ML20101G626
| ML20101G626 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 06/01/1992 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Polich T, Poslusny C NRC |
| References | |
| NUDOCS 9206260178 | |
| Download: ML20101G626 (28) | |
Text
{{#Wiki_filter:_ _ _ _ _ ' 01 '2 078014M G E IUCLEAR BLDG J p,gfgg .g N V gA GENuclevEnergy ABWR p Date GAlsa. \\ To m ys~.Pafrek Fax No. c h e+ Po slu s ng This page plus VI page(s) From Jo cic Fov MM code ___. 175 Curtner Avenue San Jose. CA 95125 Phone (408) 925 AS2A FAX (408)925-1193 or (408) 925-1687 Subject c 6 elee s4 ossa one-Ibs l 1 Message ra A%, c knes +a c % > k e s- \\r a kn Q ( Q. GAL C.4\\\\J-__ \\h WSCJ o w %t 230006 r ph 9206260178 920601 PDR ADOCK 05200001 A PDR l I eae q._ m a j _m j _a n a.m. x. Aa aa a= .m am.
Jun ci 'm en c141 G E tOCLEAR I!LDG J P. 2. '28 a FURTHER FOLLOW-UP TO CHAPTER 14 DSER OPEN ITEMS 6/1/92 Attacued are further changos to Chapter 14 of the ABWR SSAR, in response to comments obtained during various telephone conversations concerning closeout of open items from the Staff's Draft SER. This should complete all changes necessary to fully close all such open items, with the exception of items 118,120 and 121, which will be addressed in a future submittal. Furthermore, a final review has boon performed of all uses of the terms should and shall (see item 119), exclusive of those found in the criteria discussions of the power ascension phase test abstracts of section 14.2.12.2, which will be reconciled as part of the resolution of item 121. Thus, with the above exception, where the term should remains it is intended, as it represents a recommendation and not a requirement. l - ---~-
JUN 01 '92 CD 0241 G E rtJCLEAP DLDG J P.3 20 ABWR
== Sjandar(Plad ms to support RIP operation. Other interf acing (f) proper system flow rates including inds-systems shall be available, as ocedco, to udual pump capacity and discharge head. support the specified testing and the cor. respending system configurations. Reactor (g) proper manual and automatic system ope-y sessel internals AWAe capable of being ration and margin to actuation of pro. subjected to rated solumett te flow, tective dedces; g (3) General Test Methods and Acceptance Criteria (b) prooer operation of interlocks and equipment protectise devices in pump and l Testing of the recirculation systemdend be motor controls; coordinated closely with that of the recircu. larion flow control system (Subsection (i) proper operation of permissive, pro. 14,2,12.1.3) in order to adequately demon. hibit and bypass functions; strate proper integrated system response and operation. Also, the pr. perational phase of (j) proper system operation while powered the reactor internals vibration assessrnent frem primary and alternate sources, program (Subsretion 11.2.12.1.52) involves including transfers, and in degraded extended operation of the recirculation sys. modes for which the system is expected tem and shoulci be scheduled accordingly so as to temain operational; to optatize overall pla.nt integrated testing. (k) proper operation of the recirculation The scope and intensity of the preoperational motor seal purge subsystem over the full testing of the recirculation system and range of RPV pressures including tbc associated support subsystems will be limited proper functioning of the main header by the unavailability of nuclear beating, pressure control valve and proper Comprehensive testing of the system at rated distribution of seal purge flow to temperature and pra.ssure will be performed individual pumps and motorst during the startup phas DII (1) proper functioning of the recirculation l Performance Awad be observed and recorded motor cooling subsystem and its ability durine a series of individual component and to remove design beat loads from each integrated system tests to demonstrate the RIP motor via the dedicated beat exchan. follcwing: gers; (a) prcper cueration of instrumentation and (m) proper functioning of the recirculation equipment in all combinations of logic motor inflatable shaft seal subsystem and instrument channel trip; and its ability to provide a temporary backup sealing mechanism for each pu p (b) proper functioning of instrumentation and motor shaft during recirc snotor alarrns used to monitor system operation maintenance or removal; and availability; (n) acceptable pump / motor vibration levels (c) proper operation of system valves under and system piping movements during both expected operating conditions; transient and steady state operation; and (d) proper operation of pumps and motors in all normal design ope. rating modes as well (o) acceptable reactor vessel internals flow as any specified special testing induced vibration levels per the configurations: requirements of Subsection 14.2.12.1.52. (e) acceptable pump NPSH under the most System operation is considered acceptable limiting design flow conditions; when the observed / measured performance charac-Amnwm 2 in.s ?M L 4r.f-cI: C" M<id: '. ? M !.M I ::
Ji>4 01 '92 OYt'02AM G E NUCLEAR BLDG J p, v28
- 'MM Standard Plant
[ (3) General Test Meth plance Criteria levels and system piping movements dur-tb 1 usti ing both transient and steady state op. y e$ 3 { Performance served and recorded crauon; and durin5 a series of dividual component and iSi integrated system tests that includes all (en) proper operation of pump discharge (in. 2 I !' y / j demonstrate the following: 'aeep ;til system (s) and its ability tol 2 ! 5 l, } ) modes of RHR system operationingenio prevent damaging water hammer durink [ i } ) ) sptem transients. p-g i f e., f ;y j j ( (a) proper operation of insfiGrecifianoninil ' 3
- ~
equipment in all combinations of logic System operation is considered acceptabl. 3 J s{pl z and instrument channelinp; wben the observed / measured perfonnance chara / I;,g/ teristics, from the testing described abose a 1 Eg 1:~ ( j$r.' (b) proper functioning of system intrumen-meet the applicable design spedications. jjjl: [ 34 1 tation rad alarms used to monitor systern h[cE i operation and availabilityf 102.1.2.1.9 Itasesor Cort Isolation Coollag { " "j, Systeen Preoperstlosal Test 4 }y g {, (c) proper operation of system valves, in-yj g g cluding timing, under expected operating (1) Purpose 'd & 0 ( }~o y a 's -yei } conditions;%_ e. 3 erify that the operation of the reacto )jij } / y$o (d) proper operation of pumps and motors n 2 ore isolation cooling (RCIC) system, in- 0mE i E Eji all desipi operating modes; lu ling the turbine, pump, valves, instru 32 Ij. j g catation, and control,is as specified. &Nt5 ) {g j 'j \\ (e) acceptable pump NPSH under the m st !g i j limiting design flow conditions; ercquisitea ) (f) proper syster flow paths and flow rat s. 3 T e construction tests have been success- '$ f Ily completed and the SCO has renewed the 3 l \\ / including pump capacity and discher e $ 3 t st procedure and has approved Q' bead and time to rated 0cw, I f} JI (g) proper operation of containment spr y 8 ) tipo of testing. A temporary steam 2{ sliaH be available for driving the RCIC tur-modes including verfication that spr. ] 3 bi c. The turbine instruction inanual shall e: fpgb reviewed in detailin order that pre norries, head,e,,rs and piping a f 4 2 / debris; Q,Q t as relative to turbine operation are foi-i f y_ - 4 I wed. All required interfacing systems j'}a {.n) proper pump motor start sequence an m 3 J s~ all be available, as useded, to support 1 ( 3*$ l ~ s gin to actuation of protediw device; j J t e specified testl6g and the corresponding {j l 4 g b!g l
- j em configurations, gj t
j13 proper operation of interlocks a f g $ ={, (i) equipment protectiva devices la pump an General Test Methods and Acceptance Criteria 1g-@ vaQcontroinQ y y r 3f The RCIC turbine f.irst be;,,it.ted / oj ince preoperational j j a sed then while (j) proper operation of permissive, pro-while disconnected f },$ ;e hibit, and bypasa luaccioas; coupled to the pump, read utilizing a temporary 4 i 4 3 testing is } h (k) proper system operation while powered steam su t attainable RCIC pump flow t - li E from primary and alternate sources, in. may be 5!gj cluding transfers, and in degraded modes ! $ o. for which the system is crpected to re. Performance be observed and recorded U cain operational; during a series of individual component and j,6 integrated system tests to demonstrate the p.2 jj j )I (1) acceptability of pump [ motor vibration-following-Should this prevent any specified testing from being comp!sted A m nd m nt2 successf0/, suen case will be docurnented and scheduled for a:u completion durmg tr e power ascension test phase. _ m# ~ _ 06-01 AM F04 ,.... _ _ ~ _. _. _.. _. F F. ; Lt 4??-?^5 6A7 .._. _ ~,- _,9.;. n?,_ .~
JLN 01 '92 07:0341 G E tOCLEAR BLIG J P.5/28 4 'MN nA61xAN Standard Plant uva (2) Prerequisites dry ^ ell sumps. dd System construction testing has been Performance sheng e observed and recorded ( successfully completed, during a series of individual component and integrated sptem tests to de:rsonstrate the j (3) GeneralTest Methods and Acceptance Criteria following: Since this system is the primary communica-(a) proper operation of instrumentation and tica interface between the various plant controls in all combinations of logic systems it should be adequately tested dur-and instrument channel trip; l ing the preoperational phase testing per. formed on those interconnected systems. (b) proper functioning of indicators, annun. Provided the construction testing and the ciators, and alarms used to monitor sys. associated system testing has been success. tem operation and statust fully completed as it relates to proper ope-ration of the multiplexing system, no speci. (c) proper operation of leakoff and drainage fic additional testing should be necessary, rneasurement functions such as those asso. ciated with the reactor vessel head System performance would then be considered flange, drywell cooler condensate, and acceptabic provided all design specifications are various primary system valves; met. (d) proper response of related systern val-14.2.12.1.13 Leak Detection and Isolation ves, including timing, under expccted
- 5) stem Preoperational Test operating conditions; (1) Purpose (c) proper interface with related systems in regards to the input and output of leak To verify proper response and operation of detection indications and isolation ini.
the leak detection and isolation system (LDS) tlation commands; logic. (f) proper operation of bypass switches and (2) Prerequisites related logie: and The construction tests have been successfully (g) proper system operation while powered completed and the SCG has reviewed the test from primary and alternate sources, in. procedures and has approved the initiation of ciuding transfers, and in degraded modes testing. The required AC and DC electrical for which the systein is expected to re. O power _ sourcephewie be operational and the main operational, lI e it appropriate interfacing systems shall be available as required to support the System operation is considered acceptable specified testing, when the observed / measured performance charac-teristics, from the testing described above, (3) GeneralTest Methods and Acceptance Criteria meet the applicable design specifications. Since the leak detection and isolation system 14.2.12.1.14 Reactor Protection Systees is comprised 'nostly of logic, the checks of Preoperstloaal Test ' valve response at timing and the testing of - sensors will be ( s/tC'med as part of, or in (1) Purpose conjunction witti,J.c.arious systens with which they are associated. These systems in, To verify proper operation of the reactor clude RHR, RCIC, RWCU, main steam, feed *at. protection system (RPS) including complete er, recirculation,- radiation monitoring, channel logic and response time, nuclear boiler, drywell cooling and the H M6. Amenement 18 'e mu a m m.ee~ sea,_A, u me .o ese
JtJ4 01 '92 07:03AM G E NUCLEAR BLDG J P,6/28 ABWR mxe Standard Plant mo To verify proper operation of the autem 3 tic Verify the feasibility and operability of power regulator (APR) over the range of intended remote shutdown functions from the required operating modes. remote $butdown panel and other local and remote locations outside the main control (2) iNeregaisites room which will be utilized during the remote shutdown scenarlo. i The software program:ning and initial diagnos. tic test.cg has been completed and the SCG (2) Prerequisites bas resiewed the test procedure and has ap. proved the initiation of testing. The pro-The construction tests have been success. cess computer system, rod control and fully completed and the SCG has resiewed the information system, recirc flow control test procedure and has approsed the initia. system, turbine control system, and other tion of testing. Additionally, control required system interfaces shall be available y_o w3 devH be supplied to the remote lij shutdown panel and tbc required system and to support the specified system testing. Mg component interfaces shall be available, as l (3) GeneralTest Niethods and Acceptance Criteria needed, to support the specified testing. The APR is a top level controller that inter.
- 3) GeneralTest Methods and Acceptance Critena faces with various lower level controllers y
and systems APR testing, therefore, A+i4d The remote shutdown system (RSS) consists of be closely coordinated with testing of relat. the control and instrumentation available at ed interfacing and affected systems. Such the dedicated remote shutdown panel (s) and g testing sb4d include the following demon-other local and remote locations intended to strations: be used during the remote shutdown scenario. (a) proper operation of instrumentation and hiuch of the specified testing can be L:s am-controls in all combinations of logic plished in conjunction with, or as part of, for all modes of operation including the individual system and component preope. transfers; rational testing, Howeve r Ac_cessful y results of such testing Am4d be documented (b) proper functioning of annunciators, as part of this test, Performance shm4el e alarms, and displays used to monitor observed and recor ed during a series of system operation or status; individual componen and integrated sv tem tests to dernonstrate t e following: j. ppt.cate. ~ (c) verification of proper data flow and proecssing including the accuracy of (a) proper functioning of the control and calculations and control algorithms; and instrumentation associated with the RSS; (d) proper communication and interface with (b) proper operation of pumps and salves other control systems and related sup-including establishment of system flow porting and monitoring functions, paths using RSS control; iered acceptable when (c) proper functioning of RSS transfer Systern operation is the observed performans,. meets the applicable swltehes including verification of design specifications. proper override of main control room functions: 14.2.12.1.18 Remote Shutdown System Preoperational Test (d) proper operation of prohibit and permis-sive interlocks and bypass functions (1) Purpose after transfer of control; l 14 M9 Amtadment 18 .? ell JJL3'r Fr" CE ^) 37 ~;;'t.Au J. f.
Ati 01 '92 07 D-Af1 G E flVCLEcR Dl.DG J P.7/28 ABWR m-
- ' Standard Plant prv s fled in all required operating modes.
bead; (2) Prerequisites (g) proper pump motor start sequence and margin to actuation of protective The construction tests have been successful-devices; ly completed and the $CG has reviewed the test procedure and has approsed the initia. (b) proper operation of interlocks and tion of testing. The fuel poo: and suppres. equipment protective desices in pump and sion pool shall be adequately filled and the salve centrols; appropriate filter /demineralizer support fa. cilities and other system interfaces avail. (i) proper operation of pertaissive, j able, as needed, to support the specified prohibit, and bypass functionst te stin g. (j) proper system operation while providing (3) GeneralTest Methods and Acceptance Criteria ihe speelfied iniersystem refill capabilities; and Tbc suppression pool and fuel pool share com. mon water treatment facilities. The suppres. (k) acceptability of pump /motorlibration sion pool cleanup system has a dedicated pump levels and system piping movements for circulating water to and from the suppres. during both transient and steady state i slon pool and through the common filter / demi. operation. neraliser. However, the shared filter / demi. neraliter facilities are considered part of System operation is considered acceptable the fuel pool cooling and cleanup system, when the observed / measured performance h Therefore, this preoperational test +hevi11 be characteristics, from the testing described closely coordinated with that o ubsection above, meet the applicable design specifica-14.2.12.1.21. tions. Performance be obsened and recorded 14J.12.lJ1 Fuel Pool Cooling gnd Cleenup during a series r>f individual component and Splem Preoperational Test l integrated system tests to demonstrate the following: (1) Purpose (a) proper operation of instrumentation and To verify that the operation of the fuel equipment in all combinations of logic pool cooling and cleanup (FPC) system, and instrument channel trip; including the pumps, heat exchangers, controls, valves, and instrumentation, is as (b) proper functioning of instrumentation specified, and alarms used to ruonitor system operation and availability; (2) Prercquisites (c) proper operation of system valves, in. T h e c a.a st r u c tion t e st s h ave be e n cluding timing, under expected operating successfully completed and the SCG has conditions; reviewed the test procedure and has approved the initiation of-testing. The required (d) proper operation of pump and motor in interfacing systems shall be available, as all design operation modes; needed, to support the specified testing and the appropriate system configurations. (e) acceptable pump NTSH under the most limiting design flow conditions; (3) GeneralTest Methods and Acceptance Criteria i. (f) proper system flow paths and flow rates Performance iaeeki be obsened and recorded including pump capacity and discharge during a series f Individual component and sk(( Amendment IB 14 2-21 es u a _y = + c e n.._,_,,,, __ _, _.. w a., n - #u u ee
JUN 01 f92 07:0 mt1 G E f0 CLEAR BLDG J. P.9/28 ..ABWR mms Signdard Plant uv-l (3) GeneralTest Met. < and Acceptance Criteria (a) proper calibration of detector assem-y sh.J L blies and associated equipment using a 4 Il Performance sheuh1 be observed and recorded standard radiation source or portable j 3 j during a series of individual component and cahbration unit; l integrated subsystem tests to demonstrate the j following: (b) proper functioning of indicators, j recorders, annunciators, and alarms, l (a) preper calibration of detector sssemb. lies and associated equipment using a (c) proper system trips in response to high standard radiation source or portable radiation and downscale/irmperative l calibration unit; conditions; 1 (b) proper functioning of indicators, re-(d) proper operation of permissive, probi. corders, annunciators, and alarms; bit, interlock, and bypass functions; and (c) proper system trips in response to high radiation and downscale/ inoperative (e) proper operation of filtering and conditionst and sampling equipment. (d) proper operation of permissne, prohi. System operation is considered acceptable l bit, interlock, and bypass functions, when the obsersed/ measured performance charac. j teristics, from the testing described abose. 59 tem operation is considered acceptable when meet the applicable design specifications. 3 the observed / measured performance characteriu ties, from the testing described above, meet the 11.2.12.1.26 Containment Atmospheric applicable design specifications. Monitoring System Pnoperational Test 18.2.12,1.25 Dust Radiation Monitoring Sptem (1) Purpose Preoperational Test To verify the ability of the containment ~ (1) Purpose atmospheric monitoring system (CAMS) to 'i monitor oxygen, hydrogen, and gross gamma I To utify the ability of the dust radiation radiation levels in the wetwell and drywell monitoring system to indicate and alarm not. airspace regions of the primary containment. mal and abnormal airborne radiation levels throughout the plant.- (2) Prerequisites (2) Prerequisites-The construction tests have been success-fully completed and the SCG has reviewed the The construction tests have been successful-test procedure and has approsed the initia-ly completed and the SCG has reviewed the tion of testing. Initial system and compo-test procedure and has approved the initia. cent setup has been accomplished per under c tion of testing. Additionally, indicator and' instructions. l trip units, power siipplies, and sensor / con. verters have been calibrated according to (3) GeneralTest Methods and Acceptance Criteria l l vendor initructions. The containment atmosphere monitoring system l (3) GeneralTest Methods and Acceptance Criteria consists of radiation, oxygen,- and hydrogen monitoring subsystems. Performance of each { Performance shoold e observed and recorded of these subsyste shoeht be obsened and during a series of i ' - al component and record r og a series of individual i integrated subsystem ra= t emonstrate the co onent and integrated subsystem tests to following: emonstrate the following: .$kall I' 2'2d Ameatment 18 .mem a Le io,..._ w.,, -.. ~ =wuau1 a ~-
JUN 01 '92 07:05AM G E NUCLEAR ELDG J ".9/28 4 . ABWR Standard Plant uv9 when the observed / measured performance character-(c) acceptable pump NPSH under tbc most istics, from the testing described above, meet licuting design flow conditions; the applicable design specifications. (f) proper system and component flow paths, 142.12.129 Reactor Building Cooling Water flow rates, and pressure drops, includ-System Preoperational Test ing pump capacity and dis:harge head; A / (D Purpose (g) proper pump motor start secuence and mar-L g:n to actuatioc of protective de, ices; To verify proper operation of the reactor building cooling water system (RCW) in-(h) proper operation of interlocks and equip-( cluding its ability to supply design quan-ment prot r.tive devices in pump and 47 tities of cooling water at the specified vahe controls;
- j temperatures. to en
- ntial and nonessential B
-1
- cads, as appropriate, during normal, (i) proper operatior. of pern issive, po-5 h.
abnormal, and accident conditions. hibit, and bypass functions; ~ (2) Prerequisites (j) pr 6 ystern operation while powered s from primary and alternate sources, in. The ccnstruction tests have been successfully cluding dansfers, and in deFrader modes completed and t'e SCG has resiewed the ter. for which the sprem is exp cted to re. piecedure and has approsed the initiation of main operational. This includes isola-j testing. Primary and backup power, reactor tion / shedding of nonessential loads and building service w ster, indrument air, and divisional interties when a LOCA signal other required supporting systems shall be b present; m assilab!c, as needed, for the specified test-3 ing configurations The cooled components (k) acceptability of pump / motor sibration M 'neAl be operational and operating to the levels and system piping mosements dur-extent poeW+ during hea asbanger perfor-ing both transient and steady staie ) ruance evaluatio. pesethote operation; I GemlTest MethodA and Acceptance Criteria (1) proper operation of system surge tarh s sha and chemical addition tants and th 6r i T erlormance e ab ved and recorded associated functiors; and during a series of i dividuai component and 4 integrated system t Sts to demonstrate the (m) acceptable performance of heat exchang-followiag: ers. to the extent practical. (a) proper operation of instrumentation and System operation is considered acceptable equipmeut in all combinations of logic when the observed / measured perfonnance charac-and instrument channel trip; teristics, from the testing described above, meet the applictble design specificatious. Due (b) proper functioning of instrumentation to the possibility of insufficient beat loads and alarms used to monitor system opera-during the preop phase, the final system flow tion and avCability; bX acing and heat exchanger performance oalua-1 _.on may need.o be performed during the startup (c) proper operation of system valves, in-phase. = ciud.ng tvung, u. der expected operating conditions; 14.2.12.1.30 Plant Makeup Water System (s) Preoperational Test (d) proper og atior. of pumps and motcrs in all design operating modes; (1) Purpose Amendment 18 14 M m .m_ --_m
~ _ - - Jt.P 01 '92 07 3 06At1 G' C ftJCLEAR' C'2G J P,10/28 ~ 'ABWR wxe i Standard Plant uv a 4 a series of indisidual component and diesel fuel oil transfer, diesel generator integrated system tests to demonstrate the starting air supply, jacket water, and lube l following: oil. (a) proper operation of initiating, trans-(2) Prerequisites l fer, and trip devices; The construction tests have teen successful-l (b) proper operation - elaying ar.d logie, !y completed and the SCG bas reviewed the including load shedding features; test procedure and has approved the initia. tion of testing. All interfacing systems (c) proper operation vf equipment protective a.ad equipment required to support system op-desices, including permissive and prohi-eration shall be available, as needed, for l bit interlocks; the speelfled testing configuration. Addi-g j tionaly, suffic' nt diesel fuel e - - 1 (d) proper operation of instrumentation and available on site to perform the scheduled j i alarms used to monitor system and equip-
- tests, or w;h acces'.ble, ment status (including availabilitv)-
(3) GeneralTeu Meth d Actn tance Criteria } (e) proper operation and load carrying sLdl capability of breakers, motor controll-Performance observed and record:d j i-ers, switchgear, trausformers, and during a series of individual component and l cables; integrated system tests to demonstrate the l following: l (f) that a sufficient level of redundancy and electrical independence exists as (a) proper automatic startup and operation specified for each application; of the diesel generators upon simulated loss of a c voltage and attainment of l fg) the capability to transfer between the required frequency and voltage with-onsite and offsite power sources as per in the specified time limits; design: (b) pec.j,cr r sponse and operation for_ de-l (h) the ability of emergency and vital loc.. sign basis accident loading sequence to to start in the proper sequence and to design basis load requirements, and l operate properly under simulated verificetion that voltage and frequency accident conditions, while powered from are maintained within specified limits; either preferred or standby sources, and i over the specified range of available (c) proper operation of the diesel genera-l bus voltage; and tors during load shedding. load sequenc-l ing, and load rejection, including a l (i) the adequacy of the plant emergency and test of the loss of the largest sinf e l i essential lighting systems. Ioad and of the complete loss of load, i verifying that voltage and frequency are 14.2.12.1.45J Emeryocy Diesel Gesentor mainained within design limits and that m [ Peroprational Test ov*rspeed limits are not exceeded; (1) Purpose (d) that a LOCA signal will block generator breaker on field tripping bv all protec. To demonstrate the capability of the emer-tive relays except for the gen:rator gency diesel generators to provide highly re-phase differential current and engine j linie emergency electrical power during not-overspeed relays;- real and simula'ed accident conditions when normal offsite power sources are unavailable. (e) that a LOCA signal will initiate termin-i and to demonstrate the operability of the ation of parallel operations (test or - j-diesel generater at 4 4tiary systems, e.g., manual transfer) and that the diesel l -N W ] E Amesdmeru 18 4 l lL FrdM 4089251587 06-0 b% 07: N AM -F;0 ~
JUN 01 '92 07:0%f1 G E NUCLEAR BLDG J P,11/28 MNN nencAN standard Plant uv s (d) proper operation of instrumentation and groups, two at a time (A and D, B and C, A alarms used to monitor system and equip-and C), with the other divisionalload group ment status; completely isolewd from both onsite and offsite power so ncs (including DC sour-(c) proper operation and load carrying cap. ces), simulate a divisional bus under vol-ability of breakers, tuotor controllers, tage condition (LOP) fo!! owed immediately by switchgear, transformers, and cables; a LOCA signal and verify the following: (f) aufficient lesel of redundancy and elec-(a) that the appropriate disisional diesel trical independence as specified for generators automatically start, resch each application; and rated speed and voltage, and connect to their respe c tive divisional buses (g) the capability to transfer between on-according to design aad within the site and offsite power sources as per specified timet design. (b) that all rel.ying and it,terlocks related Performance of each of the various plant etee-to the LOP /LOCA condklon operate pro-trical systems is considered acceptable when perly including the specified Mding the testmg described above demonstrates that and sequencing of sources and loan;; the requirements of the applicable design and testing specifications have been met. (c) that all divisional loads operate as de-signed in response to the LOP /LOCA con-14.2.12.1.46 Integrated ECCS Loss of Ofhite dition, including establishment of the Power LLOP)/LOCA Precperational Test appropriate divisional ECCS flow to the vessel within the specified time; and (1) Purpose (d) that all loads and electrical busses To serify the proper integrated ECCS and associated with the isolated divisional plant electrical system respons: to a simu-load group remain deenergized m lated LOP /LOCA condition and to serify the skil independence of the redundant onsite disi-The test of each combination e of sional power sources and their associated sufficient duration to allow establisSment load groups. of stable operating conditions such that any adverse conditions which might result from (2) Prerequisites improper load group assignment (e.g., lack of forced cooling of a vital component or The preoperational tests of the plant elec-system) would be detected. 5d trict, system, iceluding diesel generators, and the ECCS and related auxiliary systems, After the proper response of eac ivisional base been successfully completed The reac-combination has been separate demonatrated tor vessel shall be ready to accept design the integrated response all ECCS and ECCS injection flow, all ECCS pumps shall electrical divisions dew 6d e demonstrated have an adequate suction source, the diesel by simulating a complete loss of offsite g g. generatory have sufficient fuel avail-power and LOCA ecadition and then sertfyicg -./ able, and essential DC power shall be avail-items (a) through (d) above for all three able. All other required systems shalt also diesel ;tenerators and load groups as they be available, as needed, to support the respond and operate sitnultaneousiv. specified integrated testing. r' Performsuce is acceptable when the.cose { (3) GeneralTest Methods and Acceptance Criteria testing demenstrates that the applicable design specifications have been met. For each combination of divisional load HM Amummts i t F-i4AL, J wAmm.k 3 E i A 3 ~1 M aim. aC dA__ AM_ _ Al _L _
JUN.01 '92 07 07At1 G E f 0; LEAR BLDG J - P.12/29 ABM i
- axuxo Standard Plant uvy 14.2.12.1.47 Plant Communications Sptem (f) audibility of speakers and receivers Preoperational Tast under anticipated background noise levels; i
(1) Purpose (g) the ability to establish the required To verify (be proper operation and adequacy communications with outside agencies; of all plant communications systems and and rsethods that will be used during norms! and abnormal operations including those needed to (h) proper functioning of dedic ited use carry out the plant emergency pla_. systems and of those systems expected to function under abnormal conditions such (2) Prerequisites as loss of electrical power or shutdown Tbc construction tests have been success-fully completed and the SCG has reviewed tbc System operation is considered acceptable test procedure and has approsed the initia-when the observed / measured performance tion of testing. Initial system and compo p characteristics meet the applicable design c odshd ent setdngs (ga ns, s mes, eted M spcMcations. ,.3 be ad;= d tp gexpectations of the acoustic environment and background noise 14.2.12.1.48 Fist Protection System levels for each location and for all modes of Preoperitional Test operation. (1) Purpose (3) GeneralTest Methods and Acceptance Criteria To verify the ability of the fire protection The communications systems to be tested system to detect and alarm the presence of include the plant PA system, all hardwired combustion, smoke or fire within the plant e l systems within the plant, portable radio and to initiate the appropriate suppression systems to be used within the plant boun-systems or devices. dary, normal and dedicated communications l links to outside agencies, and the plant (2) Prerequisites \\ emergency alarms. Performance shedd be l observed and recorded during a serii. of The conttruction tests have been successfut-individual component and integrated sy em - ly completed and the SCG has reviewed the l tests to demonstrate the following: g test procedure and has approved the initi-J l ation of testing. The required electeical (a) proper functioning of all transmitters power and make up water sources and other. l and receivers witheat excessive inter-appropriate interfaces and support systems, ference levels; -are available as needed for the specified testing.- l (b) proper operation of all cortrols, swit. ches, and interfaces including silencing (3) GeneralTest Methods and Acceptance Criteria -h and muting features; The fire protection system is but one part (c) proper isolation and independence of of the overall fire protection prograta. various channels and systems; This progam is the intearated effort involving compone ats, prucedures, and l (d) proper operation of systems under' multi-personnel utilized in carrying out all pie user and fully loaded conditions as activities of fire protectioniin accordance per design; with Criterion 3 of 10cFR$0, Appendix A. It includes systems and components, facility j (e) proper operation of plant emergency design, fire prevention, detection, annun. alarms; ciation, confinement, suppression, adminis-4 i N Jd9 Amendment 18 FEcM 4CS-M 1587 0$-01-92 09:c5 AM -P!E
JIN 01 '92 07107AM G.E TUCLEAR BLDG J P.13/28 .bb. . :Ms:oce.
- 5tandard Plant osv s trative controls, fire brigade organization.
(g) proper functioning of smoke, beat and training, quality assurance, inspection, test. Llame detection desices; ing, and maintenance. The fire protection program begins with the initial design of all (b) proper operation of both local and
- p. ant systems and equipment and of the build.
remote alarms including those interfac-ings and structures in which they are locat, ing with outside egencies; and ed A detailed analysis is then perforroed on this design to identify, qualify, and quanti. (i) proper operation of primary and second-fy all potential fire hazards, aan their con. ary electrical power sources including sequences, within the plant. Specific fire fire protection system diesel genera. protection equipment is then added, where tors. needed, when individual component design and features such as physical separation, walls, System operation is considered acceptable doors, and other barricts and passise devi. when the obsersed and measured performance ces, do not completely fulfill she require. characteristics, from the testing described ments of the fire protection prt' ram, above, meet the applicable design specifi. cations. The majority of the effort invched in de. monstrating that the requirements of r.he 14.2.12.1.49 Radioacthe I.lquid Drainage and overall fire protection program are met will Transfer Systems Preoperational Tests be through analysis and documentation. Pre-operational testing of the fire protection (1) Purpose system will mainly be limited to the equip. ment and facilities designed for the detec-To verify the proper ope.ranon of the tion, annuncistion, and suppression of various equipreent and pathways which ma.ke up l fir e s. This testing e4rmrki it:clude the the radioactive liquid drainage and transfer following demor trations: y system within the Nuclear Island. (a) proper operation of instrumentation and (2) Prerequisites equipment in all cornbinations of logic and control; The construction tests base been successful-ly compkted and the SCG has reviewed the (b) proper functioning of prohibit and per-test procedure (s) and has approved the missive interlocks and equipment initiation of testing, An adequate supply protective devices; of demineralized water, the.necessary electrical power, and other required (c) proper operation of system valves, interfacing systems shall be available, as pumps, and motors under expected ope-needed, to support the specified testing. rating conditions; (3) GeneralTest Methods and Acceptance Criteria 1 (d) proper system and component flow paths, flow rates and capacities; The testing described below consists of that of the equipment and pathways for the (e)' proper operation of water based suppres-drainage and transfer of radioactive and sion systems such as spray, sprinkler,. potentially radioactive liquids within the deluge, and. hose devices and.of other plant. Also included are dedicated systems supprer. ion systems such as those utill-for the handling of liquids that require zing halon, carbon dioxide, foams and -s p c cial.c olle etio n and disposal dry chemicals, including both manually consider.
- ns such as detergents, and automatically actuated systems; shdi gg Performanceg be observed and recorded H
_(O proper operation of freeze protection during a series of individual component and devices, if applicable; integrated system tests to demonstrate the . Amc..dment 18 IM i u ___________m -_m _ _. _ _ _ _. _ _ ~.... _
JUN 01 '92 07:09AM G E NJCLEAR BLDG J P 14/29 ABM unux,as S.LamlarMlant REV_B (c, proper functioning of all control, in-(3) GeneralTest Methods and Acceptance Criteria strumentation, logic, interlocks and alarms; Vibratio, and thermal expansion testing will be conducted on plant systems and components (d) pioper functioning of other fuel bandl-of the following classifications: ing and reactor component servicing equipment such as that used for cell (a) ASME Code Class 1,2 sad 3 sprema, disassembly, channel replacement, in-strument handling, CRD handling, RIP (b) high energy piping systems inside Seis-setvicing, SRV and MSIV maintenance, mic Category 1 structures; pool and vessel vacuutn cleaning, and for underwater lishting and viewing. (c) high energy portions of systems whose failure could reduce the functioning of (e) proficiency in fuel movement operations any Seismic Category 1 plant features to using dummy fuel (prior to actual fuel an unacceptable level; and loading); and (d) Seismic Category 1 portions of moderate (f) dynamic and static load testing of all energy piping systems located outside cranes, boists, and associated lifting containment. 7,: ( and rigging equipment including static
- 3, i
load testing at 125% of rated load and Thermal expansion testing during the preope-lSjj full operational testing at 100ch of rational phase will be limited to those sys- .gk rated load, tems that are expected to be heated up sig-g3,3 nificantly above their normal ambient tempe-gg/ Systern and component operation is considered ratures. The testing will oc in conformance z ; "g [ acceptable when observed and measured performance with ANSI /ASME OM7 as discussed in Subsection v 8,1 characteristics from the testing described above 3,9.2.1.2, and w!Il consist of a combination of ija meet the applicable design specifications, visual inspections and 1 peal and remote dis- @$g placement measuremetas.V' Visual inspections are 11.2.12.1.51 Expansion, Vibration and Dpamic performed to identlfy actual or potential { E *g EITects Preoperational Test constraints to free the mal growth, Displace-MEE ment measurement; will be made utilizing gd (1) Purpose specially installed instrumentations and also ggg using the position of supports such as To serify that critical components and piping snubbers. Rest its of the thermal expansisu $ =g, runs are properly designed and supported such testing are acceptable when all systems mose as p '5 g c: j that expected steady state and transient vi-predicted and :here are no observed restraints $j6 bration and movement due to thermal expansion to free thermal growth or when additional $f[ Joes not result in excessive stress or fa-analysis shows that any unexpected results will
- E.4 g tigue to safety related plant systems aud not produce unacceptable stress values.
equipment. /; Vibration testing will be performed on system (2) Prerequisites components and piping during preoperational function and flow testing. This testing will Le A!! piping and components and their associal-in accordance with ANSI /ASME.OM3 as discussed in ed supports and restraints have been inspect-Subsection 3.9.2.1.1 and will include visual ed and determined to be installed per de-observation and local and remote monitioring in sign. Additionally, support devices such as critical steady state operating modes and during snubbers and spring cans have been verified transiccts such as pump starts and stops, valve to be in their expected cold, static posi-stroking, and significant proccu flow changes. Lions and temporary restraiaing devices such Results are acceptable when visual observations as hanger locking pins hase been observed to show no signs of excessive vibration and when be removed. measured vibration amplitudes are within A-eMment 16 14 2 C i .m m m. m_ m w
JUN 01 '92 07:03At1 G E NUCLEAR ELDG J P. F G i ' C '_ ABWR mmc 4s l i St an_dard Plant-- uv a y.o e Sas@* [p 14.2.12.1.52 Reactor Vessel Flow induced program. Vibration Preoperational Test 3f j (3) GeneralTest Methods and Acceptance Criteria l $2-0 ( ) Purpose 3 j }L g Ii [ The reactor xternals vibration assessment t; j To collect information needed to verify the program cowsts of three parts: a vibra-adequacy of the reactor internals design, tion analysis program, a vibration measure-7 j } $ ; i manufacture, and assembly with respect to the ment program, and an inspection program. ye j.Q*2jy potential effects of flow induced vibration. The vibration analysis portion is pertormed W \\ Instrumectation of cuajor components and the on the final design, prior to the preopera-4g.h2 a<k flow tests and inspections will provide assur. tional test, and the results are used to I DT! anee that excessise vibration amplitudes, if develop t! e measurement and inspection $hg they exist, will be detected at the earliest portions of the program. The preoperational I possible time. The data collected will also test therefore consists of an instrumented 33 n S h 1: help establish the margin to safety associa-flow test and pre and post test inspections @j}aj j [g ted with steady state and anticipted tran. as described in the following paragraphs:
- 3,[I sient conditions and will help confirm the pretest analytical vibration calculations.
(a) Pre flow Vessellnspection f3p$] S SS This testing will fulfill the preoperational y{$FS require cents of Regulatory Guide 1.20 for a The preflow inspection is performed pri. 93jjj dbration measurement and inspection program marily to establish and document the f' for prototype reactor mternals, status of vessel internal structures and / components. Some of the inspection re-(2) Prerequisnes SM quirements may be met.by normal visual fabrication inspections. The majority The initiap ration ar.al esis com utations of the inspection requirements will be and sppgification of acc eptance riteria met by visual and remote observations of l h be complete. These results thrfd be the installed reactor internals in a uulaud to define final ins ection and mea-flushed and drained vessel. The fol-surement programs. Preop ational testing of lowing types of structures and compo-l the recirculation systern be suffi-nents AewM be included in the vessel ciently complete to ensure safe operation of nals inspection program: the reactor internal pumps at rated volumet-sJ ric flow for th? duration of the scheduled (1) m'ajor load bearing elements flow testing. This includes all required aux-including lateral, vertical and tor-iliary systems. All reactor vessel compo-sional supports; { nents and structure therm be installed and secur~ esignea in expectation of being (2) locking and bolting components whose jected to rated volumetric core flow. failure could adversely affect 3 This includes the steam separator assembly structural integrity; and reactor vessel head but excludes the (_ _ _ ' steam dryer. Also, during the flow resting, (3) known or potential contact surfaces; the control blades shall either be removed or be fully withdrawn and motion inhibited. The (4) critical locations as identified by assembly and disassembly of vessel internals the vibration analysis program; and l ah**M be choreographed such that structures and components requiring inspection are ac-($) interior surfaces for evidence of cessible at the proper times. The required lome parts or foreign material. sensors shall be installed and calibrated prior to the flow testing. All other sys-(b) Flow testmg i tems, components, and structures shall bc ) available, as required, to support the reac-The preoperational flow test will be tor sessel internals vibration assessment performed at rated volumetric core flow Amnomm is 920 FT'" 400-;O$ {)? f-P!-1. 09 [5 A?t r ' f:
nn 01 '9'2 07:09AM G.E tt> CLEAR BLDG J P.16/29 L ABWR . mums Standard Plant sn (a) proper operation ofinstrumentation and 14.2.12.1.54 Condensate Cleanup System equipment in all combinations of logic and Preoperational Test i instrument channel trip; (1) Purpose (b) proper functioning ofinstrumentation and j alarms used to monitor system operation To verify proper operation of the condensate i and availability; filters and dcmineralizers and the afsociated j support facilities. (c) proper operation of system salves, including timing. under expected operating. (2) Prerequisites conditions; j The construction tests have been succes'. ally l' (d) proper operation of pumps and motors in completed and the SCG has reviewed the test all design operating modes; pt: : dure and has approsed the initiation o' s h ah, ; testing. The condensate system Mte (c) acceptable pump NPSH under the most operational with an established flow path j limiting design How conditions; capable of supporting full condensate filter and demineralizer flow. Adequate supplies of ion j (f) proper system flow paths and Dow rates exchange resin should be available and the including pump capacity and discharge radwaste system be capable of bead; processing the expected qu les of water and i spent resins. Other requir d interfacing l (g) proper pump motor start sequence and systems eWiso be_availabl ' as needed, to g i margm to actuation of protectne desices; support the spe'esfied testmg. -- shall l (h) proper operation of interlocks and (3) GeneralTest Methods an ccep ce riteria equipment protective devices in pump, motor, and salve controls: Performance be obsersed and recorded during a series of individual component and (i) proper operation of permissive, prohibit, integrated system tests to demonstrate the and bypass functions; following: (j) proper system operation while powered (a) proper operation cfinstrumentation and from primary and alternate sources,- equipment in all combinations of logie and.. including transfers,'and in degraded modes instrument channeltrip; for which system components are expected to remain operational; (b) proper functioning ofinstrumentation and alarms used to monitor system operation (k) acceptability of pump / motor vibration and statt.s; levels and system piping movements during both transient and steady state operation;- (c) proper operation of system valvet, and ~ including timing, under expected operating condi: ions; (1) proper operation of controllers for pump (d) proper indisidual vessel and overall system drivers and flow control valves including those in minimum flow recirculation lines. flow rates and pressure drops including bypass espabilities (for both filter and System operation is considered acceptable whet. - dea.'iaer-E~ aaits); the observed / measured performance characteristics, from the testing described above, meet the - (e) proper operat:on of interlocks and applicable design speci5 cations, equipment protecti&c devices. 1$ W I Amenemni is - 9 t Mt Ln:-GTc?Wan .c nk nd Loi e - as aeb
JLil 01 '92 07: 10AM G E NUCLEAR BLDG J P.17/28 ' ' ABWR uwus Standard Plant ma generator hydrogen system and its associated during a series of individual component seal oil and cooling systems); and integrated systec tests to demonstrate the following: (e) proper operation of interlocks and equipment prctective devices in the various generator and (a) proper operation of instrutmentation and ausliary system controls; equipment in all combinations of logic, l (f) proper operation of pumissive, prchibit, and (b) proper functiomng ofinstrurnentation and 1 bypass functions; alarms used to monitor system operation and availabi!ity; l (g) proper operation while powered from primary and any alternate sources, including transfers, (c) proper operation of system salses, and in degraded modes for which the system, including timing. under expected operattag subsystem or component is expected to remain conditions; operational; (d) proper system flow paths and Gow rates j(h) proper generator alignment, including both into and out of ti-primary acceptability of clearance and v bration levels,if containment; possible, during both tra:tsient and steady state operation; (c) proper operation of interlocks and equipment protective desices in valse and System operation is considered acceptable when recombiner skid controls; the observed / measured performance characteristics, from the testing described above, meet the (f) proper operation of permissive, prohibit, applicable design specifications (while accounting for and bypass functicas; and the testing limitations imposed). (g) proper system operation wnile powered 14.2.12.1.72 Flammability Control System from primary and alternate sources. Preoperational Test including transfers, and in degraded modes 1, for which the system is expected to remain (1) Purpose operational. To serify the ability of the flamraability control System operation is considered acceptable when system (FCS) to recombine hydrogen and the observed / measured performance characteristics. oxygen and therefore maintain the specified from the testing described above, nsect the inert atmosphere in the primary containment applicable design specifications. during long term post accident conditions. 14.2.12.1.73 Loose Parts Monitoring System (2) Prerequisites Preoperational Test The construction tests have been successfully (1) Purpose completed and the SCG has resiewed the test procedure and has approved the initiation of To verify proper functioning of loose parts testing. The wetwell and drywell airspace g monitoring equipment. ,l regions of the primary containment thetrid intact, and all other required interfaces (2) Prerequisites available, 9 needed, to support the specified testing. The construun a a have been successfully. completed and the SCG has reviewed the test (3) General Test Methods and Acceptance Criteria procedure and has approved the initiation of 3 testing. Reactor internals shall be in place with { Performance shf be observed and recorded all system sensors connected. Skl Amendecet 15 N 14J IJ FEri 4'c-92E1?2' ie-c'-1 W C A 'l Fl'
? JUN 01 '9?' 07:10Ft1 G E ffJCLEAR BLDG J P.18/28 .s-ABWR uyiwo Standard Plant ng (3) Genen! Test Met 4 Acceptance Criteria System operation is considered acceptable when the $%u obsersed/ measured performance characteristics { Performance e observed and recorded meet the app'icable design specifications. during a series of systern and compoaent test to j demonstrate the folloung: 1 0.12.1.75 Liquid and Solid Radwnste Systems Preoperational Tests j (a) proper operation of instrumentation and l l alarms, and (1) Purpose j (b) the adequacy of alert level setpoints based To serify the proper ope ation of the various on preliminary data. equipment and processes which make up the liquid and solid radwaste systems. l System operation is considered acceptable when l the obsersed/ measured performance characteristics (2) Prerequisites j meet the applicable design specifications. The construction tests have been successfully 14.2.12.1.74 Seismic Monitoring System completed anc the SCG has reviewed the test j Preoperational Test r. -%;gnd has approsed the initiation of l 0g testing. Therenbeeki be access to appropriate (1) Purpose laboratory facilities and an acceptable efGuent discharge papew4d be established. To verify that the seismic monitoring system A ud.vm My, an adequate supply-of l will operate as designed in response to a deinineralized water, the necessary electrical j seismic esent, power, and other required interfacing systems shall be available. as needed, to support the (2) Prerequisites specified testieg. j The construction tests have been successfully-(3) GeneralTest Methods and Acceptance Criteria ( completed and the SCG has reviewed the test i procedure and has approved the initiation of The testing described below consists of that of l testing. The required electrical power.hweki the equipn;ent and procc5ses for ths. hand!ing. be available and ali system recording devices treatieg, storing, and preparation for the . $bedd have sufficient storage medium disposal or discharge of liquid and solid asallable teed m %c caoeded MW radwaste. Gaseous effluents are treated and l % hl+ $ cl.sedded. Shwil 6 released by the offgas system or the standby gas l(3) GeneralTest Methods and ptance Criteria treatmect systemithe testing of which is specifically described elsewnere. l Performance sheeld obserwd and recorded during a series of tests, as recommended by the er gid and solid radwaste systems manufacturer, to demonstrate the following: performanch sisound be observed and recor_ded during a series of individual component and - l (a) proper calibration and response of seismic integrate.d system tests to demonstrate _the - instrumentation including verification of following: alarm and initiation setpoints; (a) proper operation of equipment controls i [ (b) proper operation of internal calibration or and logic including prohibit and permissive i test features; interlocks; I (c) proper operation of teeording and (b) proper operation of equipment protective l pla,osek devices; and ' features and autornatic isolation functices including those for ventilation systems and l (d) proper integrated system response to a. _ liquid effluent patnways; j simulated seismic event. 1 l Arnendrnent t5 N : u 14 u,,., - A Mw- .b
] JUN 01 '92 07:1 W1 G E tOCLEAR BLDG.T P.19/28 A.BM u4simas 1 Standard Plant gg orv n service water systems be operational If and other required interfacing systems 4etrid, component systems, and associate a criterion of this nature is not satisfied, the be available, as needed, to support the plant will be placed in a suitable hold specified testing, condition until resolution is obtained. Tests compatible with this bold condition may be l (3) GeneralTest Methods and Acceptance Criteria continued. Following resolution, applicable ghm tests may be repeated to verify that the re-Perforracncc be observed and recorded quirements of the criterion are ultimately 3 during a series of component and system tests satisfied. Other criteris may be associated to demonurate tbc following: with expectations relating to the performance of systems. If this type of criterion is not satis-(a) proper operation of instrumentation and fied, operating and testing plans would not nee. alarms used to monitor system operation essarily be altered. !!oweser, investigations of and status; the measurements and of the analytical tech-niques used for the predictions would be start-(b) proper operation of active cooling ed. Specific actions for dealing with criteria devices. if applicable, suc' as forced f ailures and other testing exceptions or or natural draft towers, spray ponds, anamolies will be described in the startup ad. etc.; and ministrative manual. (c) the adequacy of intake and discharge structures, including screens or strainers, or other interfaces with the circulating water system, such as freeze protection devices, as applicable. Operation is acceptable when the observed / measured performance chstacteristics meet the applicable design specifications. t4.2.12.2 General Discussion of Startup Tests Those tests proposed and expected to comprise the startup test phase are discussed in this sub-section. For each test a general description is provided 'or test purpose, test prerequisites, test description and test acceptance criteria, where applicable. Sinc '.Ja, tic ns, deletions, and changes to these discussions are expected to occur as the test program is developed and implemented, the descriptions remain pneral in scope. In de-scribing a test h w.e<er, an attempt is made to iden ify those operating and safety oriented characteristics of the plant which are being explored and evaluated. Where applic:bic, the relevent acceptance criteria for the test are discussed. Some of the criteria relate to the value of process variables assigned in the design or analysis of the plant, Amenement is to-u :6 -, -,. ~~,
JUN 01 '92 07:11AM G E NUCLEAR BLDG J P.20/28 ABWR u-Standard Plant nv n 14.2.12.2.12 Reactor Internals Vibration response characteristics of the recircul-acion now contrcl system are in ac:ordance (1) Purpose with design 'equirements for all applicable modes of com.nl across the span of expected To collect information needed te verify the operational conditions. adequacy of the desi n, manufa:ture, and E assembly of reactoe vessel internals with (2) Prerequisites respect to the potential affects of flow induced sibration. The preoperational tests have been completed and plant managernent has reviewed the test (2) Prerequisite procedure and has approved the initiation of testing. For each scheduled testing itera-The applicable preoperational phase testing tion the plant shall be ii the appropriate is complete, including the required inspec-operational configuration with all specified tions, and plant management has reviewed the prerequisite testing complete. This in. test procedure and has approved the initia-cludes preliminary adjustment and optimiza-tion of testing. For each scheduled testing tion of control system components, as appro-l iteration the plant shall be in the appro-priate. priate operational configuration with all specified prereqwite testing complete. The (3) Description l necessary special instrutnentatio. 4.wM be 4 T calibrated and operational. Startup phase testing of the recirculation M flow control system is intended to demon-
- 0) Description strate that the overall response and stabii-ity of the system meets design requirements Reactor internal vibration testing subse-subsequent to controller optimization. Per-quent to fuel loading is tnerely an extension fortmance shall be demonstrated at a suffi.
of the program described during the preope-cient number of power and flow points to rational phase in Subsection 14.2.12.1.52. bound the expected system operational cond. - ation measurement portion of that itions including applicable toodes of controt l 's pregram dd h expanded during the power (speed, flow and automatic load following) i ascension phase to include intermediate and for each such demonstration. Testing will critical power and flow conditions during be accomplished by manual manipulation of steady state operation and anticipated controllers and/or by direct input of demand operational transients that are expected to changes at various levels of conta cl. resitlt in limiting or significant levels of Specirl control features such as those u:,co l reactor internals vibration over and above to maintain a specified margin to the high what was observed during the preoperational flux scram setpoint or to avoid regions of phase. + potential core instability should also be demonstrated as appropriate. (4) Criteria (4) Cr:teria Criteria for limits on reactor internals l. vibration levels are developed during the Above all else, system performance shall be vibration analysis portion of the assessment stable such that any type of divergent program as described in Subsection i response is avoided. The response should 14.2.12.1.52. also be sufficiently f ast but with any oscillatory mp e reyonse well damped. r 14.1 12.2.13 Recirculation F1 w Control usually with decay ratios less than.25. The overall response of the system, at all (1) Purpose levels of control, should be within design requirements with respect to such standard To demonstra that the stability and control system criteria as response time, C - ~ ,.m ~ " w s The extent to wh'ch reactor inte'nals vtrat;on test o is conducted \\ during the power ascension phase is dopendent on the cl.ssihcation of i g4 yn Araend nent is the reactor Internal $ SS prototype Of not in 00cordance w!M Regulatory Guide 1.20 as discussed in sections 3.9.2.4 a4 3.9.7.1. j - _ ~ - nn v%m:w ve r - n u-a a m
r- ^ ~- JUN 01 'o2 07 12AM G E TOCLEAR BLDG J P.21/28 '~ M N nA6tr.e; Standard Plant m 94 rise time, overshoot, and settling time. nonlinearities or dissimilarities in syste l Also, the overall system performance should response at various conditions 4+e+dilso be in accordance with expectations for be detnonstrated. The above resting will l anticipated transients, also serve to demonstrate overall core i stability to subcooling changes; j 14.2.12.2.14 Feedwater Control (4) Criteria (1) Purpose l Above all else the feedwater control system j l To demonstrate that the stability and performance shall be stable such that any response characteristics of the feedwater type of divergent response is avoided The control system are in accordance with design response should be sufficiently fast but requirenscuts for applicable system configura-with any oscillatory modes of response well { tions and operational conditions, damped, usually with decay ratios less than l 0.2L - Additionally, the open loop response l-(2) Prerequisites of the system should meet design require-ments with respect to such standard control The preoperational tests are complete and system criteria as response time, rise time, J ..... management has reviewed the test overshoot, and settling tirne. Also, the procedure and has approved the initiation of overall system response should be as expect-t e s tin g. For each scheduled testing ed following major plant transients and I l it e r a tio n the plant shall be in the trips. l appropriate operational confi uration with 6 l all specified prerequisite testing complete, 14.2.12.2.15_ Pressere Centrol l This includes preliminary adjustments and l optimization of control system components, as (1) Purpose appropriate. j l To demonstrate that the stability and i (3) Description response characteristics of the pressure regulation system are in accordance with the 3 i Startup phase testig of the feedwater design requirements for all modes of control j control system is intended to demonstrate under expceted operating conditions. that the overall tesponse and stability of j the system tacets design requirements sub. (2) Prerequisites sequent to controller optimization. Testing i will begin during plant heatup'for any The preoperational tests have been completed feedwater or condensate flow rates and will 4 [3 procedure and has appro special configurations designed for very low [ and plant management has reviewed the test i mh J For each scheduled testing itera-9 thr ugh the normal full powersiseeM include all snodes of E [-testing. l Mr control any encompass eH4xpected -d ) tion the plant shall be in the appropriate line up. Testin operational configuration with all specified i i plant puwer levels and operational condi 4 prerequisite testing complete. ;This in-t tions. Testing will be accomplished by man-cludes preliminary adjustment and optimiza-ual manipulation of controllers and/or by tion of control system components, as appro-i direct input of demand changes at various
- priate, j_
g levels of control. System response sheid ' QM-- also be evaluated under transient operatica-(3) Descriptm al conditions such as an unexpected loss of a 4 feedwater pump or a rapid reduction in core Startup phase testing of the pressure con-j_ flow arid /or power level and after plant trips trol system is intended to demonstrate that 1 such as turbine trip or main steam line-the overall response and stability of the isolation. Proper setup of control system system meets design requirements, subsequent . components or features designed to handle the to control system optimization. Performance Amcedent 18 l ..-.._.?RMJN~U%'3L..~.._._,..-- _~. &CL:?1. R Z N L..,J L _._,
JUN 01 '92 07112AM G E NUCLEAR BLDG J P.22/28 INNN 23A6100AN ,, Standard Plant _ p3.. testing. For each scheduled testing itera-(3) Description tion the plant shall be in the appropriate operational configuration with au prerequi. Startup phase testing of the RHR system is site testing complete. Applicable instrumen-intended to demonstrate the capabilities of tation shall be checked or calibrated as is the system beyond what was possible dutieg appropriate. the preoperational phase due to insufficient temperature and pressure conditions, Pert-(3) Descr:ption inent system parameters will be monitored in the suppression pool coeling sod shutdown Pertinent estem parameters, such as tempera-cooling modes to verify that overall system tures, pressures, and flows, will be e oni-operation and beat remo"al capabilities are tored at various steam flow rates in ort.cr to in accordance with design requirements. An demonstrate that system operation is in ac-attempl &;M be made to obtain results y cordance with design. The steam flow measur g with flow rates and temperatures near pro-ing devices that provide input to feedwate cess diagram values. However,'due to the k control and/or leak detection Ic.;ie e relatively low core exposures and decay beat cresschecked to verify the accuracy of design loads expected during the startup progran, cuibration.ssumptions. If appropriate, the MsM4<1 be taken such that the limit on { pressure drop developed ae oss critical ecmpo-vessel cocidown rate is not exceeded, j 76rbrfd be compared with design salues. M/ The quality of the steam leasing the reactor (4) Criteria l Aa+4d also be determined to be within design requiraments (if not predously tested). System performance, especially beat removal capability, shall meet safety analysis re-(4) Criteria quirements. Additionally, measured para-meters should indicate that overall system When applicable, measured parameters shall performance is consistent with design expec-compare consersatively with safety analysis tations. design assumptions. Additions lly, test data should demonstrate that system steady state 14.2.12.2.21 Reactor Water Cleanup System and transient performance nicets design Performance requirements. (1) Purpose 14.2.12.2.2r Residual Heat Remosal Sptem Performai.ce To verify that reactor water cleanup system performance, in all modes of operation, is (1) Purpose in accordance with design requirements at j rated reactor temperature and pressore cond-To verify that residual heat removal system itions-performance is in accordance with design for actual plant operating conditions. (2) Prerequisites (2) Prcr qutsites The preoperational testing :s complete and plant management has resiewed the test pro-The picoperational testing is complete and cedure and has approved the initiation of phnt management has reviewed the test pro-testing. For each scheduled testing itera-cedure and has approved the initiation of tion the plaut shall be in the appropriate testing. For each scheduled testing iter. operational coefiguration with the specified atica the plant shall be in the appropriate prerequisit t u; mph lestrumeta-operational configuration with all specified tion has been checked or calibrated as prerequisite testing complete. Instrumenta-appropriate. tion has been checked or calibrated as appropriate. O) Description AmcumcN 2 14.56 n en & mm_ __ _ omm _m_ a _ _ n__
I~ JUN 01 '92 07:134'1 G-E NUCLEAR BLDG J P.23/29 a ..AB M u sstoe m Standard Plant Rrv n w,tl actor at a moderate power lesel and with the luated consistent with technical specifica-turbine generator on line, the operabihty of tion and safety analysis requirements. If the control, stop, and bypass valvgs_will be appropriate, it is also desirable to deter-y demonstrated. This testing Md'Ye similar mine the maximum power level at which such to the individual valve testing required by tests can safely be performed by observing the technical specification surseillance pro, plant response during such tests at gram la addition to valve operability the successively nigher power levels. In overall plant response wiil be observed. addition, at rated temperature and pressure. Sin:e turbine valve testing is re.;uired rou-proper functioning and stroke timing of i tinely during power operation. it is a!so de-branch steamline isolation valses (e.g. on sirable to determine the maximum power level common drain line) will be demonstrated. at which such tests can safely be performed by observing plant respcase during such tests (4) Criteria at successively higher power levels. MSIV closure times shall be within the li-(4) Criteria mits required by plant technical specifi. cations and those assumed in the ::laut safe. All turbine valves sha!! operate properly and ty analysis. Overall valve performance in accordance with applicable technical should be in accordance with design require-specification requirements. Valve perfor-m e n t s. During higher power level tests mance anc plant response should be consistent mini.num plant trip avoidance margies should with design requirements. During high power be maintained. testing, minimum trip avoidance margins should be mahtained. 14.2.12.2.27 SRV Performance 14.2.12.2.26 MSIV Performance (1) Purpose i (1) Purpose To demonstrate that each safety / relief valve can be opened and closed properly in the To demonstrate proper operation of and to relief mode during reactor power operation, verify closure times for main steamline iso-lation salves, including branch steamline (2) Prerequisites irolation valves, during power operation. The preoperational tests are complete and (2) Prerequisites plant management has reviewed the test pro-cedure(s) and has approved the initiation of The preoperational tests are complete and testing. For each scheduled testing itera-plant management has reviewed the test tion, the plant shall be in the appropriate procedure (s) and has approved the initiation operational configuration with tbc specified of testing. For each scheduled testing prerequisite testing complete. All applic. Iteration, the plant shall be in the appro-able instrumentation shall be checked or priate opera:ional configuration with the calibrated as is appropriate. specified prerequisite testing complete. All applicable instrumentation shall be checked (3) Description, or calibrated as is oppropriate. A functional test of each SRV shall be made (3) Description as early in the power ascension as is practicable based uc. he valve manufat. At rated temperature and pressure, and then turer's recommendations. This is normally again at an intermediate power level, each the first time the plant reaches rated MSIV will be individua'ly stroked in the fast temperature and pressure. Opening and closure mode. Valve operability and closure closing of each valve, as well as evidence time will be verified and overall plant re-of steam now, will be serified by response sponse observed. Closure times will be eva. of SRV discharge tailpipe sensors and by observcd changes in steamflow in the main Ameridment 18 14237 .F
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JUN 01 '92 07:13AM G E NJCLEAR BLDG J P.24/28 ABWR m Sunbrd Plant N~ py G a. for th esent, shall function as designed in reactor trip erk also be, rifie d Os e r-accordance with technical specificatic n and speed of the main turbine avH also be safety analysis requirements. All other evaluated since the gene.ator is unloaded sy,7ms and equipment should perform consis-prior to complete shutoff of steam to the tent with anolicable design and testing turbine. s p e cific a tio n s. For a turbine trip, the generator remains 11112.2.2.4 Turbine Trip and Generator loaded and there is no ov:rspeed. However, Load Rejection the dynamic response of the reactor may be different if the steam shutoff rate is (1) Purpose different. If there is expected to be a sig nifii. ant dif fe re nce, then it may be To v:% that the dyramic response of the necessary to pertorm a sep, irate demonstra-reacto, and apphcable systems and equipment tion and evaluation, similar to that is in accordance with design for protective discussed above, but initiated by a direct trips of :he turbine and generator during trip of the main turbine. power operation. A turbine or generator trip should also be (2) Prerequisites performed at an initial power level that is below that where a direct reactor trip is The preoperational tests are complete and actuated and within the capacity of the plant management has resiewed the test pro-bypass valves. Reactor dynamic response is cedure and has appresed the initiation of not as impcrtant for this transient etempt testing The plant uall be in the appro-for the ability to remain operating as priate operational configuration with all designed. More important is the demonstra-specified prerequisite testing complete. All tion of proper integrated plant and system applicable instrumentation shall be checked performance, or calibrated as is appropriate. (1) Criteria p) Description The reactor shall not scram during turbine From an initial power level neas rated, the or generator trips initiated from pow er main generator will be tripped in order to levels within the capacity of the bypass verify the proper reactor and integrated valves and below the point at which the g,3 '_ pl a nt _ rgsponse. The method for initiating direct scram trip on turbine stop valse l the trip trherH be chosen so that the turbine closure or control valve fast closure is is subjected to maximum overspeed potentialg enabled. For high power turbine or l Reactor parameters such as vessel dome pres-generator trips, re - r dynamic response sure and simulated fuel surface h at flux should be consi tent with predictions H will be monitored and compared with predic-based on expected system characteristics and tions so that the adequacy and conservatism shall be conservative relative to safety of the analytical models and assumptions used analysis results based on design to license the plant can be verified. Proper assumptions. Of particular importance are response of systems and equipment such as the vessel dome pressure and simulated fuel ~ turbine stop, control, and bypass valves, surf ace heat flux. Safety related and main steam relief vahes, the reactor protec-essential equipment and systems shall tion system, and the feedwater and recircula-respond, as applicable, consistent with tion sy3tcms will also be demonstrated. The t e chnicalppe cifica, a and safety analysis core flow coastdown characteristics should be requirfbm ^ her phe wste:rs and il evaluated upon actuation of the recirculation equipment sh,ki perform in accordance with pump trip logic. The ability of the feed-the appt g riate design and testing (( water system to control vessel level after a s p e cific a tio ns. w m. ..provided there are expected to be relevant d,fferencos amongst the options ava4ble. t:20 3 + FPh 40E-9251 6*? PF 1-9 ^9 ~e AM i24
JUN 01 '92 07t i-W1 G E I4LCLEAR BLDG J P.25/28 ABWR uoms. $18J1.d21d.EQ111_ RFV 9 h 14.2.13 krterfrets COL Licede.'I~4*r M on The preceding discussion of preoperational and startup tests were limited to those systems and compocents s.ithin. or directly related to, the ABWR Standard Plant. Other testing, with respect to site specific aspects of the plant will be ll ceca.ssary to satisfy certain ABWR in@Yrface g r e q uir e mfq3s. Testing of such systems and [l components whetM be adequate to demonstrate conformance to such requirements as defined throughout the specific chapters of the SSAR. .;clow are systems that may require such testing: (1) eleetrical switchyard and equipment; L l . the site security plan; I (3) personnel monitors and radiation survey instruments; and (4) the automatic dispatcher control system (if applicable). f l Also to be sup.(plied by the aglican' referencing the ABWR design is the sti. tup administration manual described ir. Section 14.2.4, which will describe, among other things, what specific permissions are required for the approval of test results and the permission to proceed to the c. ext testing plateau. 9 <3 Q c.aCu,meaA h b] i Ament cnt 15 14 W _ _ __ n m. m.n u n r___ _ __ _ ____ _________ r,_ n :.m _1 : on-u 2u. _ r r_ _
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