pownst MP = Med Power HP = Higt: Powve
&e NW
r.
1
.u-l.4
.5 Table 14.2-1 POWER ASCENSIONTEST MATRIX
.' Page 4 g.
v.a
' 'D 19 TESTING PIXfEAU ry.
POWER ASCENSION TEST OV l tIU ;
I.P 1 MP llP N(IIES t
1_g 1
Rearsor W 4cr Cleanup 0_W Performance 2
/
/
g Sac $d; State Petformance t'i
/
o inventory Rejectiosa Mode k.
l M
/
May te eucanJtdwd dorias c,8=e www,c ptera=4 k
F/D Perfermance r-g
-a ;
RCICSy>acen Performance F.1 3,'
/
low Reactor Pressure 7,,
V llegh Rearser t'vesause As aceded no cosapine er.g.nica,,.t k.w s
,,,,,,w.t7 4
/
er llot/ Cold Quict Staris TCJ1U Plant Cooling /Semce Waser System Pesforinance
/
/
V V
Sicady State Power Operauons er er v
Danag astusin oge.
.an.
5p.
...eae OiTNosmal Operadoms IIVAC System Ferformance V
V V
V Sacady State Power Operauons er er er la in bidu I spues as <mada**ns as- (4 c.s peri-wni 3
OIENorraa! Operaikms espy.awee se operated) e/
-/
/
/
Only Sress al*cs need t.e semed at 1181 1
Turbine Valve Performance MSIV Performan<e V
V V
F**a <3<=ere ran seq'd at II v b.- 1 2
Indsvidual MSIV Closure / Timing V
V 14 Brancia f.ine Closunc/ Tivning
]
SRV Performance r
/
e Indw: dual Vabre Functumirg v
er er Dunasthr:<d asips. 45.pla W
_n Autoinatic Opening Verincatie rv g
Ws g
%ur Era we Lma (s. P e )-
y y
. 4
[
OV = Open Vesse!
- IWJ = Nuclus iteatup :
LP = Low Powe*
MP = Md Power leP = I4sgh Pcwer k4
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(
l It:lY 13 '92 02:4?Pt1 G E fOCLEAR BLDG J P 25/28 4
Figure 14.2 1 Power Flow Operating Mtp and Testing Plateau Definitions t
I I
I I
I I
~l l
I 1
I i30 -
etnCINT #UwP % pet 0 0 0 Naf UnaL cincyg atsQN 1 30 8
110 h,
i0c% Powi4
- 3121 Met e
=
ggg 6 80 7 90 100% Flow
- 115 l m4,%
9 pO an y pw., m,es, a
ioo%s,t,o,t$0o, m esacsNt moQ UNt 3
E dN 2
i
- i Po c so i
,s
/
?
e N-ef3 &
so
/y, wm-.......,
,/
v o
-h ;
hMN" p
~ ~ ~ ~
an d
h
. a um.-
fk j![i,"
~
~
o
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C,* g u
7i i/ i i
i _ - - - i a
i t
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=
o io m
3o 40 so 60 ro so on suo iio i:0 PE RCLNT Cort flow Testina P_lateau Description (1)
Open Vessel (OV)
With the RPV head removed, from initiation of fuel loading to cold conditions with a fully loaded core Nuclear Heat Up (HU)
During nuclear heat up, from ambient conditions and O'psig to rated temperature and pressure within the RPV, with reactor power typically less than 5% of rated Low Power (LP)
Between 5% and 25% rated thermal power, with the reactor internal pumo$ (RIPS) within 10% of minimum speed Mid Power (MP)
Between approximately the 50% and 75% power iod lines, with the RlPs operating between minimum and rated speeds, with the lower power corner within the capacity cf the bypass vatves.
High Power (HP)
Along and just below (+0,-5%) the 100% power rod line, from minimum RIF speed to rated core flow (1) Descriptions of testing plateaus are offered for illustrative purposes and general guidance only, as some asts are intended to be conducted outside the general testing plateaus descobed.
Neither the above descriptMns, nor th'e correspcnding boundary lines on the power. flow man, are meant to be absolute limits. Any operating limits will be specified in tne plant license. Any other testing restnctions wi!! be specified either within the Pfare administrative procedures covering the power ascension test program or within the individisal test procedure for a given test.
Fry c a n:u~
m:-
,e m
rn
f1AY-13 '92 02343PM G E f0 CLEAR BLDG J P.2G/28 s
.. ABWR 4-2watec Standpd Plant yrv c
@)
TAULE 1.8 20 RGs Applicable to ABWR (Continued)
ABWR Appl.
Issued Appil.
B9J's Reeulatory Guide Tith Bry Jhit ahM comnients 1.60 Design Response Spectra for Seismic Desip 1
12/73 Yes of Nuclear Power Plants.
1.61 Damping Values for Sciunic Design of Nu.
0 10/73 Yes c! car Power Plants.
1.62 ManualInitiation of Protective A,ons.
0 10/73 Ycs 1.63 Electric Penetradoo Assemblies in Contain-3 2/87 Yes ment Structures of Nuclear Power Plants.
1.64 Quality Assurance Requirements for the De.
Superceded See Table sign of Nuclear Power Pla.nts.
17.0-1 1.65 Materials and Inspections for Reactor Ves-0 10/73 Yc.
sel Cicsure Studs.
1.68 InidalTest Programs for Water Cooled 2
8/78 Yes
(,j-Reactor Power Plants.
1.68.1 Preoperational and Initia! G utup Testing i
I/~n Yes of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants.
1.68.2 Inidal Startup Test Program ta Demonstrate 1
-7td Remote Shutdown Capability for water-Cooled Nuclear Power Plants.
W O
1.68 3 Preoperadonal Testing of Instrumer and
/
7/?3-Y Control Air Systems.
1.69 Coacrete Radiation Shields for Nuclear Po-0 12/73 Yes wer Plants.
1.70 Standard Format and Content of Safety Ana.
3 11/78 Yes lysis Reports for Nuclear Power Plants.
1.71 Welder Qualifications for Areas of 1.imited 0
12/73 Interface Accessibility.
1.72 Spray Pond Piping Made From Fiberglass-2 11/78 Yes l
Reinforced Thermosetticg Resin.
l I
I 1 8-82 Amendment 14 l
E.
'?.
- } gmi
,,\\d.i e
5 \\f,
,&n*
r 1
NA.Y 13 '92 02:44PM G E NJQ,. EAR BLDG J P.27/28
' MN 23AM00AC Standard Plant uvc The submittals described in (1) above have been 0700. A DCRDR specified in NUREG 0737 is not
' discussed and reviewed extensively among tbc BWR required by SRP Section 18.1.
[~'/
\\
Owners' Oroup, the General Electric Company, and
\\;_.
the NRC Staff.
1A.2.3 Control Room Design Plant Safety Parameter Display Console The NRC has extensively reviewed the latest re-
[I.D.2]
vision (Revision 4) of the emergency Procedures Guidelines and issued a SER, Safety Evaluation of NRC Position BWR Owners' Group Emergency Procedure Guide-lines, Revision 4, NEDO-31331, March 19S7, letter In accordance uith Task Action Plan 1.D.2, each fro n A. C.Thadani, NRC Off'ce of Nuclear Reactor applicant and licensee shallinstall a safety parameter Regulation, to D. Grace, Chairman of BWR Owners' display system (SPDS) that will display to operating Group, dateo September 12,1958. The SER con-personnel a minimum set of parameters which define cludes that this document is acceptable for imple-the safety status of the plant. This can be ntained mentation. It further states that the SER closes all through continuous indication of direct and derMd the open items carried from the prc',ious revisions of variables as necessary to assess plant safety status.
the EPG.
Response
GE believes that in view of these findings, no further detailed justification of the analyse.
guide-The function'. of the SPDS will be integrated into lines is necessary at this time. Interface require-the overall control room design, as permitted by SRP ments pertaining to emergency procedures are dis.
Section 18.2.
cussed in Subsection 1A.3.1.
1A.2.4 Scope of Test Program. Preoper-1A 2.2 Control Room Design Reviews -
ational and Lower Power Testing [I.G.1]
Guidelines and Requirements [I.D.1(1)]
NRC Posilloo NRC Position
(
I Supplement operator "aining by co npleting the In uccordance with task Action Plan I.D.1.(1),
speciallow-power test program. Tests may be ob-all licensees and applicants for operating licenses will served by other shifts or repeated en other shifts to be required to conduct a detailed control room de-provide training to the operators.
sign review to identify and correct design deficien-cies. This detailed control room design review is
Response
expected to take about a year. Therefore, the Office of Nuclear Reactor Regulation (NRR) requires that The initial test pr presents an exce!1ent op-those applicants for operating licenses who are portunity for 11 ' ed ope ators and other plant sta5 unable to complete this review prior to issuance of a members to in v ua e experience and training h
license make preliminary assessments of their con-and in factJ ese e ' fits are objectives of the pro-trol rooms to identify significant human factors and gram (see yubsect' n 14.2.1). The degree to which instrumentation problems and establish a schedule the potenti nefit is realized will depend on such approved by NRC for correcting deficiencies. These plant speci'ic f:ctors as the organizational makeup of applicants will be required to complete ibe more the startup guup ard overall plant staff (see Subteo detailed control room reviews on the same schedule tions 14.2.2 and 13.1), as well as how the test pro-as licensees with operating,,. ants.
gram is conducted (see Subsection 14.2.4).
Response
Th; ;cn GP-L.AJ 1-CL 6 I? h a 7
sectmteb% BWR Owners' Group response to The design of the main controlioom will utihze item I.G.1 of NUREG-0737 is documented in a l accepted human factors engineering principles, in-letter of February 4,1981 from D. B. Waters to D.
corporating the results of a full systems analysis G. Eisenhut. (
s'unilar to that described in Appendix B of NUREG-
- -- ~~.-.---
.b Fer the most part, this issue concems operator training requirements.
although in tne context of the initia! test program. Thus, the BWROG response pnmarHy deals likewise with cporator traming issues. The A nendment a exception is Appendix E of the BWROG respont>e which descr.bes additional LA22 tests to be conducted curing the preoperational anc/or startup phase.
.. ~. _ _ _
v s_
F ET 4c3-92E159"
,5 -l3-3^
'4.
eu rp~
MAY 13 '92 OD44PM G E NUCLEAR BLDG J P.28/28 t
M 1sA6100AC I' ' Standard Plant uvc The specific tra'ning requirements for reactor power operated relief valves which can be manually operators are discussed in Section 13.2 of the SRP operated fortn tbc control rootu to vent he reactor
,O]
which is outside the scope >f the ABWR Standard pressure vessel. The point of connectico to the main l Plant. See Tabl: 1.91 for ioterface requirements.
steam lines which exits near the top of the vessel to these valves is such that accumulation of gases above 1A.2.5 Reactor Coolant System Vents that point in the vessel will not affect removal of
[lI.B.1]
gases from the reactor core repon.
NRC Position These power operated relief valves satisfy the in-cent of the NRC position. Information regardicg the
,p Each applicant and licensee shallinstall reactor design, qualification, power source, etc., of these
?> j j t coolant system (RCS) and reactor vessel head high valves is prodded in Subsection 5.2.2, jj$
point vents remotely operated from the control 8 j$ 7:
room. AJthough the purpose of the system is to vent The BWR Owners' Group position is that the re-X3j noncondensible gases from the RCS which may in-quirement of single-failure criteria for prevention of B # is hibit core cooling during natural circulation, the -
inadvertcut actuation of these valves, and the te-3jl Vents must not lead to an unseceptable increase in quirement that power be re=oved during normal op.
"%5 the probability of a loss-of-coolant accident (LOCA) eration, are not applicable to BWR's. These dual-f h g h or a challenge to containment integrity. Since these purpose rsfety/ relief valves serve an impcrtant pres-I vents form a part of the reactor coolant pressure sure relief function in mitigating the effects of tran-fg3 boundary, the design of the vents'shall conform to sients and concuirently provide ASME code over-g to g.E' the requirements of Appendix A to 10 CFR Part 50, pressure protection via their independent safety
( m %;
I General Design Criteria. The vent system shall be mode of operation. Therefore, the addition of a designed with sufficient redundancy that assures a second " block
- valve to the vent lines would result in
.] {5 i f
g low probability of inadvertent or irreversible ac-a less safe design and a siolation of the code.
uj o y i tuation.
Moreover, the inadvertent opening of a relief valve in 3e-l a BWR is a design basis event and results in a 3
pi Each license shall provide the follewing infor-controllable trensient.
N*
} j j9I
- matico concerning the design and operation of the high poict vent system:
In addition to these automatic (or manual) relief fuG valves, the ABWR design includes various other
,3e$
(1) Submit a description of the design, location, means of high point venting. Among these are:
{ @, W size, and power supply for the vent system along eeq with results of analyses for loss-of coolant (1) Normally closed reactor vessel head vent valves, e
y, I j accidents ioitiated by a break in the vent pipe, operable from the control room, which discharge The results of the analyses should demonstrate to the drywell. The reactor coolant vent line is 2
2
,egy, compliance with the acceptance criteria of 10 located at the very top of the reactor vessel as 3iG CFR 50A6.
shown in the nuclear boiler systera P&lD (Figure 9
5.1-3a). This 2 inch line contains two safety-
@ ~,,,
(2) Submit procedures and supporting analysis for related Ciass 1E meter-operated valves that are
[j-W.
operator use of the vents that also include the operited from the control room. The location of s
jj information avaDable to the operator for initiat-this line permits it to vent the entire reactor core ing or terminating veut usage.
system normally connected to the reactor pres-sure vessel. In addition, since this vent lice is
Response
part of the criginal design,it has already been considered in all the design basis accident The capability to vent the ABWR reactor cool-analyses contained elsewhere in this document.
ant system is prosided by the safety relief vehes and reactor coolant vent line as well as other systems.
(2) Normally open reactor bead vent line, which dis-The capability of these systems and thee satisfaction charges to a main steamline; cfItem IIA 1 is discussed below.
(3) The main steam driven reactor core isolation The ABWR design is provided with eighteen Q) 1A.N Amendment 8
. _ _ _