ML20090J979

Forwards Responses to Resolution of Issues Related to Advanced BWR Draft SER Chapters 1,2,3,5,6,9,10,12,13,14 & 15 (SECY-91-355)

ML20090J979
Person / Time
Site:	05000605
Issue date:	03/11/1992
From:	Recasha Mitchell GENERAL ELECTRIC CO.
To:	Pierson R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
EEN-9235, MFN-060-92, MFN-60-92, NUDOCS 9203180156
Download: ML20090J979 (177)

Text

{{#Wiki_filter:. L bt tim irm Im m I htarch n,1992 htFN No. 000 92 Ihwket No. STN 50-605 EEN 9235 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Itobert C. Pierson, Director Standardization and Non l'ower Reactor Project Directorate Subject Gl: Responses 6 the ltesolution of Issues llelated to AllWit 1)SI:R Chapters 1,2,3,5,6,9,10,12,13,14 & 15 (SI:C%9l 355)

Reference:

GE Responses to the Resolution of issues itelated to AllWit DSER Chapters 1,2,3,5,6.8,9,10,12,13,14 & 15 (SECY 91355) (Proptietary information), htFH No. 06192 dated March 11,1992 '1 ~ Enclosed are thirty-four (34) copies of the Gli responses to the subject issues. Responses to issues pertaining to Sections 9.3,9.5 and 11.2 contain information that is designated as General Electric Company proprietary information. These responses are being submitted under separate cover (Reference). It is intended that Gli will amend the SSAR, where appropriate, with these responses in a future amendment. Sincerely, Q.C.v % LcA a.9 S R.C. hiitchell, Acting Manager Regulatory and Analysis Services h1C-444, (408)925-6948 cc-F. A. Ross (DOE) N. D. Fletcher (DOE) C. Po:.lusny, Jr. (NRC) R. G. Ramirez (NRC) l R. C. Berglund (GE) D J. F, Quirk (GE) L e 3 p e, -v se .A. 9203180156 920311 fI PDR ADOCK 05000605 A PDR

_ _ -. ~ - l AT1ACHMLNT A 4 hESTONLL TO OUTS 1ANb1NG ISSUES (2) ThHOUGH (13) ISSUES (2) AND (3): [1.p d e 1 inIL_P.L AEW3_Co_nis_11Lme n t D LY v e I l V o l u m e E pnd ADWR (ontainment (psign TesTino(0.i.1.Q.1) Au noted in our August 9, 1991 telephone conversation with the e t a11, Abkh dryvell-to-vetvell vent configuration as considered to be sim11at t o the Mark III horizontal vent system. In AbWR, vertical ventE total area is representative of vent annulus area in Mark Ill; borarontal vent length se consistent with that in Mark III; and hor 2:ontal vente and vertical vents total area ratio is comparable vith that in Mark III. ABWR containment configuration, however, differ from Mark III design an some areat, which ares i u. Eign112 cant prescura stion of the Wetvell (WW) airspace during LOCA blevdown, -b. the precence of 6 lower dryvell (L/D), c. the cmaller number of horacontal vents (30 in AbWR vc 120 in Mark III), d. extensacts of horizontal vente into the suppress 2on pool, e. Jarger suppression pool v2dth (24.6 ft 2n APWR vs 20.5 2n Mark 331: AEWK containment precsure and t err,per a t u r e tr anc2 ent fo11oving a l o r..s - o f - c o o l a n t acc2 dent (LOCA) ver calculated using approvea unnaytacal methods (described an NI sO4.0%3 ) which are adequate for a LOC /s. ( modeling and analy:Ing ABWR containment response following Modejang scherre to account for the presence of L/D (ABWR un2que -leature) ic deccribed an deta21 on page 6.2-6 in Amendment 3. WW a2 rq ace reeponse durang pool swell phase of LOCA was determined using appr oved analytical methods (described in HEDE-21544-Fs, since the t,e t hvd1 oced in NEDO 20533 do not model and actount for rapid pool accelerutton aurang the pool uwell phace. Wath regard to-LOCA condensation oscillation (CO) and chugging (CH) Joedc dusing the steam blowdown phase of LOCA, it van antic 1 pated that, becauce of ABWh unique features (as noted above), it vac antacapated that thece loads Ior ABWR plant might differ irom pr2or (Mark IIJ) testing in herizontal-vent facilataec.. Consequently, a test p2ogram was conducted to confirm the CO and CH loading conditions-which could occur in the event of a LOCA in an ABVR plant. Thia test pr ogr am at descr ibed in detall in Appendix 3B. -f In all, a total of.24 tests which bounded ABWR LOCA blevdown' .conditionc were conducted in tect facility representing 1 one-cell (36") sector of the horizontal vent in ABWR design, which included a single vertical / horizontal vent module. ABWR CO and CH prescuze load 1ng cor datione vere. developed _ based on. data f rom these tests, and ther.e loading condationc vere conservatively speecified for application r over the full (360") configuration of the ABWR tacility. The AbWh CO Jeading specification implied all vents having CD in phase. The ADWR { CH loading cpecification defined two load casea: 1) all vents chugging x 2n phase, and 11) vente Jn one half 160" out of phase with the other j~ half vents (this loading condition conservatively boundE the condation l. of~ vents chugging out of phase). l lI ~.~. . - ~

? 1 J ( l J i I i ISSUE (4): [1Lyyz) 1 Duu_trgy r 1 r o t inrufJ.1. L.12 3 i ww/DW vacuum breaker (VD) system an ABWR containment design ut ill:e c. In all, eight 20 in vacuurn breaker valves, which includen ene valve for singJe failure (valve fall to open) c 41 t er i ori. These I j v 1 v et. to r e aritended to be sving check type valves which open pascively j due to negative differential pressuse (WW airspace greater than the DW preccur e) across the valve disk, and require no external power to l actuate them. Vb v61ves are inctalled horizontally locatitig in WW airspace. One valve per penetratson (through pedestal wall) opening anto L<D. Position locations of these valvec, both axially anJ l a :l tr u t h ul l y, are shown in Figurec 1,2-3C and 1.2-13K in CSAR, l A twrid me nt 6. Attached Fleure 6.2.1.5.1-a shows a typ2 col swing check type valve. t hesponce to

• performance demonstration recultc' will be provided by

{ lbrch si, 1997.. t ISSUE (b)t [v11;t e c a a p r Foo1 Shv loada ria Tect n ( 6. ;.1. 6 s l im n o t. e d tri Appendix 3D, ChV qvenches diccharge loade foi the A D a'R f contoantwnt will be d e v el o p e. d baced ori t he same calculatiori methodology as that used for pi l or tie r k 11/111 c o n t a i n tn e n t e. Oslor l bVh tasta have chown that ShV dischargO loads are strongly dependt.nt upon the EhV d a r.,c h a r g e line dischstge desace, and the y. quenches daccharge device used in the ADWh cont a s time n t dec1gn ar, e.ame a t: that i uced in t'. a t h II/111 d e c 1 g n t>. 30 developing and defining ShV uctustion

loadc, t.e t h first und r, u b s e q u e n t ShV actuation Lvalvec re-opening a cseend 11 *ne ) will tJ e conLideted.

F u r

• n.e 4, at noted i t.

Append 1>. 3b. recent ctudies (perfezmed by GE l in bWh Uvm r s Gr oup) have corcluded that supprescicn pool temperature . j a r,1 t s. (spe;1tled an NUREG-0783) accocaated with steady state ShV I otep alow ccacations are not-needed. Steam condensation loads with i quenches davcharge.devicer over the full r ein g e of pool temperature up tu saturattun are low c o rn p a r ed to loads due to CRV discharge line air clewing arid LOCAw wh2ch will be considered and defined for the AEWh 3 -enntoanment cec 1gn evaluatione. .hecultu and c o n c l u t.i o tic ' f z o n there JUCent Ciudies are deLCrabed and d1CCUShed in HEDO-30632. ClaEs le Decemter 1984 i

• Ell enir.a t ion of L A niit on BWh Suppreccion Fool i

Ternper at ure for ChV' Discharge With Quenchers), which is being reviewed i' by the staff. In view-of the cortcluulons from these recent studara, I t -- i c, n ~- believed that suppression pool t e rn pe r a t u r e 1 Drii t s [ '( NUhG

3) in analyr.ing steady ctate ShV steam flow conditions no Icnger apply, r

ISSUE-(6): bta for Snp r ecc l e n Fool Test Conditiono 46.2.1.6) i At t ac hed T a g ur es - 6, 2.1. 6-a - and 6, 2.1. 6-b cho w a comparison of vent { c le a ni maec flux vs pool temperature rise conditionc between-ABWh plurat ar d AbWh t.orizontal vent tects. t e yv v,w-v m oynne. _ ere -ev-- -ve.--u-.-==-f-- -=-

ISSUE (7): C J a r 2 i t c a i 1 o n ELA_nyLmM2 pur; _ (L 2,1. 6 ) i i Dr.l y one a c c u rnp t 2 on (i.e., effective pool eurface area equal t o 0. 6 l tines actual pool surface area), as unique to the ADWR dec1gn.- Other a s s u nip t a o n c as e consistent with those used in prior DWH analyseu. ISSUE (8): [BI_4facattpn of Met hods tised to Calculate Londo t v. c.1. 6 i l Ac described in Append 2x 3D, ABWh ShV actuation loads vill be de12 rie d based on approved Mark 11/311 enethodology using ABWR unique i ShV diccharge line par a niet er c. This methodolcgy is in the forit of etyazical corselationc involving physical parameterc cagn112 cant from pt.enomens point of view. With regard to LOCA Joads, CO and CH loads v.11 be defined bweed on ABWR horizonte;l vent tests, and A c a d a tig ccndaticos during pool swell phace vill be dete: mined ucing analytacal vo u d. 1 which Wdel and camulate pool swell procesc v2th pressuficing WW alaspace. ICSUE (9): /uct2Iication f o r B La h n a L ig n l Ue:encar y ccellt g 1 a vt; procedures to t r ancf or sa cubstale tect data -antc the loeds expected for the reprecentative ABWR con t aintnent donagn - wery de s eloped. Bated on a review of then available tett datu and analytical wor k on dif f erent ccaling procedures, at van dec2ded to a s;e L the tecting on a Much acaling approiach. With Mach r. aling, the- [ amplacit accumption has b ee r, enu d e that the t her inod y n c tn a c pr o por tieu ar.v.ciated v4th the ctean, condencat s on procece are tr o t e i tni e r t a n t than 9:=vatutsenal ef f ec ta,. Pseccure, crec212e enthalpy, vent c t e a n> velocity, temperature and all othei t he r enodyn u fa c pr oper t iec are r%1ntsined at f ull ecalt-valuer. ~ /: c tr o r d i n g l y, the LE tt.ntang vac performed in a lac 111ty wh2ch vac geometracally (all linear dinenuaons ccaled by a factor of

2. 5 )

t.* 2 a2 tv.the pretotypical AbWh decago, maintain 2ng full scale t h e 2 n,c d '. ri u n i c condit2ono. Thlu approach au baced on the bcl20f that condencation t he no rre n a at the vent exit are inaanly governed by the thorn:cdynanic prefertaer of the ljquad and vapor phaceu. In a,ccc r dance with thsc ecaling paocedure, measused pr ecsure amplitudec n i t-equal.to iull-ccule values at geometrically cam 2 Jar locatacoc wherenc measured frequencies are 2.5 timec higher than the corsecponding full-scale frequencies. Comparacon of test data f r e ra the AllWR scaled and f ull-scale horicontal vent tects exhibited n catacfactory confirmation of the scaling procedure used in des 49nang I and conducting SS tects foi developing CO loadc for the ADWh plar t design. Thus. this schling procedure vill make it posnable to une the I rneucured. EC data darectly for load definition purpose after the t2w l - . scale-as-compressed by a factor of 2. S. p ISSUE (10) . Add 2tlonal Mode 12na_Jysumptione t 6. 2.1. C. ) l-. e Ra ponte vill be provided by March 31, 1992. l-l. ISSUES (11)_.: Eu bc o rn p a r t me n t P escure Ana]verc t 6. 2.1, 7 ; Fellowing is the additional information requested by the ctuff. i i-L-. - -, _..-.-.:-. -. - - -....=.._- -. - -. - -. - - - -.. -.

... -. - -. -. - - - - -. -. _ _.. ~ 1 1 1. The tarte dependent maps ased eriergy relewee rates were I determined using cratacal flow homogeneous equilibriurn en od e l c, and wer e ramped to zero over the valve clocure time. Typical values used in analyzing a MSL break in steam tunnel ase s.hown in Figure 6.2.1.7-a. 2. The cubcompastment preocure unulyses were performed unang GE engineering computes pr ogram SCAM ( S u bc o m p a r t rnen t Analyc2c Method). S. No specific nedalizat3cn censitivaty studieu were performed. 4. Subcompartment 2nitial thermodynam2c conditionc were those correspond 2ng to plant n or tr a l operatang conditionc, at delaned an EEAR, Append 2x 2. ISSUE (12): pg(cor+ arty;td__b g g ure Ano).n is ( b E 1,,,2, hes. ; cnc e vill be prov2ded by herch 31, 1992. ISSUE (13): E,_1e a ro Ovraf.s ef S e Euqpreeston Tcol T.E E. i K E s Fron c t e a u, bypacc leakage point of view, ADWh containment conlaguratarr, 2 r, apparently, quate similar to the Mark II, c o re pa r ed to the Marh III decagn. In the AEWh de61go, the dryvell and vetwell sarq m-ue thyc.2cally separated by a laned diaphragm floor catsalar

t. o thet an Mark II, and the WW a2sspace volume to l>W volume ratio in AbWh 1: c o rr+ a r a b l e to that in Mark II.

I'u r ing the October '91 and.>ecember '91 meetings with the staff in San Jose, GE den:rlbed and explained the basire for specifyang a eteam Lypu.c leakage capability (A/K ) of 0.0L ft' for the ABWh dec29n. It vac also noted that the ABWR Technical Specifications will def i tie -and requare that maximum lebhape during periodic leakage rate teste chall be lesc than 10% of the dec1gn bypact capability, c o t:01 s t e n t with the.ShP requirements. It should be noted here that allowable cteam bypass leakage capability ( A / K ' ' ' ) for the Mark II des 29n i r. about D.03 1t, compared to 0.05 itv for the ABWR design. At ctaff'c request in the above meetings, GE has undertaken a tach 101 performing censitivity studies to evaluate AbWR bypass leakage capab212ty over a-full cpectrum of breakc (from small-to large). t Frimary-oblectavec of these censitivity studies will be to c on f a r r., that O. OL f t+ 12-not-at the high-point--of cliff, and evaluate feucability of 3.ch3eving leakage capability gr eater than 0.05 ft. ? Tt.ece cencativity ctudies are currently in progrece at GC. I 9 .,--my.---.y- -...-e--, m..,- -s p w,,,,pe,-.,,,,.,, mm,-.-.,--,..---.g., y -mw.,a,,,me-,--.,w,.m--- ,y., +-t-,-..n.....v.-,..

t% '\\j l laver f*oR M At1 UA A" 0AT'Cd +^ Alt CYLi>J Dgg l WITH Alt CPWAATao A T ~f~ s y' " ppp3eu ..4 y /' N

I i

- - * " ~ ~ ~ ..iN s i,h k. s j [ y N U d,,, s /

• Askev

'yg / St.Au we pouet.-t / O'IKET N ...=:= -T- / ~ W WRCT lON 4-A . p one o Swt w air c,H u. c g v4Lve.. T y Pi c At. F t G U R e (e. 2. t. S 8-O

. -.... ~. ~. -. - _. . - -. - ~ - - _ -... -.... -.. -. ~ -. _. - -. -. ~. .! iin O 3S = === Atwm PaE DICTION

==(>== 8ULL SC ALI PatDICTION 80m 3 82 5% L80st0 BRt AK gg l C 8ULL $C Att PatDiCTION FOR 2 iM IN $76 AW SAE Aa, n in _i 3 /% ~ } / \\ e j / \\ i0o ./ g G t *< N \\

to s

a s-rI asaa n s g I\\ E I \\ l] N 7 l g k \\[ gats E %) ses n I \\ l g ~ y gi 5 1 \\/\\ \\gi \\ A..ag g s s) s O '- s_ \\ \\ q ,0 \\ \\ ll l i ) x I It \\ s lll _ l llll a l \\ \\ ll 3 lil DOTTED AmtA DEN 0f t$ i l LAmCE M AS8 F LUX ' I l I P LUCTU Af TON Ili l'lli l 0 e of 10 20 30 40 to 60 0 i i f i 'C. 10 30 30 root TauPtm Atunt mitt Fiqogg 6,2,i,6.g : Comparison of Predicted Vent' Steam Mass Fluses Between ABWR and ruil-Scale Tests i LO ..-.- - -._._.-.~._. -.. - -... -. -.., _. -, -. - -

~ ,. ~ .. - -. ~,... -.. - _ ~ -..... -. - -. .....--~..s_..-.. t l 17% r n AtwR PRf DICTION Q.-. SUS $C alt PRE 01CTION 8OA 2 6 th LloviD $mt AK C Sv65CAtt pmEDICTION FDA 176 IN Llovt0 GRt AY 160 30 j 1M f\\ } ~ e / \\ n 3 i /- g 1 im a g g-

c es e

N \\ s !l .\\ e. l \\ \\Aswa f \\ a rg twLe f f k I \\ Vlg's s/g-l 75 I g-is g .\\- Nd \\ -\\ l -r O i \\- I \\ g \\/ \\ \\.- so 4ewa .o MSLO \\ \\ \\ 4 \\ l n t \\ s i I I' O 0 10~ 30 40 to -- 60 t I i

• C 16 30 30 POOL TEMPER ATURE RISE

' FIGURE; de.t. l.&.b : comparison of Predicted vent scesa Mass Fluxes between ABWR and Subscale Tests -v-4---, o .,e. ..,-.-y.- y--.

- -_~ O slo vae

e. 2

.7

• BREAK FLOW RATE VS, TIME STEAM TUNNEL: MAIN GTEAM LINE BREAK 20000 g

MPV: INVENTORY DEPLITION DME M4SS74OW I g 45: INVENTORY DEPLETION (SEC/ /'.PWSEC/ TILL 0.1 SECONDS g 2 15000 - l/ "j# a f A rp 7 40 w RPV: NORMAL PLOW AP5 mo T38: INVENTORY DEPLITION APs 7W0 H@10000 - [ / N.aJSKCONOS m mo RPV: CHOKED AT M51V 1so two I, 5' , TBS: CHOKED AT MSIV g30 go O 4 p' Tiu.s.s SECONDS LL \\ g 5000- \\ W RPV: NORMAL PLOW RPv: Ray siCE Tas: NoRuAL n.Ow Ts::tunsms niet TILL Q.8 SECONDS 0 0 2 4 6 8 Q TIME (SECONDS) ENTHALPY VS. TIME STEAM TUNNEL: MAIN STEAM LINE BREAK 1400 p 1200 cc d 1000 3 % 800 RME ENTWhof g (SEC) (BTU /LBM) 600 -Ax rmo J 1so rmo E 400 W 200 ~ 0 0 2 4 6 8 TIME (SECONDS)

ATTACHMENT B hEEPONSE TO OUTSTANDING ISSUE 17 - VALVE CLOSURE TIMES PORTION Atmospheric control system isolation valves T31-(F001, F002, F004; F006 and F009) are 22-inch diameter butterfly type with instrument air operated actuators which need only 90 degrees of travel to close. These isolation valves are normally closed because their main function supports containment purging and nitrogen anerting when the reactor is less than 15% power. Smaller air operated valves may be opened for short periods during reactor operation to lower primary containment pressure or add nitrogen to keep primary containment pressurized to prevent any air inleakage. These include T31- ( F005, F039, F040 and F041 ) all are 2-inch diameter globe _ type air op-rated laolation valves which close within S-seconds. T31-FGJ4 as a 10-inch diameter normally closed outboard air operated butterfly type Ipolation valve connected to the SGT5 and as opened in series with T31-F005. T31-F025 is a 16-inch diameter-normally closed butterfly type outboard 1selation valve opened only during lottial inerting of the primary containment when the reactor is belov 15% power. Opening / closing times of <30 seconds is planned for all except the 2-inch diameter Isolation va] ves. Flammao111ty control syctem isolation valves T49- ( F001, F002, -[ F006, and F007) are all normally closed 6-inch gate valves. These valves niay be individually actuated for tests during reactor operation. Two of the valves are air or nitrogen operated and two valves are motor operated. This system is not activated for dayc f ol lowing a LOCA and < 30 seconds opening / closing t2mes are

planned, g

l l . ~.

ATTACHMENT C C A RESPONSE TO OUTSTANDING ISSUE 16 Purge and vent valves are currently 12 censed with both inboard and outboard leolation valves located outside primary containment so they are not exposed tv the harsh environments of the wetvell and drywell and are accessable for inspection and testing during reactor operation. Criteria of BTP CSD 6-4 are addressed an Figure 6.2-39 and Subsecticn 6.2.5 as follows: 1. Radiological consequence analys2s for LOCA with the purge system initially open relates to Chapter 16 Section 3.6.3.2 Primary Containment Oxygen Concentrat2on. Purging through the ACS 22-inch purge isolation valves is perm 2tted only after reactor power is Jess than 157. and within 24-hours of reactor shutdown or startup. The potent 2a1 for LOCA at such low power levels 2s neglagable and site radiological limits do not exceed 10CFh100 lim 2ts. 2. Fenetrationc, piping, isolation valves and rupture discs ma2ntain the2r stru-tural 2ntegraty for all accident thermal hydra lac condat2ons, containment peak pressure and temperature limits with required-design margins. Periodic Type C leak rate teste of the above components will be conducted at the containment peak pressure. The design meets safety class 2 requ2rements and Seismic Category 1 limits. Isolat2on valves are sagnaled to close for LOCA asolation signals and fail close on loss of instrument air. Purge system 2 solation valves AO-F001, AD-F002. AO-F003. AO-F004 AO-F006, and AO-F025 are locked cluse whenever reactor is above 15% power. Purge exhaust isolat2on vaive AO-F005 is normally closed and is open only f or 90 huur s per year with SGTS operation for containment pressure control. . Add 2tions of natrogen to the primary containment during reactor operat2on are accomplished by opening isolation valves AO-F0039, AO-F0040 for the drywell and AO-F0039 and AD-F041 for the wetwell. 3. Drywell and wetwell purge penetrations have seismic c a t t-g o r y 1 debris screens. 4, ECCS systems with suction from the suppression pool are designed with primary containment at atmospheric pressure and without credit to NPSH for containment backpressure. 5. Case-by-case isolation valve maximum allowable leak rates l~ are based on valve size, type, containment peak pressure for Type C periodic tests ac required by the technical specifications. Test branch connections are provided. l -() 6. Purge system isolation valves AO-F005, AO-F040 and AD-F041 are opened for short periods during reactor operation for I containment pressure control. These valves are all 2-inch diameter and are capable of full closure in 5-seconds. l I t

l I ATTACHMENT D RESPONSE TO OUTSTANDING ISSUE 98 Capability is provided to obtain samples from the main condenser evacuation off gas, standby liquid control system tank, sunps inside containment, liquid radwaste system process lines, and liquid radwaste system collection and shinpling tanks. T re e guidelines in RG 1.21. RG 1.56, and ANSI N13,1969 shall be used except as nated. Farrive flow restrictorc are not provided in reactor water sam-pling 11nec to control the release of radioactive tna t e r i al s f r o ni a rupture of the sample line. These devacec become crud trapc ^ during normal operation and overly restrict sampling flow rate d u r 1 rig chutdowns when the reactor la at low pressure. Each reactor water sampling line is provided with two remotely operable icolation valves to limit reactor water loss from a capple 11ne rupture. The celsvac design and quality group clascification 'I the sam-plang 11nec ac in Subsection 9.3.7.1.1(1) and the last paragraph of Eutcectiot. 9. 3. 2. 6. e d

- ~ .... ~.. - -.--.=~ -.-_ .- -.~.-... - - - - -. - l ATTACHMENT E RESPONSE TO OUTSTANDING ISSUE 103 The staff is asking that GE supply a system operational description as well as design information for components used in the smoke removal mode of operation. The instructions to the operator are. *When a fire ic reported by the alarm system or a ro'ving operator, place the HVAC mode switch for the effected fire zone in the smoke removal mode switch for the affected fire zone in the smoke removal mode and dispatch the fire brigsde." The fire alarm system vill identify the affected fire zone and probably even the room in which the fire is located, The operator should have the information as to the rooms served by each HVAC system. A table listing the fire zoneu, room numbera and HVAC systems for each room in the reactos building is-attached to thic rewponse as an example of the information that - should be available to the operator. Similar table vill be . p2epared_for the other buildings as part cf the final design of the plant. The. requested desigt, information as in the HVAC section of the SSAR (Section 9. 4, see especially Table.9.4-4 for flow raten). O N sl ' O J f e 4 e em - e 4e-.- rre -< -e= --,+ w

j. . REACTOR BUILDINC FIRE ZONES AND llVAC SYSTEMS NORiiAL AIR SUPPLY / MEANS FJOlAUST OF ROOM FIRE C00LINC SMOKE NO. AREA SYSTEM REH0 VAL -110 F1100 NIIVAC 1 NHVAC 112 F1100 hTVAC 1 NINAC 116 F1100 ' NilVAC 1 NHVAC i 117 F1100 NHVAC-1 NHVAC 118 F1100 NHVAC 1 NHVAC 119 F1100 NHVAC 1 NHVAC 210 F1100 hTVAC 1 NHVAC 211 F1100.NHVAC 1 NHVAC 212 F1100 NHVAC 1 NHVAC 213 F1100 h%'AC 1 MWAC 214 F1100 NHVAC 1 NHVAC 215 F1100 NHVAC 1 N)(VAC 216 F1100 NHVAC+1 NHVAC 217 F1100 NiiVAC 1 NHVAC 218 F1100- NHVAC 1 N11VAC -219 F1100 NHVAC 1 'NHVAC 251 F1100 NilVAC 1 NHVAC 311 F1100 NHVAC 1 NHVAC 312 F1100. NHVAcel NHVAC 313 F1100 NHVAC 1 N1WAC 314 F1100 NHVAC+1 NiiVAC >p-318 F1100 NIWAC 1 N1!VAC lg 342 F1100 NHVAC 1 - N1WAC =- 343 F1100 NHVAC 1 NHVAC. 414 F1100 hTVAC 1 NIIVAC 518 F1100 NHVAC 1 NHVAC 121 F1200 NHVAC 2 NHVAC- -122 F1200 NiWAC 2 NHVAC-123 F1200 NHVAC 2 MiVAC 1241 F1200 mlVAC 2 NiiVAC 125 F1200 NINAC-2 ' MIVAC 126 F1200-NHVAC 2 NHVAC 129 F1200 NHVAC-2 NHVAC-133 F1200- NHVAC 2 NHVAC 134 F1200 MIVAC 2 - NHVAC

140 11200.

N1fVAC 2 NIIVAC 4 141 F1200 mWAC-2 NHVAC ' 142 F1200 - NINACL2 NHVAC l14'3 F1200' tNHVAC-2 NHVAC 144 F1200 NHVAC 2 MIVAC-146 F1200 NHVAC-2 .NHVAC _-147 F1200-NHVAC-2 - NI{VAC '148 F1200 NHVAC-2 NilVAC .149 F1200 NHVAC-2 NHVAC 220 F1200: NHVAC 2 NHVAC 221 F1200 mlVAC 2 MiVAC AU l

. -,.. ~,. -,. - - - - - -- ---- ~. _~..-. ---.. 1 i REACTOR BUILDINC FIRE ZONES AND HVAC SYSTF.HS 1[,v'y NORMAL ATR SUPPLY / HEANS E.XHAUST OF ROOH FIRE C00LINC SM0KE ) -N0; AREA SYSTEM REMOVAL 222 F1200 hTVAC 2 NHVAC 223 F1200 NHVAC 1 NHVAC - 224 F1200 NHVAC-2' NHVAC 225 F1200 hTVAC 2 NHVAC 233 F1200 hmVAC 2 NINAC 234 F1200 NHVAC 2 NINAC =241 F1200 NHVAC-2 NINAC 243 - F1200 hMVAC 2 NINAC 244 F1200. NHVAC 2' NHVAC 248 F1200 NHVAC 7 NHVAC 321-F1200 'NKVAC.2' . ENAC 323 F1200 NHVAC 2 NHVAC 324 F1200 NHVAC 2 NINAC 325 F1200 h3VAC-2 NINAC 327 F1200 MIVAC12 NHVAC. 344 F1200 NHVAC 2 NHVAC' 346 F1200- -NHVAC 2 hTVAC 347 F1200 NHVAC-2 NHVAC - 348 F120'). NHVAC 2. hTVAC 349 F1200: NHVAC 2 NINAC '421 F1200 NINAC 2 NHVAC 526,F1200..hTVAC 2 NHVAC 115 F1300 hTVAC-3 NHVAC 3 130 F1300 NHVAC 3 hTVAC-131 F1300' NHVAC-3 NHVAC-132 F1300 hMVAC-3 MNAC 230 F1300 NHVAC_3 NHVAC 231 F1300 NINAC 3 NINAC '3'10 F1300 NINAC-3 NHVAC

332_F1300:

NHVAC 3 ?HVAC 332 F1300: NINAO 3 NHVAC 335 F1300 - NINAC-3 NHVAC 431 F1300 NHVAC NHVAC - 532 F1300-hTVAC 3 NHVAC 111 F1400 i NHVAC 2 hTVAC .195 F1510' NHVAC-l' - NHVAC ( 192 F1520 NHVAC 1 NHVAC 811 F1520 hTVAC-1 NINAC "193 F1530 NINAC;2 NHVAC 194 F1540 -NHVAC 2'- NHVAC 821 F1540 NHVAC 2. NHVAC 190 F1900; N01;E PCVE 7 290 F1900 NINAC+T31(SHDVN) : PCVE 390 F1900 = NHVAC+T31(SE'N) PCVE 191 F1901 - NHVAC+T31(SHDVN) PCVE -291 F1901 NINAC+T31(SHDVN) PCVE h.j 're-W w w g g-y 'sey- - 3

. -. ~.. -. - ~... R21CTOR BUILDING FIRE ZONES AND HVAC SYSTDi$ gf NORMAL AIR i3'f 'SUFFLY/ MEANS 4 D01AUST OF ROOM '- ' FIRE-COOLING SMOKE NO, AREA SYSTEM REMOVAL 391 F1901 NHVAC+T31(SHDVN) PCVE 310 F3100 DIVAC( A)-1 EHVAC(A) 341 F3101 DIVAC( A) 1 EHVAC(A) 320 F3200 FHVAC(B)-2 DIVAC(B) 322 F3200_ _ DIVAC(B) 2 DNAC(E) 340 F3200-EHVAC(B)-2 EHVAC(B) =383 F3200 DNAC(B) 2 DNAC(B) 426 F3?00 DNAC(B) 2 EHVAC(B) 527 F3200. EHVAC(B)-2 EHVAC(B) 541 F3200 EHVAC(B)-2 EHVAC(B) 326 F3201 DNAC(B)- 2 DNAC(B) 229 F3210 NHVAC-2 NHVAC 328 F3211 hTVAC 2 hMVAC 315 F3300 EHVAC(C) 3 ElWAC(C) 331 F3300 DNAC(C)- 3 DIVAC(C) 336 F3300. DIVAC(C) 3 DWAC(C) 413 F3300 ElWAC(C)-3 DNAC(C) 517 F3300 - DIVAC(C)- 3 EHVAC(C) 63B F3300 EHVAC(C)-3 DNAC(C) 654 F3300- DiVAC(C) + 3 DIVAC(C) 715 F3300 DIVAC(C)- 3 EHVAC(C) 337 F3301 DIVAC(C)- 3 DWAC(C) .p 316 F3310 NHVAC43 NHVAC t = bj 317 F3311 NHVAC 3 NHVAC ,345 F3400 NHVAC-2 bHVAC 380 F3400-hMVAC 2 NHVAC 444 F3400 hMVAC 2 NHVAC 543 F3400 NHVAC-2 N1WAC 381 F3401-EHVAC(A) 2 DiVAC( A) 412 F4100 EHVAC(A)-1 ESA(A) 514 F4100 EHVAC(A) 1 -ESA(A) ' 515 F4100 DNAC( A) 1 ' ESA(A) 612 F4100 DIVAC(A) 1 ESA(A) -410'F4101.NHVAC-1 NHVAC ~411 F4101 NHVAC-1 NHVAC -510'F4101 NINAC-1 NHVAC 511 F4101 NHVAC 1 NHVAC 512 F410lL NHVAC-1 NHVAC 516 F4102 'EHVAC(A)-1 EHVAC(A) 613 F4102, EHVAC(A)-1 EHVAC(A) 614 F4102. DWAC(A)-1 EHVAC(A) 653-F4102-EHVAC(A)-1 EHVAC(A) 423 F4200 EHVAC(B) 2 ESA(B) 522 F4200-EHVAC(B) ESA(B). 523_F4200 DNAC(B) 2 ESA(B) 624 F4200 DNAC(B) 2 ESA(B) I f I

'-REACTOR BUILDINC FIRtfZONES AND HVAC SYSTEMS I ' NORMAL AIR . SUPPLY / MEANS -EXHAUST-0F ' ROOM TIRE C00LINC SMOKE NO. -AREA-SYSTEM REMOVAL 420 F4201 N1WAC 2 NINAC 424 F4201-.NHVAC.2 NHVAC 441 F4201-- NltVAC 2-NHVAC 442 F4201 NIWAC 2 10NAC 443 F4201 N1(VAC 2 NINAC 445 F4201 NHVAC 2 NHVAC 446 F4201 NHVAC.2 NIWAC 447 F4201 N1{VAC NINAC - 520 F4201 NilVAC42 NHVAC 521 F4201 NHVAC 2 N1(VAC .542'F4201 NINAC 2 NIIVAC 544 F4201-.N1tVAC 2 NINAC 545 F4201 NHVAC 2 M{VAC - -546 F4201 MNAC 2 MlVAC 547 F42011 NHVAC NINAC ^ 622 F4201 NHVAC-2: NHVAC 623 F4201 NHVAC 2 MNAC 626 F4201 N1WAC-2 NHVAC 641" F4201 -NHVAC 2-NiiVAC 643 F4201 M WAC 2-NINAC 632 F4201 NINA% 2 NHVAC '683 F4201 Ni[VAC 2 NINAC O 684 F4M1 3 NHVAC 2 -. NMVAC 685'F4201 NHVAC 2.. NHVAC 524'F4202 EHVAC(B)l-2 EHVAC(B) 625 F4202 EHVAC(B)-2 .EHVAC(B)- 663.F4202 EINAC(B) 2 EHVAC(B) 42$ F4230 -EltVAC(B)-2 EHVAC(B)

432 F4300' Ei!VAC(C) 3 ESA(C)

-533.F4300: EHVAC(C) 3-ESA(C) - 534i F43001: _El!VAC(C)-3 ESA(C) ._632 F4300J -ElIVAC(C)-3 ESA(C) '430<F4301- --NHVAC 3~ NHVAC 433 F4301 1NHVAC-3 NHVAC 435.F4301 NHVAC-3 NHVACa ?438 p4301- :NHVAC :NHVAC 530 F4301-NIWAC 3 'NHVAC 531 F4301-NINAC 3 NHVAC 538'F4301:.NHVAC 31 NINAC -539 F4301 -NHVAC 3 NHVAC-615 F4301 NHVAC 3-NHVAC-616.F4301L :NHVAC 3 NHVAC- '617JF43011 NilVAC 3 - NHVAC- -.634 F4301-NHVAC 3 NHVAC 639 F4301 -NilVAC 3 NHVAC 7 657 F4301-NHVAC-3 NINAC O

.m __ REACTOR'BUILDINC FIRE ZCNES AND HVAC SYSTEMS

[

NORMAL AIR-l( SOFFLY/_ MEANS EXHAUST OF _' ROOM FIRE-COOLINC-SMOKE NO, AREA -SYSTEM REMOVAL 658 F4301-NFVAC-3 N!WAC 664 F4301 NHVAC 3 NHVAC 665 F4301 NHVAC 3 NHVAC 674 F4301 NHVAC 3 NHVAC 690 F4301 NHVAC.3 NHVAC 692 F4301 - NHVAC 3 NHVAC 693 F4301' NHVAC 3 NHVAC 711 F4301 NHVAC 3 N}NAC 716 F4301 NHVAC 3 NHVAC -720 F4301 NHVAC 3 NHVAC 721 F4301 NINAC 3 NHVAC 722 F4301 NINAC 3 NHVAC 723 F4301 NHVAC 3 NHVAC 733 F4301 NHVAC 3' NHVAC -734 F4301 NHVAC 3 NHVAC 741 F4301 NHVAC 3 NHVAC 742 F4301 NHVAC 3 NHVAC 743 F4301 NHVAC-3 - NHVAC 760 F4301 NHVAC 3 NHVAC 761 F4301 NHVAC 3 N1WAC 762 F4301. NHVAC 3 NHVAC 763 F4301 'NHVAC-3 NHVAC 536 F4302 EHVAC(C) 3 EHVAC(C) 633 F4302 L DWAC(C) 3 EHVAC(C) 635 F4302 DNAC(C) 3 EHVAC(C) ~673 F4302' EHVAC(C)-3 EHVAC(C) 730 F4302 DNAC(C)- 3 EHVAC(C) 436 F4320 DNAC(C) 3 EHVAC(C) '440 F4900 NHVAC NHVAC 491 F4901- _NHVAC+T31(SHDWN) PCVE '591 F4901 NHVAC+T31(SHDWN) PCVE 691 F4901 NHVAC+T31(SHDWN) PCVE -1659 F6100- NHVAC 1 NHVAC 610 F6101-ElWAC(A) 1 EVHAC(A) -640 F6200- -EHVAC(B)-2 EHVAC(B) 680 F6200 EHVAC(B) EHVAC(B) 620 F6201 EHVAC(B) 2 EHVAC(B) 642 F6201 - NHVAC-2 NHVAC-630 F63012 EHVAC(C)-3 EHVAC(C) 710 F7100 NHVAC-1 NHVAC '681 F7200- EHVAC(B) 2 EINAC(B) 740 F7200: lEHVAC(B)-2 EHVAC(B)- 764 F7200. EHVAC(C)-2 EHVAC(C) 820 F9200 NO AREA IS GUTSIDE 840 F9200 NO AREA IS OUTSIDE 810 F9300 NO-AREA IS OUTSIDE-v er e ,., + w w>,.,4p_ pw aw y ~ ,-n.,, ,py, .. - -n y. y. ,,y y-- ,gir-49-.-. y-- . e

REACTOR BUILDING FIRE ZONES AND HVAC SYSTEMS (' NORMAL AIR (f). SUPPLY / MEANS EXHAUST OF ROOM FIRE COOLING SMOKE NO. AREA SYSTEM REMOVAL 830 F9300 NO AREA IS OUTSIDE NHVH INPUT FRNON ESSENTI AL NORMAL SUPPLEMENTAL C00LIN SHVH(FCU) INPUT FRFAN. COIL UNIT NORMAL SUPPLEMENTAL ~ COOL EHVAC INPUT FRESSENTIAL COOLING SYSTEM NHVAC INPUT FRNORMAL AIR SUPPLY / EXHAUST COOLING SYSTEM SHVAC INPUT FRNORMAL SUPPLEMENTAL COOLING SYSTEM EHVH INPUT FRESSENTIAL COOLING SYSTEM DWC INPUT FRDRY WELL COOLING ESA OUTSIDE EMERGENCY SUPPLY AIR O O

ATTACH ME NT F RE SPoN5t ic OUTST AN0t NG 1 %Sv6 12 3 Resolution Status of Specific Staff Comments on Line item Testing Requirements from Reg Guide 1.68, Rev. 2, Appendix A Reg Guide 1.68 Append!x A Item Heslution/ Comment 1.a.(2)(d) see Amendment 18, also Museol Sdreehor 5.4.1.14 to cross-reference 3.9.2.1.1 1.a.(4) see Amendment 18 1.c see Amendment 18 1.h.(4) see Amendmer.t 18 1.h(9) see Amendment 18 1.i.(1) see Amendment 18 1.j,(12) see Amendment 18 1.j.(15) see Amendment 18 1.k.(2) see Amendment 18 ?.n.(14)(f) see Amendment 18 2.c see Amendment 18 2.d see Amendment 18 4.k - see new Section 14.2,12.2.39 4.1 see Amendment 18 5.) see Amendment 18 5.n - see new Section 14.2.12.2.36 5o see Amendment 18 5.q see Amendment 18 5.u see Amendment 18 5.w see new Section 14.2.12.2.37 l 5.x see Amendment 18 5.z see Amendment 18 5.c.c see new Section 14.2.12.2.38 5.g.g see Amendment 18 S.h.h see Amendment 18 I-' pg i l l I

) .pb ATTACHMENT G RESPONSE TO OUTSTANDING ISSUE (99) DISCHARGES FROM PLANT AND CONTAINMENT DURING THE DEVELOPMENT OF AN ACCIDENT, SAMPLES OF LIQUID AND GASEOUS DISCHARGES FROM BOTH THE PLANT AND CONTAINMENT WILL BE OBTAINED. CHEMICAL AND RADIOCHEMICAL ANALYSES WILL BE PERFORMED FOR PROTECTION OF THE HEALTH AND SAFETY OF THE PUBLIC AND THE PLANT OPERATORS. THESE SAMPLES WILL BE 00-TAINED FROM THE PROCESS SAMPLING SYSTEM. THE POST ACCIDENT SAMPLING SYSTEMS WILL NOT BE RECUIRED TO OBTAIN THESE SAM-

PLES, (QJlt DAMAGE _AS.SJ.$SMENT DURING THIS INITIAL PERIOD, INSTRUMENTATION WILL PROVIDE SUFFICIENT INFORMATION FOR THE OPERATORS TO PERFORM THEIR DUTIES.

FOR EXAMPLE, THE CONTAINMENT HIGH RANGE RADIATION METERS WILL GIVE INSTANT INFORMATION CONCERNING THE RADIATION LEVF.L IN CONTAINMENT. (TO OBTAIN DATA FROM THE PASS SEVERAL HOURS MAY BE REQUIRED FOR SAMPLING AND ANALY-SES.) CALCULATIONS CAN BE PERFORMED TO RELATE CONTAINMENT RADIATION LEVEL WITH THE PROBABLE EXTENT OF CORE DAMAGE. '~ CORE DAMAGE ASSESSMENT INSTRUMENTATION IS DESCRIBED IN SEC-TION 18.4.6 0F THE ABWR SSAR. .THIS SECTION DESCRIBES THE SAFETY PARAMETER DISPLAY SYSTEM (SPDS). THE PRINCIPLE PUR-POSE OF THE SPDS IS TO AID THE CONTROL ROOM PERSONNEL DURING ABNORMAL AND EMERGENCY CONDITIONS IN DETERMINING THE SAFETY STATUS OF THE PLANT AND IN ASSESSING WHETHER ABNORMAL CONDI-TIONS WARRANT CORRECTIVE ACTION BY OPERATORS TO AVOID A DE-GRADED CORE. DISPLAYS OF. CRITICAL PLANT VARIABLES SUFFI-CIENT TO PROVIDE INFORMATION TO PLANT OPERATORS ABOUT THE FOLLOWING CRITICAL SAFETY FUNCTIONS ARE TO DE PROVIDED AT THE WIDE SCREEN DISPLAY PANEL IN THE MAIN CONTROL ROOM: l (1) REACTIVITY CONTROL, (2) REACTOR CORE COOLING AND HEAT R EM0'! A L FROM THE PRIMARY SYSTEM, l (3) REACTOR COOLANT SYSTEM 2NTEGRI1Y, (4) RADIOACTIVITY CONTROL, AND (5) CONTAMINATION CONDITIONS. 1 O. ) v

pLJ THIS INSTRUMENTATION AND THE PASS WORK TOGETHER TO OBTAIN COMPLEMENTARY INFORMATION. AFTER THIS INITIAL PERIOD DURING THE DEVELOPMENT OF AN ACCI-DENT, THE ABWR PASS WILL BE USED TO OBTAIN SAMPLES OF REAC-TOR WATER AND CONTAINMENT ATMOSPHERE TO ASSESS THE EXTENT OF CORE DAMAGE. THE ABWR PASS HAS BEEN DESIGNED TO SAFELY OBTAIN SAMPLES WITH RADI0 ACTIVITY LEVELS UP TO 1 CI/G. IT IS EXPECTED THAT SAMPLE RADIOACTIVITY LEVELS WILL BE NO MORE THAN THIS VALUE APPROXIMATELY ONE DAY AFTER A SERIOUS CORE DAMAGE ACCIDENT. EARLY IN SUCH AN ACCIDENT, THE PLANT IN-STRUMENTATION IN THE MAIN CONTROL ROOM WOULD BE INDICATING THAT ABNORMAL CONDITIONS EXIST. IF A REACTOR COOLANT SAMPLE WERE OBTAINED WHICH HAD EXCESSIVE RADIOACTIVITY, AS MEASURED BY THE AREA RADIATION MONITOR IN THE PASS AREA, THE PLANT OPERATORS WOULD USE THIS HIGH RADIATION SIGNAL AS CONFIRMATORY EVIDENCE THAT SEVERE CORE DAMAGE HAS OCCURRED AND CONTINUE FOLLOWING THE EMERGENCY OPERATING PROCEDURES. IT WOULD NOT BE NECESSARY TO PERFORM ANY RADIOCHEMICAL ANALYSES TO REACH THIS CONCLUSION. DURING LESS SEVERE ACCIDENTS, IN WHICH ONLY SOME CLADDING DAMAGE HAS OCCURRED, SAMPLES MAY BE OBTAINED FROM EITHER THE Pn0 CESS SAMPLING SYSTEM OR PASS. f3 'd NUREG-0737 RElQIREMENT_S THE ABWR PASS HAS BEEN DESIGNED TO MEET THE ELEVEN REOUIRE-MENTS LISTED IN NUREG-0737 EXCEPT AS NOTED IN THE FOLLOWING TABLE. U

O O O REQUIREMENT IN NUREG-0737 FEATURES OF ABWR PASS (ABBREVIATED) 1-THE COMBINED TIME ALLOTTED FOR MEETS THE REQUIREMENTS OF NUREG-0737. SAMPLING AND ANALYSIS SHOULD BE 3 HOURS OR LESS FROM THE TIME A DE-CISION IS MADE TO TAKE A SAMPLE 2-THERE SHALL BE ONSITE CAPABILITY TO PERFORM THE FOLLOWING WITHIN THE 3 HOUR TIME PERIOD: (A) DETERMINE THE PRESENCE AND MEETS THE REQUIREMENTS OF NUREG-0737. AMOUNT OF CERTAIN RADIONUCLIDES IN THE REACTOR COOLANT AND CON-TAINMENT ATMOSPHERE THAT MAY BE INDICATORS OF THE DEGREE OF CORE DAMAGE; (B) HYDROGEN IN CONTAINMENT AT-HYDROGEN IN CONTAINMENT ATMOSPHERE IS MOSPHERE; MEASURED BY THE CONTAINMENT ATMOSPHERE MONITORING $YSTEM. (C) DISSOLVED GASES, CHLORIDE DISSOLVED GASES ARE DI$ CUSSED IN ITEM AND BORON IN LIG'J ID S ; 4 BELOW. MEETS THE REQUIREMENTS CON-CERNING CHLORIDE AND BORON OF NUREG-0737. (D) IPLINE MONITORING CAPABILITY NO INLINE MONITORS ARE PROVIDED IN IS ACCEPTABLE. PASS. m

O O O j 'i REQUIREMENT IN NUREG-0737 FEATURES OF ABWR PASS l (ABBREVIATED)- i 3-SAMPLING NEED NOT DEPEND UPON AN MEETS THE REQUIREMENTS OF NUREG-0737. ISOLATED AUXILIARY-SYSTEM BEING l PUT INTO OPERATION. l I ) 4- ' REACTOR COOLANT' SAMPLES AND' ANAL-DURING A SEVERE CORE DAMAGE ACCIDENT YSES FOR TOTAL DISSOLVED GASES FOR THE ABWR, THE REACTOR' WATER WILL AND HYDROGEN ARE REQUIRED. BECOME MIXED WITH.THE SUPFRESSION POOL [ l WATER. THE, PRESSURE IN THE REACTOR VESSEL WILL DECREASE TO APPROXIMATELY THE PRESSURE WITHIN THE WETWELL AND l THE DRYWELL. AS A RESULT OF THIS.DE-1 CREASE IN PRESSURE, DISSOLVED GASES WILL PARTIALLY PASS OUT OF THE WATER f PHASE INTO THE GAS PHASE. DATA ON 7' GASES DISSOLVED IN THE REACTOR WATER 4 UNDER THESE CONDITIONS WILL HAVE LITTLE MEANING IN RESPONDING TO THE i ACCIDENT. Dt1 RING ACCIDENTS IN WHICH i ONLY SMALL AMOUNTS OF CLADDING DAMAGE 1 i HAS OCCURRED OR IN ACCIDENTS IN WHICH THE REACTOR VESSEL HAS NOT BEEN DE- [ PRESSURIZED, PRESSURIZED REACTOR WATER SAMPLES MAY BE OBTAINED FROM THE PRO-CESS SAMPLING SYSTEM. THEREFORE, THE [ ABILITY TO OBTAIN PRESSURIZED OR UNPRESSURIZED REACTOR WATER SAMPLES i FOR DISSOLVED GAS ANALYSES HAS NOT i BEEN PROVIDED. r i I i.

-g 7-REQUIREMENT IN NUREG-0737 FEATURES OF ABWR PASS (ABBREVIATED) 5-IF BOTH OF THE FOLLOWING ARE ' MEETS THE REQUIREMENTS OF NUREG-0737.

PRESENT, (A) THERE IS ONLY A SINGLE BARRIER BETWEEN PRIMARY (NOTE THAT THERE ARE SEVERAL enRRIERS CONTAINMENT AND THE COOLING WATER

.TO PREVENT CHLORIDE INTRUSION FR0M THE AND (B) IF THE COOLING WATER IS POWER CYCLE COOLING WATER INTO THE RE-SEAWATER OR BRACKISH WATER, CHLO-ACTOR VESSEL. THESE BARRIERS ARE: THE RIDE ANALYSIS WITHIN 24 HOURS MAIN CONDENSER TUBING, THE CONDENSATE AFTER SAMPLING SHALL BE PROVIDED. POLISHING DEMINERALIZERS AND THE PUMPS IF BOTH ARE NOT PRESENT, THE TIME AND VALVES IN THE CONDENSATE /FEEDWATER TO COMPLETE THE ANALYSES IS IN-SYSTEMS. THESE PUMPS ARE STOPPED AND CREASED TO 4 DAYS. ANALYSIS DOES THESE VALVES CLOSED DURING UPSET CON-NOT HAVE TO BE DONE ONSITE. D1TIONS. THUS, BECAUSE BOTH FACTORS ARE NOT PRESENT, THE TIME TO COMPLETE THE ANALYSIS IS INCREASED TO 4 DAYS.) i 6-IT MUST BE POSSIBLE TO OBTAIN AND MEETS THE REQUIREMENTS OF NUREG-0737. ANALYZE A SAMPLE WITHOUT RADIA-TION EXPOSURES TO ANY INDIVIDUAL EXCEEDING ~5 REM FOR WHOLE BODY AND 75 REM FOR EXTREMITIES. 7-ABILITY TO SAMPLE AND ANALYZE FOR MEETS THE REQUIREMENTS OF NUREG-0737. REACTOR COOLANT BORON MUST BE PROVIDED. 8-IF INLINE. MONITORING IS GSED, INLINE MONITORING IS NOT USED. BACKUP SAMPLING AND ANALYSIS CA-PABILITY HUST BE PROVIDED.

L Us- .,V REQUIREMENT IN-NUREG-0737 FEATURES OF ABWR PASS (ABBREVIATED) 9-(A) CAPABILITY TO IDENTIFY AND CAPABILITY IS PROVIDED TO IDENTIFY AND QUANTIFY A SPECIFIED NUMBER OF QUANTIFY THE DESIRED ISOTOPES IN SAM-ISOTOPES OVER A RANGE OF NUCLIDE PLES OVER A RANGE FROM APPROXIMATELY l CONCENTRATIONS FROM APPROXIMATELY MICROCI/G TO 1 CI/G. SAMPLES OBTAINED 1 MICROCI/G TO 10 CI/G'. DURING THE ACCIDENT RECOVERY' PHASE WOULD BE WITHIN THIS RANGE FOR MOST CORE DAMAGE ACCIDENTS. IF THE GROSS RADIOACTIVITY LEVELS ARE HIGHER THAN 1 CI/G,.THIS WOULD CONFIRM THAT SEVERE CORE DAMAGE HAS OCCURRED. (B) RESTRICT BACKGROUND LEVELS MEETS THE REQUIREMENTS OF NUREG-0737 OF RADIATION IN THE LABORATORY AND PROVIDE PROPER VENTILATION. 10-PROVIDE ADEQUATE ACCURACY, RANGE MEETS THE REQUIREMENTS OF NUREG-0737. AND SENSITIVITY TO PROVIDE PERTI-NENT INFORMATION. 11-(A) PROVIDE SAMPLE LINES WITH MEETS THE REQUIREMENTS OF NUREG-0737. PROPER FEATURES FOR SAMPLING DURING ACCIDENT CONDITIONS. (B) PASS VENTILATION EXHAUST MEETS THE REQUIREMENTS OF NUREG-0737. SHOULD BE FILTERED WITH CHARCOAL ADSORBERS AND HEPA FILTERS. i

._.__.~.,_.m_..~ 1 F k

SUMMARY

' RESPONSE TO OUTSTANDING AND CONFIRMATORY ISSUES OF f ABWh DSER CHAPTERS 1,2,3,b,6,8,10,12,13,14 and 15- -SECY-91-355-i i _i [. Outstanding Issue-Description Resolution / Comment 4 1 Access 2bility to ASME Class 1, Response provided on attached pages i 2, and 3 components (5.4.2, 4.5-4.1, 5.2vi, 5.2-15.1, 5.2-16, i 6.6) 5.2-17, 5.2-17.1, 5.2-17.2 and 5.2-36.1. 2 Modeling-of ABWR containment See Attachment A testing ( 6. ~2.1. 2.1 ) 1 3 ABWh containment design See Attachment A l testing (6.2.1.6) 4 Dryvell deprescura ation See Attachment A (6.2.1.5.1, 5' 'Euppr ecslon pool SRV loading See Attachment A l tects1(C.2.1.6) i I 6. Data f or supprecslon pool See Attachment A tect conditionc (6.2.1.6) 7 Clar121 cation of accumptione See Attachment A (6.2.1.6) t -B-Clar111eation of methods used See Attachment A to calculate loads (6.2.1.6) 9' Juct111 cation for scaling See Attachment A laws (6.2.1.6) -10

Additional-lmodeling See Attachment A-assumptions ( 6. 2. 1. 6 )'

ill -Subcompartment pressure See Attachment 1A analycis-(6,2.1.7) s 12 'Subcompartment pressure See Attachment-A y analysis inconsistencies (6.2.1.7) y '13' Steam bypass of the-See' Attachment A ^ suppression pool--(6.2.1.8)= l' 14-Adminastretive c < trol of Response provided on attached pages openings, doors and hatches .6.2-50.55 and 6.2-50.56 ( 6.- 2. 3 ) ) ..... - -. _ +,. - m.,.-_-.._.,...,_,__,.-,,,..m,_~r..- .,J-,,-..,.,,-m -_.__,,~~,.-._m,-...gv,m--,-

.. _ ~ --.. ~. ~_- - ~ -._.-- I ("] 15 Response to questions Question 430.32 -%,f; regarding containment The deferred response to this isolation system (6.2.4) question de provided on attached pages 20.3-40, 6.5-2 and 6.5-6. Question 430.31 Instrumentation requirements for the secondary containment openingo are contained in Subsection 6.2.3.5 and discussed on a system by system basis in each system descriptaon i question 430.34 The information on asolat2on valves is given on a system by system basis.in Table 3.2-1 Classification Summery

16 Commatment_to GDCs 1,2,4,16 Commitmert to_QDCe 12,4 and 16 and 56 (G.2.4)-

The ABWR commitments to GDCs 1, 2, 4 and 16 are contained an Lub-sections 3.1.2.1.1, 3.1.2.1.2, 3.1.2.1.4 and 3.1.2.2.7, -respectively Gommitment to GDC 56 Frevious NRC reviews on-operatinD BWRs and.GESSAR II have agreed that suppression pool lines connected to closed loops are sealed against direct connection to the contaln-ment atmosphere 17 Containment isolation valve _ Valve Condition information (6.2.4)- Valve condition is detaaled on the system piping and'instrumentat1on da gram P&ID as locked open closed, normally open. closed and normc11y. energized deenergized Valve Closure Times See Attachment ~B 18 Containment-purge system See Attachment C design information'(6.2.4.1) .[ l

. ~. - - ~. ~.... - - 19: Atmospheric control system The flammability control system desa'gn (6.2.5) consists of redundant safety grade hydrogen recombiners for post LOCA combustible gas contral. The atmospheric control system is not required for perform a LOCA function and therefore only the isolation valves and piping are safety grade. Thio includes the wetwell rupture discs for emergency containment overpressure venting with normally open stop valve Ifs'[enFdcNidr"VEr#NeMe M' Subsection 6.2.5.2. 20 Capability of post-LOCA Following a LOCA the primary con-purg2ng oi the containment tainment pressure will exceed . < u, ;, 5 ) 0.719 paig'specified for normal operating conditions. The normal operating purge system for-main-talning the pressure and oxygen concentration la not required post LOCA. Tte ECCS containment-cpray systeme will control the post LOCA cont.. ment p r'+ s u r e and the [ hydrogen tecombiners will control \\ the post LOC 8 <xygen concentration. All purge line valves will be closed arsd any minor leakage drbwn te the.,*perating SGTS. Thi s r.ia nor letL6go s incorporated in the verall 0.5*/. per day primary ecntainment leakage specification a.* -the radiological consequenceu of this leakage shown-in Subsection

15. 6. 5.-

Design bases are covered ic Subsection 6.2.5.1(8) through 6.2.5.1113). L 1-l 21-Availability of'hyt?ngen Redundant dedicated primary cont-recombiners followin, s. ainment penetrations are provided ' LOCAL (6.2.5) for each recombiner as shown in Figure 6.2-20 and Subsection 6.2.5.2.7. L l' 22 Chapter 6 issues Response to these-issues will .thru be provided in:a separate document 68-at the conclusion.of the GE/NRC Chapter 8.DSER meetings and telephone calle. U I!. D g ~ -..

+ . -. ~. - -. . ~. -. i 69 Compressed air system ICAS) Revised P&lDe have been transmitted volve number and valve in letter from R.C. Mitchell to R.C

operator inconcistencies Pierson dated 2/3/92.

Numbering inconsistencies, including valve (9.3.1). numbers and valve operatore have s been resolved. 70 Identification of CAS comp-Revised P& ids have been transmitted enent safety claestfication in letter from R.C. Mitchell to R.C-(9.3.1) Pierson dated 2/3/92 The inconsistency in Figure 20.3-55 (page 20.3-354.30 attached) hac been cox rected. 71 Identi11 cation of CAS failure In the HPIN, IA and SA systems, all modec ( '3. 3.1 ) motor operated valves fail ao i s, unless otherwise noted and air operated valves fail open, unless otherwise noted. In the AC system, all air operated valves fail closed. 72 Failure position c1 CAS valves These valves have been changed to AO F018A & B (9.3.1) motor operateo valves and are normally locked closed. They are ( opened by a low pressure in the line supplying nitrogen to the ADS accu-'.iulatorc. 73 ANil compliance 01-high nitrogen supply subsystem, The precsure n2trogen gas supply which is part of the AC system. cystem (9.3.1) provides oil-free nitrogen with a moisture content of less than 2.5-ppm..This_ nitrogen.1c provided to.the-HPIN system through carbon steel piping which may not maintain an acceptable amount of -particulates. FilterF. which-remove particles-larger than 5 microns, are provided in the HPIN system piping. Downstream of the filters'the HPIN piping is-stain-less steel. Requirements added to Subsection 6.7.2 (page 6.7-1 attached) and Subsection 6.2.5 (page 6.2-32 . attached). '/ l u-e

1 L/~T74 ^ Dicerepancy in identification The first sentence of the response - (,/' system (9.3.3) 20.3-354.12 has been changed to of' instrument air (IA) to Question 430.218 on page state that the instrument air system does serve as a backup to the HPIN system to opeiste pneumatically operated equipment inside containment.(The page changed is pr oprietary and Ac provided under separate cover). '75 Justification for particulate The instrument air ayatem providec I s22e for IA system (9.3.1) compressed air that has been filtered to remove particles larger than 5 microno. All componente using specifications which state the 5 micron eriteria. There have

1. s been no problems with air quality at those plants at which the S-micron criteria hac been used.

76 Dicerepancy.an identification Figure 11.2-2 has been revised of radioactive drain transfer and have been transmitted 2n. ayctem containment 2 solation letter from R. C. Mitchell to'R.C. valves (9.3.8)- Pierson dated 2/3/92. 77c -Clacelfication of radioactive The ECCS equipment room sump 1 \\- draan-transfer syatem check backflow protection check valvec A valvec-(9.3.8) have been classif2ed as safety class 3 and designed to seismic Category I and Quality Group C criteria as shown on revised Figure 11.2-2 and Table 3,2-1. (Figure 11.2-2 ic: proprietary and is provided under separate cover). l Dicerepancy resolution and Figure 11.2-la-has been modified L78 component: qualification. to chow the shower facility requirements 19.3.8) discharging into the HSD receiver-tank. (The changed page is proprietary and is provided under separate cover)..The component j qualification requirements have been added to the P& ids submitted in letter R.C. Mitchell to-R.C. Pieroon dated 2/3/92. An-inter-4 face requirement has been-added to W attached page 9.3-13.2 which ' require monitoring of the 'non-l:, radioactive effluents. (Page 9.3-13.2 is proprietary-and 7-4{ provided under-separate cover). c L 1

+ n u >">--ac ' ~~ -s --a.. ~e- > ~ ' ' = + - - - ~

79 Safety related dec1gnation Item (1) of Subsection 9.3.12.1

.,f ' oi crain system (9.3.8) states that only a portion of the -(, drain transfer uyelva is considered safety-related. 80 Provisions for tornado missile The DSER has already indicated that auxiliary suppr rt systems damage to the vent pipe assembly (9.5.4.1) would have no adverse safety consequencer. In addition, each diesel generator has its own day tank, which is located incide the react or building. This providec another level of protected fuel supply for each diesel generator. Also, there are three independent diesel generator systems, any one of which can safely shut down the plant. For thece reasons, no .pecific miscile protection la provided for each vent pipe, nor is considered necessary. SJ4 Twt ond calibrat2cn The diesel generator units are frequencim (9.5.4.1) tested per Regulatory Guide 1.108, ac delineated in Subsections 14.2.12.1.45.3 (preop) and 16.11.1 (curve 111ance - see pages 16.11-10 through 16,11 19). \\ neg Guide 1.108 unambiguoucly definec " diesel generator unitc' an both the diesel gentratcr and its auxiliaries. Generally, the successful operation of the auxillaries is confirmed by the successful testing of-the complete unita. Testing of the auxiliaries is therefore coincident with that of the diecel gener ators, and ic done at-the same frequency. Separate surveillance testing ic required for fuel transfer equipment and the storage and day tanks. The surveillance frequency for this equipment is given in Subsection 16.11.3 (pages 16.11-24 and 16.11-25). 81' _ Interface requirement for There are two transfer pumpn - DG fuel oil transfer pump provided with each diesel. generator retive power (9.5.4.2) unit. These have been added.to the attached Figure 9.5-G (page 9.5-18) in response to Issue 83. The pumps are motor-driven. (

m._ _.m_ (~S( Item (1) of Subsection 9.5.13.5 has --(_/ J been deleted on. attached page 9.5-10.6, and item (a) of Response to Question 430.274 (page 20.3-359) has been appropriately mod 2fied. Page 20.3-259 is proprietary and ic provided under separate cover. 82-Ver112 cation of interfaces A new Table 8.3-11

• Diesel and instrumentation Generator Alarma* in being added diccrepancies (9.5.4.2) in con]Vnction with the Chapter 6 FUEL DSER review.

A

• LOW LEVEL STORAGE TANK
• alarm is included in this table.

Also, the first sentence of Subsection 9.5.4.5 (page 9.5-4.2) and interface item 9.5.13.5(2) (page 9.5-10.6 attached) have been modified to show the storage tanks. Also, a stick gunge symbol hac been added, along with the storage tank steelf, to Figure 9.0-6 (page 9.b-18 attached). (Page 9.5-4.2 is proprietary and provided under separate cover).- 62 FAgure O.5-6 discrepancleu Figure 9.5-6 (page 9.5-16 attached)

19. 5. 4 i 2 f has been modified to show the 7 day storage tank, and secociated T

inctrumentation. pumpe, valvec and piping. The neutence

• Connection for an optional motor-driven-fuel oil booster. pump are also provided*

'was added first paragraph of.-page 9.5-4.1. (This page is proprietary and is provided under separate. O o Ver.). A temperature indicator hac been i added to discharge line of~the fuel oil tank in Figure 9.5-6-(page 9.5-18 attached). 84 clnterface requirement for New interface Subsection 9.5.13.13 verifying day tank full (page.9.5-10.7 attached) has been ( 9. 5.~ 4. 2 ) - added for diesel fuel refueling procedures. o O I L

Y% ' ( )85 Discrepanclea in SSAR regard-Subsection 9.5.5.2 (page 9.5-5) \\+/ . i r.g ' j a c k e t circulating water has been modified and. pump (9.5.5)- the wordo " motor driven' have been deleted from both jacket water pumps on Figure 9.5-7 (pace 9.5-19 attached). The interface require-ment is correct in that the type of jacket water pump is dependent on the specific diesel manufacturer. (Page 9.5-5 is proprietary and in provided under separate cover). 86' Interface _seguirement for See revised Item (2) of Subsection temperature eensor (9.5.5) 9.5.13.6 (page 9.5-10.6 attached).- 87 DG c io11 rig water heat Subsection 9.5.13.6 requirec a renoval capacity (9.5.5) table to be provided which identiljes the design flow and heat removal requirements for-the diecel generator cooling water syc tem. With regar d to the keep var m syotem, Subsection 9. 5. 5. 2 (page 9.5-5) has been modified accordingly. (Page 9.5-5 in . (~g/ - propiletary and ic provided under (, separate covea). Also, the words

• MOTOR - Dh 1 V E.N " were added the keep-warm pump cymbol on Figure 9.5-7 (page 9.5-1G attached)

Alco, the cold start tine (conaictent with Chapter 8 btER aecolution) has been changed from 13 to 20 seconds (page 9.5-5.1) This_page is proprietary and-is-provided under separate cover). ~88 Documentation of DG start-See new Note 4 on Figure 9.5-6 Ing air system filter (page 9.5-20 attached). arrangement (9.5.G) 89 DG_ starting air eystem See.new items (7) and (8) added interface requirements to Subsection 9.5.13.5 (page l (9.5.61 9.5-10.6 attached). Also, the " ready to load" status t r.onsistent with the Chapter-8 DSER resolution) has been changed l__ (~'g on page 9.5-6 from 13 to 20~secondc. (,) (This page is proprietary and is provided under separate cover). l' i

l ( 9 0 - Omission of reference-to See modified second sentence of .61r compressor-diacharge Subsection 9.5.6.2 (page'9.5-6) ' coolers (9.5.7) (This page is proprietary and ic provided under ceparate cover). 91 Omaccion of-DG lubrication The flow transmitter (FT) shown i cystem level indication on the lube oil sump tank on ' ' ';. v. 7 ) Figure 9.5-9.(page 9.5-1 attached)-- is an errcr and corrected to."LT. . Also, a locally m o u A., e z. t. e.e t e + i-v. indicctor (LI) has been added to thic figure. 92 Identif2 cation of design Item 3 of Subudie. A S 13.t i p sp cri_teria-ac interiace 9.5-10.6 attached) has been "equirenente (9.5.7) clarified. Subsection 9.5.8.2.1 (page 9.5-8) has been expanded to include protection against crank exploclonc. (This page ac proprietary and is provided under l' reparate cover). f The responce to Question 430.234 p. on page 20.3-309 was. modified f accordingly. (This page ac k proprietary and ic provided-under separate cover).

9 '-

Class 411catien of components . Note 2-of Figure 9.5-9 (page 9.5-21 1: tnc DU l'ubrication cyctem attached) has been expanded to 19.5.7) identify the requiremonto of ANSI B31.1. Also, Item 4 of the F.esponse to Quection-430.271 (page 20.3-357 has-teen appropriately p L modified. '(Page 20.3-357 is proprietary and is provided under. eeparate cover). I-See response to outstanding ~1caue l: '34 Identi11 cation of--ASME and-

ANSI components-(9.547) 9 3.-

95 Selection of a: combustion Response is provided in new air:ficv capacity (9.5.8) Item (6).of Subsection 9.5.13.5 (page 9.5-10.6 attached). 96-DG combustion otr intake Responce provided-in revised g and exhauct.cyctem pro-Subsection 9.5.8.1-(page 9.5*e) ,Thiu'page in proprietary and ic-( visionsifor tornado m i s c i l e c.T ( 9. 5. 8 ) provided under. separate cover). f*) .Y .-.n ..~ L - .li.,,-L.--+ i.-, - _ _ ~ - -,--, _ n. s _, _,,.,.., ,,,.,_,~,,_,,,,v,nnen,,,~,cnn_.n.~,-,. e,-- ,,m

97 b e r i p t. arftsmatiori or. Eee r e c ; c t.c c. to c u t t: t o.id i n g le.aue arear ntt included ite 9;. L; A T. (9.b.b) 96 Adequacy ci p s o c e n.: Eee Attachment D conpling cyctett. (9.3.2.11 G r hd revised 99 Adequacy of post accidct.1 See A t t b c h nient s . w ; 11 r.g t y,;t e re ( 9. 's. 2. 4 ! Eubcection 9.3.2 ( page e 9.J-11. 9.3-Ic orid 9.3-Id> terio Ta ble 9.3-2 (page 9,3-1Ld). All of thete p u g m.; g are proprietary ra r. d are I'tovided under neparate cover. j IN A ; c q u ' ;. y c1 bydregn watei T h t, response in provided c ri reviced a ch.!-..ts - y c t e rn (9.3.9i page 9.3-12 ottached IC) A J.; ; a c y u! c a ric 1,tjection The respon!Fe i ts provided on revised uyJ** page 9.3*13 u t t ric hed 10. F.. n a ;; a n d ; a n a l y c i a. Undes ctaff reviev .o 1M H = /.

4. *; ; 1: t-4(.!=D.'6j-cygtCtri Ceu A t t a c h me rit [

Ci.j 40n 4 # I.1. 2 ) .v. 1. 4. 4. 101 'a s t. dactr1Lut2;n and U r.d e r ctaff revlev

t a re g s 1 E I. a ng cyc t eF 4 1.i

' '.. '. 1. u.." 175 Acequa 21 condencate Mcm _! _ . ; c t n.>, . I t e 'n (1c, 4. C > There are f. c.

c. a f c t y - ; e l a t e d ty;.tena in the tur b1ne b u il d a t.g LLe I Referer,ce to the evaluution of the chield2ng dec1gn for the condenLate cleanup c y s t t-in ic Jocated in Table 12.2-S 13, e. rn 3 The recponcre as provided on attached page 10.4-12 I t e en 4 The r ec p o r's e is provided on attsched page 10.4-12 106 Uppe4 dryvell chielding Recponae vill be pr ovided by ec,cernc 412.1.2) tia r c h 31, 1992 i

.. - ~ .~ .- -.-. - _ - -. ~.-. - - - -. -... - -. ~. - - - - - i i .f C7 Identification and descript-Respons,e will be provided by Jon of conttined and airborne March 31, 1992 4.adacactive nousces in SSAR ! operation and accident conditions) (12.2.1) 108 Plant 4aycut drawing hesponse will be provided by deliciencies regarding March 31, 1992 identification of radiation

s. o u r c e s, legibility, and cc.>castency (12.3.1) 109 Identificistion of poct-Subnectier. 12.3.1 hee bee n exper.ded LCCA vatel areae (12.3.1) in Amendmerate 10 and 17 to better define the plant vital areas, acceso and egrens pathwayr to the I

vital areas has been added to the zone drawings and the vitha Components shoVn on the cofie dravingc. -310 M *.ificatsun et high The pool arrac have been renoned in 6 rucaytlon ;cc ne 4bove spent A rrie nd me n t 17 c ons a c t ere t with the Avel pool during operation level of shielding provided and the t 4 2 ?. 3 i rene druvangs updated. i 21. Identification of " highly Decontaminationr., inf or ma tion will 4adlobative cyctem "~ included in Amendment 20. All heat ( 12. 3.1 ) exchangess except the fuel ; coa cleanup best exchangers are provided with either chemichl or water fluching decontaminatior-contiectionc. The fuel pool cleanup heat exchanger as located down-stream of the filter.demineralizer pack and does not require separate I decontamination. 112 bryvell and reactor veccel Drywell and reactor drawings are chielding desagn given in Section 1.2. Sonie drytell information ( 1. 2. 3 ) details wall be added to the radiation zone drawings in Section )2.3 by March 31, 1992. In ~ addition, Table 12.2-5 will ue expanded in Amendment 20 to provide shielding dimencion and data-for componenta and major pipe chases. 113 Airbctne centsalnation This lacue is being covered by a i n f e r raa t i o n s'12.3.2) PAC on radiation protectiori and monitoring. -O' O

i i i l t i' 1 .14 A21 borne raJ2ation This i ra s u e of being covered by a l. -acostering (12.3.4) D/iC on radaat Aon pr otection and monitoring. i i lib l'o c e a c c e s s N n t background, Section 12.4 has been expanded l baceu, consistency, a rid rewritten and submitted as;, jus.tafication (12.4) Amendtoent 16 and will be exparaded [ i in Amendtrent 20. I 4 h wer-to-flow operatang See new Figure 14.2-1 (page J 11C tr a p (14.2.11) 14.2-G7) attached l J17 Tatle li e. t i n g 4: t a r t u p See new Table 14.2-1 (pages l teste and test conditiona 14.2-06.2 through 14 / 2-65. t, ) l 14.2.11) attached I i l lie C+nerie 2 nter iwei ng cupport rJnder NRC review ,qptev avetiubility l 1 andavadual teet abstracte i 14.J.1;- l l k -119-C1 cormstwent'te per3orm hee revired Subsect.lon 14.2.12.1 l tests ( 24.2.12)- trage 14.2-7) attached i (- T i ) ' 1 ~. 0 .Meditacutione to individual under NhC revsed l l text etstaacts (14.2.12) l I l-121 Clardly acceptanco e/steria Under HhC review o.d modl.ty Lturtup tett } L l u t t u c *. e '14.2.12) 1.";2 Ecreenang to identaty t e c t s, - COL Action Item; cee revired l _ rat u;aentaal to demerctrate Subzectjor. 14.2.33 ( p a g es. 14.2 00 c o ni or m a r.c o (14,2.12! bhd 34.2-6b.1) attoched j .i 123 C c4nt er war.ce of the'APWR wath See Att achttent F j RG J. Lb he.' laden 2 (14.2.12.3) i 104. TMI a t e m.; (14.2.12,3) See Section 1A2.4 10r general 'f assessment: Ch a pt er -- 14 c ompl i e:. i with tert 4ng'r. elated item" -123 ' Functioning of conductivity P ovided 2n-Amendment 18 tre te r s ' ( l a. 2. l'. 4 ) 2 a 12G '. Mod 111catton to feedwater See current Subsect2on control test deccription 14.2.12.2.14(3) (page 14.2-53) (14.2.12.41 and-nev Table 14.2+1 (pager., l 14.2-66.'2 througn 14.2-60.5) attached 127. Clarificition of feodwater Provided in Amendment 18-i ~ %tr01;tect' accepts 6cen-l c r 1.l e i 1 U .( 1 4. 2, 1 2. 4 l-1 i i l ,. - ~,,.. -., _.. _., -, _, - - -. ~

i d i i 5 i l 1 I i l l 4 j e 23 Total a l'r d e rt: te n d f o r f'rovaded in Atnendment 16 4, .anatrutnent a i r ' a ri d. e l a t ). o n j l air'(14.2.1;.4) 1 4 [ 129 Funct2cnal testing of f rovided in Amendinent 18 -t i tite t s u m e n t rend control te i r [- r, y c t etw (14.0 12.4) j 1 e l 130-liVAC preoperat1

testing Provided an Amendment le seqv'semente

(' '4) l 102 De L a g ts, rn a i n t e n s t.c e, and Irovided in Attendtvent 18 j teut1ng crater 10 f oi f V M t a l u t i o n c y c t e t<2. <14.2.1^ 4* 132 1.H G O y c t e rn acolutat9 See revised Subsectiori i tl'.". 12.4) 14.2.12,1.S(!(1) (page j 14.2-3) attached r 133 'a.a111;ation cel relief Provided in Amendrent 18 l alve t e t t a r.g r. by vendor t". n r h t e,e t r, (14.2.12,41 Eviette1.ircueu 12ce In addition to the DGER. --+ OC ' NM t1o r c h b,.19% 1ccuese several of-the a c c.u e a i. c o n j i. s vac e c.,a l l identified in the (;ubject cosu J' forence. call hevo been addrecced l 1J4 App oval vi hLDYA und bl>Yli A The liRC c.taf f and itu concultunt, { (IN i) th ochhaven National L. abor atory, j perf or reed an on*aate eudat at GE ls officen an Can .l w e, Califernia L Janualy 20 30, 1992. G L l ii. vaatang .i ior the audat report. { l' 105 6. af feeVwates heater GE a.ubinitted eddstional: 2 n f or tna tion tr.inz.leat (10.1 Item (1)) to the NRC in letter I. W. !!arrAott t i t o R. C. Pierson dated 1/10/92. l GE la vaiting for NRC responce { 136 U:>ftware re11ab112ty in the February 26 l'#R determining 11 mating.Aaults-stemming from t 1% 1 Item <3)) GE/NRC meeting.-in Rockville 137-had bioch algorfthm.and GC submitted additional informataon [ setpoint (IS 1 Item ( 4 ) ( b ) )-- to the NRC in letter P. W. 114 r a c t t t o R. C. Piercon c'a ted 1,10/92. IDE' C4edst for-nonicafety grade [GE provided additional anfornation equitocnt-in safety-analycic as requested by the NRC on t (1% 1 Iten (6)) February 28, 1992. f G.39 dlow-turbine contr:1 volve .DE vill cubmit addstional cloeure event (15.1 Item (G)) -information by March 6,-199. D

dp 8 i d I I i . i l 1 - 4C Compliance of ATWS Rule GE vill revise Appendix lbE by 3 i 2 0C TR50. G2 (15.4) March 31, 19 0.?. 141 Precoure eupprecuron pool as A repubmittal of the rediological 4 l-a faccion product cleanup portionc of Subsection 15.6,b hac l cyatem 4 3 L. 3 (1)) been made (TAX, Carevay to Lee, I dated 2/1/92 and FAX, Fox to Poslucny, dated 2/13/92) w i t. h further detalles arid j urst i f ica t 2 on for ucing suppressiori pool 1 scrubbing. The staff has stated l 3 that there la t rasuf ticient. t.ime to l ]I revaew thiu area and therefore a revised submittal is under prep-j 1 l1 paration it. which credit f or j l cuppressioti poc1 scrubbAng ic F deleted. i i ) - 142 haoacactive iodine deposition The resubmattal under iceve (141) a n t he rtw n stcau lire and also utill ed the DWROD ICIV - n ce r. (15,3 (3)) methodology. Additionally l l -discucsaonc between the HRv and GC A i have resolved the question of the l upplicability of uulng the clean i linen and the main condencer j j mitigation pathvuy. l l l lonk rate Eccponov to be paovaded by l l= - 43;

t. o n Uu n me n t l

i15.a.1: tiarch 31, 19%. { l l ' 144 Comp 12.at.c of-ATWC Hulo GE will revir.e Append 1>. 1LE ty l 1 M FTw 3. C ; i I S. 4 > March 31, 1992. 145 Ccwpliam.e with 10CFR Reeponse provide d on attached pagen l 50.LLstgi t 5. 2, t.G)* is 6 - 11 :. and 6.6-1 thrcugh 6.6-D. l l'4 C ' N r.19 r. boss r torn ^ do analysee GE ic waltang ior f o r tr a l atafi l a ..a.2> guidance on the tornado j characteristics l ? 1 e t I i 'h i t ? ? f. --wa.om-,,,s---__ - n _ - --._ ,0-_ a a.,._ m w A m-S -. _ m,menes.ww.. - -... se* v

\\ k f 1. $UMM AfiY ' RESPO!4SE TO OUTST/.HDiNG AND CONTIRM ATORY ISSUES OF 4 i ADWh DOEh CHAPTEh3 1,2,3,S.L 8,10,12,13,14 and 15 4 SCCY *1-353 ) Coniir tr ster y lerve Dr.;L;;,t.A ri t i ;.s R e r; o l u t i o n / C o mtr e n t 1 i-l- 1 GL c o mni t tne r,t to add Frovided in A enendir en t 16 f.t.d a d d i t i c r.ts j r es crencec t c-revised Tabic 1.8-20 (page 1.D 42's i h6; i 14. 2. 7 > attached. 1 [- 2 Completic.n of pre-operatior:a1 Pr ovided in Amet.dtrerst 10 t es t ing -( 1 -1. 2.10 )

1. '

1 I~ 1-N i 1 3 i e 4 )- i s T i N 1 2 t + 5 4 m i i n f-e 2 I i .w,L.-...--~_ -..,_r.

ABWR mac Samlant P1 ant yrv, c TAllLF 1.8 20 f3 } }(Gs Appilrable to AllW}t (Continued) AllWR Appl. Inued Appil- ] RG No. Reculaton Gu!Atlith Em Datt ratld 1.'coautnta 1.60 Design Response Spectra for Seismic Design 1 12/73 Yes of Nuclear Power Placits. 1.61 Damping Values for $cistnie Dei,ign of Nu-0 10/73 Yes clear Power Plants. 1.62 Manuallnitiation of Protenive Actiora. 0 10/73 Yes 1.63 Electric Penetration Antablies in Contain-3 2/87 Yes ment Structures of Nuc!t:0 Power Plants. i 1.(4 Ouality Assurarme Rena(rtments for the De. Superceded See Table 6ign of Nuclear Power Plat ts. 17.0 1 1.65 Materials and Inspections for Reactor Yes. 0 10/73 Yes sel Closurc Studs. 1.68 laitialTest Programs for Water Cooled 2 8/78 Yes p)g Reactor Power Plains. q 1.fdl Picoperational and initial Stattup Ter, ting 1 1/77 Yes of Feedwater and Condenate Systems for Boiling Water Reactor Power Plants. 148.2 initial Startup Test Program to Demonstrate 1 7/~'8 Yes Remote Shutdown Capability for Water Cooled Nuclear Power Plants. O A/82 1.f&3 Preoperatiotial Testing of Instrument and + 46s Yes Control Ali Systems. 1.69 Concrete Radiation Shields for Nuclear Po-0 12ff3 Yes wer Plants. 1.70 Standa?d format and Content of Safety Ana-3 11/78 Yes lysis Reports for Nuclear Power Plants. laterface 1.71 Welder Qualifications for Areas of Limited 0 12/73 Accessibility. 1.72 Spray Pond Piping Made from Fiberglass-2 11/78 Yes Reinforced Thermosetting Resin. /T NY 3b4 Amtedment 14

i ABWR zway Standard Plant Prv,_D b TABLE 3.2 1 J CLASSif'ICATION SUMhiAM (Continued) Quality Group Quality Safety loca. Clant. Assursate Seismic l'EitdPd.C2mranfJ11" Clan g,ge kabd M rmtM' h m# h b i til Main Control Room Panel i B/E l/~ (aa) { L Panels 3/N X B I 2. Electrical Moduhs with 3 X ~ tafety related function B 1 3. Cable with safety.related 3 X ~ function E l* 4 Other snechardcal and N X ~ electrical module % I fG 'rt2 Local Coiitrol Panels V D/E 1/-- (aa) L Panels or Rkcks 3/N C.SC,X = .X E I 2, 5;lectrical enodules with 3 C.SC.X ~ safety related furaction B 1 3. Cable with aafety-related 3 C.SC,X, functbn E l 4. Other mechanimi and N C.SC,X chcaricti rnodules l K1 Radioatthe Drain Transfer Syste:m k L Draia piping including supports N ALL D E (p) and vahn. radioactive (except) RZ,X) (p) 2. Drain piping including r,upports N ALL D E and valves. nontadioactive 3. Piping and valves. contain. 2 C,$C B B 1 i ment isolation O 4, Other succhanical and N ALL (p) I E ~ d electrical modules F. E C C,$ q s & t0% h C 0

• [

fed m p b r,, l0W pf8' At:ct,dmerit 17 g go g f.Qs.K ydm 3221

mnxo ABWR nv c $1sndard Plant ) ( years in BWR applications. Estenthe laboratory tests base demonstrated that XM.19 is a suitable material and that it is resistant to stress corrosion in a BWR ensjtonenent. i 4JJ Interfacts 4J.3.1 CRD inslection Program \\ The CRD inspection prograta shallinclude provisions to dettet incipient defects before they could becerne serious enough to eaune operating problems. (See Subsection 4.5.1.2(2)J The CRD nogle and C AD boi4sr c r e t e cl u d e. d i n %.g. g n j oy vs c. e.3 (,S4< in s pe c. hoc pro p e. um bu Toble s.2-s, spim Bi t / Sit] CRD boldW3ti av a s \\ ab\\ t f o r in 5 avvs c e, e 3, a vm a csk\\ow ; dee3 6 ov yn allg s ek4da\\ ed c g.o mm-h ow e.e. P s F 'd l mt n. .. a

l ABWR nune i Sandard Plant uvc I s(v) SECTION S.2 CONTENTS (Continued) &ction Title Euc 5.2.43.23 Suriace Euminations $.217 5.2.43.2.4 Volumetric Ultrasonic Direct Eurnination $217.1 5.243.2.5 Alternative Examination Techniques 5.2 17.1 %24 1A '* *th h' a + * ' I P ' ' " " I U * * * *' d ' * ^ 5.2 17.1 5.2.433 Data Recording 5 t.n. t $2di in%e$Io^n'IItErds ' " * ' ' ~ " 5.2 17.1 5.2.4.5 Evaluation of Examination Results 5.2 17.1 5.2.46 System Leakage and Hydrostalle Pressure Tests 5.2 17.1 5.2.4.6.1 System Leakage Tests 5.2 17.1 12.4.6.2 flydrostatic Pressure Tesa 5.2 17.2 5.2.4.7 Code Exemptions 5.2 17.2 Y5.2.4.8 Relief Requests 5217.2 j 5.2.4.8.1 Reactor Pressure Vessel Nonles 5.2 17.2 5.2.4.8.2 Reactor Pressure Vessel Bottom llead Weld 5.2 17.2 5.2.4.81 Reactor Pressure Vessel Bottom llead to Shell Weld 5.2171 a 5.2.5 Beactor Coolanthissurt f.laundars and Cort Coollne Siskms 14mkare Detectipjl 5.2 18 5.2.51 L4akage Detection Methods 5.2 18 5.2.5.1.1 Detection of Leakage Within Drywell 5218 5.2.5.1.2 Detection of Leakage External to Drywcli 5.2 19 5.2.5.2 leak Detection Instrumentation and Monitoring 5.2 20 5.2,5.2.1 Leak Detection Instrumentation and Monitoring inside the Drywell 5.2 21 ( 5.2-vi \\ Amendment 13

I ABWR mn. mc &ndard I'larit l radiograrby or UT, the length of the weld to ol4he,W,4M". "V C - !- S ^ % IA Os be examined shall include the location least fasorable for the welder. fl.4.1 Class 1 Sptrm floundary Records of the results obtained in welder !J.J.l.1 Definition accessibility qualification shall be as certified by the manufacturer or installer, The class I system boundar) for both shall be maintained and shall be made preservice and inservice inspection programs and accessible to authorized personnel. the system pressure test program includes all those items within the Class 1 and Quality Group Socket weld with a 50A nominal pipe site and A boundary on the piping and instrumentation under are excluded from the above drawings (P&lDs). That boundar) includes the r e quir e m e at 5. following-p (2) (a) for acces ibility, when more restricted (1) Reactor pressure sessel access conditions than qualificd uill (2) Portions of the main steam sptem N obscure the welder's line of sight to (3) Portion > of the feedwater sptem the extent that production welding will (4) Portions of the standby liquid control require the use of visual aids such as system mirrors. Th: qualification test as. (5) Portions of reactor water cleanup system sembly shall be welded under the more (6) Portions of the residual heat temmal system restricted access conditions using the (7) Portions of tbc reactor core isolation visual aid required for production cooling system welding. (8) Portions of the high pressure core flooder system (b) GE cotoplies with ASME Section IX. f Those portions of the above systems within x ()) Surseillance of accessibility qualification the Class 1 boundary are those items which are requirements will be performed along with part sf the reactor coolant system up to and normal surveillance of ASME Section IX including any and all of the following: performance qualification requirements. (1) the outermost containment isclation valve in 5.3.3.4.3 Hegulatory Gulde 1.66: the system piping which penetrates prirnary Nondatructise Examination of Tubular Products reactor containment. For discussion of compliance wit'n Regulatory (2) the second of two valves normally closed Guide 1.66, see Subsection 5.2.3.3.3. during normal reactor operation in system piping which does not penetrate primary 5.2.4 Prescrdce and Inservice teactor containment, inspection and Testing of Reactor Coolant Pressure Iloundary (3) the reactor coolant sptem safety and relief

valves, This subsection describes the preservice and inservice inspection and system pressure test (4) the main steam and feedwater system up to programs for NRC Ouality Group A, ASME Boiler and including the outermost containment Class 1, items.' It describes those programs isolation valve.

implementing the te uisements of Subsection IWB Pressure Vessel (B& QCode,Section@ XI 5.2.4.1.2 Exclusions i Portions of systems wituin the reactor

• Items as used in this subsection are products coolant pressure boundary, as defined in constructed under a Certificate of Authori:ation 5.2.4.1.1, that are excluded from the Class 1 (NC t-3120) and material (NCA 1220). See Section boundary are as follows:

g J 111. NCA 1000, footnote 2. $.215 t Amendment 17 [

E ) hl S G RTS F OR-PA G C 5 2-t 5. t !O I l IA The ASME Code requirements provided in this section for nformation are based on the 1989 Edition of ASME Section J XI. The preservice and inservice inspection requirements and accepted code Editions and Addenda are specified by 10 CFR, Section 50.55a. I i l ID Based on 10 CFR (1-1-90 Edition) and Regulatory Guide .26, Revision 3, I I j. h based on 10 CFR (1-1-90 Edition), l i l 1 j.. t

j. -

l l: i i I l lO 4 i \\ i [ i O i L..--...-. m. ..___,._--.._m_-~ -. ~.. -.. - -

1 ABWR wmn .. p ts c Sandard Plant (1) th >se components where,in the event of (2) RPV Welds Abose Top of the Biological Shield l pos;ulated failure of the ecmponent during Wall normal reactor operation, the reactor can be shut down and cooled down in an orderly Auess to the reactor pressure sessel welds abose rusnner, anuming makeup is presided by the tcp of the biological shield wallis prodded by the reactor coolant makeup system only; and removable insulation pantis. This design provides reasonable acceu for both automated as wc!! as (2) components which are or can be isolated manual ultrasonic cumination. from the reactor coolant system by two s alves (both closed, both open, or one closed (3) Closure Head, RPV Studs, Nuts and Wasbers and one open). Each such open salve is capable of automatic actuation and if the The closure head is dry stored during refueling. other vahe is open its closure tirne is such Remosable insulation is designed to prodde accen that,in the event of postulated failure of the for manaal ultrasonic euminations of closure head component during normal reactor operation, welds. RPV uuts and wasbers are dry stored and each vahe remains operabe and the reactor are accessible for surface and visual (VT 1) can be shut down and cooled down in an examination. RPV studs may be volumetrically orderly manner assuming makeup is cumined in placc or when removed. prodded by the reactor coolant makeup sptem only. (4) Bottom Head Welds iD 7 Access to the bottom bead to shell weld and bottom $J.4.2 Accessibility head seam welds is provided through openings in Allitems within the Class 1 boundary are the RI'V support pedestal and removable insulation designedM 'b :":e ;= d':Ito prodde panels around the cylindricallower portion of tne access for the examinations required by ASMK E venel This destra trovides accen for manual or Section XI, IWB 2500. !' n fr- %h4he-automated ultrasonic examination equipment. 1-- " - h w+-4ekmal-+:::: : Sufficient aucu is provided to partial penetration O dadp ( e4%m ::: d: :% d F %m a.W e n or rie w eld s,1.c., CR D p e n e t r a tion s, instrumentation nonles and recirculation internal 1E !J.4.2.1 Reactor Prtssurr Vessel Access pump penetration welds, for performance of the visual, \\T.?, cumination during the system leakage Access for etaminations of the teactor and system hydrostatic examiaations, pressure vessel (RPV)is incorporated into the design of the vessel, biological shield wall and (5) Reactor Vessel Support Skirt vesselinsulation as fo!Jowv The integral attachment weld from the number four (1) RPV Welds Below the Top Biological Shield shell course forging to the RPV skirt will be examined ultrasonically. Sufficient access is Wall provided for either manual or automated ultrasonic The shield wall and ve.selinsulation behind examinatica. Access is provided to the balance of t the shield wall are spaced away from the tbc support skirt for performance of visual, VT 3, RPV outside surface to provide access for cumination. remotely operated ultrasonic examination devices as described in Subsection 5.2 4.3.1.1 $.2.4.2.2 Piping, Pumps Yahes and Supports Access for the insertion of automated devices is provided through removable Physical arrangement of piping pumps and vahes insulation panels at the top of the shiclu wall provide personnel access to each weld location for and at access ports at reactor vessel nonles. performance of ultrasonic and surface (maEnctic Platforms are attached to the bioshbid wall partic!c or liquid penetrant) examinations and sufficient to prodde access for installation of remotely access to supports for performance of visual, VT 3, operated noule examination devices. cumination. Working platforms are provided in some $2 M Ams tdment D

gNssRTS FOR P AGG

5. 2-\\6 O

h Items (1) and (2) above describe the Class 1 boundary only and are not exemptions as defined by Section XI of the ASME Boiler and Pressure Vessel Code (ASME Section XI) IE Items such as nozzle-to-vessel velds often have inherent ccess restrictions when vessel internais are installed therefore the preservice examination shall be perforraed on these items prior to installation of internals which would interfere with examination. 1 O O

ABWR -n Standard Plant sen iWA-2BMeh-and %~ V, Artide-4Iln addition thb) / \\G f areas to facilitate servicin;; of pumps and vahes. \\m Platforms and ladders are prodded for access to ultrasonic examination system shall meet the - piping melds iacluding the pipe.to reactor vessel requirements of Regulatory Guide 1.150 as described in nortle welds. Removable thermalinsulation is Table 5.2 9. RPV welds and corries subject to prcnided on welds and components which require cumination are shown in Figure 5.2 7a. frequent access for cumination or are located in high radiation areu. Welds are located to permit The GE reactor sesselinspection system (GERIS) ultrasonic enmination from at least one side, but meets the deteetion and siring requirements of where component geornetries permit, access Regulatory Guide 1.150, as cited in Table 5.2 9. Inner from toth sides is presided radius cuminations are performed from the outside of the corric using several corupound angle transducer Restrictions: For piping systems and wedges to obtain complete coverage of tbc required portions of piping systerns subject to volumetric examination volume. Electronic gating used in GERIS and surface curnination, the follov.ing piping system records up to 8 different reflectors designs are not used. simultaneously to assure that all relevant indications are recorded. Appendix 5A demonstgted compliance with (1) Valve to Vahe Regulatory Guide 1.150. (2) Vahr to Reducer (3) Valve to Tee 5.2.43.2.2 Visual Examination (4) Elbow to Elbow (5) Elbow to Tee Visual examination methods, NT 1, VT 2 and W 3, (6) Norzle to elbow shall be conducted in accordance with ASME Section (7) Reducer to c! bow XI, IWA 2210. In addition, VT 2 cuminations shall (8) Tec to tee meet the requrements of IWA 5240. (9) Pump to valve Direct visual, VT 1, examinations shall be O Straight sections of pipe and spool pieces conducted w.tb sufficient lighting to resolve a 0.8mm l d shall be added between fittinEs. The minimum black lice on in 18% neutral grey card. Where direct length of the spool piece bas bece determined by visual, VT 1, xaminations are conducted without the l using the formulate L = 2T + 152mm, where L use of mirrors s r with other viewing aids, clearance (of equals the leagth of tbe spool piece (not at least 610mm of clear space)is provided where feasible l including weld preparation) and T equals tbc for the head and shoulders of a man within a working pipe wall thickneu. arm's length (50Rmm) of the surface to be enmined. l 5.2.4.3 Eumination Categories and Methods At locations where leakages are aormally expected and leakage collection systems are located, (e.g., valve stems and pump seals), the visual, \\T 2, examination 5.2.4.3.1 Eumination Ca"gories g (provud a s % eep O sball verify that abe leakage collection system is The cumina ion category of each item is listed operative. in Table 5.2 8 The items are listed by system and line number where applicable. Table 5.2 8 Piping runs shall be clearly identified and laid out also states the snethod of exarnination for each such that insulation damage, leaks and structural distie s item. Tbc presenice and insenice examination will be evident to a trained visual cuminer. plans will be supplemented with detailed drawings showing the examination areas, such as 5.2.4.3.2.3 Surface Examination Figures 5.2 7a and 5.2 7b. tF Magnetic particle and liquid penetrant examination 5.2.43J Eumination Methods techniques shall be performed in accordance with ASME Section XI, !WA 2221 and IWA 2222, 5.2.4.3.2.1 Ultrasonle Esemination of the respectisely. Direct examination access for magnetic Reactoe Vessel particle (MT) and penetrant (PT) examination is the same as that required for direct visual (VT 1) p Ett*tes mme.w of-tht-RM wrtr-tv-- examination (Subsection 5.2.4.3.2.3), except that 1 -umdwh*cor4anwh-A&MIMeetien-M-- (J Amendment t$ $ 2-17

.. ~ -.. -. - (N sG0LTS FOR PAGG s.2-17 l w IF For the preservice examination, all of the items selected or inservice examination shall be performed once in accordance with ASME Section XI, IWB-2200 with the exception of the examinations specifically excluded by ASME Section XI from preservice requirements, such as VT-3 examination of valve body and pump casing internal surfaces (B-L-2 and B-M-2 examination categories, respectively) and the visual VT-2 examinations for categories B-E and B-P. h Ultrasonic examination of the RPV will be conducted in accordance with applicable ASME section XI requirements, including qualification of ultrasonic examination systems in accordance with an accepted industry program implementing the rules of Section XI, Appendix VIII. [\\

ABWR uumn me Standard Plant additional acteu shall be provided a necessary to snay result in improvements in cumination rehabibry coable physical contact with the item in order to and reductions in personnel exposure, i perform the examinatibn. Remote MT and PT generally are not appropriate as a standard 5.2.4JJ Data Recording examination process, homeser, boroscopes and minors can be used at close range to improse tbc Manual data recording will be performed where angle of vision. As a minimum, insulation manual ultrasonic examinations are performed. removal shall expose the area of each weld plus at Electronic data recording and comparision analysis are least 152mm from the toe of the weld on each to be employed with automated ultrasonic ex. amination side, lasulation mill generally be removed 406mm equipment. Signals form each ultrasonic transducer on each side of the weld. will be fed into a data acquisition system in which the key partrneters of any reflectors will be recorded. The 5.2.4J.2.4 Volumetric l'ltrasonic Direct data to be re4crded for manual and automated smethods Eumination are: Volumetric ultrasonic dirett examination (1) Location shallbe performed in accordance with ASME (2) Position Section XI,IWA.2232. In order to perform the (3) Depth below the scann'ng surface (4)1.ength of the reflector l examination, visual eccess to place the head and (5) Transducer data including angle and frequency shoulders within 508mm of the area of interest shall be provided where feasible. Nine inches (6) Calibratien data between adjacent pipes is sufficient spacing if there is free acteu on each side of the pipes. The The data so recorded shall be compared with the transducer dimension has been considered: a results of subsequent examinations to determine the [ 35mm diameter cylinder,76mm long placed with behavior of the reflector, accns at a right angle to the surface to be M \\H cumined.' Tbc ultrasonic examincion instrument 5.2.4.4 Inspection latervals has been considered as a rectangular box 305 x 305 x $0Smm located within 12m from the Tbc inservice inspection intervals for the ABWR transducer. Space for a second examiner to will conform to inspection Program B as described in monitor the instrument shall be provided if Section XI,lWB 2412. Excent where deferralis pertoitted by Table IWB 25001, the percentages of l L neceuary. exarrinations completed within each period of the Insulation ternoval for inspection is to allow interval shall conespond to Table IWB 24121. It+w+ sufficient room for tbc u!trasonic transducer to 6+1+ cad 4oS - of ^ S S y Wes m [II i scan the examination area. A distance of 2T plus de$mbed is; Tebk 5.2-6. 4 b l52mm where T is pipe thickness,is the minknum required on each side of the examination area.The 5.2A5 Evaluation of Examinttloa Results l insulation design generally leaves 406mm on each side of the weld, which exceeds minimum Examination results will be evaluated in accordance with ASME Section XI,IWB 3000 with repairs based requirements, on the requirements of IWA.4000 and IWB 4000. 5.2.43.2.5 Alternative Examination Techniques Re examination shall be conducted in accordance with the requirements of IWA.2200. The recorded results As provided by ASME Section XI, shall meet the acceptance standards specified in IWA 2240, alternative examination methods, a IWB44001. c l-combination of methods, or newly developed l, . techniques xnay be substituted for the methods 5.2M Sptem I4akage and Hydrostatic Passert Tests specified for a given item in this section, provided that they are demonstrated to be equivalent or 5.2.4.6.1 Sptem Isakage Tests superior to the specificd method. This provision allows for the use of newly developed As required by Section XI IWB 2500 for Category examination methods, techniques, ete_., which B P, a system leakage test shall be performed 1.2.t7,t Arne ndment 13 .,--6 y , g,y g. r-y---ym_77,,p, ..,,,,.,pw..__9,, ,m,.,, ,.,,,,,3ym , m. % _,._%%v.y,.,. ,,,----m.rw-,

I N S EP:.T C FO(t PAGs $. 2 - t ~7. I () t i (b i 5.2.4.3.4 Qualification of Personnel and Examination Systems for Ultrasonic Examination Personnel performing examinations shall be qualified in accordance with ASME Section XI, Appendix VII. Ultrasonic examination systems shall be qualified in accordance with an industry accepted program for implementation of ASME section XI, Appendix VIII. [b)e conducted within the 10-year intervals are described in I An example of the selection of items and examinations to Table 5.2-8. Supplemental examinations recommended in GE Service Information Letters (SILs) and Rapid Communication Service Information Letters (RICSILs) for previous BWR designs are not applicable to the ABWR. The ABWR design has cither eliminated the components addressed by the SIL or

RICSIL, e.g.,

jet pumps, or has eliminated the need for the examination by eliminating creviced designs and using O-materials resistant to the known 3egradation mechanisms, such as intergranular stress corrosion cracking, upon which the SIL and RICSIL examinations were based. F 1 O h ,, - - -., - - - + -...,. ,n,,

ABWR mm Sandard Plant %e in accordance witb IWB 5221 on all Class I beetion X1, Table IWB 1Mo.1 for catego[B.D. willId inacteuible for ultrasonic eumination. The ultras l components and piping within the pressure O examination is conducted from the outside surface of retaining boundary following each refueling outage. For the purposes of the sptem leakage the RPV and, as such, tbc outside radius of the nozzle test, the preuure retaining boundary is deftned in ferging limits tue mesement of the ultrasonic search Table IWB 15001. Category B P, Note 1. The unit. The typical scan litnitation resulting from this system leakage test shall include a VT.: geometry is illustrated in rigure 5.2 7c. The extent of cumination in accordance with IWA 5240. The the cumination coverage limitation for each noale will system leakage test will be conducted be determined during the presmice tumination of tbe I approximately at the roaximum operating RPV oonje tcrveuel welds. pressure and temperature indicated in the applicable proceu flow diagram for the system as

!.2.43.2 Reactor Pressurt Vessel httom llead Weld indicated in Table 1.71. The system bydrostatic test (Subsection $14.6.2), when performed is Access to the bottom head weld for ultraionic acceptable in lieu of the system leakage test.

examination is limited due to penettations in the bottom head for the reactor internal pumps, contio! rod !J.J.6.2 flydrostatic Pressurt Tests drives and incore econitors. Partial coverage will be , possible. Tbc extent of the examination coverage As required by Section XI,IWB 2500 for i limitation for each nonje will be determined during the ', Category B.P.the hydrostatic pressure test shall presenice cumination tbc RPV bottom head weld. j be perfortned in accordance with ASME Sectisn TNB.5222 on all Clau 1 components and piping 5.2.4JJ Reactor Pressure Vessel httom IIcad.to Shell within the pressure retaining boundary once Weld during each 10 year inspection interval. For purposes of the hydrostatic pressure test the Access to the RPV bottom head to shell weld for ultrasonic cumination is limited due to the proximity of pressure retaining boundary is defined in Table IWB.15001, Category B P, Note 1. Tbc system the RTV skirt pedestal on the sbcIl side, and the cuned O hydrostatic test shallinclude a VT 2 eumination surface of the bottom head itself interferes with in accordance with IWA 5240. For the purposes examination from the bottom bead side of the weld. l of determining the test pressuf e for tbc system Only !imited cumination coverage can be achieved on l bydrostatic test in accordance with fWB-5222 (a), this weld, however, the actual extent of the cumination the nominal operating pressure shall be the coverage will be detemined during the presersice maximum operating pressure indicated in the cumination of the RPV bottom head to4 bell weld. j / process flow diagram for the nuclear boiler system, Tipre 5.13, 52.4.7 Code Exemptions As provided in ASME Section XI, fWB 1220, certain portio':t, of Class 1 systems are exempt from the volumetric and surface cumination regt.irements of IWB 2500. These portions of systeras are specifically identified in Table 5.2 8. .2.4J Relief Requests 5.2.4.8.1 Reactor Pressurt Vessel Nonles l Due to the inherent geornetry of the RPV nozzles, some portion of the nozzle to vessel weld required volume as specified in ASME 52172 Amenompt 13

O O O p Table 5.2-a EXANINATION CATEGORIES [ lii.I. il [N [ b Quality System Systes System P&ID Sec. X! Itces Exam Group Number Title Description Diagram Exas Cat. Examined Method y

s A

B11/821 Reactor Reactor Pressure Vessel Figure Pressure 5.1-3 Vessel / Vessel Shell Welds B-A Welds UT (Note 7) i Nuclear Boller Vessel Head Welds B-A Welds UT (Note 7) Shell-to-Flange Weld B-A Weld UT l Head-to-Flange Weld B-A Weld UT, MT t Nozzles for: B-D

Welds, UT Inner Main Steam, Feedwater, Radius 50 Outlet, CCS(Fidg.) &

50 Inlet, 50 - RWCU SD Outlet, CCS(Spray) & SD Inlet Nozzles for CRD, RIP & B-E External VT-2 Surfaces (Note 8) ( I lastrumentation S-G-2 s.145 v T-s Closure Head Nuts B-G-1 Nuts MT [ + I Closure Studs B-G-1 Studs UT, NT f (Note 9) l + I Threads in Flange B-G-1 Threads UT I Closure Washers, Bushings B-G-1 VT-1 p i I B-H Welds UT or MT ,{ integral Attachments (Note 10) Qh n" 2 5 B-N-1 Vessel VT-3 Vessel Interior (Note II) { { i fo M'E d N" occl Mid Ji@ 'F%$<.+=SpeeI CRD pousm tct 8*I I I

ABWR zwun SinndardyJattL., MT c Support types and materials used for lisolatable portions of the following systems: $1.C, Ri1R,11PCF, and RCIC. The tel el nhes fabricated support elements are to conform with Q] r will be selected in accordance with the rules set Sections NT 2000 and NF 3000 of ash 1E Code forth in the AshtE Code Section 111, Class 1,2 Section Ill. Pipe support spacing guidelines of and 3 components. Other applicable sections of Table 121.14 of ANSI B31.1, Power Piping Code, the AShtE Code, as well as ANS1, API, and ASThi are to be followed. Codes, will be followed. $A.ld.2 Description 5.4.13.2 Description The use and ti.e location of rigid type Pressure relief valves bute been designed and supports, variable or constant spring type ccostructed in accordance with the same code supports, snubbers, and anchors or guides are to class as that of the line valves in the system. be determined by flexibility and seismic / dynamic stress analyses. Component support elements are Table 3.21 lists the applicable code classes manufacturer standard items. Direct weldment to for valves. The design criteria, design loading, thin wall pipe is to be avoided where possible. and design procedure are described in Subsection 3.9.3. 5.4.14.3 Safety Daluation f.4.13.3 Safety Daluation The flexibility and seismic / dynamic analyses are to be performed for the design of adequate The use of pressure relievint desices will component support systems including all tran. l assure that oser pressure will not exceed 109 sient loading conditions expected by each abose the design pressure of the system. The component. Provisions are to be made to provide number of pressure. relieving devices on a system spring type supports for the initial dead weight or portion of a system has been determined on loading due to hydrostatic testing of steam this basis. systems to prevera damage to this type support. A $.4.13.4 (Deleted) $ 4.14.4 Inspection and Testing - n...,. a - s.. w-m n, After completion of the installation of a j support system, all hanger elements are to be j visually examined to assure ti at the) are in / correct adjustment to their cold setting / position. Upon hot start up operations,[ thermal growth will be observed to confifm that spring type hangers will function properl) 5,4,14 Cornponcat Supports between their hot and cold setting positions. Final adjustment capability is provided on all Support elements are provided for those hanger or support types. Weld inspections and components included in the RCPB and the connected standards c.re to be in accordance with AShfE Code systems. Section Ill. Welder qualifications and welding procedures are in accordance with AShtE Code !.4.14,1 Saftty De>lgn Bases Section IX and NT-430C f AShtE Code Section 111. Design leading combinations, design 5.4.15 References procedures, and acceptability criteria are as described in Saksection 3.9.3. Fle xibilir y 1. Design and Performance of General Electric calculations and Seismic analysis for Class 1 2, Bolling Water Reactor Muin Stram Line and 3 components are to be confirmed with the Isolation l'olrrs, General Electric Co., appropriate requirements of AShtE Code Section Atomic Power Equipment Department, hiarcb 111. 1%9 (APED.5750). O a Amet.dment 13 $ 4-30

ABWR nu un Sandatdj%Bt MVc Table 6.2 9 Secondary Containment Penetration Listi / Pene tration Name Eleistion Diameter N u rr...- (mm) (mm) 1 RCW (B) 8%0 ((O 2 RCW (B) 8%0 6(O 3 HPCF 8%O MO 4 SS 8No 50 5 RD (LCW) 8%O 60 6 RD (SD) 8%0 65 7 RD (flCW) 8NO 150 8 TV -8200 250 9 RCW (A) 8%0 NO 10 RCW(A) 4NO NO 11 RCW (C) 8%0 $50 12 RCW (C) 8200 550 13 IIPCF 4%0 MO 14 MUWC 8%0 250 15 CRD 8%0 150 16 CRD 8%U 50 17 SPl! 8NO 150 18 RCW (B) 17(0 150 19 RCW (B) 17(O 150 20 RCW (B) 17(0 30 21 RCW (B) 1700 200 22 MS 1700 80 (]) ( 23 SA 1700 65 24 1A 1700 50 25 FP 1700 150 26 RCW (A) 1700 150 27 RCW (A) 1700 150 28 RCW (A) 1'r00 200 29 RCW (A) 1700 NIO 30 HSR 1700 130 31 RCW (C) 1700 100 32 RCW (C) 1700 100 33 RCW (C) 1700 200 34 RCW (C) 1700 XO l 35 HS 4900 150 l 36 MS 4800 80 l 37 LCW (FPC) 4800 150 l SS LCW (CUW) 4800 150 39 RClC 4800 50 l 40 MS (4) 16191 700 l 41 FDW (2) 13810 NO 42 HVAC Exhaust 27%D 4 43 HVAC Supply 31700 4 44 Controlled Access (2) 12M0 vv 45 Equipment Lock 12300 % 'd 46 Railroad Car Door 12300

• 4 47 HS 12300 150 7-48 HWH 12300 150

(( Ama ncment 14 623035

ABWR momo Slandatdflant MLC i Table 6.2 9 Secondary Containment Penetration List (Continued) (f Penetration Name Eleistion tilameter Number (mm) (mm) 49 liWil 12X0 150 50 IINCW 12XO 200 51 liNCW 12X0 2(O $2 MUWP 4MO 150 $3 AC 4MO $0 54 AC 4MO IV) 55 11Wil 4MO 50 56 11Wll 4MO 50 57 Cabletrays 23500 58 Cabletrays 12300 59 Cabletrays 4MO Note: 1. This Table prmided in response to Question 430.34 a h e-v e. S dsk. M cM L d 5 T h e 3c. NV A C, o p om o g \\/ G V C 3 wds hcMs koca( waoss d oei.sg s sC Ok\\On k I Ci *$ d v' C e 04C ( i n% Cord rok V o o tw) \\" O n \\ of$^CJ-gy ThcSQ d O Q($ G 4 m CW s or4 h 4 n TC C, C s fC( \\" 0 0 WS Cs 5 {"> c r bu 3CC \\06 i 3. 6. 3. 4 LJ AV Amendment 14 023036

ABWR muun Standard Plant aiv c i SECTION 6.6 CONTENTS (Continued) SectIpn 1111e East 7 t 6.6,7 Anamented laserdct Ininection 6.43 l 6 4.11 Code Exemntions 6.65 j h,9 ~ EfHeilfGufill D.h.) 6.6.9.1 Class 2 Hydroststic Test Pressure 6.G$ [ 6.6.9.2 RHR Heat Exchanger Nonje to Shell Welds 6.45 ~ TABLES l Table Iltle East i 6.G1 . Examination Categories and Methods 6.6-6 W b Gnerg g PPu)

0. G.'7.1 y

- C, c ;7, 7. g r o ss i n-Co v e c t s o n i i r I ? 4 ? + 5 6.Glii j Amendment 13 4 ~. ...;....--..-~..___;_;.____._.. ..__._-,,-_.s____,_._.,___,...-___,.....,4_._.__

ABWR mm r_rv c Standard Plant producing the design basis hydrogen and backup purge function need not meet this osygen has occurred. criterion. (2) Tbc hydrogen generation frotn metal water (10) Components of the AC system inside the { reaction is defined in Regulatory Guide 1.7. reaetor building are protec ed itom s' postulated missiles and from pipe whip, as (3) The hydrogen and oxygen generation from required to assure proper action as well as radiolysis is defined in Regulatory Guide other dynamic effects such as tornado 1.7. missiles and flooding. 2 (4) The ACS establishes an inert atmosphere (11) The AC system isolation function has the throughout the primary containment following capability to withstand the dynamic effects 0 an outage or other occasions when the associated with the safe shutdown containment has been purged with air to ao caribquake without loss of function, oxygen concentration greater than 3.5 percent. (12) The system is designed so that all components subjected to the primary (5) Tbc ACS maintains the primary containment containment atmosphere (inboard isolatien crygen concentration below the maximum vahes) are capable of withstanding the permissible lirait per Regulatory Guide 1.7 temperature and pressure transients during normal abnormal and accident resulting from a LOCA. These components conditions in order to assure an inert will withstand the humidity and radiation atmosphere. conditions in the wetwell or dryw ell following a LOCA. (6) Tbc ACS also maintains a slightly posithe O pressure in the primary containment during (13) The ACS is nonsafety class except as O normal. abnormal and accident conditions to necessary to assure primary containment pervent air (oxyger) leakage into the inte grity (penet rations. isolation inerted volumes f om the secondary vahes). The ACS and TCS are derigned and containment, and ' rovides non-essential built to ti e requirements specified in monitoring of the r xygen concentration in Section 3.0. Ibc primary cortainment to assure a breathable mixture for safe personnel access or an inert atmosphere, as required. Essential monitoring is provided by the (14) The ACS includes the nitrogen storage containment atmospheric monitoring system tanks, vaporizers. valves and piping (CAMS) as described in Chapter 7. carrying nitrogen to the containment, vabes and piping from the containment to (7) ne drywell and the suppression chamber will the SGTS and HVAC (U41) exhabst line, be mixed uniformly after the design basis aon safety oxygen monitoring, and all LOCA due to natural convection and molecular related instruments and controls. The ACS diffusion. Mixing will be further promoted does not include any structures housing or by operation of the containment spra)s. supporting the aforementioned equipment or any ducting in the primary containment. 7 (S) The system is capable of controlling combustible gas concentrations in the (15) The system is desirned to facilitate containment atmosphere for the design bases periodic inspections and tests. The ACS LOCA without relying on purging and without can be inspected or tested during normal releasing radioactive material to the plant conditions, environment. i (9) Tbc system is designed to maintain an inert priinary containment after the design bases LOCA assuming a single. active failure. The CM Ammendment 16

s i 1 j 3 T N $6 N i s j. The nitrogen supplied from the AC system shall be oil-free 1-With a moisture content of less than 2.5 ppm. Filters are provide to remove particulates larger than 5 microns. i i 3 1 i i i ' 1 a I LO l l l i e 5 i j. I t i l-. i-l I., Le l

ABWR 23Aws.n Slitt1dard Planf ru e (] ventilation exhaust, the SGTS is automatically efficiencies are outlined in Table 6.51. Dose Q ectuated. If system operation is not confirmed, the analyses of events requiring SGTS operation. redundant process fan and dryer train are described in Subsections 15.6.5 and 55.7,4, automatically p!sced into service, in the event a indicate that offsite doses are within the limits malfunction disables an operating process fan or established by 10 CFR 100. dryer train, the standby process fan and dryer train are manuallyinitiated. (3) The SGTS is designated as an engineered safety feature since it rnitigates the 6J.1.23.2 Manual consequences of a postulated accident by controlling and reducing the release of The SGTS is on standby during normal plant radioacthity to the environment. The SGTS, operation and may be manually initiated before or except for the deluge,is designed and built to during priraary containment purging (de inerting) the requirements for Safety Class 3 equipment when required tolimit the discharge of contaminants as defined in Section 3.2, and 10 CFR 50, to the environment, it may be manually initiated Appendix D. whenever its use may be needed to avoid exceeding radiation monitor setpoints. The SGTS has independent, redundant acthe components. Should any aethe component fail, 63.1.2JJ Decay licat Removal SGTS functions can be performed by the redundant component. The electrical devices Cooling of the SGTS Tdters may be required to of independent components are powered from prevent the gradual accumulatica of decay heat in separate Class 1E electrical buses. the charcoal. This heat is generated by the decay of radioactive iodine adsorbed on the SGTS charcoal. (4) The SGTS is designed to Seismic Category 1 The charcoalis typically cooled by the air from the requirements as specified in Section 3.2. The process fan. SGTS is housed in a Category I structure. All [ surrounding equipment, components, and A water deluge cap 4bility is also provided, but supports are designed to approp>I te safety primarily for fire protection since redundant process class and seismic requi sments. fans are provided for air cooling. Shce the deluge is available, it may also be used to remove decay heat (5) The SGTS design is based on the maximum for sequences outside the normal design basis, pressure and differential pressure, maximum Temperature instrumentation is provided for control integrated dose rate, maximum relative of the SGTS process and space electric heaters. This humidity, and maximum temperature expected instrumentation may also be used by the operator to in secondary containment for the LOCA event. [re ] establish a coor.ng air flow post. accident, if 4 lo required. 63.1J.: Sizing flasts Water is supplied from the fire protection system Figure 6.5 2 provides an assessment of the and is connected to the SGTS via a spool piece. secondary containment pressure after the design basis LOCA assuming an SGTS fan capacity 61.13 Design Evaluation of 4000 stfm (70'F,1 almosphere) per fan and the leakage rates shown in Table 6.5 2. Credit for 63.13.1 General secondary containment as a fission product control system is only taken if the secondary containment is (1) A slight negative pressure is normally actually at a negative pressure by considering the maintained in the secondary containment by potential effect of wind on the ambient pressure in the reactor building HVAC system (Subsection the vicinity of the reactor building. For the ABWR 9.4.5). On SGTS initiation per Subsection dose analysis, direct transport of cortainment 6.5.1.2.3.1, the secondary containment is leakage to the environment was assumed la the first automatically isolated from the HVAC system. 20 minutes after LOCA event initiation (in addition .O to the leakage through the MSIVs to the main i (2) The SGTS filter particulate and charcoal turbine condenser). Each SGTS fan was sired to Amendment 17 6.52

1 i a 1 1 I l 16J S 6 A7 15 A sec er.dar y cont aintnent draw-down analysis vill 14e per f orniec !;y the 00L applicant to derr.onstrate the capability of the SGTS to maintaan the design negative prescure following a LOCA including anleal: age f r o n. the open, non-isolated penetration linec ident111ed during construction engineering and the event of the vor st u.a rap l e failure of a secondary containtnent isolation valve i to cloce. (See Sutmeetion 6.L.$.I for interiace r eq ui r etren t o ). i i 1 1 1 i J r l i J I f 4 l s Ie i l l

ABWR

• • • D S. tandard Plant Prv C U['T 6.5.4 Ice Condenser as a Fission Pn duct Control System The GE ABWR does not utilize any kind of an ice condenser feature as a fission product control system.

G.5 5 InicJaces U c.5.5.i SGTs PcJormame< q w s 1i P w.f o rm dre w dc,pphc.n,s+ a s-re s Tbc Cot ci

o. c c o c J % c e_

m, ni g n 5 us em &b h b s c c + 1 o.s c. s. t. s. ( I t e w, (s). a 'q,)b l Amendment 11

ABWR z w w,n Standard Plant to e 6.6 PRESERVICE AND INSERVICE 6.6.1.1 Class 2 Sptem Itoundary Description (' INSPECTION AND TESTING OF CIASS \\ 2 AND 3 COMPONENTS AND PIPING Those portions of the systems listed in Subsection 6.6.1 within the Class 2 boutdary aah al,,s This subsection describes the preservice and described in Regulatory Guide 1.26,for Quality inservice inspectiqs and systeen pressure test Group B, are as follows: ,g ,g programs for@Ouality Groups B and C,i.e., CMC ScJ'cr d Premic VJ (DaPV) Code (1) Portions of the reactor coolant pressure 4.MotAH-end41 Class 2 and 3 items, respectively.' boundary as defined in Subsection 5.2.4.1.1, but it describes those programs implementing the which are excluded from the Class 1 bcandary requirements of Subsections TWC and 'D of tha pursuant to Subsection 5.2.4.1.2. ASME B& PV Code Section XI. -*- MS A (2) Sptems or portions of sptems important to 6.6.1 Class 2 and 3 Systern Boun a es safety that are designed for reactor shutdown or residual heat removal. The Class 2 and 3 system boundaries for both presenice and insenice inspection programs ano the (3) Portions of the steam spiems extending fron. sys'em pressure test program includes all those items the outermost containment isolation valve up to within the 3 boundary and applicable items within but not including the turbine stop and bypass the 4 boundary, respectively, on the piping and valves and connected piping up to and including instrumentation drawings (P&lDs). Those the first vahe that is either normally closed or boundaries include all or part of the following-capable of automatic closure during all modes of normal reactor operstion. (1) Main arcam sptem (2) Feedwater system (4) Systerns or portions of sptems that are (3) Reactor core isolation cooling system conneeted to the riactor coolant pressure (4) High preaure core flooder sptem boundary and are mit capable of being isolated (5) Standbyliquid control sys:em from the boundary during all modes of normal n) (6) Residual heat ternoval system, reactor operation by two valves, each of which ( (7) Rt. actor water clean up system is normally closed or capable of automatic (S) Control rod drin sptem closure. (9) Supression pool clean up system (10) Purified make up water system (5) Sptems or portions of systems important to (11) Atmospheric control sysicm safety tbt are designed for (1) emergency cos e (12) Radwaste system cooling,(2) post accident containment hea' (13) HVAC normal cooling water system removal, or (3) post accident fission product (14) Service air system removal. f (15) High pressure nitrogen gas supply system ' H '3 g (16) Instrument air splem 6.6.1.2 Class 3 Sysam Boundary Description (17) Reactor building cooling water sptem (18) Flammability control system Those portions of the systems listed in (19) Fuel pool cooling and clean-up system Subsection 6.6.1 within the Class 3 boundary, x6 id or (20) Reactor senice water sptem described in Regulatory Guide 1.26 for Quality Group C, are not part of the reactor ant pressure boundary but are as follows: / (1) Cooling water systems or portions of cooliag

• Items as used in this Section are products water systems important to safety that are constructed under a Cersificate of Authori:ation designed for emergency core cooling, (NCA 3120) and material (NCA 1220). See Section post accident containment beat removal, III, NCA 1000, footnote 2 post accident containment atmosphere cleanup, or residual heat removal from the reactor and from the spent fuel storage pool (including

(% Amendment 13 661 l

l l INsGFTS F o F-PAGts G.6-t 1 V l USA The preservice and inservice inspection requirements are efined by 20 CFR, Section 50.55a. \\ M5B; Items (1) through (5) above describe the Clasa 2 boundary N'nly-and are not exemptions as defined by Section XI of the ASME Boiler and Pressure Vessel Code. O S e l-. ty e.

ABWR-man Jiandard Plant %e primary and secondary cooling systems). for performance of ultrasonic and surface (magnetic / Portions of these systems that are required for particle or liquid penetrant) examinations and 5 their safety functions and that do not operate sufficient access to supports for performance of during any mode of normal operation and visual, VT 3, examination. Working platforms are cannot be tested adequately, however, are provided in some areas to facilitate servicing of included in Class 2. pu ups and valves. Removable thermalinsulation is provided on welds and components which require (2) Cooling water and seal water systeins or frequent access for examination or are located in portions of these systems important to safety high radiation areas. Welds are located to permit that ate designed for functioning of . ultrasonic examination from at least one side, but components and sptems important to safety, uhere component geomMries permit, access from (3) Systems or portions of systems that are connected to the rector coolant pressure Restrictions: For piping systems and portions boundary and are capable of being isolated of piping systems subject to volumetric and surface from that boundary during all modes of no* mal examination, the following piping designs are not reactor operation by two valves each of which is used: normally closed or capable of automatic closure. (1) Valve to valve (2) Valve to reducer (4). Systems, other that radioactive waste (3) Valve to tee management systems, not covered by items a, b (4) Elbow to elbow and e above, that contain or may contain (5) Elbow to tee radioactive material and whose postulated (6) Nozzle to elbow failure would result in conservatively calculated (7) Reducer to cibow potential offsite doses (ref. Regulatory Guides (8)Tec to tee 1.3 and 1.4), that exceed 0.5 rem to the whole (9) Pump to valve body or its equivalent to any part of the body. 145 y. Straight sections of pipe and spool pieces shall -D: C 6.6.2 Accessibility be added between fittings. The minimum length of 11 x spool piece has been determined by using the Allitems within the Class 2 and 3 boundaries fortnulate L = 2T + 6 icebes, where L equals the are designed, to the extent practicable, to provide length of the spool piece (not including weld access for the examinations required by IWC 2500 preparation) and T equals the pipe wall thickness. and IWD 2500. Items for which the design is known to have inhera.t access restrictions are described in 6.6.3 Exarnination Categories ar,3 Methods Subsection 6.6.9. 64.3.1 Examination Categories 64.2.1 Class 2 RHR Heat Exchangers ,(pren.L.J e m.ea yb )_. The enmination category of each item is listed The physical arrangement of the residual heat in Table 6.61 The items are listed by system and 3 removal (RHR) beat exchangers shall, to the extent line number where applicable. Table 6.61 also feasible be conducive to the performance of the states the method of examination for each item. [ required ultrasonic and surface examinations. Removable thermal insulation is provided for those 64.3.2 Examlaation Methods welds and nozzles selected for freques.t e_xamination . during the inservice inspection. Platforms and 64.3.2.1 Visual Examination ~ ladders are provided as necessary to frcilitate mmintion. Visual Examination Methods, VT 2 and VT 3, 'y shall be conducted in accordance with ASME-X 64.2.2 Class 2 Pipirg, Pumps Valves and Supports _ Se etion XI, IWA+2210. In addition, VT 2 examinations shall also meet the requirements of Physical arrangement of piping pumps and fWA 5240. valves provide personnel access to each weld location - Amendment 13 66-2 -~a

gqSgprs 908 P A G s G. G. '2-O i4 5C Items (1) through (4) above describe the Class 3 boundary nly and are not exemptions as defined by Section XI of the _ASME Boiler and Pressure Vessel Code. A50 Items such as nozzle-to-vessel velds often have inherent ccess restrictions when vessel internals are installed therefore the preservice examination shall be performed on these items prior to installation of internals which would ,_ interfere with examination. H5E) For the preservice examination, all of the items selected or inservice-examination shall be performed once in accordance with ASME Section XI, IWC-2200 ar. IWD-2200, with the exception of-the examinations specifically excluded by ASME Section XI from preservice requirements, such as the visual VT-2 examinations for Category C-H, D-A, D-B and D-C. D(%' L l .e.+

ABWR mama Standard Plant we At locations where leakages are normally losulation removal for inspection is to allow O cxpected and leakage collea'en systems are located, sufficient room for the ultrasonic transducer to scan Cl (e g., valve stems and pump seals), the visual. \\T 2, the examination area. A distance of 2T plus 6 examination shall verify that the leakage collectioe inches, where T is the pipe thicknera, is the minimum l sptem is operative, required on each side of the cumination area. The insulation design generally leaves 16 inches on each Piping runs shall be clearly identified and laid side of Ibe weld, wbich er:ceds rninimum out such that insulation damage, leaks and structural requirements. distress will be esident to a trained sisual examiner. 64J,2A Altrrnathe Examination Techniques 643.2.2 Surface Examination As provided by ASME Section XI, IWA.2240, Magnetic Particle and Liquid Penetrant alternative examination methods, a combination of examination techniques shall be performed in methods, or newly developed techniques may be accordance with ASME Section XI, IWA 2221 and substituted for the methods specified for a given item IWA-2222, respectively. For direct examination in this section, provided that they are demonstrated access for magnetic particle (MT) and penetrant to be equivalent or superior to the specified method. (PT) examination, a clearance (of at least 24 inches This provision allows for the use of newly developed of clear space)is provided where feasible for the examination methods, techniques, etc., which may head and shoulders of a man within a working arm's resuh in improvements in examination reliability aad length (20 inches) of the surface to be examined. in reductions in personnel exposure. addition, access shall be provided as necessary to enable physical contact with the item as necessary to 643.2.5 Data Recording perform the examination. Remote MT and PT generally are not appropriate as a standard Manual data recording will be performed examination process, however, borescopes and where manual ultrasonic examinations are mirrors can be used at close range to imprave the performed, if automated systems are used, angle of vision. As e minimum, insulation removal electronic data recording and comparison analpis shall expose tbc area of each weld plus at least six are to be employed with automated ultrasonic 1 inches from the toe of the weld on each side. examination equipment. Signals from each Insulation will generally be remosed 16 incbes on ultrasonic transducer would be fed into a data cach side of the weld, acquisition system in which the key parameters of any reflectors will be recorded. Tbc data to be 643.23 Volumetric Ultrasonic Direct Examination recorded for manual and automated methods are: Volumetric ultrasonic direct examination shall (1) location; be performed in accordance with ASME Section XI, (2) position; IWA 2232. In order to perform the examination, (3) depth below the scanning surface; visual recess to place the bead and shoulder within (4) length of the reflector; 20 inches of the area of interest shall be provided (5) transducer data inc!uding angle and where feasible. Nineinches between adhcent pipes frequency; and is sufficient spacing if there is free access on each (6) calibration data, side of tbc pipes. The transducer dimension bas The data so recorded shall be compared with been censidered: a 11/2 inch diameter cylinder,3 inches long placed with the access at a right angle to the results of subsequent examinations to determine the surface to be examined. T' e ultrasonic the behavior of the reflector. A u /H5 examination instrument has been considered as a F rectangular box 12 x 12 x 20 inches located witbin 40 6.6.4 Inspection Intenals feet from the transducer. Space for a second examiner to monitor the instrument shall be 6.6.4.1 Class 2 Systems prosided if necessary The inservice inspection intervals for Class 2 systems will conform to inspection Program B as O I\\ Amendment 13 663

--__=-. I N SG 0t.7 (~ o R. PAG 5

6. G - 3

• T F 6.6.3.2.6 Qualification of Personnel and Examination Systems for Ultrasonic Examination Personnel performing examinations shall be qualified in accordance with ASME Section XI, Appendix VII.

Ultrasonic examination systems shall be qualified in accordance with an industry accepted program for implementation of ASME Section XI, Appendix VIII. a a

ABWR mamn 1 Slandard PlanL A nev c f described in Section X;, IWC 2412. Except where Table IWD 25001, for categories D A, D B and deferral is pt"nitted ay Table IWC 2500-1, the D C. The sprem insenice test shall include a VT 2 percentages et esamity tions completed within each examination in accordance with IWA 5240, escept period of the intervallhall correspond to Table that, abere portions of a system are subject to IWC 24;21 ftems dicded :c be cumbl+isia system pressure tests associated with two different. the an*16-aseulwebe-am.e4aa*+ith-functions, the VT-2 examination shall only be t 'remenu-c6TeHe4WG25004 Ocs sex performed during the test coeducted at the higher of ,/!Isac4iaJAld,64-the test pressures. The sptem insenice test will be as ' conducted at approximately the max 2mu'n operating G 6.6.4.2 Class 3 Spttms pressure and temperature indicated in the applicable process flow diagram for the system as indicated in The insenice inspection intervals for Class 3 Table 1.71. The system hydrostatic test (Subsection systems will conform to Inspection Program B as 5.2.4.6.2), when performed is acceptable in lieu of described in Section XI,IWD 2412. Except where the system insenice test, deferral is permitted by Table IWD 25001, the percentages of examinations completed within cacL 644.2 Sptem Functional Tes,t period of the interval! ball correspond to Table FWD 24121. Issmuskad 4c b: :==bd ahin As required by Section XI, IWC 2500 for g the 10 year intervals are4electedin occordaceemith category C H and by IWD-2500 for categories D A, th iremectref-TeMe4WD-25004-he a :hme D B and D-C, a system functional test shall be die Teblehir performed in accordance with IWC 5221 on Clau 2 systerns, and IWD 5221 on Class 3 systems, which y 6.6 5 Esaluatlun of Examination Results are not required to operate during normal operation y[ but for which a periodic system functional test is b Examination results will be evaluated in performed. The system functional test sballinclude accordance with ASME Section XI,IWC,3000 for all Class 2 or 3 components and piping within the Class 2 components, with repairs based on the pressure retaining boundary and shall be performed ( requirements of IWA 4000 and IWC 4000, once during each inspection period as defined in Examination results will be evaluated in accordanu Tables nVC 24121 and IWD41121 for Program B. x wkh ASME Section XI,IWD 3000 for Class 3 For the purposes of the system functional test of components, with repairs based on the requirements Class 2 systems, the pressure retaining boundary is of IWA-4000 and IWD-4000. defined in Table IWC-25001, Category C H, Note 7. For the purposes of the rystem functional test for 6.6 6 Sys!em Prenure Tests Class 3 systems, the system boundary is defined in Note 1 of Table IWD4500-1, categories D-A, D B 6.6.6.1 System Inservice Test and D-C. The system insenice test shall include a VT 2 examination in accordance with IWA 5240, As requited by Section XI IWC-2500 for except that, where portions of a system are subject to category C-H and by IWD-2500 tar categoriesD A, system pressure tests associated with two different D B and D.C, a system insenice test shall be functions, the VT 2 examination shall only be performed in accordance with IWC-5221 on Clan 2 performed during the test conducted at the higher of systeme, and IWD-5221 on Clau 3 systems, which the test pressures. The system functions! test will be l are required to operate during normal operation. conducted at the nominal operating pressure and i The system insenice test shall include all Class 2 or 3 se.mperature indicated in the applicable process flow I components and piping sithin the pressure retaining diagram for the functional test for each system as boundary and shall be performed once during each indicated in Table 1.7-1. The system hydrostatic test l inspection period as defined in Tables IWC 24121 (Subsection 5.2A6.2), when performed is acceptable and IWD 2412-1 for Program B. For the purposes in lieu of the system inservice test. of the system insenice test of Class 2 systems, the l pressure retaining boundary is defined in Table 644.3 Hydrostatic Pressurt Tests IWC 25001, Category C-H, Note 7. For the purposes of the system inservice test for Class 3 As required by Section XI, IWC 2500 for systems, the syste m boundary is defined in Note 1 of Category B P, the hydrostatic pressure test shall be i mO Amn& nut 13 64J

I N s G F.TS F o c.- PAGG 6.6-4 - O '4 5 G An example of the selection of Code Class 2 items and xaminations to be conducted within the 10-year intervals are described in Table 5.2-8. T 95 H) An e'xample. of the selection of Code Class 3 itemn and xaminations to be conducted within the 10-year intervals are described in Table 5.2-8. ,V l : 5 l. M I l f f I

s

ABWR ummin Standard Plant me performed in accordance with ASME Section hSME Section XI Table IWC 2500 for categ O IWC 5222 on all Class 2 components and piping C B, may not be accessible for ultrasonic h (d within the pressure retaining boundary once during examination. The examination is conducted from the cach 10 year inspection interval. For purposes of the outside surface of the vessel and, as such, the outside hydrostatic pressure test, the pressure retaining radius of the nonje forging may limit the movement beundary is defined in Table IWB-25001, Category of the ultrasonic search unit. The extent of the B P, Note 1. The sysicm hydrostatic test shall examination coverage limitation for each nonle will include a VT 2 examination in accordance with be determined during the preservice examination of IWA 5240. For the purposes of determining the test gthe vessel-to-nonJe w/ elds - - pressure for the system hydrostatic test in h_ accordance with IWB 5222 (a), the system design pressure as indicated on the applicable piping and instrumentation diagram for the system, as shown in Table 1.71, shall be used for P,y inaDcases. 6.6,7 Augmented Inservice Inspection G.6.7.I W c3k be vt33 6 n " *) f All high energy piping between the containment isolation valves are subject to the following additional inspection requirements: All circumferential welds shall be 100 p:rcent volumetrically examined each inspection interval as defined in Subsection 6.6.3.2.3. Further, accessibility, examination requirements and procedures shall be as discussed in Subsections 6.6.2, 6.6.3 and 6.6.5, respectively. Piping in these areas shall be seamless, [ ] 14 5 thereby climinating all longitudinal welds. j v + 1 / 6.6.8 Code Exemptions As provided in ASME Section XI,IWC 1220 and IWD 1220, certain portions of Class 2 and 3 systems are exempt from the volumetric and surface and sisual examination requirements of IWC-2500 and IWD 2500. These portions of systems are specifically identified in Tab:e 6.6-1 '6.6.9 RellAf Requests 6.6.9.1 Class 2 II)drostatic Test Pressurt } \\ For portions of Class 2 systems, which cannot i be isolated from the reactor vessel, such as the bianch connection of line 25A NB 728 to 50A NB 129, the system hydrostatic test pressure shall be in accordance with the system hydrostatic test pressure requirements for the Class 1 system. 6.6.9.2 RHR Heat Exchanger Nonle to-Shell Welds \\ _(yme of the weld required volume as specified in Due to the inherent geometry of vessc! nonles (', ~ ~ ~ - - j %/ Amendment 13 66-5

I N S E CCT FOR PAGG 6,6 - T ) 73 U -~ l'6 I 6.6.7.2 Erosion-Corrosion Piping systems determined-to be susceptible to single-phase erosion-corrosion shall be subject to a program of nondestructive examinations to verify the system structural integrity. The examination schedule and examination methods shall be determined in accordance with applicable regulations and regulatory documents, such-as NRC Bulletin 87-01, and applicable rules of Section XI of the ASME Boiler and Pressure Vessel Code. O

ABM us.ioosa Standard Plant nrv c (v] 6.7 HIGH PRESSURE NITROGEN GAS during an SSE. The bottles are als' covered by SUPPLY SYSTEM a heavy steel plate, which serves as a barrier to potential missiles. 6.7.1 Functions Flow rate and capacity requirements are The high pressure nitrogen gas supply system divided into an initial requirement and a is divided into two independent divisions, with continuous supply. An initial requirement for ,j cach division containing a safety related each ADS SRV provides for actuations of the emergency stored nitrogen supply. The essential valve aEainst drywell pressure. Fifty gallon stored nitrogen supply is Safety Class 3, Seismic accumulators supplied for each main steam ADS Category 1, designed for operation of the main SRV actuator fulfill the steam valve steam S/R valve ADS function accumulators. requirement. The continuous supply is divid d into safety and nonsafety portions. The function of the nonsafety related, makeup Compressed nitrogen at a rate adequate to nitrogen gas supply system is: make up the nitrogen leakage of each serviced valve is provided by the safety portion. This

0) relief function accumulators of main steam assumes an air leakage rate for each valve of 1 S/R valves, scfh for a period of at least seven dap. The essential system with associated lines, valve.

(2) pneumatically operated valves and and fittings are classified as Safety Class 3, instruments inside tbc PCV, Seismic Category 1. (3) leak detection system radiation monitor The nonsafety portion provides compressed calibration nitrogen at a rate adequate to recharge the ADS SRV accumulators. The nonessential system has e ( t) ADS function accumulators to compensate for two pressure control valves to depressuri:e the C} the leakage from main steam S/R solenoid nitrogen gas from the AC system. One is to valves durmg normal operation depressurize to 200 psi for the SRV accumulators and the other is to depressurize to 100 psi for 6.72 Systern Description other pneumatic uses. Sitrogen gas for the essential system is Tbc continuous supply portion of the supplied from high pressure nitrogen gas storage pneumatic system, extending from the AC system bottles. Nitrogen gas for the nonessential to the isolation valve prior to the essential makeup system is supplied from the nitrogen gas system is not safety related. graporator v.is the makeup line to the ttmospheric 73 o ' control f A a system.AThe essential system is Nonsafety piping and valves of the system are separated into two divisions. There are ticlines designed to ANSI B31.1, Power Piping Code, and between the nonessential and each division of the the requirements of Quality Group D of essential system. Each ticline has a motor Regulatory Guide 1.26. Pressure vessels and operated shuto'.f valve. For details, s-:e Figure beat exebangers are designed to ASME Section 6.71 and Table 6.7-1. Vlli, Division I. i l Each division of the essential system has ten System design pressure is 200 psig with the bottles. Normally, outlet valves from five of system.lesign temperature at 1500F. l the ten bottles are kept open. Eaeb division has.a pressure control valve to depressurize the 6.7.3 Systern Evaluation ritrogen gas from the bottles. Vessels, piping and fittings of the safety The bottles are mechanically restrained to portion of the system are designed to Seismic l preclude generation of high pressure missiles V l 6N Amend-acnt 16 l 1

N soact r,3 The nitrogen supply system shall supply nitrogen which is oil-free with a moisture content of less than 2.5 ppm. i !. = 1 4-j_ r l j. 4 e h l. i i. f b l d I a 1

?

4 l. i 1* 1 4 i - I 9 l' 4 i 4 t 1

ABWR 23xuwi Standard Plant wn 9.3.9 Hydrogen Water Chemistry System feedwater system, the lower plenum region and the O CufiW'W inlet, hydrogen and pH levels in the \\j 93.9.1 Design Bases ., feedwater system, the lower plenum region and the Cl%RWCt! inlet, and crack growth of pre. cracked 93.9.1.2 Safety Design Basis samples in water from the lower plenum region. The hydrogen water chemistry (HWC) sptem The hydrogen supply system will be site is non nudear, non-safety related and is required to dependent. Hydrogen can be supplied either as a be safe and reliable, consistent with the requirement high pressure gas or as a cryogenic liquid. Hydrogen of using hydrogen gas. The hydrogen piping in the and oxygen can also be generated on site by the turbine building shall be designed to Seismic dissociation of water by electrolysis. The HWC Category I requirements to e imply with BTP 9.5-1. hydrogen supply system is integrated with the generator hydrogen supply system to save the cost of 93.9.1.: Power Generation Design Basis having separate gas storage facilities for both systems. BWR reactor coolant is demineralized water, The oxygen supply system will be site typically containing 100 to 200 parts per billion (ppb) dependent. A single oxygen supply system could be dissohed oxygen from the radiolpic decomposition provided to meet the requirements of HWC system of wate:. To mitigate the potential for intergranular and the condensate oxygen injection system described stress corrosion cracking (IGSCC) of sensitized in Subsection 93.10. austeriti stairdess steels, the dissolved oxygen in the reactor water can be reduced 'o less than 20 ppb by 93.93 Safety Daluation the addition of hydrogen to the feedwater. The amount of hydrogen required is in the range of 1.0 to The operation of the HWC system is not 1.5 ppa. The exact amount required depends on necessary to assure: many factors including incore recirculation rates. The atnount required will be determined by tests (1) The integrity of tne reactor coolant pressure ( performed during the initial operation of the plant.

boundary, The concentration of hydrogen and oxygen in (2) The capability to shut down the reactor; or the main steam line and esentually in the main a

condenser is altered in this process. This leaves an (3) The capability to prevent or mitigate the excess of hydrogen in the main condenser that would consecuences of esents which could result in not have equivalent oxygen to combine with in the potential offsite exposures. offgas system. 't o maintain the offgas system near its ~ normal cperating characteristics, a flow rate of The HWC system is used, along with other oxygen equal to approximately one-half the injected measures, to reduce the likelihood of corrosion hydrogen flow rate is injected in the offgas system failures which would adversely affect plant availability. upstream of the recombiner. The means of storing and handling hydrogen 6 hall b utilize the guidelines in EPRI NP-5283 SR A, The HWC systern utilizes the guidelines given " Guidelines for Permanent BWR Hydrogen Water in EPRI report NP-5283-SR-A, " Guidelines for Chemistry Installations". Permanent BWR Hydrogen Water Chemistry Installation; 93.9A Inspection and Testing Requirements p,

1 93.9.2 System Description The HWC system is proved operable during the initial operation of the plant. During a refueling or The HWC system, illustrated in Figure 93-8, is maintenance outage, hydrogen injection is not composed of hydrogen and oxygen supply systems, recuired. System maintenance or testing can be systems to inject hydrogen in the feedwater and petforued duing such p

riot.

oxygen in the offgas and subsystems to monitor the effectiveness of the HWC system. These systems p monitor the oxygen levels in the offgas system, the U Amendment 11 9 3-12 l

... -.. -... -. - _. - -. -. -. ~ - - ~ ~ _... -. ~. ~. - ~. -.... - - -. -. - - - ~... a b O BWR Hydrogen Water Chemistry gooo and EPRI--report NP-4947-SR, Guddelines: 1987 Revision," October 1988. Ioob and oxygen h i e i lY =. l-: l n -. -, -... -. ~ - - ,+,-.1-.--,.i., ,c --a ,i.,, -...:... ,-.-,,L.n-

ABWR uumui Standard Plant un 93.9.5 Instrumentation and Controls (5) Sensors for measuring dissolved orygen content. h Automatic control features in the HWC system (6) Sensors for measuring pH and dissolved U minimize the need for operator attention and bydrogen. improve performance. These are: (7) A system for verifying the effectiveness of HWC (1) Automatic variation of hydrogen and oxygen by measuring electrochemical potential (ECP) flow rates with reactor power level. and crack growth rate. (2) Automatic oxygen injection rate change delay. 93.10 Oxygen Injection System This function is alsa augmented as a function of reactor power level. 93.10.1 Design Bases (3) Automatic shutdown on several alarms. The oxygen injection system is designed to add sufficient oxygen to the Condensate System to (4) Isolation on system power loss, operator suppress erstrosion and corrosion prodt.ct release in restart. the condensate and feedwater systems. Experience has shown that the preferred feedwater oxygen (5) Reprograramable alarms and cont' roller concentration is 20 to 50 ppb. During shutdown and c!cetronics. startup operation the feedwater oxygen concentration is usually much above the 20 to 50 ppb range. (6) Hydrogen and orvgen flow monitor correction However, during power operation, deaeration in the function to compensate for nonlinearities. main condenser may reduce the condensate oxygen concentration below 20 ppb, thus, requiring that some The recommended trips of the oxygen and oxygen be added. The amount required is up to hydre;en injection systems include: approx.imately 5 cubic feet per hour. (1) Reactor scram 93.10.: System Descriptien b (2) Low or high residual or. gen in the off. gas The oxygen supply consists of high presp k" cylinders 2 ':qud !ank. A condensate oxygen ( (3) High area hydrogen concentration injection module is provided with pressure regulators and associated piping, valves, and controls to (.1) Low oxypen injection system supply pressute depressurize the gaseous oxygen and route it to the condensate injection modules. There are check valves (5) High by drogen flow and isolation valves between the condensate injection modules and the condensate lines dowmstream of the The instrumentation provided includes: condensate demineralizers and the optional injection point upstream of the filters. (1) Flow monitors for measurement of hydrogen and oxygen flow rates. The flow regulating valves in this system are operated from the main control room. The oxygen l (2) Hydrogen area monitor sensors to detect any concentration in the condensate /feedwater system is hydrogen to the atmosphere. monitored by analyzers in the sampling system (Subsection 93.2). An operator will make changes in (3) Pressure gages for measurement of hydrogen the exygen injection rate in response to changes in the and oxygen supply pressures and instrument air condensate /feedwater concentration. An automatic pressure. control system is not required because instantaneous I changes in oxygen injection rate are not required. (.8) An oxygen analyzer for measuring the percent oxygen leaving the offgas recombiner. l l l C\\ \\ V Amenemem 11 9.3-13 ~

. - _.. ~ - -. t lu SSG'T The oxygen injection system shall use the guidelines for gaseous-oxygen injection systems in EPRI report NP-5283-SR-A,-. " Guidelines f or Permanent 11ydrogen Water Chem-1987 Revision," September 1987, istry Installations n i != I + J@ I

mei:cs>i ABM nvD Sandard Plant 93.13J Vendor Speelfic Design of Diesel 9J.13.7 Firt Rating for Penetration Seals Generator Aux 111arles The applicant referencing the ABWR design f' The vendor specific diesel generator support shall provide 3. hour fire rated penetration systems (i.e., the D/G fuel oil system, the D/G seals for all high energy piping or, as a 3 cooling water system, the D/G starting air minimutn, state those conditions when such seats s 5 syste=, the D/G lubrication system, the D/G cannot be provided and what will be installed as C combustion air intake and exhaust system) shall a substitute. The detail design shall provide be reviewed for differences in design with those completely equivalent construction to tested disct ssed in Subsections 9.5.4 through 9.5.5, wall assemblies er testing will be required. respectively. A discussion of such differences 93.13.8 Diesel Generator Requirtments shall be provided. Specific NRC requested information lists as (1) the diesel generator operating procedures for a particular diesel. engine make and follows: ( rele + c ch model shall require loading of the engine up y (1) 4 edhelcamfer p=pr-E to a minimum of 40cc of full load (or lower E t bl 3f ers 3 e load per manufacturer's recommendation) for (2) Presision for stick gauces on fuel tanks. I hour after up to 8 hours of continuous '4 no. load or light load operation. F 'l-(3) Description of engine cracking devices, 9 (2) selection of diesel generator shall include 79' O (4) Duration of cranking cyc!c and number of prudent component design with dust tight j engine revolutions /aze-c.r'c r Start ed traf. enclosures. Construction guidelines shal! 4 t include prosisions f or minimizing F) 1.ubrication syst em design crite riap.4 -< accumulation of dust and dirt into 4, h g p ot m -; f; m a equipment. 4 ( s ^4 (3) the diesel generator operating procedere j j 93.13.6 Diesel Generator Cooling Water S,* stem \\y shall include provisiens to avoid as much as Design Flow and lic.at Remosal Requirtments 'N possible or otherwise restrict the no. load A table shall be provided which identifies i or low liad operation of the engine / generator for prolonged periods of time; or [ the design flow and heat removal requirements for e s the diesel generator cooling water system. It operate the engine at nearly full load l' shallinclude the design heat removal capacities following every no-load or low. load (20cc or of all the coolers or heat exchangers in the less) operation lasting for a period of 30 minutes or snore. system. Specific NRC requested information lists as f 93.13.9 Appilcant Fire Protection Program follows: The following areas are out of the ABWR g (1) Type of jacket water circulating pumps i Standard Plant design scope, and shall be 3 (i.e,, motor driven or others),

included in the applicant fire protection

! program. 5 j Type of t.=perature sens [i$h,yOC "7, (Orc % et" bo4 l (2) 7ec*e e%f,# b (1) Main transformer 3 b c e k (3) Expansion tank capacity, l l R (2) Equip =ent entry lock { (4) NPSH ofjacket water circulating pump, and l (3) Fire protection pumphouse f

/

l Cooling water loss estimates, yL (;;[,W(nsa(5) wcfa ce+ A ~ I wy. ) o, pea cyo c s ty set imen* ((p,,p pw 1,~ ~.. m _,, _ m,,., p c m r( ,9 J ,o - s k e,? rLs, eval co p o h t,1, c," l 9y s tem,-_, m, . og) / - - te .. q t Vele wc o

• d des y f r chrc p-c5 s n co r reer w r(avrfwsen

\\ '*? f W!& ?'M k (n>e w t e ) we % c y c - , m'___ 3d DV E Sfort Clj t N f(t f(C f 'VC9k On

J nc a

n t i!.

. - ---..-. - - - ~. - AB R 224siooxa Standard Plant - nry n (4) Ultimate heat sick be conducted. Any con compliance shall be ' documented as being required and acceptable on (Q: 9A The applicant's fire protection program shall the basis of the Fire Hazard Analysis, Appendix [d 1$ ; comply with the SRP Section 9.5.1, with ability 9A, and the fire Hazard Probabilistic Risk to bring the plant to safe shutdown condition A sessment, Appendix 19M. ,j

• I following a complete fire burnout without a need for recovery.

9.5.14 References { 4 9.5.13.10 HVAC Pressure Calculations I 1. Stello, Victor, Jr., Design Requirements Related To The Evolutionary Advanced Lifst + 8 The applicast referencing the ABWR design ; Water Reactors (ALWRS), Policy issue, &.shall provide pressure calculations and confirm ; SECY 89 013, The Cornmissioners, United capability during pre operational testing of the States Nuclear Regulatory Commission, January 19, 1989. l smoke control mode of the HVAC systems as described in Subsection 9.5.1.0.6. 2. Cote, Authur E., NFPA Fire Protection r 9.5.13.11 Plant Security Systems Criteria Handbocc, National Fire Protection Association, Sixteenth Edition. 'The design of the security system shall include an evaluation of its impact on plant 3. Design of Smoke Control Systems for epsration,-testing, and maintenance. This Buildings, American Society of Heating, evaluation shall assure that the security Refrigerating, and Air Conditioning restrictions for access to equipment and plant Engineers, Inc., September 1983, regions is compatible with required operator actious during all operating and emergency modes ' 4. Recommended Practice for Smoke Control i of operation (i.e., loss of offsite power, access ( Systems, NFPA 92A, National Fire Protact c:: for fire protection, health plyt cs. maintenance, g Association,1988. i G[] testing and local operator), in addition, this ( cvaluation shall assure that: E 9.5.13.13 olesel fuel refueling procee res There are no areas w. hin the Nuclear Island s .(a) it where communication with central and Proce&rn shall be established to verify that the secondary alarm stations is not possible; .j day tank is futt prior to refitting the storese i tank. This minimizes the likelihood of sediment (b) Portable security radio; will not_ interfere - ,,,,,,ction,,,v,( tino,no,ny 6,t.i,riou, with plant monitoring equipment;- ,,,,c,, on et,,,g,,n,e cor op,r tion, (c) Minimum isolation zone and protected area i~llumination capabilities cannot be defeated by sabotage actions outside of the protected area; and, (d) Electromagnetic interference from plant equipment startups or power transfers wil!

not create nuisance' alarms or trip security

-access control systems. ~ 9.5.13.12 Fire Hazard Analysis - i A compliance review of the as built design ~ against the assumptions and requirements stated in the fire hazard analysis.(Appendix 9A) shall ~ 9.5 10.7 Amendmenr 17

,,;- i *4lu A =i.l 14: 1 - 1,;;g,ama,5m - + l 7 N 9 6 -{K Q 11/2"Itf H AkC O W - 11/2*tt6.b I AkC ."......V 4 hY DRAM L [h _ LO 11/TILf b abc gEMALDATTAhd ""I p,,,, 1 3/4' I 3# A, ""t hyyy 11/2" l@ t-StT AT 40 P5tG IL41Agogy DAv TANK b"*** 1 _ urgw* STOP 4 ST Amt ataC g.nC TRM Hf R) "* W y [D/CDAC OgCE - ---*- D AY 1 ANil R00W f 4Tth STS 08 '* 3 / FL AWt ARREST [R 5 REEN\\ , ]f I 4'U6b*Ai*C "E 0/0 R fog h [H@ - W FILitR [ ~ / E ] ? atactet exo 2 ~ A d, 1 L VENT ~ DPS DC A00W AIR k[ I lW [ (2"rth-As-c wtant ,o, D CmL .-.) a,,A. y o-o DuPLtw a lf ST R AiNti 7,, Y Duis!DE =*- '- l---*-lNg \\ ) ,- y 3"lLIb A1-C [nf wtTH h MREEN b t~h~*0~0 f ) p-ClMhbl-C ( sit mote s to"sTc'EAct 1 AE's s'. 5 FUEL 01. 9,, /( at,A C,T,O,R DAY TA** l 3 A-stopt e - ) st[ =ott. e a b.A1.e.3e, y i- ~ 0$*' .\\--- % c Mdr A stt mott 3 aAI "TauintEJt" 4 DRAIN U 0 0 / O m res*- [ L, ( As c Q-2*ILibAbc i 0 SEE hof t 7 3,,. l 3*(t#) Al C g "gTh," '$ I't h ,Y, - ,Y, 1 "G w my. - A1-C

9"(L#)* A l* C --

-- \\ x. 4 u i tr > u Lt A ong ay,A _ n,,;, L > G#C1, A g -- - g - t f 7~ ,. 4 7 day STORAGE TAM o FiGcRE 'l. 5 -G 9.s-te

ABWR Standard Plant 1 -- = i = I i I l i 4 I i 4a n e,..... m 1^ y p .u.,'. q Q 1 e r

n Q

"" 6 d' (N V i i c i r;;,y' L J L J ";M' ' "' x I 'Tf-- b k.? "**'k!T." 5 3 , i .c _d = = V 4' k-h"[a

• ve i vi-s gg s

p .x.: c

====- j at.at i g'. astett SM .I s a ft e ,1 i se sg C tnn.L R 0 cox a cosa e, 1 O, w-

n'.

- H A -

-3 gra r m 4, ye, _..e u m 1 c c Jn'. ". fit, i g.. . N- + - vc g.. p - 6 d h5itpiiTI ..e.1,...t.,y a r e m. r r c i o f.". lr*R1"#, t... _( - s-. - .. =a a.w - (p v I T C um o = = ._..,, m l 5 L-I Figure 9.5-7 STANDBY DIE: Amendment 16 9, $ - l 9

ABWR ma m Standard Plant nov n f l l l l l l 6 5 3 4 1 n LJ j{R_RE FE tVE;1,4$$ EW3iY AIR RECEIV'R ASSEUSLY Nott s: t (QJtPWthT W'Twth DTSCL thC ht DUTLINt runySHED g y %g 04 thGiNE SY SELLit. g ry 2. % DP10%ATED COVWWthT rueyguto 31 OttttL v X C*mteatom stLitm. CLassicATcq is $artTY C A$$ J QUAL 11Y G# dup. 1 8

3. FUfutt LIht FJuttR$ Att ACP4t$tNTtQ gY *(! b" g

y v TO 9 ~ $JpriTO AT rihai DltiGN ST A00. 7 3'** 1/ *] [_ 3/4" 1/ 4" l g gjg g , pg g 9 y, fre one o f f er i sitets to re wo *C C*A, r n y X at,$,n X woStc,Cv3f cad day P'#t 5(#'e f r e = I getn 3,,. 3 W 3,,, gggQs t Si r ea m. y h ST Attika Am CCupet$504 rs wof ce D4'vtN Ki y h FLER.0LI CONNECtem @ atutr vAtyt i 4 @ stavet vatvt / CHECK YALyt I ~ /2" I 1: h CRAIN VALvt h Patssunt.NoiCA TOR 8tDL'CER h*k, 3 / 4"IL h-R A -C A,H (4 fc 4/ h PRttsunt smTCH fAm COWPRES5CR C0hTROL) gg t I r s 'V 4e -- Cth0Ti$ PPING 5PEC CMANCE -c--iM ^ 2 i l I l l l l web no. a43-mso i 11/2' tLh-5 A-C l l i s l E m 91 120 23 Figure 9.5-8 STANDBY DIESEL GENERATOR STARTING AIR SYSTEM l Amendmer.t 16 WO

ABWR Sandant Plant l I sl l l i l l 5 4 a 7 /N i 's ./ D:ESCL th 'NE AURfLIAtt WODJLt TuatD ~N i O noCute V 2' I ' LVIE y A.... v ;,pr 3 A VAivt V4* vtNT T M h0f t 4 g CIA

• CAtt L.J s

r y gpp l F STRA:NER c 4A:t= l,,,r CIc -- atta = A=w'-] LC (LTER .' ) 1 l v 1/4* VthT 1/4" VIh? 7 h07t & h0TE & ' t ps r' 1/4" vtNT %TE 4 3 t/7 j, 2' N' 'M DuPit t ^ F t. T E R 5t n Ai%t R A15EweiY STRA,%te~ f8 h Lp_* \\ I .m.,, m (

---

4.----

I I e WE C M A Ntt, AL q n,/ LINE A G( t p 1/4* vt47 500 C8W NOTE 4 40 Pt:C tSt *F AIA A A i m I C y y Co't$tt Cth!R A109 cims m ATER SYS 3" e* B* 8" di $30 CPW 3" F 70 P51G LL:St 0?L 1/ 4

• NE 04 VIN 19 5 'T

%n EN0'o P.,w' , C00itt t to er:a= U f L --+ ) LT p p i e4c stl :tst = Aion LI ,vr i: set av .L Cooti=c =&ita sys r(j bL " "*# dtj y. j h / 1 t/2* .s 4

1. ~

6* 1/4* y H h ' 5tf Af @3% D ~ V ' 1&T 7 c T c 4*

• vr l

STRA*itR \\ lc g to gttp [M w Aand PJWP U _L_ CRA;N =- ,m l ( ) l Figure 9.5-9 STANDBY Dli 9I Amendment 16

A.BWR m om^n Stanrf ard Plant PIV D l l l l l 2 3 1 4 5 --x \\ f O.tt.$.tt ( NG met.AUERI A R Y..W DD A t ~> NOtt$ t ALL IOUIPWt%T. P#ihC, h$f RJWthTS 4 CONT #iOL$ 1/4 VENT ,:TM'N Dit1tL thG.ht 00TWL AND A' nOARY u n0tt 4 Woputt OutLiht art ryog sstD tv Twt c't1CL /* h thG'NE Stilt 4 ERCEPT FOR 5 WP 1 Ahu vtNT.

2. alt,(CUPWINT, PtP!NO AND lh5TauwthTS

' }C 21/2* ^^ w TWh AUX:UARY WOSULL QUTLWE 15 A L/ g ggg,,,,, ~ 5tC*a0% W CLAll J. CO M FO Nf *'rt C MIN Thl P.ffM L E W& rki-O 6ovE Mti u l7 firi Af avergo fpas LO gL,LR CF A N$1 I

• l A no 9 ti $ $so Tt 3 rr p in t.y yapsg-, pgygg (pg $$vg y v

J. FOR 1t00Cl CF Of st Ct=tR ATOR C04 f ROL SY1?LWS SEE SELLER S, D* L1 P L SCHEWAtics. %Oss $"o"gf47 4 riLTim AND STR Antr vrmit ARE TO St C0hmtCTED 21/2 thD4tiDVALLY 10 LO SUWP 1 Ah4 TCP w;TMouf V ALyts. L

1. thCivt STRastR$ ARE 10 fit CChhteit0 IN0tyl0VALLY I4 w.Th00t V ALvt110 thCWL CC AR C Alt.

@ AsstheiY 5. FUTURE LINT NUWBERE ARE RIPRtst%ttD BY *fih / l 10 DE SVPPut0 Al FihAL DES;GN $1 A;t. I.... I l b " " ~ = - [_) $ --- DINOTES PIPWG SPEC CMANGC WECH A NtC A L o ( f s.M A GE %./ (d 1/4* vtNT SCO CPW N0f t 4 80 PStC 134 *F ) >-- *

• q M

D:E$tL CthtRe f CR g C00uhG wattR SYE 4* 8" 4" b b 500 CP1 7D 05:G LUBE DIL 185 *F CCOLER 3 V I L.. e l DistL CthtRaf CR 1 COCUNC W ATER SYS SHELL DRAW J' [ SET AY h 50 P54 21/2" WPL hD,R43-1Ca0 LO KEEP DARW PgWP L R, g 5' ) 91 120 24 s ./ Figure 9.5-9 STANDBY DIESEL GENERATOR LUBRICATING OIL SYSTEM 95 21 Amendment 16 l - ~. - - .. -.. ~..

ABWR muow Standard Plant mx coa.~.a,p[m,....-'$lg$'.S4 ['d4$,[L,U being deaned, emptied or reClled. ne serwce run 10AD Evaluation (q for each polisher wsselis terminated by either high '] differential pressure acrou the veuel or high con-The CCS does not serve or support any safe;y ducthity or sodium content in the polisher effluent function and has no ufety deugn basis. water. Alarms for each of these parameters are provided on the local control panet The condensate deanup systeta removes some radioactive material, activated corrosion products The local control panel is equipped with the and fluion products that are carried over from the appropriate instruments and controls to allow the reactor. While these radioactive sources do not operators to perform the following operations: a5ect the capacity of the resin, the concentration of such radioactive material requires shielding (see (1) Remove an exhausted pothber from service and Chapter 12). Vent gases and other wastes from the replace it with a standby unit condensate cleanup system are collected in con-trolled areas and sent to the radwaste system for (2) Transfer the resin inventory of any polisher treatment and/or disposal Chapter 11 describes veuelinto the resin receiwr tank for mechanical the activity len) and removal of radioactive material deaning or disposal. from the condensate system. (3) Process the as received resin through the The condensate cleanup system complies with ultrasonic resia cleaner as it is transfered from Regulatory Guide 1.56, Alaintenance of Water Purity m'd'-494

• 5 0 the ree:iver tank to the storage tank.

.In bolhag Wafer ReactTo>r c.W.~EP ya a Gu% s : w an k oa,m.ed. vuocA.ker i s t e. a or (4) Transfer the resin storage tank resins to any The condensa,te cleanup system and related polisher vessel. support facilities are located in non safety related buildings. As a result, potential equipment or piping ($) Transfer exhausted resin from the receiver tank failures can ocg affect plant safety. to the radwaste system. [V,) 10AM Testa and Inspections On termination of a service run, the exhausted polisher vessel is taken out of service, and the Preoperational tests are performed on the con-standby unit is placed in service by remote manual densate cleanup system to ensure operability, reli-operation from the local control panel. The resin ability, and integrity of the system. Each polisher from the exhausted vesselis transferred to the resin veuel and system support equipment can be isolated receiver tank and replaced by a dean resin bed that during normal plant operation to permit testieg and is transferred from the resin s! prate tank. A final maintenance. rinse of the new bed is performed in the polisher by l, condensate full flow recyde to the condenser before 10AM lastrumentation App!! cations M it is placed in service. The rinse is monitored by con-ductivity analyzers, and the proecss is terminated Conductivity elements are provided for the when the required minimum rinse has been system influent and for each polisher vessel efnuent. completed and normal clean bed conductivity is System influent conductivity detects condenser obtained. leakage; whereas, polisher effluent conductivities ' provide indication of resin exhaustion. The polisher Through periodic condensate makeup and re-effluent conductivity elements also monitor the ject, the condensate storage tank water inventory is quality of the condensate that is recycled to the processed through the CCS and tank water quality is condenser after proccuing through a standby vessel maintained as required for condensate makeup to before it is returned to service. DiNerential preuure the cycle and miscellaneous condensate supply is monitored acrou cach polisher vessel and each services. The diagram of the condensate storage and wuel discharge resin strainer to detect b!xkage of transfer system is illustrated in Figure 10A-5. flow. The flow through each polisher is monitored and used as controlinput to auure even distribution The condensate cleanup and related snpport of condensate flow through all operating vessels and systems wastes are processed by the radwaste system by correlation with the vessel pressure drop, to O as described in Chapter 11. V Amendment tt 10 4.t2

ABWR 23AmeAN Standard Plant RTT A designs. During the construction and testing representatises of the plant owner / operator, GE, f.s / phases of the plant cycle GE personnel are onsite and others. The duties of the SCG are to review to offer consultation and technical direction and approse project testing schedules and to with regard to GE supplied systems and equip-effect timely change, to construction or testing ment. The GE resident site manager is respon, in order to facilitate execution of tbc preoper-sible for all GE supplied equipment disposition ational and initial startup test programs. and as the senior NSSS vendor representative on-site is tbc official site spokesman for GE. He 14.2 3 Test Procedures coordinates with the plant owner's normai and augmented plant staff for the performance of his in general, testing during all phases of the duties which are as fc! lows: initial test program is conducted using detail-ed, step by step written procedures to control (1) resiewing and approsing all test procedures, the conduct of each test. Such test procedures changes to test procedures, and test specify testing prerequisites, describe desired l resuh [ e _ 4 9, initial conditions, include appropriate methods to direct and control test performance (includ-(2) prosiding technical direction to the station ing the sequencing of testing), specify accep-M staff; tance t:riteria by which the test is to be C evaluated, and proside for or specify the format p (3) managing the actisities of the GE site by which data or observations are to be record, y personnel in prosiding technical direction ed. The procedures will be developed and M to shift personnel in the testing and opera-reviewed by personnel with appropriate technical tion of GE supplied systems; backgrounds and experience. This includes the participation of principal dedgn organizations (4) liaison between the site and the GE San Jose in the establishment of test pe rfposc.tta uir e-home office to pro $ide rapid and effective ments and acceptance criteris.TAvailable infor-(3 solutions for problems which cannot be mation on operating and testing experiences of () sched onsite; and operating power reactors will be factored into test procedures as appropriate. Test procedures (5) participating as a member of the Startup will be reviewed by the SCG and will receise Coordinating Group (SCG). final approval by designated plant management personnel. Approsed test procedures for satis-1422.4 Others %5M fying the commitments of this chapter will be made available to the NRC staff approximately 60 Other concerned parties, outside the plant days prior to their intended use[ c staff orcanization, such as the architect-Lsce r D] engineer, the constructor, the turbine generator 14.2,4 Conduct of Test Program supplier, and sendors of other system and equip-ment, will be insched in the testing program to The.nitial test program is conducted by the 2 sarious degrees. Such involvement may be in a startup group in accordance with the startup direct role in the startup group as discussed administrative manual. This manual contains the abose or in an indirect capacity offering con-administrative procedures and requirements that sultation or technical direction concerning the govern the activities of the startup group and testing, operation, or resolution of problems or their interfaces with other organizations. The concerns with equipment and systems for which startup administrative manual receives the same they are responsible or are uniquely familiar level of review and approval as do other plant wit h. administrative procedures. It defines the spe-cific format and content of preoperational and 14.2.2.5 Interrelationships and lnterfaces startup test procedures as well as the review and approval process for both initial procedures Effective coordination between the various and subsequent revisions or changes. Tbc start-site organizations invoked in the test program up manual also specifies the process for (7) is achiesed through the SCG which is composed of V j 1 Amendment 2 1424

14,2.2.3 General Electric Company INSERT A for equipment and systems within the GE scope of supply; INSERT B [ 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 purposes only) 14.2.3 Test-Procedures U,CN INSERT C Specifically, GE will provide the plant owner! operator referencing the ABWR Standard Plant design with scoping documents (i.e. preoperational 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. l l l INSERTD for preoperational tests and 60 days prior to scheduled fuel loading for power ascension tests. l

ABWR m-SigJ : ard Plant nrv n O resiew and approval of test results and for re-that for selected milestones or hold points U solution of failures to meet acceptance crite-within the test phases. ria and of other operational problems or design deficiencies noted, it describes tne various 14.2.6 Test Records phases of the initial test program and establi-sbes the requirements for progressing from one initial test program results are compiled and phase to the next as well as those for moving be-maintained according to the startup manual, yond selected hold points or milestones within a plant administrative procedures, and applicable gisen phase. It also describes the controls in regulatory requirements. Test records that plac.. hat will assure the as tested status of demonstrate the adequacy of safetv related sb.d each system is known and that will track modi-components, systems and structures Eher@bc fications, including rctest requirements, deemed retained for tbc life of the plant. Retention necessary for systems undergoing or already periods for other test records will be based on hasing completed specified testing, Additional-coasideration of their usefulaess in ly, the startup manual delineates the qualifica-documenting initial plant performance tions and responsibilities of the different characteristics. positicas within the startup group. The startup administratise procedures are intended to supple-14.2,7 Conforrnance of Test Prograrn with ment normal plant administrative procedures by Regulatory Guides addressing those concerns that are unique to the startup program or that are best approached in a The NRC Regulatory Guides listed below were different manner. To avoid confusion, the start-esed in the deselopment of the initial tes; up program will attempt to be consistent with program and the applicable tests comply with normal plant procedure where practical. The these guides except as noted. The applicable plant staff will typically carry out their duties revisions of the regulatory guides listed below l according to norrnal plant procedures. Howeser, can be found in Table 1.8-20. l ( in areas of potential conflict with the goals of the startup program, the startup manual or the (1) R e g ulat< Guide 1.68--Initial Test individual test procedures will address the Program (*arcr Cooled Nuclear Power required interface. Plan ts. 14.2.5 Review, Evaluation, and Approsal (2) Regulatory Guide 1.68.1 Preoperational and of Test Results Initial Startup Terting of Fredwater and Condensate Systems for Boiling it'ater Reactor Individual test results are evaluated and Power Plants, reviewed by cognizant members of the startup I group. Test exceptions or acceptance criteria (3) Regulatory Guide 1.68.2 -Initial Startup violations are communicated to the affected and Test Program to Demonstrate Remote Shutdown responsible organizations who will help resolse Ccpability for Water Cooled Nuclear Power the issues by suggesting corrective actions,

Plants, design modifications, and retests. GE and others outside ; e plant staff organization, as (4) Regulatory Guide 1.68.3 Preoperational appropriate, will have the opportunity to review Testing of Instrument and Control Air the results for conformance to predictions and Sys t em s.

expectations. Test results, including final resolutions, are then reviewed and approved by (5) Regulatory Guide 1.20 Comprehensive designated startup group supervisory personnel. Vibration Assessment Program for Reactor Final approval is obtained from the SCG and the Internals During Preoperation and initial appropriate level of plant management as defined Startup Testing. in the startup administrative manual. The SCG and the designated level of plant management will (6) Regulatory Guide 1.41 -Preoperational /^)\\ also have responsibility for final review and Testing of Redundant Onsite Electnc Power (._. approsal of overall test phase results and of Systems to Verify Proper Load Group A ssign m en ts. Amendment 18 im

. ~. AIMIt mme Sundard Plant, uvn (7) Regulatory Guide 1.52..DeJ/gn. Testing. To the estent practicable throughout the pre. O. and Alaintenanct Criteria for Engin;rrru operational and initial startup test program. Sofety Fraturt Atmospherr Clranup Sptem test procedures will utilhe operating, emer. Air 1iltration and Adsorption Units of gency, and abnottnal procedures whett applicable Light it'ater Cooled Nuctrar Poner Plants. in the performance of tests. The use of these procedures is intended to do the following: (8) Regulatory Guide 1.56-Alaintenance of li' aver Punty m Botling Water Bractors. (1) prose the sptsific procedure or illustrate changes which may be required; (9) R e gulat ory G uide 1.95.. Protection of Nuctrar fontr Plant Contro/ Room Operators (2) provide training cf plant personnel in the Agamst an Accidental Chlonne Rr! rase. use of thest procedutu; and (10) Regulatory Guide 1.105-Periodic Testing of (3) increase the level of knowledge of phut Dorsel Generators Used as Onsite Electric personnel on the systems being tested. Fon5r Syttmi at Nuclear Power Plants. A testing procedure utilizing an oper.iting, (11) Regulatory Guide 1.139..Guldance for emergency, or abnormal procedure will reference Residual #cc' Remo5al. the procedure directly, extract a series of steps from the procedure, or both in a way that l (12) Regulatory Guide 1.140 Design. Trsting and is optimum to accomplishing the abose goals Alainernance Criterna for Normal t'entilation while efficiently performing the specified E.theast Sytcm Air Fsitration and At'sorVion testing Unit, of Light it'ater Cooled Nuctrar Poner Plants. 14.2.10 Initial Fuelloading and Initlai Criticality 14.2.8 Utillration of Reactor Operating and Testing Experience in the Deselopment Fuel loading and initial criticality ate e of Test Prograrn conducted in a sery controlled reanner in Ju accordance with specific written procedures as J @M Since every reactor / plant in a GE BWR product part of the stattun test phase (see Subsection 14.2.12.2). Ap T line is.a etolutionary development of the loading ub!!goval for commencement of fuel , a gianted by the NRCyWeqr l previous f ant in the product line (and each product line is an evolutionary deselopment from b " ' - pih-h s,c a f t e r Wil I the presion produ t line), it is evident that prerequisite testing has been satisf actorily the ABWR plants hr e the benefits of experience completed. However, there may be unforeseen acqu..ef with the successful and safe startup of circumstances that arise that would present the more than 30 presious BWR/1/2/3/d/5/6 plants. completion of all preoperational testing The operational esperience and knowledge gained (including the review and approval of the test from roese plants and other reactor types has results) that would not necessarily justify the been factored into the design and test speci-delay of fuel loading. Under such circustanns. fications of GE supplied systems and equipment the applicant referencing the ABWR design ma) l that will be demonstrated durin:: the preopera. decide to request permission from the NRC to l tional and startup test programs. Additionally, proceed with fuel losding. If portions of any l reactor operating and testing esperience of preoperational tests are intended to be l Similar nuclear pcact plants obtained from NRC conducted, or their results approved, after i licensee Event Reports and through other industry commencement of fuelloading, then the following sourees will be u ilized io Ihe extent shall be documented in such a requese (1) list practicable ie, developing and carrying out the each test;(2) state which partions of each test initia' test program, will be delayed until ifter fuel loading; (3) provide technical jusufication for delaying 14.2.9 Trial Use of Plant Operating and these portions; and (4) state wheu each test Emergency Procedures will be completed and the results approved. Amendment 1B Id I3 l l

ABWR mnus 20.dadEIABL RIT fi 14110.1 Pre fuel Lad Checks i Once the plant has b3co declared ready to / s load fuel, there are a eurober of specific checks l thaw 4 be made prior n proceed

p. Ta:Se

'ttflude a final resiew of be preoperational test results and Ibe statu of any design changes, work piclages, andAr retests that were initiated as a result of escemious noted during this phase. Also, the technical specifications surseillance program requirernents, as described L Sh"N in Chapter 16 shall be instituted at this time L~ 40 a:sure the operability of systems required let fuel loading., lust prior to the iaitiation url in u Ale agbe proper sessel water level l and chemistry 64M be verified and the calibration and response of nuclear instruments should be checked. 1,tJ.10J Inliial fuel Loading Fuel loading requires the movement of the full core complement of assemblics from the fuel v \\ L .e(J Amendment 18 1G51

AIMR

n. o Slam!Jrd Plant erv s pool to the core, with each assembly being test procedure preparation will be scheduled identified b.s number before being placed in the such that approsed procedures are asailable correct coordinate position. The procedure appraimately 60 days prior to their intended corarolling this mosernent will specify that use or 60 days prior to fuel load for power shutdown margin and subcritical checks be made at ascension test proceduret Although there is predetermined interials throughcut the loading, conside r able fle xibility available in the thus ensuring safe loading incremento Irmessel sequencing of testing within a gine:, phaic there neutron monitors preside continuous indication of is also a basic order that will rasult in the the core flus lesel as each assembly is added A most efficient schedule. During the preopera-complete check is made of the fully loaded core tional phase, testing should be performed as to ascertain that all assemblies are properl) sprem turnoser from cormruction alloas. Ilow-installed, coreectly oriented, and occupying ever, the interdependence of systems should also their desVnated positions be considered so that common support systems.

such as electrical power distribution, sersice 142.10.3 pre Criticality Testing Qg, and instrument air, and the sarious makeup water y 'jyA and cooling water sptems, are tested as earl) Psior to initp!1riticality Jhe f hut own as pouible. Sequencing of testing during the margin 4*A!Te serified for/he ftilly h aded startup phase will depend primarily on specified core. The control rods AMc function I and power and flow conditions and intersptem pic. scram tested with the fuel in plap. T post r e q uisit e s. To the extent practicable, the fuct load flow test of the react t intet als si. schedule should establish that, prior to ex. bration assessment program be corducted at creding 25"< power, the test requirements will be this time as well. Addit onally, a fi[al serifi-met for those plant structures, splems, and -. f components that are relied on to present, limit,WU cation that the required technical sp.ecification surseillances base beca per armed 4 ate be made. or mitigate the consequences of postulated acci['j rv% dents. Additionally, testing AeddTe sequenc-p 142.10A Initial Critkality. L,@ olg ed so that the safety of the plant is neser \\,.,.,s.f e - ~ d totally dependent on unlegd,systernsdon3pg Initial criticality shall he achieved in an nents, or features / The detailed te) ting scheJ, orderly, controlled fashion following specific ult wil) be generated and snairdainerd at the job - site'so/thafit may bi updated and contin detailed procedures in an approsed rod withdrawal optirrdred/ o toilect/ actual progress.and'subse. sequcnce. Core neutron flux shall be continuous-t l} monitored during the approach to criticality ent' revised pr6jectidns. #~ '._ -%g~ m,. and periodically compared to predictions to allow ~* _"" k carly detection and esaluation of potential ano-14.2.12 Individual Test Descriptions malies f / To insute that theaests are conducted, inn c f ' the flant'and'sptem preope.tatiptal'and ga 14.2.11 Ten Pro;; ram Schedule a Qh'e NRC resIden/ site'insp}ector,tesi speci b The schedule, relative to the initial fuel load date, for coaducFng cack major phase of the initial test program will be proided by the ap-plicant k Wmrt+vei p;" n;ma-142.12.1 Preoper,stional Test Procedures Fu %- This includes the timetable for ge-ne r atiorde.siew, and approsal of procedures as The following general descriptions relate the glWs'the actual testing and analysis of re. objectises of each preoperational test. During [e sults. As a minimum, at least 9 months should be the final construction phase, it may be allowed for conducting the preoperational phase necessary to, adify the preoperational test I prior to the fuel loading date and at least 3 methods as opeuting and preoperational test j months should be allowed for conducting the procedures are developed. Consequently, methods startup and power ascension testing that commen. in the following descriptions are general, noi \\ ecs with fuel loading. To allow for NRC resiew, specific. ( 7% - ~.w wm ~ Y (them %.OCMQ %dstd & dtsyn. j k es ~~. % _., s._,_, g Amendment 2 14 N .,e. . _.. ~.

Od 14.2.11 Test Program Schedulo INSERT E Power asterision tejting will be conducted in estentially three chates: O initial fugj leadino and ooen vessel testin;}J) Testino durinc nuclear hgatuo to ratedlemoerature and cressure: ano Si oqWer ope. ration J inshttonL5,1to 100% rated onwer. Further. otwer coeration testing will be divided !nto three secuential testino o!ateaus as thown on Ficure 14.2 1. The test D!ateaus consig.13Ugyy,, cower testino at less than 25% oower. mid onwer testing on to_about 75% oower between aporoximate!v the 50% and 75% tod knet and hich pawer testino along the 100% rod hne un to ratedjawer, ThusJhere will be a total oUigg different testino otateaus desionated asdesenbod on Ficure 14.21. Table .14.21 iridicatet in which testino of ateaus the varioutpower attention Igsts will be cerformed. Althouch the order of testino within a olven clateau is somewhat flgnh'e. the normal recornmendgd_gggggnce of tests would be 1) coreagrformance analysis: 2) steadv state tests;3) control system tuniDot 4) systern trantient tesis* and. 5) maiqLolant transients (includino itips). A!so. br a civen festino clateau. testino at lower oowet levels should oenerally be cerformed orior to that at hicher oower levels. The detaited testing schedule will be generated kihe acclicant referencina the ABWR Standard Plant desian and will be made available to g the NRC crioLlo actualimolementation. The schedule will then be W maintained at the job site so that it may be updated and continually optimized to reflect actual progress and subsequent revl Sed projections. e.,

. - _. ~ j l AMM a4woss sarAumant mn ,m-wJ applicah}c ac,ing to be performed and the. ration splem (ADS); S pe cifi& t e s t ding that of the automatic depressuri-cef t an $t crit e ria/f or/f a ch ( / , picoperational tett are in suordar.cc o h the / dilailed sys' tem speelficatibns add q'uip3r'ent (c) proper operation of MSIVs and main f ( specifications for ettuipment in'those spfemf. ' steamline drain vahes, including seri. T h e f e s t s d e m o n s t r at e t his th'e iru t dJt d fication of closure time in the isola. ( of these' spec fications.' perforrn within the Idnits (' equfmeta and s.6 tem > ' tion mode, and test mode, if applicable; s h'" p F (d) serincation of SRV tnd MSIV accumulator Tbc preoperational tests antigated for the capasity; ABWR Standard f ant are listed and described in thc iollowing paragraphs. Testing of sptems (c) proper operation of SRV air piston outside the scope of the ABWR Standard Plant, but attuators and discharge line vacuum that inay have related design and therefore breakers; testing requirementt, are discussed in Subsect:on 14.2.13, along with other interf ace requirements (f) verification of the acceptable lest related to the initial test program, tightness and overall integrity of the reactor coolant pressure boundary sia 14.2.12.1.1 Nuclear ' loller Splem the leakage rate and/or hydrstatic Preoperational Tr.t Iesting as described in Section 5,2.4.6.1 a nd 5 2.4.6.2 t e spe etis cip (1) Purpose and To serify that all pumps.,ahes, actuators, (g) proper sptem instrumentation and j instrumentation, trip logic, alartns, annun-equipment operation while powered from l tiators, and indications associated with the primary and alternate sources, including nuclear boiler 2ptem function as specified. transfers, and in degraded modes for \\ which the sprem and/or components are (2) Prercquisites prM l-expected to remain operational. I J i The conttruction tests base been success-Other checks *he,M be performed, as appro-l fully completed and the SCG has reviewed the priate, to demo' strate that design requirements, n test procedure and has approved the initia-such as those for siring or installation, are lion of testing. All required interfacing met via as built calcultitions, visual inspe c-spiems shall be asailable, as needed, to tions, review of qualification documentation or support the specificd testing and the kiher methods, For instance, SRV setpoints and appropriate spiern configuration;. capacitishbm4d be serified from certification ( or bench tuts to be consistent with applicable (3) General Te Methods and Acceptance Criteria requirements. Additionally, proper installation mil and setting of supports and restraints for SRV Performanceg be obsersed snd recorded discharge piping will be verified as part of the during a series of individual component and testing described in 14.2.12.1.51. int: grated splem tests to demonstrate the following: 14.2.12.1.2 Reactor Recirculation Sptem Preoperational Test (a) serification that all senting devices respond to actual process variables and (1) Purpose provide alarms and trips at specified values; To serify the proper operation of the reactor recirculation spiem at conditions (b) proper operation of system iratrumen-approaching rated volumetric flow, including n tation and any associated logic, inclu-the reactor internal pumps (RIPS) and ( motors, and the equipment associated with t he motor cooling, se al purge, and inflatable shaf t se al subsystems. Amenbent il 14 M

~ 14.2.12.1 Preoperational Test Procedures INSERT F Specific testing to be performed and the applicable a0CEptance criteria for each preoperational test are will befgumented in detailed test crosedures to be made available to the NRC accro6Tatelv 60 davs orioLio their intended use, Preocerational testina will to in DCCordance with the detailed systern specifications and associated equipment cecifications for equipment in those systems forovided as part of sc;oino documents 1/ be sunolied bv GE and others as described in subsection 14.2.3). The tests demor.st 310 that the installed equipment and systems perform within the limits of the e spuifications. To insure that the tests are conducted in c accordance wth estEM2hed methods and accrobriate acceotance critella. the olant and system otecoerat'onal test soecifications will also be made available to the NRC. 3 V y w ---s u ,w.. .-~ -,

AllWR nome Signdard Mant rua. (2) Prerequisites t ( } The construction tests base been success-U fully cotopleted and tbt SCG bas reticued the test procedure and has approsed the initia-tion of testing. Cooling water from the re. actor building cooling water tptem and seal purge flow from the CRD hydsaulic sptem shall be asailable. The tecirculation flow control splem *)+vW be sufficienth tested t Shall \\ j k%/ f' M i i \\x) Arr.cndment Ig 14 2.* 1

AMW 2mre Standard Plant u.u p to support RIP operation. Olber interfacing (f) proper splem flow rates including indi-(j sptems shall be available, as needed, to vidual pump capacity and discharge head. support the specified testing and the ror responding splem configurations. Reactor (g) preper manual and aviomatic sptem ope. s essel internatt 4.*WAe capable of being ration and margin to actuation of pro. subjected to rated sokmetri(core flow {' tective dedces; (3) General Test Methods and Acceptance Criteria (b) proper operation of interlocks and equipment protectise devices in pump and Testing of the recirculation splem should be ruotor controb; coordinated closely with that of the recircu. lation flow control spiern (Subsection (i) proper operation of permissise, pro. 14.L12.1.3) in order to adequalcly demon. hibit and bypass functions; strate propes integrated system respont,e and operation. Also, the pr. perational phase of (j) proper sptem operation while powered the reactor internals Obration assessment from primary and alternate sources, program (Subsection 14.2.1L1.32) insches including transfers, and in degraded estenced operation of the recirculation sp. modes for which the sptem is expected tem and should be scheduled accordingly so as to remain operational; to optimize oserall plant integrated testing. (L) proper operation of the recirculation The scope and intensity of the preoperational rootor seal purge subsprem oser the full testing of the recirculation sptem and range of RPV pressures including the aswehted support subsptems will be limited proper functioning of the main header by the unavailability of nuclear heating. pressure control vahe and proper Comprehensise testing of the splem at rated distribution of seal purge flow to O temperature and pressure will be performed indiddual pumps and rnotors; during the stariup phas*PS d) (1) proper functioning of the recirculation { Perfermance .1 be obserwed and recorded motor cooling subaptem and its ability during a series of indisidual component and to remove design heat loads from each integrated sptem tests to d5monstrate the RIP motor via the dedicated heat exchan. following: gers; (a) proper operation of instrumentation and (m) proper functioning of the recirculation equipment in all cornbinations of logic motor inflatable shaft seal subsystern and instrument channel trip; and its ability to provide a temporary backup scaling mechanism for each pump (b) proper functioning of instrumentation and rnotor shaf t during recire motor alarms used to monitor sptem operation maintenance or removal; and as allability; (n) acceptable pump / motor vibration lesels (c) proper operation of system vahes under and rystem piping movements during both expected operating conditions; transient and steady sute operation; and (d) proper operation of pumps and motors in all normal design operating modes as well (o) acceptable reactor vessel internals flow as any.pecified 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-Amendment 2 1424 s s

ABWR Sandard PlanL__ ro u teristics, from the testag described abose, meet (d) proper operation of control splems in d the applicable design specifications. all design operating modes and all le-sels of controls; 14.2.12.1 3 Recirculation Flow Control Splem Preoperational Test (c) proper operation of the adjustable speed drineh; (1) Purpose (f) ability of the control system to comm-To serify that the operation of the recir-unicate properly with equipment and culation flow control splem, including that controllers in other systems; of the aditstable speed drites, RIP trip and runbeck bgic, and the core flow measurement (g) proper control of pump motor start subsptem, is as specified. sequenee; (0) Prerequisites (b) proper operation of interlocks and equipment protective devices: The conaruction tests base been success- .!!y completed eSd the SCG has reviewed the (i) proper operation of p,9tmissive, probi-test p'ocedure and has approved the initia. bit and bypass functions; and tion oftuting. All required interfacing spiems shall be asailable, as needed, to (j) proper sptem operation while powered support :he specified testing and the f rom primary and alternate sources, corresponding system configurations. including transfers, and io degraded modes for which the system is espected (3) General Test Me: hods and Ac - ge C teria to remain operational. d,(I f.Le Some portions of the rect e Wy ow con. Sptem operation is considered acceptable trol nstem testing htATbe performed in when the obsersed/rneasured performance charac, conjunction with that of the recirculation teristin, from the testing described abos e, system, as described in Subsection meet the applicable design specifications. 14.2.12.1.2. Close coordination of the testing specified for the two sptems is 14 2.12.i.4 feedwater Control Sptem required in order to demonurate the proper Prs 9perational Test integrated sptem res onse and operation. p ai (1) Purpose Perfermacce s ,e observed and recorded during a series of ihdividual component and To verify proper operation of the feedwater integrated system tests to demonstrate the control system, including individual cornpo. following; uents such as controllers, indicators, and controller software settings such as y,ains (a) proper operation of instrumentation and and function generator curves. equipment in all comb nations 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 reviewed the function); lest procedures and has approsed the initi. ation of testing. Preoperational tests musi (b) proper functioning of instrumentation be completed on lower level cor trollers that and alarms used to monitor system do not strictly belong to the feedwater con. operation and availability; trol system but that may affect system te-(]) sponse. All feedwater control system com-( (c) proper functioning of the core flow measurement subsystem; Amen.1 nent 18 112 9

ABWR uums Standar.d Plant 3%)\\ uv3 ponents have an ici al calibration Sprem operation is considered acceptable in accordance with sendor i,structions. All when the obsersed/ measured perfortnance required interfacing splems M be asail-characterisocs, from the testing desc*ibed able, as needed, to support the specified above, m e e t Ibe a p plic a ble design testing and the appropriate system configu-5 p e cifie aiio o s. rations. 14.2.12.1.5 Standby Liquid Control Splem (3) GeneralTest Methods and Acceptance Criteria Preoperatlanal Test Testing of the feedwater control sptem dur-(1) Purpose ing the preoperational phase may be limited b) the absence of an acceptable feedwater To serify that the operatior of the standb.s recirculation flow path. Comprehentise flow liquid control (SLC) system, including testing will be conducted during startup pu m ps, t a n k s, con t r ol, logic, and phase. instrumentation, is as specified. Perfermance si4+d e obsersed and recorded (2) Prerequisite:, l during a series of[indisidual component and oserall sptem response tests to demonstrate The construction tests base been success. the following: fully cornpleted and thr: SCG has redewed the test procedure and has approsed the (a) proper operation of instrumentation and initiation of testing. Valses should be controls in a;) combinations of logic presiously bench tested and othen pre-l and instrument channel trips including cautions relat ve to positive displacen a s,%ll i serifical;on of setpoints; pumps taken Ths reactor sessel M e available for injecting demineralized (b) proper functioning of instrurnentation wa t e r. All required interfacing sptems g*j and alarms used to monitor sptem opera-shall be available, as needed, to support tion and status, the specified testirig and the appropriate system configurations. (c) proper operatinn of sprem vahes, in-ciuding timing and stroke, in response (3) General T" f. thods and Acceptance Criteria to control demands (including the sMI reactor water cleanup sptem dump vahe Performance be observed and recorded l 3 response to the low flow controller); during a series of individual component and integrated sptem tests to dec'onstrate the (d) proper operation of interlocks and following: equipment protecthe desices in pump and sahe controls; (a) proper operation of instrumentation and equipment in all combinations of logic (c) proper operation of perinissive, prohi-and instrument channel trip; bit, and bypass functions; (b) proper functio'iing of instrumentation (f) proper system operation while powered and alarans used to monitor system opera-from prirnary and alternate sources, in-tion and availability; cluding transfers, and in degraded modes l for which the sptem is expected to re. (c) proper operation of sprem vahes, in-main operational; and ciuding timing, under expected operating vonditions; (g) Proper communication and interface with other control systems and related (d) proper operation of pumps and rnotors in equipment, all design operating modes; () C Amen 3.atnt 19 14 LM

ABWR

wms g}d Standard Plant

. nv e (c) Proper operation of the tank beaters and M be installed and ready to be stroked proper mixing of tbc neutron absorber and scrammed. Reactor building cooling solution; water, instrument air, and other required interfacing systems shall be available, as (f) proper system flow paths and flow rates needed, to support the specified testing and including pump capacity and discharge the corresponding system configurations. bead (with demineralized water substi-toted for the neutron absorber mix. A d dition ally, t he rod cont rol and ture); information system shall be functional when needed, with tbc applicable portion of its (g) proper pump inotor start sequence and specified preoperational testing complete. margin to actuation of protecthe de-sices; (3) GeneralTest Meth - Acceptance Criteria shall (b) proper operation of interlocks and equi-Performance bl+cwgt'e observed and recorded f ment protective devices in pump and during a series of individual component and sahe controls; integrated system tests to demonstrate the following: (i) proper operation of permissive, pro-bibit, and bypass functions; (a) proper functioning of instrumentation and alarms esed to monitor system opera-(j) proper system operation while powered tion and status; frcm primary and alternate sources, in. cluding transfers, and in degraded modes (b) proper comraunication with, and response for which the system is expected to re-to demands from, the rod control and main operational; and information system and tbc reactor pro-O tection system, including that associa. V (L) acceptability of pump / motor sibration ted with alternate rod insertion (AT% 5), lesels and system piping movements dur-alternate cod in (post scram), and select ing both tra sient and steady state control rod run in unctions; operation. (c) proper functioning of s)strm vahes, in. System operation is considered acceptable when cluding purge water pressure control the obserted/mer.sured performance characteris-vahes, under expected operating condi-tics, from the testing described above, meet the tions;

.ppli:able design specifications.

(d) proper operation of CRD bydrau;ic sub-14 2,12.1 S Control Rod Drhe System system pumps and motors in all design Preoperational Test operating modes; (1) Purpase (c) acceptable pump NPSH under the most lim. iting design flow conditions; To verify that the control rod (CRD) system, incliding the CRD hydraulic and fine (f) proper pump motor start sequence and mar-motion control subsystems, functions as de-gin to actuation of protective desices; signed. (g) proper system flow paths and flow rates (2) Prerequisites including sufficient pump capacity and distbarge head; The construction tests have been success-l fully completed and the SCG has reviewed the (b) proper operation of interlocks and test procedure and has approved the equipment protective devices in pump, initiation of testing. The control blades motor, and vahe controls; iL j Amendment 18 14211 l

ABWR nAcime Sandard Plant uv n (i) proper operation of permissise, prohi-ciated alarms and annunciators in all (7 bit, and bypass functions; combinations of logic and instrument V channel trip including all positions of (j) proper system operation while powered the reactor mode switch; from primary and alterute sources, including transfers, and in degraded (b) proper operation of control rod run in modes for which the system is espected logic including that associated with ARI to remain operational; (ATWS), SCRRI and normal post SCRAM follow in; (1) acceptability of pump / motor vibration lesels and system piping movemen;s (c) proper functioning oj inittumentation during both transient and steady state used to monitor CRD system status such as operation; tod position indication instrumenta-tion And that used to monitor continuous (1) proper operation of fine motion motors full in and rod / drive separation status; ar.d drises and associated control units, including ictification of acceptable (d) proper operation of RCals software in-l normal insert and withdraw timing; cluding verificatico of gang and group assignments and predictor comparator, (m) proper operation of hydraulic control rod worth limiter, and banked position units and associated salves including withdrawal sequence functions; and CRD scram timing demonstrations against atmospheric pressure. (e) proper communication with interfacing l systems such as the power generation con-System operation is considered acceptable when trol system, the automatic power regula-ti.e obsersed,a asured performance characteris-tor, and the automatic rod block f-tics, from the testing described above, meet the monitor. I applicable design specifications. System operation is considered acceptable 14.2.12.1.7 Rod Control and Information Sptem 'Ahen the obsersed/ measured performance charac-Preoperational Test teristics, from the testing described above, meet the applicable design specifications. (1) Purpose 14.2.12.1.8 Residual liest Remosal System To serify that the rod control and informa-Preoperational Test tion system (RC&lS) functions as designed. (1) Purpose (2) Prerequisites To verify the proper operation of the resi-The construction tests, including initial dual beat retnoval (RHR) system under its i check out of RC&lS software, have been suc. various modes of operation: core cooling, i cessfully completed and the SCG has reviewed shutdown cooling, wetwell and drywell spray, the test procedure and has approved the ini-suppression pool cooling, and supplemental tiatico of testing, fuel pool cooling. (3) General Test Methods ceptance Criteria (2) Prerequisites Perfortnance , - be obsersed and recorded The construction tests have been successful-i during a series of tests to demonstrate the ly completed and the SCG has revi:wed the following: test procedure and has approsed the initia-tion of testing. The reactor sessel shall be l (a) proper operation of rod b;ock.s and asso-intact and capable of receiving injection flow from the various modes of RilR. The Amendment 18 14212

MN mim Standard Plant an 4 (3) GeneralTest Methods cceptance Criteria levels and system piping mosements dur. shall ing both transient and steady state op. Performance show6d dibserved and recoided erstion; and 3 during a series of individual cornponent and [. m integrated systern tests that includes all (m) proper operation of pump discharge line s 3 keep fill system (s) and its ability to f - ). modes of RHR system operation in order to demonstrate the following: prevent damaging mater hammer during system transients. p=j g 2 (a) proper operation of instrumentation and g equipment in al_1 combinations of logic System operation is considered acceptable j,g and instrument channel trip; when the observed / measured performance charac. 5 re E teristics, from the testing described above, j g j, (b) proper functioning of system instrumen. meet the applicable design specificatiota. e f c. tation and alarms used to monitor systern g*% operation and availabilityl" !I.2.12.1.9 Reactor Cort Isolation Cooling 8E System Preoperational Test . l .i E $ (c) proper operation of system valves, in. - l,j : D cluding timing, under expected operating (1) Pu, pose I !i $ ' . conditions; eE Verify that the operation of the reactor Ih8 (d) proper operation of pumps and rootors in core isolation cooling (RCIC) system, in. i -.! E j - all design operating modes;- ciuding the turbine, pump, valves, instru. Egy mentation, and control,is as specified. 6 7 E-(e) acceptable pump NPSH under the most f f limiting design flow conditions: (2) Prerequisites 3 e 2 (( 1)- proper system flow paths and flow rates j [j )(. The construction tests have b:en success. including pump capacity and discharge fully completed and the SCG has redewed the j yg%.e/ i head and time to rated flow; test procedure and has approved the initia..

,le lion of testing. A temporary steam supply 3

(g) proper operation of containment spray shall be available for. driving the RCIC tur+ Sg modes including verfication that spray bine, The turbine instruction manual shall s ::: i nozzles, headers and piping are free of be reviewed in detailin order that precau. g @, debris; tions relative to turbine operation are fol. / ~ lowed. All required interfacing systems ' 8$ ( (b) proper pump motor start sequence and mar. shall be available, as needed, to support (j i . }# gin to actuation of protective dedces; the specificd testing and the correspondinF f P{.., r,ystem configurations. 2 $ p l' og ji! (i) proper operation of interiocks and. i equipment protective devices in pump and (3) General Test Methods and Acceptance Criteria e- }3E j,[ - l valve control #g 62 { 8 Tbc RCIC turbine sb Id first be tetted 3[ $g7 1 (j)- proper operation of permissive, pro. while disconnected f m and then while ji k . S.g ; hibit, and bypass functions; coupled to the pump, ince preoperational _3 @* ' 9E ta testing is formed utilizing a temporary i a y jb steam su 1 the attainable RCIC pump flow r a; / i ! y ' (k) proper system operation while powered .5 y _5 from piimary and alternate sources, in. may be li ./ ' - ciuding transfers, and in degraded modes. sWI t j a- - ' for which the system is expected to re. Performance be o served and recorded main operational; ~ during a series of individui component and ga. g g integrated system tests to acmonstrate the l n, [$y@j i(l) acceptability of pdmp/ motor Vibration following: (j ~ \\ f-w Should this prevent any specified testing from being Completed Amendmeri: 2 successfully, such cases will be documented and scheduled for g;.33 completion during the power ascension test phase, W .y 9 v w..-t* .'wer.-wi.p w-ow-,e,,,v3 s,,--,,-...~,e-.-,,,,-,,-- ,,,---vywr,-, ,-y .-t w owe,,, y.,, , -,,,,,-y,-,w. -#g----m-e- -cw-m--c-9-w,i.g-+-g9rw-se ,e, + ' v g - w wre, ie g g - g 3 -y e y39+-we i e

_~ - - _.- - ~. - ABM useimis Standard Plant RIT A (a) proper operation of instrumentation and (1) proper operation of the barometric con. equipment in all combinations of logic denser condensate purop and vacuum pwnp. and instrumeat channel uip; (m)tbe ability of the system to swap pu:ap (b) proper functioning of instrumentation and suction source from tbc coed:nsate stor. alarrns used to monitor systern operation age pool to the suppression pool witbout i and availability; interrupting system operation; and 4 (c) proper operation of system valves,includ. (n) proper operation of the pump discharge ing timing, under espected operating line keep fill system and its ability to conditions; prevent damaging water hammer during system tiansients. (d) proper operation of turbine and pump in all design operating modes; System operation it considered acceptable wheri the observed / measured performance charac-(e) acceptable pump NPSH under the most teristics, from the testing described abose, limiting design Dow conditions; meet the applicable design specifications (wbMe accounting for the limitations imposed by the (f) proper system flow paths and flow rates :ernporary stearn supply). including pump capacity, discharge head and time to rated flow; 14.2.12.1.10 High Pressure Cor Flooder System Preoperational Test (g) proper manual and automatic system ope. ration and margin to actuation of pro-(1) Purpose tective devices; To verify the operation of the high pressure - 3 (b) proper operation of interlocks and core flooder (HPCF) systern includieg relat. equipment protective devices in turbine, ed auxiliary equipment, pumps, vahes, in-pump, and vahe controls; strumentation and contio!,is as specificd. (i) proper operation of permissive, probi-(2) Prerequisites bit, and bypass functions; The construction tests have been success. (j) proper system operation while powered fully corapleted and tbc SCO bas reviewed tbc from primary and alternate sources,in-test procedure and has approved the initia-ciuding reansfers, and in degraded modes tion of testing. The suppression pool and - odensate storage pooPAe=W be available l for which the system is expected to .{ main operational. Included sheeW ea as HPCF pump suction sources and the reactor demonstration of RCIC system ability to vR6heeW be sufficiently intact to re-l 3 ceive HPCF injection flow. Tbc required start without the aid of AC power, ex-e cept for RCIC DC/AC inverters; an eval E 'gegacing systernW be available, as l untion of RCIC operation beyond its needed, to support the specified testing and design basis during an extended loss of the appropriate system configurations. AC power to it and its support systems and verification of RCIC DC component (3) encralTest Methodt and Acceptance Criteria operability when tbc non RCIC station batteries are disconnected; Performance aboeW be observed and recorded l during a series of individual component and 3 (k) acceptability of pump / turbine vibration integrated system tests to demonstrate the levels and system piping movements dur-following: ing both transient and steady state operation; (a) proper operation of instrumentation and g equipment in all combinations of logic Amendment 2 14214

AB M uxwe Standard Plant uv s (2) Prerequisites dryw ell sumps. g shd \\ System constructiou testing has been Performance themid >e obsersed and recorded ( 3 successfully completed. during a series of indhidual component and integrated system tests to demonstrate the l (3) General Test Methods and Acceptance Criteria following: Since this sptem is the primary communica. (a) proper operation of instrumentation and tion interface bstween the various plant controls in all combinations of logic sptemr, it should be adequately tested dur-and instrument channel trip; ing the preoperational phase testing per-formed on those interconnected systems. (b) proper functioning of indicators, annun-Prosided the construction testing and the ciators, and alarms used to monitor sys-associated system testing has been success-tem op. ration and status; fully completed as it relates to proper ope-ration of the multiplexing sys'.cm no speci-(c) proper operation of leakoff and drainage fic additional testing should be necessary. measurement functions such as those asso-i ciated with the reactor vessel head Ssstem performance would then be considered flange, drywell cooler condensate, and acceptable presided all design specifications are various primary system vahes; m e t. (d) proper response of related sptem val. 14.2.12.1.13 leak Detection and Isolation ses, inclnding timing, under expected Splem Preoperational Test operating conditions; (1) Purpose (c) proper interface with related sptems in regards to the input and output of leak O To serify proper response and operation of detection indications and isolation ini-the leak detection and isolation system (LDS) tiation commands; logic. (f) proper operation of bypass switches and (2) Prerequisites related logic; and The construction tests hase 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 approsed the initiation of cluding transfers, and in degraded modes testing. The required AC and DC electrical for which the system is expected to re-power sources should be operational and the main operational. appropriate interfacing systems shall be available as required to support the . System operation is considered accepiable specified testing. when the observed / measured perfettnance charac- -teristics, from the testing described above, (3) General Test Methods and Acceptance Criteria meet the applicable design specifications. Since the leak detection and isolation system 14.2.12.1.14 Reactor Protection System is comprised mostly of logic, the checks of Preoperational Test valve response and timing and the testing of sensors will be performed as part of, or in (1) Purpose conjunction with, the various systems with which they are associated. These systems in. To verify prope.r operation of the reactor clude RHR, RCIC, RWCU, main steam, feedwat-protection system (RPS) including complete er, recirculation, radiation monitoring, channel logic and response time. ( nuclear bniler< drywell cooling and the %d AmenJm:nt IB 14216 4

AB M uxsm4s Standard Plant nv ( (2) Prerequisites ties, from the testing described abose, meet the (oV) appheable design specifications. The construction tests have been successfully completed and tbc SCG bas reviewed the test Tbc ability of the system to scram the reac. procedures and has appresed the initiation of tot within a specified time must be demonstrated testing. Tbc rod contrcl system, instrument in conjunction with the CRD systern preoperation-air system, and tbc required AC and DC elto al test (Subsection 14.2.12.1.6). trical power sources are operational. All other required interfacing systems shall be 14.2.12.1.15 Neutron Monitoring Gatem available, as needed, to support the Prtoper3tional Test specified testing. (1) Purpose General Test Met.b Acceptance Criteria m shat To verify the proper operation of the neu- { Performance A e obsened and recorded tron monitoring system (NMS) including fixed during a series of dividual component and incore startup and power range detectors, integrated system tests to demcastrate the trasersing incore probes (TIPS) and related following: bardware and software. (a) proper operation of instrumentation and (2) Prerequisites controls in all combinations of logic and instrument channel trip including The construction tests have been success. those associated with all positions of fully completed and the SCG bas resiewed the the reactor mode switch; test procedure and has approved tbc initia-tion of testing. All startup range neutron (b) proper functioning of instrumentation monitor subsystem components and power range and alarms used to enonitor sensor and neutron monitor subsystem compouents base [U} channel operation and availability; been calibrated per vendor instructions. Additionally, all required interfacing sys. (c) proper calibration of primary sensors; tem edd be available, as needed, to sup-(d) proper trip and alarm tettings; operability of bypass switches including \\ ) GeneralTest Methods and Accepta (3 (c) related logic: Performa,nce sbid be observed and recorded l during a series of individual compotent and (f) proper operation of permissive and pro-integrated system tests to demonstrate tbc bibit interlocks; following: (g) proper system operation while powered ta) psoper operation of instrumentation and from primary and alternate sources, in-equipment in all combinations of logic cluding transfers, and in degraded modes and instrument channel trip including for which the system is expected to re-rod block and scram signals feeding the main operational; and rod control system and the reactor trip sptem, r.:speetistly; (b) acceptability of instrument channel re. sponse times, as measured from cach (b) proper functioning of instrumentation, applicable process variable -(except for displays, alarms, and annunciators used neutton sensors) to the de-energiration to monitor system operation and status; of the scram pilot valve solencids. (c) proper operation of detectors and ass-p System operation is considered acceptable when ociated cabling, preamplif,ers, and pow-the observed / measured performance characteris-ce supplies: Amendment 2 1421*

i 23A6100AN Standard Plant poA uv4 (d) proper operation cf TIP drive mechanisms output desices and various system interfaces O and indeaers; A shv+d be connected and available, as needed, for supporting the specified testing (c) proper operation of interlocks and conngurations. equipment protective devices including those associated with Ibc TIP indexers (3) General Test Methods and Acceptance Criteria and drive control units; I Proper performance of system hardware and (f) proper operation of permissive, probi-software will be verified by a series of bit, and b> pan functions; individual and lategral tests that include the following demonstrations: (g) proper system operation while powered from ptimary and alternate sources,in. (a) proper connection and calibration of all cluding transfers, and in degraded modes analog and digital signals; for which the system is capected to re-main operational; (b) proper operation of data logging and plotting features; (b) proper operation of system and subsystem self test diagnostic and calibration (c) verification of computer printouts and functions; CRT displays; (i). the ability to communicate and interface (d) proper communication and interface with with appropriate plant systems and bet. other plant equipment, computers and l ween NMS subsystems; and control systems; (i) the ability to generate core flow biased (e) verification of proper data flow and pro-trip setpoints from core plate differen-cessing and of calculational accuracy; tial pressure measurements. (f) proper operation of calibration and System operation is considered acceptable when surveillance support functions; and the observed /inessured performance characteris-tics, from the testing described abose, meet the (g) proper operation of operator guidance applicabic design specifications, and prompting functions, including alarms 'and status messages, in all 14.2.12.1.16 Process Computer System operating modes for plant startup, shut. Preoperational Test down and power maneuvering iterations. (1) Purpose Much of the testing performed during the pre-operational phase is done utilizing simulated To verify the proper operation of the process conditions and inputs via system hardware and computer system (PCS) including the perfor-software. Final system performance during live mance monitoring and control system (PMCS) conditions will be evaluated during the startup and the power generation control system phase. (PGCS) and their related functions. System operation is considered accepteble (2) Prerequisites when the observed / measured performance charac-teristics, from the testing described above, The construction tests have been successfully meet the applicable design specifications. completed and the SCG has reviewed the test procedure and has approved the initiation of 14.2.12.1.17 Automatic Power Regulator { testing. All prograroming sierht be complete Preoperational Test and initial software diagnostichecks deter. mined acceptable. The requ red input and (1) Purpose SfMll ^ Amendmtra 2 18216 1 a^-W w-' t-w e-. w + r 1-t a w-eo,-w----ea s--w-m.---

---

e w-t--u-&4-e-m - e w '- %-

,s r we -m-s---mm=e+ww--

ABWR

w =

Standard Plant uv n O To serify proper operation of the automatic Verify tbc feasibility and operability of () power regulator ( APR) oser the range of intended remote shutdown functions from the required operating modes. remote shutdown panel and other local and remote locations outside the rnain control (2) Prerequisites room which will be utilized during the rernote shutdown scenario. The software programming and initial diagnos-tic testing has been completed and the SCG (2) Prerequisites has 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 reviewed the information system, recirc flow centrol test procedure and has approsed the initia-splem, turbine control system, and o ther tion of testing. Additionally, control required sptem interfaces shall be availale powe4 she+d be supplied to the remote l Q ]* / 'sbutdown panel and the required system and to support the specified system testing.f component interfaces iball be available, as l (3) GenerelTest Methods and Acceptance Criteria needed, to support the specified testing. The APR is a top level controller that inter. (3) General Test Methods and Acceptance Criteria faces with various lower lesel controllers and systems. APR testing, therefore, should 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 Mi ine'ude the following demon-other local and remote locations intended to strations: be used during the remote shutdown scenario. O (a) proper operation of instrumentation and Much of the specified testing can be accom-controls in all combinations of logic plished in conjunction with, or as part of, for all modes of operation including the individual systern and component preope-transfers; rational testing. Howeverp gccessful y results of such testing Aevtd be documented (b) proper functioning of annunciators, as part of this test, Perfortnance sb.wW c alarms, and displays used to monitor observed and recor ed during a series of system operation or status; individual componen and integrated system tests to demonstrate e followi .p p t.c ate, \\ (c) verification of proper data flow and d processing 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 vahes other control systems and related sup-including establishment of system flow porting and monitoring functions. paths using RSS control; System operation is considered acceptable when (c) proper functioning of RSS transfer the observed performance meets the applicable switches 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; O Amedmem 18 HW

ABWR

== Sandard Plant mn (e) proper sptem operation while powered (c) proper operation of spiem sabes, in. T from primary and alternate electrical cluding timing, under expected operating sources; and conditions; (f) the ability to establish and maintain (d) proper operation of pumps and motors in communication among personnel stationed all design operating modes; throughout the plant who would be per-forming the remote shutdown operation. (e) acceptable pump NPSH under the most limiting design flow conditions; itSS operation is considered acceptable when the obserseJ and measured performance meets the (f) proper splem flow paths and flow rates applicable design specifications, including pump capacity and discharge head; 14.2.12.1.19 Reactor Water Cleanup Sptem Preoperational Tnt (g) proper pump motor start sequence and mar. gin to actuation of protectise devices; (1) Purpose (b) proper operation of interlocks and To serify that the operation of the reactor equipment protectise devices in pump and water cleanup sprem (CUW), including pumps, sahe controls; sabes, and filter /demineraliter equipment, is as specified. (i) proper operation of permissise, probi. bit, and bypass functions; (2) Prerequisites (j) proper sptem operation while powered The construction tests base been successfully from primary and alternate sources,in. completed and the SCG has reviewed the test cluding transfers, and in degraded modes f-) (d procedure and has approved the initiation of for which the system is expected to testing. Filter aid and resin material remain operational; { gu amiki be available. Reactor building cool. ing water, instrument air, CRD purge supply, (k) acceptability of pump / motor sibration and other required interfacing systems shall levels and system piping mosements be asailable, as needed, to support the during both transient end steady state specified testing and the appropriate spiem eperation; and configurations. Special prosisions may be required for testing the CUW system in the (1) proper operation of the reactor water sessel head spray mode, cleanup filter /demineralizers and as-sociated support facilities. (3) GeneralTest MethoSq1e :ceptance Criteria s l Shdl Sptem operation is considered acceptable l Performance hW e o served and recorded when the observed / measured performance characte. 4 during a series of individual component and ristics, from the testing described above, tacet integrated system tests to demonstrate the the applicable design specifications. Proper following: operation of sampling stations and displap will be demonstrated per Subsection 14.2.12,1.22. (a) proper operation of instrumentation and contiois in all combinations of logie 14.2.12.L20 Suppression Pool Cleanup Splem and instrument channel trip including Preoperational Test Gose associated with the leak detection and isolation system; (1) Purpose (b) proper functioning of instrumentation To verify that the operation of the suppres. and alarras used to monitor system sion pool cleanup system (SPCU) is as speci operation and availability; Amenement 18 14200 _,w-, ,,w-.-

ABWR

w ms Sindard Plant ptv y fied in al! required ope rating modes.

bead, O

(2) pterequisites (g) Proper pump motor start sequence and margin to actuation of protective The construction tests base been successful. desices; ly completed and the SCO has resiewed the test procedure and has approsed the initia. (h) proper operation of interlocks and tion of testing. The fuel pool and suppres-equipment protectise devices iri pump and sion pool shall be adequately filled and the valve controls; appropriate filter /demineraliter support f a-cilities and other system interf aces avail-(i) proper operation of per missive. able, as needed, to support the specified prohibit, and bypass functions; testing. (j) proper system opt-ration while presiding (3) GeneralTest Methods and Acceptance Criteria t he spe cified inte rsystem r efill capabilities; and The suppression pool and fuel pool share com-mon water treatment facilities. The sur pres. (k) asceptability of pump /metor vibration 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 sion pool and through the common filter / demi-ope t ation. neraliter, lloweser, the shared filter /dceni-neralizer facilities are considered part of System operation is considered acceptable the fuel pool cooling and cleanup system. when the observed / measured performance Therefore, this preoperational test should be characteristico, from the testing described closely coordinated with that of Subsection above, meet the applicable design specirica. 14.2.12.1.21. tions. k( Performance 4 Af be obsened and recorded 14.2.12.1.21 Fuel Pool Cooling and Cleanup during a series of individual component and Splem Prvoperational Test 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 pur.ips, heat exchangers, controls, valves, and instrumentation, is as (b) proper functioning of instrumentation specified, and alarms used to monitor sys'em operation and availability; (2) Prerequisites (c) proper operation of system valves, in. The construction tests have been ciuding timing, undet 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 splems shall be available, as all design operation modes; needed, to support the specified testing and the approg late systern configurations. (e) acceptable pump NPSil under the most limiting design flow conditions; (3) GeneralTest Methods and Acceptance Criteria i (f) proper system flow paths and flow ratei Performance sked! be observed and recorded including pump capacity and discharge during a series [f individual corr ponent and holl Amendment is 14 M3

ABWR mms SandArd Plant av n integrated sptem tests to demonstrate gaskets or bellows; the followieg: (m) proper functioning of the s) stem in (a) proper operation of instrumentation and conjunction with tbc RHR system in the equipment in all combinations of logic supplemental fuel pool cooling n ode, and and instrument channel trip. including l isolation and b> pass of the nonsafety (a) proper operation of filter /demineralizer related fuel pool cleanup filter / demi-units and their associated support neralizers; f acilitie s. (b) proper functioning of instrumentation Integrated system testing with flow to and and alarrns used to monitor s) stem opera-from the fuel pool cleanup subsystern will be tion and availability, including those performed in cc, junction with the appropriate associated with pool water lescl; portions of the suppression pool cleanup sptem preop described in Subsection 14 1 12.1.20. (c) proper operation of system valves, in-cluding timing, under expected operat. Sptem operatino is considered acceptable ing conditions; when the obsersed/ measured pttformance charac-teristics, f70m the testing described abose. (d, proper operation of purups and motors in meet the applicable desigu specifications, all design operating modes; 14.2.12.1.22 Piarit Process Sampling Splem (c) acceptable pump NPSH under the most Preoperational Test limiting design flow conditions; (1) Purpose (0 proper sptem flow paths and flow rates including pump capacity and discharge To serify the proper operation and the O heaj; accuracy of equipment and techniques to be V used for on line and periodic sampling and (g) proper pump motor start sequence and analpis of oserall reactor water chemistry ruargin to actuation of protective as well as that of indvidual plant process desices; streams, including the post accident sampling system (PASS). (b) proper opt ration of interlocks and equipmcat protective devices in pump. (2) Prerequisites motor, at,d vehe controls; Construction tests have been successfull) (i) proper operation of permissive, probi. completed and the SCG has reviewed the test bii, and bypass functions; procedure and has approsed the initiation of testing. Adequate laboratory facilities and (j) proper systera operation while powered appropriate analytical procedures shall be from primary and alternate sources, including transfers, and in degraded in place, taodes for which the system is expected (3) GeneralTest Methodyal cceptance Criteria to remain operational; ( All Performance simrhi e o served and recorded l g (L) acceptability of pump / motor vibration during a series of tests to demonstrate the I levels and system piping movements dur-followiug: ing both transient and steady state operation; (a) proper operation of on !!ne sampling and monitoring equipment considering cali-(1) proper functioning of pool satisiphon bration, indication and alarm / functions devices and acceptable no:deakage from including reactor water conductisity p) y pool drains, sectionalizing devices, and in st r u tn e n t a tion; ArtMmem 18 1422 l l l

ABMR m-Sandard Plant nx

• cabbration indication, and alarms; eshausts, and plant and process effluents.

s The offgas splem and the main steam lines s (b) the capability of obtaining grab samples are also monitored. of designated process streams at the 56ll drsired locations; Performance obe4J,be obsersed and recorded { during a series of individual component and (c) proper functioning of personnel protec-integrated subsptem tests to demonstrate tise desices at local sampling stations the following: and (a) pror calibration of detector assem-(d) the adequacy and accuracy of sample Hies and associated equiprnent using a anlpis methods. standard radiation source or portable calibration unit; The abose tests should be performed using actual process streams where practicable. Sprem (b) proper functioning of indicators, re-operation is considered acceptable when the ob. corders, annunciators, and alarms; sersed/ measured performance characteristics meet the applicable design specifications. (c) proper system trips in response to high radiation and downscale/inoperatisc 14.2.12.1.23 Process Radiation Stonitoring conditions; Splem Preoperational Test (d) proper operation of permir.sive, prohi-(1) Purpose bit, interlock, and bypass functions; and To serify the ability ci the proce,s radia. tion monitoring sptem (PRh15) to ;ndicate and (c) proper operation of primary and backup C alarm normal and abnormal ra/,sation lesels, sampling functions. ( and to initiate, if appropr'. ate, isolation and/or cleanup spiems upon attection of high System op ration is considered acceptable radiation levels in any of the process when the observed / measured performance charac-streams that are monitored. teristics, from the testing described abose, meet the arplicable design specifications. (2) Prerequisites 14.2.12.1.24 Area Radiation hionitoring Sptem The construction tests base been successfully Preoperational Test completed and the SCG has reviewed the test procedure and has appioved the initiation of (1) Purpose testing. The various process radiation moni. toring subsystems, including picamplifiers, To vesify the ability of the area radiation power supplies, indicator and trip units, and monitosing (ARht) system to indicate and sensors and conserters, base been calibrated alarra normal and abnormal general area according to vendor instructions. The re-radiation levels throughout the plant. quired interfacing systems shall be avail. able, as needed, to support the specified (2) Prerequisites testing. The construction tests have been successful-(3) GeneralTest hfethods and Acceptance Criteria ly completed and the SCO has reviewed the l' test procedure and has approved the initia. The PRhfS consists of a number of subsptems tion of testing. Indicator and trip units, that monitor various liquid and gaseous pro, power supplies, and sensor / converters have cess streams, building and area ventilation been calibrated according to vendor instruc-tions. t Amendment 2 9 24) l

ABWR n-Slandard Plant nrv n (3) GeneralTest hlethods and Acceptance Criteria (a) proper calibration of detector assem-blies and associated equipment using a Perfortnance should be obsersed and recorded standard radiation source or portable during a series of indisidual component and calibration unit; integrated subsystem tests to demonstrate abe following: (b) proper functioning of indicators, recorders, annunciators, and alarms; (a) proper calibration of detector assemb. lies and associated equipment using a (c) proper system trips in response to high standard radistion source or pollable radiation and downscale/inoperatise calibration unit; conditions; (b) proper functioning of indicators, re-(d) proper operation of permissise, prohi-corders, annunciators, and alarms; bit, interlock, and bypass functions; and (c) proper system trips in response to high radiation and downscale/ inoperative (c) proper operation of filtering and conditions; and sampling equipment. (d) proper operation of permissise, prohi. System operation is considered acceptable bit, interlock, and bypass functions, when the obsersed/ measured performance charac-teristics, from the testing described abose. Sptem operation is considered acceptable when meet the applicable design specifications. the obsersed/ measured performance characteris-tics, from the testing described abose, meet the 1,8,2,12,1.26 Containment Atmospheric applicable design specifications. Afonitoring Spiem Preoperational Test V 102.12.1 25 Dust Radiation Stonitoring Sptem (1) Purpose Preoperational Test To verify the ability of the containment (1) Purpose atmospheric monitoring system (CAhtS) to monitoi ox)Eco, hydrogen, and gross gamma To verify the ability of the dust radiation radiation lesels in the wetwell and drywell monitoring sptem to indicate and alarm nor-airspace regions of the primary containment, mal and abnormal airborne radiation levels throughout the plant. (2) Prerequisites (2) Prerequhites The construction tests have been success-fully completed and the SCG has reviewed the The construction tests hase been successful-test procedure and has approved the initia-ly completed and the SCG has 'eviewed the lion of testing, Initial system and compo-test procedure and has apriroved the initia-nent setup has been accomplished per sendor tion of testing. Additionally, indicator and instructions. trip units, power supplies, and sensov/ con-veriers have been calibtated according to (3) GeneralTest hiethods and Acceptance Criteria l sendor instructions, The containment atmosphere monitoring system l (3) GeneralTest hiethods and Acceptance Criteria consists of radiation, oxygen, and hydrogen monitoring subsystems. Performance of each g { Performance vimvfd e observed and recorded of these subsyste AMM be obsersed and I during a series of i al component and record ring a series of indisidual integrated subsptem tests emonstrate the co onent and integrated subsptem tests to (g) following: emonstrate the following: %.J Skdl Amendment 18 14 2 N - _ ~,

ABWR mom Sinubrd Plant ra v o (a) proper calibration of detector assern. (3) GeneralTest Methods and Acceptance Criteria A blies and associated equipment using a standard source or portable calibration The instrument air systeta and the sersice unit; air system are specified as separate sp-tems. Iloweser, since they are so closel) (b) proper functioning of judicators, recor-related the preop lest requirements are ders. annunciators, and alarms including essentially the same. those monitoring sptem asailability; M Performance tmad be observed and recorded 8 (c) proper sptem trips in response to high during a series of indhidusi component and setpoint and dow nscale/ inoperative integrated sptem tests to demonstrate the conditions; following: (d) proper operation of permissive, pro-(a) proper operation of instrutnentation and bibit, interlock, and bypass functions; equiproect in all combinations of logic and instrument channel trip; (e) proper initiation and operation of detec-tion and sampling functions including (b) proper functionirig of instrumentation pump start and sahe sequencing, if ap-r.nd alarms i to rnonitor sptem opera-propriate, in response to a LOCA signal; tion and asa. and (c) pro;<r operat < > of sptem vahes, in. (f) proper operation of calibration gas sup. cluding timing, under etrected operating ply sy st e m s and self calibration conditions; f u n c tio n s. (d) proper operation of c mpressors and Splem operation is considered acceptable when raotors in all design operating modes, the obsersed/rneasured performance characteris-L tics, frorn the testing described abose, meet the (c) ability of compressor (s) to maintain applicabic design specifications. receiver at specified pressure (s) and to recharge within specified time under de-11.2.12.1.27 Instrutnent Air and Station sign loading conditions; Senice Air Sptems PreoperationalTests (f) proper system flow paths and acca, table (1) Purpose flow rates to indhidual loads at spec-ified temperatures and pressures under To serify the ability of the instrument air design loading conditions, including a and service cir systems (IA and SA) to determination that the total air demand proside the design quantities of clean dry at steady state conditions, inhiing compressed air to user systems and leakage for the sptem, is in accordanic components, with design; f 2) Prerequisites (g) proper cornpressor start sequence (including load and unload) and margin The construction tests have been successful-to actuation of protective devices; ly completed and the SCO has reviewed the test procedure and has approved the initia. (b) proper operation of interlocks and tion of testing. Primary and backup clee-equipment protective devices in trical power, the supplied system and compo-comptessor and valve controls; nents loads, and other required system in-terfaces are available, as needed, to support (i) proper operation of permissive, tbc specified testing. prohibit, and bypass functions; Amendmcra 18 N M5

ABWR SlalldEdflMll h (j) proper system operation while powered as needed, to support the specified system ( from primary and alternate sources, testing. ("]f including transfers, and in degraded modes for wbich abe sptem is espected (3) GeneralTes thods and Acceptance Criteria l to remain operational; ceu k Performance be observed and recorded g (k) acceptability of cornprenor/ motor sibra. during a series of indisidual component and tion lesels and sptem piping mosements integrated system tests to demonstrate the during both transient and stead) state following: operation; (a) proper operation of instrumentation and (1) the ability of tbc air to meet end use equipment in all combinations of logic cleanliness requirements with respect to and instrument channel trip; oil, water, and particulate matter con. tent; (b) proper functioning of instrumentation and alarms used to monitor system (m) continued operability of supplied loads operation and availability; in response to credible failures that result in an increase in the supply (c) proper operation of s) stem valses. System pressure; including timing, under expected operating conditions; (n) proper ' failure * (open, close, or as is) of supplied components to both instanta. (d) ability to maintain receiser(s) at spe. neous (pipe break) and slow (plugging or cified pressure (s) under desi n loading F freezinF) simulated air losses (per Reg. conditions; ulatory Guide 1.68JJ; and (c) proper system flow paths and acceptable [' l (o) the ability of the service air sptem to flow rates to individual loads at speci. act as backup to the instrument air sys. fied temperatures and pressures under tem. design loading conditions; Spiem operation is considered acceptable when (f) proper operation of interlocks and the obsened/ measured performance characteris. equipment protective devices; tics, from Ibe testing described abose, meet the applicable design specifications. (g) proper operction of permissive, pro. bibit, and bypass functions; 11.2.12.1.28 liigh Pressure Nitrogen Gas Supply Sptem Preoperational Test (b) proper system operation while powered from primsry and alternate sources, in. (1) Purpme ciuding transfers, and in degraded modes for which the sptem is expected to To serify the ability of the high pressure remain operational, nitrogen gas supply system (HPIN) to furnish compressed nitrogen gas to user systems at (i) acceptability of vibration levels and design quantity and quality, system piping movements during both transient and steady state operation; (2) Prerequisites (j) the ability of the nitregen Eas to meet The construction tests have been successfully cod use cleanliness rs quirements with completed and the SCG has reviewed the test respect to oil, water, and particulate procedure and has approsed the initiation of matter content; and t e stin g. User system loads and other re. p quired sptem interfaces shall be available, V Arbendmcel IR 14226

ABWR Standard Plant nrv n p) when the observed / measured performance character-(c) acceptable pump NPSH under the most istics, from !be testing described abose, meet limiting design flow conditions; t the applicable design specifications. (f) proper splem and component flow paths. 14.2.12.1.29 Reactor Building Cooling Water flow rates, and pressure drops, includ. System Preoperational Test ing pump capacity and discharge head; (1) Purpose (g) proper pump motor start sequence and snar. gin to actuation of protective devices; To verify proper operation of the reactor building cooling water system (RCW) in. (b) proper operation of interlocks and equip-ciuding its ability to supply design quan. ment protectise deuces in pump and tities of cooling water, at the specified vahe controls; temperatures, to essential and nonessential loads, as appropriate, during normal, (i) proper operation of permiHve, pro-abnormal, and accident conditions. bibit, and bypass functions; (2) Prerequisites (j) proper system operation while powered from primary and alternate sources, in-Tbc construction tests base been successfully ciuding transfers, and in degraded anodes completed and the SCG has resiewed the test for which the system is expected to re-procedure and has approved the initiation of main operational. This includes isola. testing. Primary and backup power, reactor tion / shedding of nonessential loads and building service water, instrument air, and divisionalinterties when a LOCA signal other required supporting systems shall be is present; asailable, as needed, for the specified test. 3 ing configurations. The cooled components (k) acceptability of pump / motor vibration [V should be operational and operating to the lesels and system piping mosernents dur. extent possible during heat exchanger oerfor. ing both transient and steady state mance evaluation. operation; (3) GeneralTest Methods and Acceptance Criteria (1) proper operation of system surge tanks e and chemical addition tanks and their l Performance e observed and recorded associated functions; and during a series of i dividual component arid integrated system iests to demonstrate the (m) acceptable performance of heat exchang. following: ers, to the extent practical. (a) proper operation of instrumentation and System operation is considered acceptable equipment in all combinations of logic when the observed / measured performance charac. and instrument channel trip; teristics, from the testing described above, meet the applicable design specifications. Due (b) proper functior.ing 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 availability; balaccing and heat exchanger performance evalua-tion may need to be performed during the startup (c) proper operation of system valves, in. phase. cluding timing, under expected operating conditions; 14.2.12.1.30 Plant Makeup Water System (s) Preoperational Test (d) proper operation of pumps and motors in p all design operating modes; (1) Purpose Amndment 18 14M l .l

ABWR ma.e Mdard Plant nvn 1 To serify the ability of the plant make up Splem operction is considered acceptable if water spiem(s) to resupply the designated the obsersed/ measured performance characterie b plant spterns wish water of the design tics mce: the applicable design specifications. \\ - quantit) and quality for each such system. 11.2.12.1.31 flot Water linting Sptem (2) prerequisites Prroperational Test The construction tests base been success-(1) Purpose fully completed and the SCG has resiewed the test procedure and has approsed he initia. Verify the ability of the hot water heating tion of testing. Final interconnec; ion with system to provide hot water to the appropri. the supplied spterns is complete and those ate HVAC splems in order to maintain the sptems are ready to accept transfer of de-specified design temperatures within the si n quantities of makeup water, various building rooms and areas. F (3) GeneralTest Methods and

1pnce Criteria (2) Prerequisites A ll

[ Sptem performance obsersed and The construction tests base been completed recorded during a series chindisidual com-and the SCG has reviewed the test procedure ponent and it.tegrated splem tests to demon-and has approsed the initiation of testing strate the following: Electrical power, the appropriate heating source (s), the various llVAC sptems heat;ng (a) proper operation of instrumentation and eoils, and ather required inierIacing equipment in all combinations of logic; systems shall be asailable, as needed, to support the specified testing. (b) proper functioning of instrumentation and alarms used to monitor sptem opera. (3) Generaj Test Me j,ytod Acceptance Criteria l p tion and status; s%tl Performance a e obsersed and recorded l (c) proper operation of pumps, rnotors, and during a series of ndividual component c,nd sabes under expected operating condi-integrated spiem tests to demonstrate the tions; followinB: (d) proper functioning of interlocks and (a) proper operation of instrumentation and equipment protectise devices in pump, equipment ir, all combinations of logic motor, and valve controls; and instrument channel trip; (c) the adequacy of system flow paths and (b) proper functioning of instrumentation flow rates including pump and ta9k and alarms used to monitor sptem oper.i-capacities; tion; (f) proper functioning of chemical addition (c) proper operation of system valves under and water treatment facilities and expected operating conditions; equipment; (d) proper operation of pumps and motors in (g) proper functioning of freeze protection all design operating modes; devices, if applicable; and (e) acceptabl: pump NPSH under the most (h) acceptability of pump and motor limiting design flow conditions; vibration levels and system piping movements during both transient and (f) proper system flow paths and flow rates steady state operations. including pump capacity and discharge head; ( Amendenent IB N NS l

ABWR mn. Sandard Plant nvn p (g) proper putop motor start sequence and during a series of indisidual component and Q margin to actuation of protectise de-integrated tastem tests to demonstrate the uces; following: (b) proper operation of interlocks and (a) proper operation of instrumentation and equipment protectise devices in pump, equipment in all combinations of logic mctor and valse controls; and instrument channel trip; (i) roper operation of perrnissive, pro-(b) proper functioning of instrutnentation tubit, and bypass functions; and and alartos used to monitor system operation and availability; (j) acceptability of pump / motor vibration lesels and system piping movements (c) proper operation of system *.alves, during both transient and steady state including isolation functions, under operation, expected operating conditions; System operatwn is considered acceptable when (d) proper operation of pumps and rooto. in the obsersed/ measured performance characteris-all design opetaling modes; tics, from the testing described above, meet the applicable design occifications, it may not be (e) acceptable pump NP5H under tbc most possible to fully evaluate beat exchanger ancI limiting design flow conditions: beating coil performance during the preoperation. al test phase because of process temperature (f) proper system flow paths and flow rates limitations. to all supplied loads including pump capacity and discharge head; 102.12.1.32 HVAC Emergency Chilled Water [] System Prtoperational Test (g) proper pump motor start sequence and U margin to actuation of protectise (1) Purpose devices: To verify the ability of the HVAC emergency (h) proper operation of interlocks and chilled water system (HECW) to supply the de-equipment protective devices in purnp and sign quantitics of chilled water at the spe-salve controls; cified temperatures to the various cooling coils of the HVAC systems serving rooms and (i) proper operation of permissis e, areas containing esse.ial systems and prohibit, and bypass functions; equipment, (j) proper system operation while powered (2) Prerequisites from primary and alternate sources, including transfers, and in degraded The construction tests have been successfully modes foi which the system is expected completed and tbc SCG bas reviewed the test to remain operational; procedure and has approved the initiation of testing, Normal and auxiliary electrical (k) acceptability of pump / motor vibration power, reactor building cooling water, appli-levels and system piping movements cable HVAC system cooling coils, and other during both transient and steady state required system interfaces shall be avail-operation; and able, as needed, to support tbc specified system testing. (1) proper functioning of system surge tank and chemical addition features. l (3) GeneralTest Methods and Acceptance Criteria System operatiou is considered acceptable (q) Performanc thedl be observed and recorded when the obsersed/ measured performance 6 Amendment is 142 29

i ABWR i nwxe Standard.fbnt RFV D characteristics, from the testing described (f) proper system flow paths and flow rates m (V) above, meet the applicable design specifications, to all suppli::d loads including pump capacity and discharge head 14.2,12.1.33 IfVAC Normal Chilled Water System i Preoperational Test (g) proper pump motor start sequence and margin to actuation of protective (1) Purpose devices; To serify the ability of the HVAC normal (b) proper opvation of interlocks and equip-chilled water system (HNCW) to supply the ment pro'ectise devices in pump and des:go quantities of chilled water at the valve con.rols; specified temperatures to the various cooling coils of the HVAC systerns serving rooms and (i) proper operation of permissive, prohi-areas containing nonessential equipment and bit, and bypass functions; systems. (j) proper system operation whik poweted (2) Prerequisites from 7timary and alternate sources, inciuling transfers, and in degraded The construction tests have been success. modes for which the system is expected fully completed and the SCG has resiewed the to remain operational; test procedure and has approsed the initia-tion of testing. Primary and auxiliary (k) acceptability of pump /inotor vibration electrical power, the associated cooling leiels and system piping movements water system (s), Ge awlicable HVAC system during both transient and steady state cooling coils, and oth :r required system operation; and interfaces shall be ava lable, as aceded, to i p support the specified.ystem testing. (1) proper functioning of system surge tank Q and chemical addition features. l (3) GeneralTest Met odyutd Acceptance Criteria Gad System operation is considered acceptable Performance hed e obsersed and recorded when the observed / measured performance charac- } during a series of individual component and teristics, from the testing described above, integrated system tests to demonstrate the meet the applicable design specifications. following: 14.2,12,1.31 Ilesting, Ventilation,aod Air (a) proper operation of instrumenta':on and Conditioning Systems Preoperational Test equipment in all combinations of logic and instrument channel trip; (1) Purpose (b) proper functioning of instrumentation. To verify the ability of the various HVAC and alarms used to monitor system aystems to estab!ish and maintain the speci-operation and availability; fled environment, with regards to tempera-ture, pressure, and airborne particulate l (c) proper operation of system valves, level, in the applicable rooms, areas, and including isolation functions, under buildings throughout the plant, supporting expen ed operating conditions; essential and nonessential equipment and l systems. (d) proper operation of pumps and motors in l all design operating modes; (2) Prerequisites (e) acceptable pump NPSH under the most The construction tests, including inith' limiting design flow conditions; flow balancing, have been successfu4 '(V) Amendmem IS I4 W l

tGWR meixe Standard Plant REV H completed and the SCG has reviewed the test (d) proper operation of fans and motors in ~ -[ sV]' procedure (s) and has approved the initiation all design operating modes; of testing. Additionally, the normal and N Wp ejectrical power sources, the applic-(c) proper system flow paths and flow rates die heating, cooling and chilled water sys-including individual compo:ent and total tems, and any other required system inter-s) stem capacities and overall system faces shall be available, as needed, to flow balancing; support the specified testing. (f) proper operation of interlocks and l (3) General Test Methods and Acceptance Criteria equipment protective devices; There are numerous HVAC systems in the plant, (g) proper operation of permissive, pro-located throughout the various buildings, bibit, and bypass functions; Each system typically ccasists of some combi-nation of supply and exhaust air handling (b) proper system operation while powered units and local coolin6 units, and the asso-frorn primary and alternate sources, ciated fans, dampers, valses, filters, heat-incl'Hing transfers, and in degraded ing and cooling coils, and control and instrte mm6 which the system is expected f-e mentation. The HVAC systems to be tested P tm ' operational; l she +kedd include the following: those sup ort-ing the reactor building rooms containing su-(i) the ability to maintain the specified 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 ciectrical equipment rooms of the control local and total ai ' low, including any building; those supporting the divisional potential leaka., relative to the cooling water rooms; those supporting the anticipated contamination levels; o 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 maintain building and turbine building; and the the specified dust and contamination dedicated systems of the drywell and the main free environment (s); control room (includita ibe control room habitability function). (k) the ability of the control room habitability function to detect the Since the sarious HVAC systems are similar in presence of smoke and/cr toxic gas and -design of equipment and function, they are to remove or prevent in-leakage of such; subject to the same basic testing require-ments. (1) proper operation of MEPA filters and M charcoal adsorber sections, if { Performance Aedd be observed and recorded applicable, includin;; relative to the g during a series of individual component and in place testing tequirements of integrated system tests to demonstrate the Regulatory Guide 1.140 regarding visual following: inspections and airflow distribution, DCP penetration and bypass leakage (a) proper operation of instrumentatior and testing; equipment in all combinations of logic and instrument channel trip; (m)the ability of the heating and cooling l coils to maintain the specified thermal (b) proper functioning of instrumentation environment (s) while considering the and alarms used to monitor system heat loads present during the preop test operation and availability; phase; and im' (c) proper operation of system valves and (n) the ability of primary and secondary l lV; dampers, including isolation functions, containment HVAC systems to provide under expected operating conditions, j l Amndm<nt 11 112 31

ABWR 23A6190AN Standard fjant pra To serify the ability of the atmospheric g} control system (ACS) to establish and (k maintain the specified inert atmosphere in the primary containment during all expected plant conditions. System operation is considered acceptable when the observed / measured performance charac-(2) Prerequisites dIt teristics, from the testing described above, meet the applicable design specifications. The construction t is have been successfully cornpleted and tpe SCG has resiewed the test IG.12.1.36 Standby Gas Treatment System procedure and as approved the initiation of Preoperational Test testing. "I primary and secondary l containments dd h intact, their HVAC (1) Purpose systems operational, and all other required interfaces asailable, as needed, to support To verify the ability of the standby gas the specified testing. treatment system (SGTS) to establish and maintain a negative p. essure within the (3) GeneralT:st Metho Acceptance Criteria secor. dry containment and to adequately s I filter the resultant exhaust air flow. j Performance e o sened and recorded during a series of individual cotoponent and (2) h. requisites integrated system tests to demonstrate the fc!!owing: The construction tests base been success-fully completed and the SCG has reviewed the (a) proper operation of instrumentation and test procedure and has approved the initia-equipment in all combinatior.s of logic; tion of testing. The primary and secondary Q containments are intact and the appropriate Q (b) proper functioning of instrumentation interfacing systeu..s are available as re-and alarms used to monitor system quired to suppcrt the specified testing. operation and availability; (3) GeneralTest Metho Acceptance Criteria j (c) proper operation of system valves, in- $hd e served and recorded l cluding timing, under expected operating Performance. - g conditions; during a series of individual component and integrated system tests to demonstrate the (d) proper nitrogen / air flow paths and flow following: rates both into and out of the primary containment; (a) proper operation of instrumentation and equipment in all combinations of loS c i (e) proper operation of interlocks and equip. and instrument channc! trip; ment protective devices; (b) proper functioning of instrumentation (f) proper operation of permissive, prohl-and alarms used to monitor system bit, and bypass functions; and operation and availability; (g) proper system operation while powered (c) proper operation of system valves and from primary and altercate sources, dampers, including timing, under including transfers, and in degraded expected operating conditions:- modes for which the system is expected to remain operational. (d) proper operation of exhaust fans in all design operating modes; [.m (c) efficiency of IIEPA filters and leak AmeMment 18 14232

ABWR mm S.tandard Plant par n e tightness of charcoal adsorber section 14.2.12.1.40.1 Containment latrgrated Leakage l ( per Regulatory Guide 1.5: Rate Test (O proper system and compone t flow paths Description of and criteria for conisioment and flow rates including overall system integrated leakage rate tests are given in Sub-flow balance; section 6.2.6.1. (g) ability to maintain the specified oega. 14.2.12.1.40.2 Containment Structural tive pressure in the secondary lategrity Test containment; Description of and criteria for the required (b) proper operation of interlocks and containtoent structural integrity test is given equipment protective desices; in Subsection 3.8.1.7.1. (i) proper operation of permissiye, 14.2.12.1.41 Pressure Suppression Containment prohibit, and bypass functions; B,spass teakage Tests (j) proper operation of heaters, demister, Test procedures are 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 system operation while powered f rom primary and alternate sources, 14.2.12.1.42 Containment lsolation Vabe including transfers, and in degraded Functional and Closure Timing Tests modes for which the system is expected to remain operational. Preoperational functional and closure timing tests of containment isolation valves is dis. O Refer also to Subsection 6.5.1.4.1. cussed in Subsection 6.2.4. Q System operation is considered acceptable when 14.2.12.1.43 Wetwell to-Dr)wil Vacuum Breaker the observed / measured performance characteris-System Preoperational Test tics, from the testing described abose, meet the applicable design specificatioas. (1) Purpose 14.2.12.137 Containment iso:stion Yahe To verify proper functioning of the wetwell-Leakage Rate Tests to-drywell vacuum breakers. Description of and criteria for preopera. (2) Prerequisites tional leakage 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 14.2.12.1.38 Containment Penetration Leakage test procedure and has approved the initia-Rate Tests tion of testing. Description of and criteria for preoperationa: (3) GeneralTest Methods Acceptance Criteria !cakage rate tests of containment penetrations sko.t are gisen in Subsection 6.2.6.2. Performance sketridge served and recorded l during a series of individual component and 14.2.12.139 Containment Airlock Leakags Rate inte; rated system tests to demonstrate the Tests following: Description of and criteria for preoperational (a) proper operation of vacuum breaker p leakage rate tests of containment airlocks are valves and system logic including h given in Subsection 6.2.6.2. verification of opening and closing setpoints and tmang; Amendment 18 142 33

ABWR mom Sandard Plant Rrv n power conditions duting a series of individual component and Q integsated system tests to demonstrate ibe (c) proper functioning of salve positive following: closure devices including verification cf adequate valve leak tightness; and (a) proper tracking of drywell pressure by all instrument channels during contain-(d) proper functioning of vacuum breaker ment integrated leak rate testing; lest features. (b) proper response of all suppression pool System operation is considered acceptable when lesel instrumentation during actual the obsersed/ measured performance characteristics changes in pool level; meet the applicable design specifications. (c) proper tracking by all suppression pool 142.12.144 Primary Containment Monitoring temperature instrument channe.!s of an Instrumentation Preoperational Test actual change in pool temperature; (1) Purpose (d) proper functioning of associated indica. tors, recorders, annunciators, and To serify the proper operation of instru-alarms including those monitoring mentation used for long term monitoring of instrumentation 1,tatus; and the drywril and wetwell atmospheres and suppression pool temperature and lesel during (c) proper system trips in response to the both normal operations and accident appropriate high and/or low setpoin's conditions in the primary containment. and inoperatise conditions. (2) Prerequisites System operation is considered acceptable (g) when the c,bserved/ measured performance character-u The construction tests have been success-istics, from the testing described abose, meet fully completed and the SCG has reviewed the the applicable design specifications. test procedure and has approved the initit. tion of testing. The suppression pool shall 142.12.1.40 Electrical Systems Preoperational be filled and expected to undergo measurable Test !csel 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 conjunction with (1) unit auxillary AC power system; the testing of this subsection is appropri-(2) unit Class 1E AC power system; ately scheduled. (3) safety system logic and control system power system; l (3) GeneralTest Methods and Acceptance Criteria (4) instrument power system; (5) uninterruptible power system; A description of the instrumentation requir. (6) unit auxillary DC power system; and ed for containment monitoring is presented in (7). tait class IE DC power system. Subsection 6.2.1.7. 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 able systems. Oni; that instrumentation systems, and their respective components, can be requiring special condderations is discus-divided into tbc four general categories as sed below. described below. The specific testing required /7 for each system is described in tbc applicable C,f Performance Amid be observed and recorded design and testing specifications. $b4 Amendmnt I$ I4M

ABWR ururo Standard Plant PIV n Q(j 14.2.12.1.45.1 DC Power Supply System trical independence for its particular Preoperational Test application; (1) Purpose (c) proper functioning of transfer devices, breakers, cables and inverters (includ. To serify the ability of DC power supply ing load capability); systems to supply highly reliable, uninter-ruptable power for instrumentation, logic, (f) proper calibration and trip settings of control, lighting and other normal and protective desices, including relaying, einergency loads that t'aust remain operational and proper operation of permissise and during and after a loss of AC power. prohibit interlocks; (2) Prerequisitu (g) proper operation of instrumentation and alarms associated with under voltage, The construction tests base been success. oser Soltage, and ground conditions; and fully completed and the SCG has reviewed the test procedures and has approved the initia-(h) proper operation of emergency DC tion of testing. All interfacing systems i nd lighting, including capacity of self equipment required to suppc,rt syst :m contained batteries, operation shall be asailable, as needer', for the specified testing configurations. 14.2.12.1.45.2 Emergency AC Power Distribution System Preoperational Test l (3) General Test Methods and Acceptance Criteria (1) Purpose The DC power supply systems consist of es-sential and nonessential equipment, includ. To verify the ability of the Class IE AC / T-ing batteries, battery chargers, inserters, power distribution system to provide both V static transfer switches, and associated manual and fully automatic means for supply-instrumentation and alarms, that is used to ing and regulating AC power to safety equip-khat normal and emergency loads, ment, from both offsite and onsite sources, h ,_ _saft 5W [ Performance 4.eed be observed and recorded via independent distribution subsystems for during a series of individual component and each redundant Class 1E load group. integrated systems tests to demonstrate the following: (2) Prerequisites (a) capability of each battery bank to The construction tests have been success-supply its design load for the specified fully completed and the SCG has reviewed the time withou: the voltage dropping below test procedure and hav yproved the initia-minimum u.ttery or cell limits; tion of testing. All interfacing systems and equipment required to support system (b) capability of each battery charger to operation shall be available, as needed, for fully recharge its associated battery the specified testing configurations. (or bank), from the discharged state, within the specified time while (3) Genera! Test Methods a.nd Acceptance Criteria simultaneously supplyir g the specified loads; The Class 1E AC power distribution system is comprised of the equipment requirad for (c) verification that actual loading of each transformation, conversion, and regulation DC bus is consistent with battery sizing of voltage to the essential busses, the assumptions; switchgear and motor control required for the individual loads served, and the coordi-n (d) verification that each DC bus meetc. the nated system protective relaying. Perfor- ) specified lesel of redundancy and elec-mance Aceld be observed and recorded during S hall Amendment 18 1G15

ABWR u-m Standard Plant uv a a series of individual component and diesel fuel oil transfer, diesel generator te integrated system tests to demonstrate the start ng air supply, jacket water, and lube following: oil. (a) proper operation of initiating, trans-(2) Preuquisites fer, and trip devices; The construction tests have been successful-(b) proper operation of relaying and logic, ly completed and the SCG has reviewed the including load shedding features; test procedure and has approved time initia tion of testing. All interfacing systems (c) proper operation of equipment protective and equipment required to support system op-devices, including permissive and prohi-eration shall be available, as needed, for bit interlocks; the specified testing configuration. Addi-tionaly, sufficient diesel fuel should be (d) proper operation of instrumentation and available on site to perform the scheduled alarms used to monitor system and equip-

tests, ment status (including availability);

(3) GeneralTest Meth ad Acceptance Criteria l (c) proper operation and load carrying skll capability of breakers, motor controll-Performancep e observed and recorded ers, switchgear, transformers, and during a series of individual component and cables; integrated system tests to demonstrate the following: (f) that a sufficient level of redundancy and c!ectrical independence exists as (a) pwper automatic startup and operation specificci for each application; of the diesel generators upon simulated loss of a-c voltage and attainment of \\ _ (c) 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) proper response and operation for de. (h) the ability of emergency and vital loads sign-basis accident loading sequence to to start in the proper sequence and to design basis load requirements, and operate properly under simulated verification that voltage and frequency accident conditions, while powered from are maintained within specified limits; cither preferred or standby sources, and over the specified range of available (c) proper operation of the diesel genera-bus voltage, and tors during, load shedding load sequenc-ing, and load rejection, including a (i) the adequacy of the plant emergency and test of the loss of the largest single essential lighting systems. load and of the complete loss of load, verifying that voltage and frequency at: 14.2.12.1.452 Emergency Diesel Generator maintained within design limits and that Preoperational Test overspeed limits are not exceeded; (1) Purpose (d) that a LOCA signal will block generator breaker or field tripping by all protec-To demonstrate the capability of the emer-tive relays except for the generator gency diesel generators tc provide nighly re-phase differential current and engine liable emergency electrical power during nor-overspeed relays; mal and simulated accident conditions when normal offsite power sources are unavailable, (c) that a LOCA signal will initiate termin-(_, and to demonstrate the operability of the ation of parallel operations (test or dasel generator auxiliary systems, e.g., manual transfer) and that the diesel A nendrtent 18 HM

ABWR UA61'#AN Standard Plant mn generator will continue to run unloaded (m) proper operation and correct setpoints (fs) and available; for initiating and trip devices and V verification of system logie not tested (f) that the engine speed governor and the otherwise; and generator voltage regulator ault,matj-cally return to an isochronous (constant (a) proper operation of auxiliary systems speed) mode of operation upon initiation such as those used for starting, cool-of a LOCA signal; ing, beating, ventilating, lubricating, and fueling the diesel generators. (g) full-load carrying capability of the diesel generators for a period of not 14.2.12.1,45.4 Nortnal AC Power Distribuilon less than 24 hours, of which 22 hours Systern Preoperational Test are at a load equivalent to the con-tinuous rating of the diesel generator (1) Purpose and 2 hours are at the 2 hour load rating as described in Reg Guide 1.108 To verify the ability of the normal AC power including verification that the diesel distribution ;ystem to provide a means for cooling systems function within design supplying AC power to nonessential equip-limits, and the diesel generator HVAC ment, from both onsite sud offsite sources, system maintains the diesel generator via the appropriate distr;bution network (s). room within design limits; (2) Prerequisites (b) functional capability at operating temperature conditions bv reperforming The construction tests have been success-tne tests in (a) and (b) above immedi-fully completed and the SCG has reviewed the ately after completion of the 24 hour test procedure and has approved the initia-load test per (g) above; tion of testing. All interfacing systems C. and equipment required to support system (i) the ability to synchronite the diesel operation shall be available, as needed, for generef ors with offsite power while con-the specified testing cc,nfigurations. nected to the emergency load, transfer the load from the diesel generators to (3) GeneralTest Methods and Acceptance Criteria the offsite power, isolate the diesel generators, and restore them to standby The normal AC power distribution system is status; comprised of the equipment used for trans-formation, conversion, regulation, and (j) that the rate of fuel consumption and distribution ol' voltage to plant nonessen. the operation of any fuel oil supply tial equipment during normal operation, pumping or transfer devices, while Performancedev4be observed and recorded operating at the design basis accident during a series of individual component and load, are such that the requirements for integrated system ests to demonstrate the 7 day storage inventory are met for each following: g diesel generator; (a) proper operation of initiating, trans-(k) that all permissive and prohibit fer, and trip devices; interlocks, controls, and alarms (both local and remote) operate in accordance (b) proper operation of relaying and logic, with design specifications; including load shedding features; (1) acceptable diesel generator reliability (c) proper operation of equipment protective during starting and loading sequences as devices, including permissive and prchi-described in Reg. Guide 1.108; bit interlocks; Amendment 18 y.37

AMVR u^mw, j Standard Plant Prv y (d) proper operation of instrumentation and groups, two at a time (A and B, B and C, A O alarms used to monitor systern and equip-and C), with the other divisionalload group V ment status; completely isolated from both onsite ar,d offsite power sources (including DC sour-(c) proper operation and load carrying cap-ces), simulate a divisional bus under vol. ability of bre,skers, motor controllers, tage condition (LOP) iollowed immediately by switchgear, transformers, and cables; a LOCA signal and verify the following-(f) sufficient lesel of redundancy and elec-(a) that the appropriate divisional diesel trical independence as specified for generators automatically start, reach each application; and rated speed and voltage, and connect to their respective divisional buses (g) the capability to transfer between on. according to design and within the site and offsite power sources as per specified time; design. (b) that all relaying and interlocks related Performance of each of the sarious plant elec-to the LOP /LOCA condition operate pro-trical systems is considered acceptable when perly including the specified shedding the testing described abose demonstrates that and sequencing of sources and loads; the requirements of the applicable design and testit.g spe.cNications have been met. (c) that all divisional leads operate as de-signed in response to the LOP /LCCA con-1 L2.12.1.46 Integrated ECCS Loss of OITsite dition, including establishment of th: Power (LOP)/LOCA Preoperational Test appropriate divisional ECCS flow to the sessel within the specified time; and (1) Purpose (d) that all loads and electrical busses (p To verify the proper integrated ECCS and associated with the isolated divisional ) plant cit.ctrical syrtem response to a simu-load group remain deenergized lated LOP /LOCA condition and to scrify the M I independence of the redundant onsite divi. The test of each cenbination A-sufficient duration to allow establishme sional power sources and their associated ment 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. g trical system, including diesel generators, s and the ECCS and related auxiliary systems, After the proper response of eac ivisional base been successfully completed. The reac-combinatioe has ocen separate demonstrated tor vessel shall be ready to accept design the integrated response f/all ECCS and ECCS injection flow, all ECCS pumps shall electrical divisions 4mrhi e demonstrated l hase an adequate suction source, the diesel by simulating a complete loss of offsite generators should have sufficient tuel avail-power and LOCA condition and then serifymg able, and essential DC power shall be avail. items (a) through (d) above for all three able. All other required systems shall also diesel generators and load groups as they be available, as needed, to support the respond and operate simultaneously, specified integrat-d testing. Performance is acceptable when the abose { (3) GeneralTest Methods and Acceptance Criteria testing demonstrates that the applicable design specifications have been met. For each combination of divisional load 4 V Amendment 18 14 2G

ABWR m-s Standard Plant prv n 14.2.12.1.47 Plant Communications Sptem (f) audibility of speakers and receivers (' Preoperational Test under anticipated background uise levela; (1) Purpose (g) the ability to establish the required To verify the proper operation and adequacy communications with outside agencies; of all plant communications systems and and methods that will be used during normal and abnormal operations including those needed to (h) proper functioning of dedicated use carry out the plant emergency plan. systems and of those systems expected to function under abnormal cot ditions such (2) herequisites as loss of electrical power or shutdown from outside the control room scenarios. The construction tests have been success-fully completed and the SCG has reviewed the System operation is considered acceptable test procedure and has approsed the initia-when the observed /measuied performance tion of testing. Initial system and compo-characteristics meet the applicable design nent settings (gains, volumes, etc.) should specifications. be adjusted cased on expectations of the acoustic environment and background noise 14.2.12.1.48 Fire Protection System lesels for each location and for all modes of Preoperational Test operation. (1) Purpose (3) GeneralTest Methods and Acceptance Criteria To verify the ability of the fire protection The communications systerns to be tested system to detect and alarm the presence of G include the plant PA system, all hardwired combustion, smoke or fire within the plant 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 links to outside agencies, and the plant (2) Prerequisites l emergency alarms Performance Ar&d be obsersed and recorded during a seri of The construction tests have been successful-individual component and integrated sy em ly completed and the SCG has reviewed the tests to demonstrate the following: gg test procedure and has approved the initi-ation of testing. The required electrical (a) proper functioning of all transmitters power and make up water sources, and other and receivers without excessive inter-appropriate interfaces and support systems, ference levels; are available as needed for the specified testing. (b) proper operation of all controls, swit-ches, and interfaces including silencing (3) General Test Methods and Acceptance Criteria l and muting features; The fire protection system is but one part (c) proper isolation and independence of of the overall fire protection program. various channels and systems; This program is the integrated effort involving components, procedures, and (d) proper operation of systems under multi-personnel utilized in carrying out all ple user and fully loaded conditions as activities of fire protection, in accordance per design; with Criterion 3 of 10CFR50, Appendix A. It includes systems and components, facility ,(d ) (e) proper operation of plant emergency design, fire prevention, detection, annun-alerms; ciation, confinement, suppression, adminis-AmeMment Is 14 2 M

ABM uww Standard Plant nrv n (3 tratise controls, fire brigade organization, (g) proper functioning of smoke, beat and V training, quality assurance, inspection, test-flame detection devices; ing, and maintenance. The fire protection program begins with the initial design of all (b) proper operation of both local and plant systems and equipment and of the build-remote alarms including those interfac-ings and structures in which they are locat. ing with outside agencier,; and ed. A detailed analysis is then performed on this design to ident:fy, qualify, and quanti-(i) proper operation of primary and second-fy all potential fire barards, and 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 barriers and passive devi-when the observed and measured performance ces, do not complete;y fulfill the require-characteristics, from the testing described ments of the fire protection program. above, meet the applicable design specifi-cations. The majority of the effort involved in de-monstrating that the requirements of the 14112,1A9 Radioacthe Liquid Drainage and overall fire protection program ?re met will Transfer Systems Preoperational Tests be through analysis and documer.tation. 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 operation of the tion, annunciation, and suppression of vuious equipment and pathways which make up fir e s. T his t e s t i n g the atd in clu d e t h e the radioactive liquid drainage and transfer foliowing demonstrations: system within the Nuclear bland. y (a) proper operation of instrumentation and (2) Prerequisites equipment in all combinations of logic and control; The construction tests base been successful-ly completed and the SCG has reviewed the (b) proner functioning of prohibit and per-test procedure (s) and has approsed 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, ano motors under expected ope-needed, to support the specified testing. rating conditions; (3) GeneralTest Methods and Acceptance Criteria l (d) proper system and component flow paths, - The testing described below consists of that ' low rates and capacities; of the equipment and pathways for the (c) proper operation of water based suppres-drainage and transfer of radioactive and sioa systems such as spray, sprinkler, potentially radioactive liquids within the deluge, and hose devices and of "her plant. Also included are dedicated systems suppression systems such as those utili-for the handling of liquids that require zing halon, carbon dioxide, foams and special eolle etion and disposal dry chemicals, including both manually considerations such as detergents. and automatically actuated systems; Performance should be observed and recorded p (f) proper operation of freeze protection during a series of individual component and () devices, if applicable; integrated system tests to demonstrate the Amendment 18 1410

ABWR 23Acl00AN Standard Plant Rrv s O(O following: fuel, vessel internals, and reactor compo. nents during the refueling and servicing (a) proper operation of equipment controls operations. and logic including prohibit and permissive interlocks; (2) Prerequisites (b) proper operation of equipment protectise The construction tests hase been successful-features and automatic isolation ly completed and the SCG has reviewed the functions; test procedure and has approved the initia-tion of testing. The required electrical (c) proper functioning of instrumentation power sources and sufficient lighting shall and alarms used to monitor system be available under vessel, in the drywell, operation and status; and on the refueling floor. The refueling floor (including the upper pools and reactor (d) acceptable system and component flow cavity) and drywell and ander vessel areas paths and flow rates including pump shall b>. capable d supporting load and tra-capacities and sump or tank volumes; vel testing of the various cranes, bridges, and hoists. Other interfacing systems shalt (e) proper operation of system pumps, be available as required to support the valves, and motors under expected specified testing. operating conditions; (3) GeneralTest Methods and Acceptance Criteria (f) proper functioning of drains and sumps including those dedicated for handling Fuel bandling and reactor component servic-of specific agents such as detergents; ing equipment testing described herein in-r and cludes that of the reactor buisding craec, ( w) refueling biidge, auxiliary platform, and I (g) proper calibration and operation of the associated hoists and grapples, as well radiation detectors and monitors. as cther lifting and rigging devices. Also included are specialized hand tools and System operation is considered acceptable when viewing aids. Fuel pool cooling ar.d cleanup the observed and measured performance characteris-functions are tested as described in Subsec-ties, from the testing described above, meet the tion 14.2.12.1.21. The HVAC systems serving applicable design specifications. the refueling floor and drywell are t:sted as described in etion 14.2.12.1.34 112.12.1.50 Fueldiandling and Reactor Aall Component Senicing Equipme'it Preoperational Performance ebeddpe observed and recorded l Test during a stries of individual component and integrated systere tests to demonstrate the (1) Purpose following: To verify proper operation of the fuel (a) proper operation for each crane, bridge, handling and reactor component sersicing trolley, or platform through its full equipment. This includes cranes, hoists, travel and at up to its maximum speed grapples, trolleys, platforms, hand tools, including verification of braking action I viewing aids, and other equipment used to and overspee 3 or overtravel protection lift, transport, or otherwise raanipulate devices; fuci, control rods, neutron instrumentation, I and other in vessel, under-vessel, and dry-(b) proper operation of the various cabks, l well components. Also included is equipment grapples, and boists including brakes, l needed to lih and relocate structures and limit switches, load cells, and other (G) components necessary to provide access to equipment protective devices; l Amend.aent 19 14 2'il

AMVR mm Standard Plant PFV D (V) 14.2.12.1.52 Reactor Vessel Flow luduced program. Vibration Preoperational Test (3) General Test Methods and Acceptance Critena l (1) Purpose The reactor internals vibration assessment To collect information needed to serify the prograrn consists of three parts: e vibra-adequacy of the reactor internals design, tion analysis program, a vibration measure-manufacture, and assembly with respect to the ment program, and an inspection program. potential effects of fiow induced vibration. The vibration analysis portion is performed instrumentation of major compone.its and the on the final dr. sign, prior to the preopera-flow tests and inspections will provide assur-tional test, and the results are used to ance that excessive vibration amplitudes. if dev: lop the measurement and inspection they exist, will be detected at the earliest portions of the program. The preoperational possible time. The data collected will also test therefore consists of an instrumented help establish the margin to safety associa-flow test and pre-and post-test inspections ted with steady state and anticipated tran-as described in the following paragraphs: sient conditions and will help confirm the pretest analytical vibration calcul" ions. (a) Pre-flew Vesselinspection This testing will fulfill the pe roperational requirements of Regulatory Guide 1.20 for a The preflow inspection is performed pri-vibration measurement and inspection program marily to establish and document the for prototype reactor internals. status of versel internal structures and components. Some of the inspection re-(2) Prerequisites GN quirerr.ents may be met by normal visual \\ fabrication inspections. The majority The initial rstion ana', sis com utations of the inspection requirements will be and srpfication of acceptancepriteria met by visual and remote observations of iA w+d be complete. Thes: results shatrhi be the installed reactor internals in a utilized to define final ins ection and mea-flushed and drained vessel. The fol-g surement programs. Preop ational testing of lowing types of structures and compo-the recirculation system be suffi-nent.< Aw+d be included in the sessel l ciently complete to ensure safe operation of nals inspection program; the reactor internal pumps at rated volumet. <fd ric flow for tbc duration of the schedulet (1) m ajor loa d be a ring ele m e nt s flow testing. This includes all required aux-including lateral, vertical and tor-iliary systems. All reactor vessel compo-sional supports; { nents and structure *be*J be installed and esigned in expectation of being (2) locking and bolting componen:s whose secur- ,a jected to rated volumetric core flow. failure could adscrsely affect / This includes the steam separator assembly structural integrity; y and reactor vess I head but excludes the steam dryer. Also, during the flow testing, (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 vesselinternals the vibration analysis program; and l hwM be choreographed such that struct' ares and compoaents requiring inspection are ac-(5) interior surfaces for evidence of cessible at the proper times. The required loose p..n 'r foreign material. sensors shall be installed and calibrated prior to the flow testing. All other sys-(b) Flow testing tems, components, and structures shall be available. as required, to support the reac-The preoperational flow test wi!! be (u; tor vessel internals vibration assessment performed at rated volemetric core flow Amendment 18 14 M

ABWR u-Standard Plant nrv n Q() with the vessel internals completely in. considered acceptable when results of tact with the exception of the fuel bun-the measurement program correlate and dies, tbc control blades (unless fully compare fawrably with those of the ana, withdrawn), and tbc steam dryer assem-lysis progrtm, and, when the results of bly. A post fuel load, suberitical flow the inspections show no signs of de-test will be performed later on the com-Iccts, loose parts, extraneous material, plete reactor assembly unless it is or excessive wear due to flow testing, shown analytically or expetirr.utally and are consistent with the results ob-that tbe preoperadonal results are tained from the analysis and measurement already conservstively bounding. Addi-programs. tionally internals vibration will be measured during individual compci.cnt or 14.2.12.1.53 Condensate and Feedwater Systears system preoperational testing where Preoperational Test operation my result in significant vibrational excitation of reactor (1) Purpose internals, ach as HPCF testing. To verify proper operation of the The duration of preoperational testing various components that comprise the at the various f;ow configurations condensate and feedwate systuos and g4 dedd ensure that each critical com-their capability to deliver the required ponent is subjected to at least 106 flow from the condenser hotwell to the cycles of vibration, as calculated using nuclear boiler system, the lowest frequency for which the com-ponent is expected to experience a sign-(2) Prerequisites ificant structurai response. The construction tests have been h (c) Post Flow Vessel Inspection successfully completed acd the SCG has V reviewed the test procedure (r) and has The post flow inspection shall be per-approved the initiation of testing. The formed after the resultant vibrational required interfacing systems shall be excitation from the preoperational flow available as needed, to support the testing described above. The structures specified testing. For all flow testing and components inspected shall be the their shall be an adequate saction same as specified for the preflow in-source available and an appropriate flow spection. Visual and remote observa-path established. tions are performed after the sessel has been depressurind and drained. Inspec-(3) GeneralTest Methods and Acceptance l tion of critical surfaces and components Criteria { g,_+ hrtd be performed prior to any disas-sembly required for access to other Preoperational testing of tbc condensate internal structures. and feedwater systems will include the piping, components, and instrumertation (d) Acceptance Criteria between the condenser and tbc nuclear boiler but not the condensate filters or The acceptance criteria are generated as demineralizers nor the feedwater part of the analytical portion of the heaters, which will be tested separately program in terrns of maximum vibrational per the specific discussions provided response levels of overall structures far those features. SM and components and translated to speci. l fic sensor locations. Performance Add be observed and g recorded during a series of individual .. p Reactor vessel internals vibration is component and integrated system tests to V demonstrate the following: Amendment 18 p M4

ABWR = Standard Plant (a) proper operation of instrumentation and 14.2.12.1.54 Condensate Cleanup System equipment in au combinations of logic and Preoperational Test y instrumect channel trip; (1) Purpose (b) proper functioning of u..irumentation and alarms used to monitor system operation To verify proper operation of the condensate and availability; filters and demineralizers and the associated support facilities. (c) proper operation of sistem sabes, including timing, under expected operating (2) Prerequisites conditions; The construction tests have been successfully (d) pcoper operation of pumps and motors in completed and the SCG has resiewed the test G all design ope.attng modes; procedure atd has approved the initiation of shad testing. The condensate system Mtc l (e) accep*able pump NPSH under the most operational with an established flow path limiting design flow cond? ions; capable of supporting full condensate Qter and demineralizer now. Adequate supplies of ion (f) proper system flow paths and flow rates exchange resin should be asaileble and the including pump capacity and discharge radwaste system rimM be capable of l

head, processing the expected quarfties of water and spent resins. Other requir d interfacing (g) proper pump motor start sequence and

ystems should also be availabl. as needed, to margin to actuaton of protectise devices; support the specined testicg.

sWi l (h) proper operatioe of interlocks and (3) General Test Methods an ccep ance riteria l equipment protectne devices in pump, L motor, and vahe contrals; Performance be obsersed and reco ded { 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 of instrumentation and from primary and alternate sources, equipment in all combinaticas of logic and including transfers, and in degraded modes instrument channel trip; 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 status; levels and system piping movements during both transient and steady state operation; (c) proper operation of system valves, and including timing, under expected operating conditions; (1) proper operation of contr "ers for pump drivers and flow control v,es including (d) proper indhidual vessel and overall system those in minimum flow recirculation lines. now iates and pressure drops including bypass capabilities (for both filter and System operation is considered acceptable when demineralizer units); the obsersed/ measured performance characteristics, from the testing described above, meet the (c) proper operation of interlocks and applicable design specincations. equipment protective device 5; A ArneMment 18 14 M l

J ' ABWR um was Standard Plant-m m - ed '(f) ' proper operation of permissise, prohibit, Performa e. be obsersed and recorded l, .N and bypass functions; during a series ofindividual component and integrated system tests (to the extent possible) (g) the ability to perform on.iine exchange cf to demonstrate the following: standby and spent-filter units and demineralizer vessels; and (a) proper operation ofinstrumentation and equipment in all combinations of logic and (b)l proper opcration of filter and instrument channel trip; dernincializer support facilities such as those used for recencration of resins or for (b) proper functioning ofinstrumentation and - handling of wastes, alarms used to monitor system operation and availability; System operation is considered acceptable when ~ he observed / measured performance characteristics (c) proper operation of system valves. t - meet the applicable design specifications. including timing and sequencing, under expected operating conditions, 14.2.12.1.55 Reactor Water Chemistry. Control Systems Preoperational Test (d) proper systerr Gow paths, now rates and pressures; (1) - Purpose To verify proper operation of the various ' (c) proper operation of system interlocks and equipment protective devices; and, chemical addition systems designed for actively controlling the reactor water chemistry, (f) proper operation of permissive, prohibit, . including the oxygen injection system, the zine and bypass functions; s injection passivation system, the iron ion injection system, and the hydrogen water chemistry system. System operation is considered acceptable when the observed / measured performance char 4cteristics. (2). Prerequisites from the testing described above, meet the applicable design specifications. . The construction tests have been successfu"v completed and the SCG hes reviewed the tes 14.2.12.1.56 Condenser Air Removal System

procedure (s) and has approved the initiation of.

Preoperational Test testing. The required interfacing systems shall - be available, as needed, to support the specified (1)' Purpose testing. The appropriate vendor precautions shallbe followed with regards to *he operation To verify the ability for the mechanical vacum of the affected syt;;ms and componenets and pumps and the steam jet air ejectore to. for the actual reactor water cher.ey given the establish and maintain a vacuum in the main erk:ing reactor operating state. ' condenser as per design, c. ' l - (3). General Test Methods antl Acceptance Criteria (2) Prerequisites Preoperational, testing of these _ systems will Construction tests have been successfully concentrate o.n verifying proper operation of completed and the SCG has reviewed the test the equipment skids and the various individual procedure and has approved the initiation of components. ~ Actual chemical injection testing. The main condenser abemd be intact ' demonstrations and/or simulations shall be - and steam shee4d be availablDfrom the limitad to only those cases where it is deemed-auxiliary boiler .some other temporary practicable or appropriate.with regards to the source. Other req ired interfa ing systems aforementioned precautions. shall be available, a needed, to support the f/ e A ~ specified testing. c

sMI 4:noen a nw2

.~,..

MN awme Standard Plant Res D (m) (3) GeneralTest M 4 and Acceptance Criteria (2) Prerequisites Al Performance ' 4e observed and recorded The construction tests have been successfulh { during a series ofinkividual component and completed and the SCG has reviewed the test integrated system tests to demonstrate the procedure and has approved the initiation of following: testing. Additionally, instrument air, electrical power, cooling water, and other required (a) propa operation of instrumentation and system interfaces shall be available, as needed, equipmeut in all combinations of logic and to support the specified testing. instrument channel trip; (3) General Test Methods d Acceptance Criteria (b) proper functioning ofinurumentation and gg alarms used to monitor system operation Performance ehemh! o served and recorded l and status; during a series of inkividual component and integrated system tests tc demonstrate th (c) proper operation of system valves, following: including timing, under expested operating (a) proper operation ofinstrumentation and conditions; equipment in all combinations of logic and nstrurne I channel trip; (d) proper operation of the mechanical vacuum pumps including the ability t (b) proper functioning of instrumentation and estabtish the required vacuum within the alarms used to monitor system operation design time frame; and availability; (e) proper operation of the steamjet air p,9 g,y '} ejectors acluding their ability to maintain g including isolation features, under the specified vacuum in the main expected operating conditions; condenser (while a: counting for the source of the dridng staan used); p ro i d goes in all ' E" P# "E *0 * * (f) proper pump ractor start sequence arid margin to actr.ation of protective desices; g g (g) proper e,peration of interlocks and equiprnent protective devices in pump * (f) proper operation of interlocks and moter, and salve controls; and equipment protectise devices; (b) p oper operation of permissive, prohibit, proper operation d missive, prohibit, and bypass functions; and bypass functions; and Operation is acceptable when the observed / (h) proper system operation while powered measured performance characteristics meet the f i d he soms, applicable design specifications. including transfers, ard in degraded modes 'I "" * #9## # 11.2.12.1.57 Origas System Preoperational Test operational. (1) Purpose System operation is considered acceptable when the observed / measured performece characteristics. To verify proper operation of the offgas system from the testing described above, meet the .neluding 'alves, recombiner, condensers, applicable design specifications. coolers, 'ilters, and hydrogen analgers. b Amendment 16 N

ABWR maxw Standard Plant un - 14.2.12,1.58 Hotwell Lesel Control System To verify the ability of the condensate storage Preoperational Test and transfer system to provide an adequate reserve of condensate quality water for (1) Purpose make up to the condensate system, as a preferred suction source for the RCIC and To verify design level control capability in the HPCS systems, and for other uses as designed. rnain condenser hotwell. (2) Prerequisites - (2) Prr.tequisites The construction tests have been successfully The construction tests have been successfully completed and the SCG has reviewed the test completed and the SCG has reviewed the test procedure and has approved the initiation of procedure and has approved the initiation of testing. All required interfacing systems shall testing. The condenser, condensate storage be available, as needed, to support the specified tank, condensate pumps, and associated valves. testing. and piping shall be operational and the other required interfacing sptems shall be available, (3) GeneralTest Methods and Acceptance Criteria j as needed, to support the specified testin l-(3) GeneralTest Methods and Ac nee Criteria during a series ofindividual component and integrated system tests to demonstrate the [' Performance hW ic observed and recorded following: during a series of individual component and integrated system tests to demonstrate the (a) proper operation of instrumentation and following: equipment in all combinations of logic; (a) proper operation of system components in (b) proper functioning of permissive and all combinations of logic and in reriponse prohibit interlocks; S. tt all expected controller demands;. (c) proper fur,2aning of instrumentation and (b) proper functioning ofinstrumentation and alarms used to monitor system operation alarms used to monitor system operation and status including CST volume and/or and status; ' !cvel;- -(c) proper operation of system valves (d) proper operation of freeze protection including stroke and timing; and - devices,if applicable;and (d) the ability to maintain the desired hotwell (c) the ability of the system to proside desired condensate inventory in conjunction with - flow rates and volumes to the applicable the condensate storage and transfer systems and/or components. system.- L 1-Operation is considered acceptable when the Systern operation is considered acceptable when observed / measured performance characteristics = the observed / measured performance characteristics, - meet the applicable design specifications. from the testing described above, meet the applicable design specifications. 14.2.12.1.60 Circulating Water System Prvoperational Test 14.2.12,1.39 Condensate Storage and Transfer Q System Prtoperr.tlonal Test. (1) Purpose L b - (l) - Purpose To verify the proper operation of the circulating water system and its ability to circulate cooling water from the ultimate heat N l Amendmcm 18 p2 u4

ABWR maxxs Standard Plant %n (n) sink through the tubes of the main condenser in (i) proper operation of permissive, prohibit, sufficient quantities to condense the steam and bypass functions; mbausted from the main turbine under all cgected operating conditions. (j) proper operation of freeze protection devices,if applicable; (2) Prerequisites (k) proper system operation while powered The construction tests hase been successfully from primary and alternate sources, completed and the SCG has reviewed the test including transfers, and in degraded modes procedure and has approsed the initiation of for which the system is expected to remain testing. The rnain condenser, ultimate heat operational; and sink, appropriate electrical power source (s) and other required interfacing systems shall b: (1) acceptability of pump / motor vibration available, as needed, to support the specified levels and system piping movemetts during testing. both transient and steady state operation. General Test Me ds and Acceptance Criteria System operatinn is considered acceptable when hti the observed / enured pe 'ormance characteristics, { Performance be observed and recorded from the testing described above, meet the g during a series of indisidual component and applicable design specifications. However, due to integrated system tests to demor.3trate the the lack of significant beat loads during the following: preoperational test phase, condenser and ultimate heat sink performance evaluatiou will be performed (a) proper operation ofinstrumentation and during the startup phase with the turbine generator equipment in all combinations of logic and on line. D instrument channel trip; (h 11.2.12.1.61 Reactor Sersice Water System (b) proper functioning ofinstrumentation and Preoperational Test alarms used to rnonitor system operation and asailability; (1) Purpose (c) proper operation of system salves, To verify proper opera: ion of the reactor induding timing, under expected operating service water (RSW) system and its ability to condaians; supply design quantities of cooling wa:er to the RCW system heat exchangers. (d) proper operation of pumps and motors in all design operating modes; (2) Prerequisites (c) acceptable pump NPSH under the most The construction tests have been successfully limiting design flow conditions; com%eted and the SCG has reviewed the test procedure and has approved the initiation of (f) croper system flow paths and flow rates testing. Primary and backup electrical power, including pump capacity and discharge the RCW system (including heat exchangers), head; instrument air, and other required interfacing systems shall be available, as needed, to l (g; proper pump motor start sequence and support the specified testing. margin to actuation of protective devices; (3) General T Vethods and Acceptance Criteria ( l (h) proper operation of interlocks and AU l equipment proteuise devices in pump and Performa ce. be observed and recorded g salve controls; during a series of individual component and (q") integrated system tests to de:nonstrate the followitig: Amendment IB 14 2 k4 5 i. f L g

23A6190AN Standard Plant u (a) proper operation of instrumentation ar.d preoperational test phase, it is likely that 1. cat U equiprnent it di combinations of logic and exchanger performance verification will be delayed instrument channel trip; until the startup phase. (b) proper functioning ofinstrurutntation and 11.2.12.1.62 Turbine Building Cooling Water alarms used to monitor system operation System Preoperational Test and availability; (1) Purpose (c) proper operation of system vabes, includmg timing, under expected operating To verify proper operation of the turbine conditions; building cooling water (TCW) system and its ability to supply design quantities of cooling (d) proper operation of pumps and motors in water, at the specificd temperatures, to all design operating modes; designated plant loads. (e) acceptable pump NPSH under the most (2) Prerequisites limiting design flow conditions; The construction tests have been successfully (f) proper system flox paths and flow rates completed and the SCG has reviewed the test including pump capacity and discharge procedure and has approved the initiation of testing. head; Primary and backup power, turbine senice water (TSW), instrument air, and other required (g) proper pump motor start sequence and supporting systems shall be available, as needed, for margin to actuation of protective desices; the specified testing configurations. The cooled components should be operational and operating to p (h) proper operation of interlocks and the extent possible during heat exchanger equipment protective devices in pump, performance evaluation. motor and sahe controls; (3) General Test Meth - Acceptance Criteria (i) proper operation of permissive, prohibit, sMll and bypass functions; Performance she+dg e c' served and recorded l during a series ofindividual component and (j) proper operation of freeze protection integrated system tests to demonstrate the desices,if applicable; following: (k) prc,per system operation while powered (a) proper operation of instrumentation and from primary and alternate sources, equipment in all combinations of logic and i including transfers, and in degraded modes instrument channel trip; for which the system is expected to remain operational; and (b) proper functioning ofinstrumentation and alarms used to monitor system operation (1) acceptability of pump / motor vibration and availability, levels and system piping movements during (c) proper operation of system valves, both transient and steady state operation including timing, under expected operating conditions; System operation is considered acceptable when the observed / measured performance characteristics, (d) proper operation of pumps and motors in from the testing described above, meet the all design eperating modes; applicable design specifications. The heat exchangers which ser e as the interface with the (e) acceptable prmp NPSH under the most RCW system are considered part of that system and limiting design flow conditions; ~ / s will be tested as such. However, due to the C/ probability of insufficient heat loads during the Anandmeni is 14 W 6

ABWR m-Standard Plant %n (f) proper system and component Gow paths, procedure and has approved the initiation of testing [,T f:ow rates, and pressure drops, including Primary and backup electrical power, TCW r,ystem \\ pump capacity and discharge head; heat exchangert instrument air, and other required mterfacing systems shall be availab!c, as needed, to (g) proper pump motor start sequence and support the specified testing. margin to actuation of protecthe desices; (3) General Test Metho aniAcceptance Criteria (b) proper operation of interlocks and W) equipment protecthe desices in pump and Performance e obsened and recorded { vahe controls; during a series of inkividual component and integrated splem tests to demonstrate the (i) proper operation of permisshe, prohibit, following: and bypass functions; (a) proper operation ofinstrumentation and (j) proper system operation while powered equipment in all combinations of logic and from primary and alternate sources, instrument channel trip; including transfers, and in degraded modes for which the s> stem is expected to remain (b) proper functioning ofinstrumentation and operational; alarms used to monitor system operation and availability; (k) acceptability of pump / motor vibration levels and system piping mosements during N proper operation of system vahes, both transient and steady state operation; including timing, under expected operating conditions; (1) proper operation of system surge tanks and chemical addition tanks and their (d) proper operation of pumps and motors in g3 associated functions; and all design operating modes; \\") (m) acceptable performance of TCW system (c) acceptable pump NPSH under the most heat exchangers, to the extent practical. limiting design flow conditions; System operation is considered acceptable when (f) proper system now paths and flow rates the obsened/ measured performance characteristics, including pump capacity and discharge from the testing described above, meet the head; applicable design specifications. Due to the possibility of insufficient heat loads during the preop (g) proper pump motor start sequence and phase, the final system flow balancing and heat mr.rgin to actuation of protective devices; exchanger performance evaluation may have to be performed during the startup phase, (h) proper operation of interlocks and equipment protective desices in pump and valve controls; 14.2.12,1.63 Turbine Senice Water System Preoperational Test (i) proper operation of permissive, prohibit, l (1) Purpose and bypass functions; 1 To verify the ability of the turbine senice water (j) proper operation of freeze protection (TSW) system to supply design quantities of devices,if applicable; cooling water to the TCW heat exchangers. (k) proper system operation while powered (2) Prerequisites from primary and alternate sources, including transfers, and in degraded modes The construction tests hoe been successfully for which the system is expected to remain f'} completed and the SCG has reviewed the test operational; and %/ Amendment 18 14 W '

ABWR mm Standard Plant Re, H (O (1) acceptability of pump / motor sibration valves in normal control, trip and test !,/ lesels and system piping movements during modes (including timing); both transient and steady state operation. (d) proper operation of vahe auxiliaries such System operation is considered acceptable wben as hydraulic fluid systems,includmg pumps the obsersed/ measured performance characteristics, and accumulators, and power supplies; and from the testing described above, meet the applicable design specifications. Tbc heat (e) proper interface with (i.e. response and exchangers which serse as the interface with the feedback to) the steam bypass and TBCWS are considered part of that system and will pressure control system. be tested as such. Howeser, due to the probability of insuf6cient best loads during the preoperational test Operation is considered acceptable when the phase,it is likely that heat exchanger performance observed / measured performance characteristics verification will be delayed until the startup phase. meet the applicable design specifications. 14112.i.64 Main Turbine Control System 14.2.12.1.65 Main Turbine Bypass System Preoperational Test Preoperational Test (1) Purpose (1) Purpose To serify proper operation of the turbine To verify proper operation of the turbine control system which ir,cludes the turbine stop bypass system which includes the main turbine valves, control vahes, intermediate stop and bypass vahes and their associated actuators and in;ercept vahes, and their associated actuators hydraulic control, and hydraulic control. (2) Prerequisites n ( ) (2) Prerequisites v' The construction tests have been successfully The construction tests hase been successfully completed and the SCG has reviewed the test completed and the TCG bas reviewed the test procedure and has approved the initiation of procedure and hai approsed the initiation of testing. The steam bypass and pressure control testing The steam bypass and pressure control system shall be operational and other required system shall be operational and other required interfacing system shall be available, as needed, interfacing systems shall be available, as to support the specified testing. needed. so support the specified testing. (3) General Test Methods and Acceptance Criteria j(3) General T:st Methods and Acceptance CritM Performance shewid be observed and recorded ( [ Performance be observed and recor ed during a series of component and system tests during a seri:s of component and system tests to demonstrate the following: to demonstrate the following: (a) proper functioning of instrumentation and (a) proper functioning ofinstrumentation and equipment in all combinations of logic and equipment in all combinations of logic and instrument channel trip; instrument channel trip; (b) proper operation ofinstrumentation and (b) proper operation ofinstrumentation and alarms used to rnonitor system operation alarms used to monitor system operation and status; and status; (c) proper operation of main turbine bypass (c) proper operation of main stop and control vahes in normal control, trip and test (3 vahes and intermediate stop and intercept modes (including timing); \\ l t .s Amerdmem IB I42-448

ABWR mmow Standard Plant as (d) proper operation of valve auxiliaries such Performan be observed and recorded fN as hydraulic fluid systems, meluding pumps during a series of individual component and V and accumulators, and power supplies; and integrated system test to demonstrate the following: (e) proper interface with (i e. response and feedback to) the steam bypass and (a) proper operation ofinstrumentation and pressure control system, controls in all combinations of logic and instrument channel trip, including Operation is considered acceptable when the verification of setpoints; obsersed/ measured performance characteristics meet the applicable design specifications. (b) proper functioning of instrumentation and alarms used to monitor system operation 11.2.12.1.66 Steam Bypass and Pressure Control and availability; Splem Preoperational Test (c) proper operation of associated valves, (1) Purpose including timing and stroke, in response to con *rol system demands; To serify proper operation of the steam bypass and preuure control system (SBPCS) (d) proper operation of interlocks and including, as appropriate, higher lesel control equipment protective dedces; of the turbine bypass system, the turbine control system, and the recirc flow control (c) proper operation of permissive, prohibit, system. and bypass functions; (2) Prerequisites (f) proper system operation while powered from primary and alternate sources, n The construction tests hase been successfully including transfers, and in degraded modes ('} completed and the SCG has resiewed the test for which the system is expected to remain procedure and has approsed the initietion of operational; and testing. The preoperational tests have been completed on the turbine bypass and control (g) proper communication and interface with systems (including the EHC system) to extent other equipment and control systems. necessary to support integrated system testing and all SBPCS components have been initially System operation it considered acceptable when calibrated in accordance with vendor the observed / measured performance characteristics, instructions. The required supporting systems from the testing described above, meet the and equipment shall be asailable, as needed, applicable design specifications fer the specified testing configuratioas. 14.2.12.1.67 Feedvmter Heater and Drain System l(3) GeneralTest Methods and Acceptance Criteria Preoperational Test The SBPCS is primarily an electronic control (1) system. It does not include any large Purpose mechanical equipment (i.e. turbine stop, control and bypass valves) nor any associated To verify proper operation of the feedwater hydraulic actuators, but does provide for their heaters and their associated drains including integrated control. System preoperational heater level control capabill:ies. testing will be lirnited to demonstrations without (or with significantly reduced, from a (2) Prerequisites temporary source) turbine steam flow. Comprehensive steam flow testing will be The construction tests have been successfully conducted during the startup phase. completed and the SCG has reviewed the test (] procedure and has approved the initiation of V Amendment 18 142-&49

ABWR u^umas Standard Pjant Rn a testing. All required interfacing systems shall be (2) Prerequisites c ( available, as needed, to support the speciEed testing. L The construction tests have been suceessfully (3) GeneralTest Methad and Acceptance Criteria completed and the SCG has reviewed the test procedure and has approved the initiation of The feedwater beater and drain system includes testing All required interfacing systems shall the feedwater beaters, internal and euernal be available, as needed, to support the specified drain coolers, normal and emergency dump testing. vahes, shell and tube side isolation valves, shell side vents and safety relicf vahes, and (3) General Test Methods and Acceptance Criteria l associated > umentation, control and logic. n4 Comprehensive testing of the extraction steam l Performance w=W be observed and recorded system will require the turbine generator to be g during a series ofindividual component and on line with a substantial amount of steam now integrated system tests to demonstrate the available. Since significant : team flow following: conditions are dependent on nuclear beating,the preoperational phase test'.g that is u (a) proper operation of instrumentation and possible will be limited. Performance equipment in all cumbinations of logic and be observed and recorded during a series of instrument channel trip; component and system tests to demonstri e the following: (b) proper functioning ofinstrumentation and alarms used to monitor system operation (a) proper operation of instrumentation and and status; equipment in all combinations of logic and instrument channel trip; l (c) proper operation of system valves and p actuators under expected operating (b) proper functionir.g ofinstrumentation and j g conditions; alarms used to monitor systern operation i and status; I (d) proper operation of interlocks and equipment protective devices; (c) proper operation of system vahes under expected operating conditions including (e) proper operation of permissive, prohibit, response of air assisted nonreturn check l and bypass functions; and valves to a turbine trip signal; l l (f) proper operation of heater level controls (d) proper operation of interlocks and l including response of the associated equipment protective desices; and drain / dump valves. (c) proper operation of permissive, prohibit, Operation is aeceptabie when the and bypass functions. observed / measured performance characteristics meet the applicable design specifications. Operation is acceptabie wheo tbe observed / measured performance characteristics 14.2.12.1.68 Extraction Steam System meet the applicable design specifications. Preoperational Test 14.2.12.1.69 Moisture Seperator/Rebeater System (1) Purpose Preoperational Test To verify proper operation of tt. components (1) Purpose which comprise the extraction steam system. To verify proper operation of the turbine moisture sperator/ reheaters (MSRs) rad their 4 'd Amedme: t 18 14 2.&4 to

ABWR

== Standard Plant w O associated drain pathwa>s, steam extraction lines. (f) proper operation of moisture seperator and isolation and non return check vahes. and reheater rompartment drain pathwap. (2) Prerequisites Operation is acceptable when the obsened/ measured performance characteristics The construction tests hase been successfully meet the applicable design specifications. completed and the SCG has resiewed the test procedure and has approved the initiation of 14.2.12.1.70 Main Turbine and Auxillaries testing. All required interfacing sprems shall Preoperational Test be asailable, as needed, to support the specified testing. (1) Purpose (3) GeneralTest Methods and Acceptance Criteria To serify that the operation of the main turbine and its auxiliariy systems, including the gland The MSRs include both a moisture seperator sealing system, lube oil system, turning gear, and reheater compartment each with their supervisory instrumen'tation, and turbine owndrains, shell and tube side isolation vahes, protection system (iocIuding shell side vents and safety relief vahes, and overspeedprotection),is as specified. Testing associated instrumentation, control and logic. of the turbine vahes and associated control sptems is specified separately (elsewhere). Comprehensive testing of the extraction steam sptem wiu require the turbine generator to be (2) Prerequisites on line with a substantial amount of steam flow available. Since significant steam flow The construction tests have been successfully conditions are dependent on nuclear heating, completed and the SCG has resiewed the test the preoperational phase testing that is possible procedure and has approved the initiation of ( 3) will be limited. ^ testing. To the extent practicable, a temporary Shd steam supply shall be available for driving the { Performance hd be observed and recorded turbine. The turbine instruction manual shall g during a series ofindividual component and be reviewed in detailin order that precautions integrated system tests to demonstrate the relative to turbine operation are foUowed. All following: required inter sing systems shall be available, as needed, to supp,rt the specified testing and (a) proper operation of instrumentation and the corresponding sptem configurations. equipment in all combinations of logic and instrument channel trip; (3) GeneralTest Methods and Acceptance Criteria (b) proper functioning ofinstrumentation.nd Since preoperational testing is performed alarms used to monitor system operation utilizing a temporary steam supply, the extent and status; to which the turbine itself can be tested may be limited. Therefore, the testing effort at this (c) proper operation of system vahes and stage will concentrate on assuring that the actuators (including isolation and necessary turbine auxiliaries are functioning non return check valves) under expected properly. operating conditions; shJ Performance skeWpe observed and recorded l (d) proper operation of interlocks and during a series oIindividual component, equipment protective devices; subsystem and integrated system tests (to the extent possible) to demonstrate the following, (e) proper operation of permissive, prohibit, with regrads to both the turbine and its ard bypass functions; and auxiliaries: v Amendment !$

424.411

ABWR

w o Standard Plant n~n

(,0 proper operation of instrumentation and generator exciter, stator, circuit breakers and ( equipment in all combinations of logic and isophase bus duct, and the generator protection A instrument channel trip; system, is as speciGed. (M proper functioning of instrumentation and (0) Prerequisites alatms used to monitor systsm operation and availability, including the turbine The construction tests have been successfully supervisory instrumentation; completed and the SCG has reviewed the test procedure (s) and has approved the initiation of (c) proper operation of system pumps and testing. To the extent practicable, and in vahes in all design operating modes; conjunction with the turbine preoperational testing, a temporary steam supply shall be (d) proper system flow paths, Dow rates and available for drivine the turbine / generator. pressures (particularly with regards to the The generator instr ction manual shall be lube oil and gland sealing steam sptems); reviewed in detailin order that precautions relative to generator operation are followed. (el proper operation of interlocks and All required interfacing systems shall be equipment protective devices in available, as needed, to support the sariousturbine, pump, and vahe controls specifiedtesting and the corresponding system (including the sarious primary and backup configurations. turbine oserspeed protection devices); (3) GeneralTest Methods and Acceptance Criteria if) proper operation of permissisc, prohibit, i and bypass functions; Since preoperational testing in part is performed utilizing a temporary steam supply. 6 l (g) proper operation while powered from both the extent to which the turbine, and therefore ,3 j primary and alternate sources,inc!uding the generator, can be tested may be limited I j i transfers, and in degraded modes for Therefore, the testing effort at this stage will which the systen, subsystem or component concentrate on assuring that the necessary is expected to remain operational; individual generator components and auxiliaries -tioning properly. th) proper turbine alignment, including sU l acceptabihty of displacement and sibration Performanc be observed and recorded l 7 levels.if possible, during both transient and during a series of individual component, steady state operation; subsystem and integrated system tests (to the extent possible) to demonstrate the following. 5ptem operation is considered acceptable when with regrads to both the generator and its the obsersed/ measured performance characteristics, auxiliaries: from the testing described above, meet the appheaNe design specifications (while accounting for (a) proper operation ofinstrumentation and the tcsting limitations imposed), equipment in all combinations of logic and instrument channel trip; 11.2.12.1.71 Main Generator and Auxiliary Spiems PreoperationalTest (b) proper functioning ofinstrumentation and alarms used to monitor system operation (1) Per use and availability; Verify that the operation of the main generator (c) proper operation of system pumps, valves, and its auxiliarly systems, including the fans, and piping or ducting in all design centrator hydrogen system and its associated operating modes; scal oil and cooling systems, those subsystems and/or components that provide ccoling to the (d) proper system flow paths, flow rates and Q pressut es (particularly with regards to the v) .s**cadmect !! t4 21412 m

ABWR uu - Standard Plant %s i O) generator hydrogen system and its associated during a series of individual component ( seal oil and cooling systems); and integrated system tests to demonstrate I' the following: (c) proper operation of interlocks and equipment protective desices in the various generator and (a) proper operation ofinstrumentation and auxiliary sptem controls; equipment in all combinations oflogic; (f) proper operation of permissise, prohibit, and (b) proper functioning ofinstrumentation and bypass functions; alarms used to monitor systern operation i and availability; (g) proper operation while powered fron, primary l. and any ahernate sources, including transfers, (c) proper operation of system valves, 8 and in degraded modes for which the system, including timing, under expected operating subsystem or component is expected to remain conditions; operational; (d) proper system now paths and flow rates l(h) proper generator alignment, including both into and out of the primary acceptabihty of clearance and sibration !ctels,if containment; possible, during both trans.ent and steady state operation; (c) proper operation of interlocks and equipment protective desices in valve and System operation is considered acceptable when recombiner skid controls; the observed / measured performance characteristics, from the testing described abose, meet the (f) proper operation of permissive, prohibit, applicable design specifications (while accounting for and bypass functions; and the testing limitations imposed). ( ) (g) proper system operation while powered %./ 14.2.12.1.72 Flammability Control System from primary and alternate sources, Preoperational Test including transfers, and in degraded modes for which the system is expected to remain (1) Purpose operational. To serify the ability of the flammability control System operation is considered acceptable when system (FCS) to recombine hydrogen and the observed / measured performance characteristics, oxygen and therefore maintain the speciGed from the testing described above, meet the inert atmosphere in the primary containment - applicable design specifications. durir g 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 reviewed the test procedure and has approved the initiation of To verify proper functioning of loose parts testing. The wetwell and drywell airspace monitoring equipment. regions of the primary containment should be intact, and all other required interfaces (2) Prerequisites asailable, as needed, to support the specified testing. The construction tests have been successfully completed and the SCG has reviewed the test (3) GeneralTest Methods and Acceptance Critena procedure and has approved the initiation of testing. Reactor internals shall be in place with /^ Performance sL#4t be observed and recorded all system sensors connected. Shall Ameneent 15 14 W 13

tYS n^ume Standad. Plant FevR j (3) GeneralTest Met A,and Acceptance Criteria System operation is considered acceptable when the j shnu obsersed/ measured performance characteristics Performance -- oc o > served and recorded meet the appbcable desig;n specincations. during a series of system and component test to demonstrate the following-14.2.12.1.?! Liquid and Solid Radwaste Sptems (a) pioper operation of instrumentation and l alarms; and (1) Purpose (b) the adequacy of alert lesel setpoints based To verify the proper operation of the various on preliminary data. equipment and processes which make up the liquid and solid radwaste sprems. Sptem operation is considered acceptable when the obsersed/ measured performance characteristics (2) Prerequisites meet the applicable design specifications. The construction tests base been successfully comp eted and the SCG has reviewed the test l 14.2.12.1.74 Seismic Monitoring Sptem Preoperational Test r.-

s d has approsed the imtiation of mg' testing. There >& wed be access to appropriate l

(1) Purpose laboratory facilities and an acceptable effluent discharge pat Md be established. l To serify that the seismic monitoring system A u ii m n s., an adequate supply of I operate as designed in response to a demineralized water, the necessary electrical seismic esent. power, and other required interfacing sprems shall be available, as needed, to support the (0) Prerequisites speciGed testing. /3 Q The construction tests have been successfully (3) General Test Methods and Acceptance Criteria l completed and the SCG has reviewed the test procedure and has approsed the initiation of The testing described below consists of that of h testing. The required electrical power *heekig the equipment and processes for the bandling, be asailable and all system recording devices treating, storing, and preparation for the should base sufficient storage medium disposal or discharge of liquid and solid available. radwaste. Gaseous effluents are treated and Shad released by the offgas system or the standby gas l(3) General Test Methods a efptance Criteria treatment system, the testing of which is specifically described elsewhere. l Performance -%4dhe observed.and re mrded during a series of tests, as recommendeu ey ihe f or,. pid and solid radw:ste systems manufacturer, to demonstrate the following: performance shev41 be observed and recorded l during a series of individual component and (a) proper calioration and response of seismic integrated system tests to demonstrate the instrumentation including verification of following: alarm and initiation setpoints; (a) proper operation of equipment controls (b) proper operation ofinternal calibration or and logic including prohibit and pertnissise test features; interlocks; (c) proper operation of recording and (b) proper operation of equipment protcctise playback desices; ar.d features and automatic isolation functions including those frr ventilation systems and (d) proper integrated system response to a liquid effluent painways; , [s] simulated seismic event. l N.) l Am<nemen 18 }4 244 la

ABWR m =ne Standard Plant Nu at u service water systems be perational g omponent systems, and associated equipment. If c and other required interfacing systeins davH a criterion of this ruture is not satisfied, the be available, a needed, to :upport the plant will be placed in a suitable hold specified testing. condition until resolution is obtained. Tests compatible with this hold condition may be (3) GeneralTe,t Methods and Acceptanct Cri;eria continued. Following resolution, applicable tests may be repeated to serify that the te-performance should be obsened and recorded quirements of the criterion are ultimately during a merks of component and system tests s a t is fie d. Other criteria may be associated to demonstrate the following: with espectations relating to the priormance of systems. If this type of criterion is not satis-(a) proper operation of instrumentation and fied, operating and trsting plans would not nec-alarms used to monitor system operation estarily be altered. Howeser, investigations of and status; the measurements and of the analytical tech. niques used for the predictions would be start. (b) proper operation of active coding ed. Specific action for dealing with criteria desices. if applicable, such as forced f ailures and other testing exceptions or or natural draft towers,.pra) ponds, ansmolics will be described in the startup ad-etc.; and ministrative manual. 1 (c) the adequac) of intake and discharge st r uctur es, including screens or strainers, or other interfaces with the circulatinF water system, such as freeze protection desices, as applicable. Operation is acceptable when the obsersed/ measured performance characteristics meet the applicable design specifications. 14.2.12.2 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 prosided for test purpose, test prerequisites, test description and test acceptance criteria, w he'e applicable. Since additions, deletions, and changes to these discussions are expected to occur as the i test program is developed and implemented, the. descriptions remain general in scope. In de. I scribing a test however, an attempt is made to identify those operating and safety. oriented characteristics of the plant which are being explored and evaluated. Where applicable, the relevant 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, /^ i (x AmfndmCf4 ls 14 b44 If,

_ __. ~ ABWR umo.s Standard Plant nx n Thus, after it is verified that all CRDs reviewed the test procedure (s) and has s < perate properly when installed, tests are approved Ibe initiation of testing. Por performed periodicauy during heatup to e :b.cheduled test iteration the plant assure that there in 90 significant binding shall be in Ibc appropriate operational caused by thermal expansion of the core c o n fig u r a tion wit h all spe cific d components and no significant effect on per-pr e r e q uisit e t e sting cort ple t e. The formance due to incrrased pressure, power or applicaHe instrumentation shall be checked flo w. Additionallb software functions such or calibrated as is appropriate, as those associated witn the RC&lS are tested to the extent that they could not be checked (3) Description during preoperaGonal testing. Testing will also be conduc.ted to serify proper op-ration Testing of the neutron monitoring sptem of the SCRRI logic and fuoctix The part-will commence prior to fuel load a d will icular testing st the SC3R1 function might be conti:nac at intersals up to and including conducted at least in part, with tbc RIP rated power. The SRNMs and operational trip test described in 14.2.12.2.30 where the sources will be tested during fuel loading planned trip will auton.aticall) result in and during rod withdrawal on ibe approach to SCRRI actuation. criticality and heatup to rated teroperature and pressure. The LPRMs, APRMs and TIPS (4) Criteria will be tested as soon as sufficient flux lev.ls exist and at specified intervals Each CRD sball hase a measused scram time during the asc:nsion to rated power. Test-that is less than the technical specifi-ing will include response checks, calibra-cations requirements and consistent with tions and verification of system software safet) analpis assumptions during both in-calculations using actual core fiux levels di+1 dual rod pair and full core scrams, as and other lise plant inputs. A applicable Each CRD shall hase a measured ( insert / withdrawal speed consistent with spe-(4) Criteria cified design requirements including those associated with group or gang movement. Tbc $RNMs,in conjunction with the installed Additionally, the CRDs shall meet friction neutron sources, sball base count rates and test regoirements and those for demonstri.. signal to noise ratios that meet technical ting proper operation of rod deceleration specifications and/or der,ign requirements, d e vic e s. Also, all so'tware functions or as applicable. Tbc respective range func. features shall perfern es specified, tions of the SRNMs and APRMs All preside for o.erlapping neutron flux indication as 14.2.12 2.6 Neutron Monitoring System required by plant technical specifications Performance and rbe applicable destgn specifications. The APRMs shall be calibrated against core (b Turpcse thermal power by means of a beat balance. The accuracy of this csubration ehertd/c l To ',erify response, calibration and operation consistent with technical specification 6h of startup range neutron monitors (SRNMs), When technical spec.lications are not appli-local power range monitors (LPRMs), average cable the APRMs skreldfonservatnely indi-I power range monitors (APRMs), traversing cate react.a power. The LPRMs sL4d@c in core probes (TIPS), and other bardware and calibrated consistent with design calibra-software of the neutron monitoring system tion and accuracy requirements. Additionq during fuel loading, control rod withdrawal, ally, all system hardware and software shall heatup and power as:ension, functico properly in response to actual core flux levels. (2) Prerequisites The applicable preogrational phase testing \\ is complete and the plant management has AmeMmtet 18 14 M

ABWR ams Slaitdard Plant ma e various plant control sptems during actual (2) Presequisites ( plant operating conditions. The applicable preoperational te sts base (2) Prerequisites been completed and plant rnana,ement has resiewed the test procedure;s) and 1.as The applicable preoperational tests base beca ar pro.ed the initiation of testing. For completed and plant management has eviewed each scheduled testing iteration the plant i the testing procedure (s) and has appresed the shall be in ibe appropriate operational initiation of testing. For each scheduled configuration with all specified prerequi-l testing iteration the plant skall be in the site testing complete, especially on plant appropriate operational configuration with systerns to be used for collection or all specified prerequisite testing complete, evaluation of pertinent data. (3) Description (3) Description During plant bestup and the ascension to rat. This test will collect data sufficient to cd power the virious NS$5 and BOP process demonstrate that reactor and core perfor. satiables that are rnonitored by the PCS begin inance characteristics remain within design to enter their tespectise ranges for normal limits and expectations for all operational plant operation. During this time it will be conditions which the plant is normally ex. serified that the PCS correctly receises, va-pected to ennuntes, lleginninp with rod lidates, processes, and display Ibc applic. withdrawal and continuing through initial able plant information. Recording ard play. criticality, plant beatup, and the ascension back fea,ures will also be tested. Data ma-to rated power, pertinent data will be col. nipulation and plant performance calculations lected at various rod patterns and power and using actual plant inputs will be serified flow conditions sufficient to determine the for accuracy, using independent calculations axial and 'adial core power distributions. ( for comparison. Also, the ability of the PCS compliance with core thermallimits, and the to interface correctly with other plant con-lesel of consistency with predicted core trol systems during operation will be reactivity and power sersas flow characterio demonstrated. tics. Unusual plant :onditions such as dur. ing control rod sequence exchange or natural (J) Criteria circulation will also be investicated, if cpplicable. The performance of the PCS shall be as speci. fied by the applicable design rnpitements. (4) Criteria Additionally, plant performance calculations, especially those used to dernonstrate com. Technical specification and license condi-l pliar.ce with core thermal limits, shall meet tion requirements involving core thermal the accuracy requirements o,f the applicable limits, maximum powt;r level, total core plant safety analysis design assumptions. flow, and any observed reactivity anamolies or core instabilities shall be met when 14.2.12.2.8 Core Performance applicable. Other observations should meet predictions and expectations or else Aceti MSN (1) Purpose be evaluated and explained accordingly. To demonstrate that the various core and 14.2.12.2.9 Nuclear Boller Process Monitoring reactor perfcirmance characteristics such as power versus flow, core power distributions, (1) Purpose and those parameters used to demonstrate compliance with core thermallimits and plant To verify proper operation of various nucle-l license conditions are in accordance with at boiler process instrumentivo and to col-y design limits and expectations. lect pertinent data from such instrumenta-l 14 M Amendmem 15 i

AON nAnmo '51iimtittd_l'lant nrv 4 tion at sarious plant operating conditions in is working as designed and the piping is order to utidate design assumptions and iden-free of obstructions that could constrain lif> any operational limitatiot* that may free pipe movemcot caused by thermal c6st. expansion. (2) Prerequisites (2) Prerequisites The applicable preoperational testing has The preeperational tests have been cornpleted been completed and plant managernent has re. and plant management has reviewed the test siewed the test procrdure(s) and has approsed procedures and has approved the initiation the initiation of testing. For each sche-of testin6 For each scheduled testing duled testing iteration the plant shall be in iteration the plant shall be in the appro-the appropriate operational corificuration priate operatiosal configuration with toe with all specified pierequisite 13 sting specified prerequisite testing complete. complete. The applicable instrumentation shall be checked or cabbrated as is appropriate. (3) Description (3) Description During plant bestup and power ascension pert-inent parameters such as reactor coolant tem-The thermal expansion tests consist of perature, sessel dome pres.sure, sessel water measuring displamm nts and temperatures of lesel, and core flow will be monitored at se-piping during various operating modes. The lected intersals and plant conditions. This first power level used to serify expansion data will be used to serify proper instruraent shall be as low as practicable. Thermal respanse to changing plant conditions and to mos ement and t emperat ure measurement s4*wM 4 sW) i document the relationships amongst these pa-be recorded at at least the following test ramete:S and with other important parameters ooints (following a suitable hold ietiod to O. such as reactor power,. feedwater flow and assure steady state temperatures): steam flaw. The dita will also be used to salidate design assumptions such as those (a) during reactor pressure vessel heatup at used in the calibration of vessel lesel or at least one intermediate temperature core flow indication. Additionally, the data prior to reaching normal operating will be used to help identify potential temperature, including an inspection of operational condition limitations such as the piping and its suspension for excessise coolent temperature stratification obstructions or inoperable supports, in the sessel bottom head region, (b) following reactor pressure vessel beat (4) Criteria up to normal operating temperature; The sarious nuclear boiler process instrurnen-(c) following heatup of other piping systems talion shall operate as designed in response to normal operating temperature (thcm to changes in plant conditions. The obscrsed systems whose beatup cycles differ from process characteristics shall be conservatise (2) above); and tr.lative to applicab!c safety analysis assumptions and should be consistent with (d) on subsequent beatup/cooldown cycles, as design expectations. specified, at the applicable operating and shutdown temperatures, to measure 14.2.12.2.16 Sptem Expansion possible shakedown effects. (1) Purpose Thermal expansion shall be conducted on plant sptems of the following classifi-The purpose of the thermal expansion :est is cations: to confirm that the pipe suspension system \\ AMmt 2 14 M ~

.-_ ~ ~ - ~ _ _ - tN N

3Ame Slandard Plant

w. s (a) A$ME Code Class 1,2. and 3 systems; ihe iest procedurc(s) and has approved the initiation of testing. For each scheduled (b) high caergy piping systems inside test iteration the plant shall be in the ap.

Senrmc Category I structures; propriate opetational configuration with all spec!fied prerequisite testing complete. (c) high energy portions of systems whose The regubed remote monitoring instrumen. failure could reduce tae funstioning of tation kirW be calibrated and operational. l any seismic Category I plant fea'utes to th] an unacceptable level; and (3) Description (d) Scismic Category I portions of moderate Vibration testing during the power ascension energy piping tptems located outside phase will be limited to those systems that cmtainment, could not be adequately tested during the preoperational pha:.e. Systems within the (4) Criteria scope of this testing are therefore the same as mentioned in Subsection 14.2,12.1.51. The thermal expansion acceptance criteria are However, the systems that ternain to be based upon the actual m,'ements being within tested wili prirnarily be those exposed to a procribed tolerance of the movements pre-and affected by steam flow rad high rates of dicted by analpis. Measured mmements are core flow. Due to the potentially bigh le. not expected to preciscly correspond with vels of radiation present during power those mathematically predicted. Therefore, a operation, the testing will be performed tolerance is specified for differences bel-using remote monitoring instrumentation. ween measured and preficted movement. The Displacement, acce!cration, and strain data tolerances are based on consideration of will be collected at various critical steady measurement accuracy, suspension free play. state operating conditions and during signi-and piping temperature distributions if the ficant transients such as turbine or genera-k measured mmement does not vary from the pre-tor trip, main steamline isolation, SRV act-dictions by more than the specified tole-nation and RIP trip (if not air,:ady per-rance, the piping is expanding in a manner formed). Stead) state and transient vibra. consistent with predictions and is therefore tion affecting tb: RCIC steamline will also ac< cpt able. Tolerances should be the same be monitored. for all operating test conditions. The loca. tions to be rnonitored and the predicted dis-(4) Criteria placements for the monitored locations in each plant will be provided by the epplicable Criteria will be calculated for those points design or testing specification. monitored for vibration for both steady state and transient cases. Two lesels of l<til lli Sptem Vibration criteria will be generated, one level for predicted vibration and one level based on (1) Purpose acceptable value: of displacement and accel-eration and the associated stress to assure To serify that the vibration of critical that there will be no failures from fatigue plant system components and piping is within over the life of the plant. Failures to acceptable limits during normal steady state remain within the predicted levels of vibra-p er operation and during expected tion should be investigated but do not neces-operational transients, sarily preclude the continuation of further testing. However, failure to meet the (2) Prerequkites criteria based on stress limits will require imrnediate irsestigation and resolution while The applicable preoperational phase testing the plant or affected system is placed in a l l is complete and plant management has reviewed safe condition. ( l Amendmem 2 14 2N l w-+-,- m- = v- ,,.,-c,.-. ~w,.m.-- ,---w 4ew-e-w - - - - - -, em -r-- r-evr-w-- 4

ABWR

== Sundard Plfwt m 14.2.12.2.1. Reactor Internals \\*ibration respose characteristics of Ibc recircul-atire flow control splem are in accordance (1) Purpose aith design requirements for all applicable modes of cc:ntrol across the span of espected To collect information veeJed tu scrify the operational conditions, adequacy of the desigo, manufacture, and assembly of reactor vessel internals with (2) Prerequisites respect to the potential affects of flow i induced sibtstion. The preoperational tests have been completed and plant management has reviewed the test (2) Prerequisite procedure and has approved the initiation of l testing. For each scheduled testing itera-The applicable preoperational phase testing tion the plant shall be in the appropriate is complete, including the required inspec. operational configuration with all specified tions, and plant management has reviewed the prettquisite testing complete. This in-test procedure and has approved the initia-cludes preliminary adjustment and optimira-tion of testing. For each scheduled testing tion of control system components, as appro-l iteration the plant shall be in Ibc appro-priate. priate operational configuration with all specified prercquisite testing complete. Tbc (3) Description [ cecessary specialinstrumentation hid be calibrated and operational. Startup phase testing of the recirculation flow control system is intended to de:non-(3) Description strate that the overall response and stabil. ity of the sptem meets design requirements Reactor internal vibration testing subse. subsequent to controller optirnization. Per-qtent to fuelloading is roetely an extension formance shall be demonstrated at a suffi-of tbc 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. jation measurement portion of that itions including applicable modes of contral t is program +k. 4+e expanded during the power (speed, flow and automatic load following) ascension phase to include intermediate and for :sch 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 control. result in limiting or significant levels of Special control features such as those used scactor intercals vibration over and above to maintain a specified margin to the high what was observed during the preoperatiot.al flux scram setpoint or to avoid regions of phase. potential cose instability should also be demonstrated as appropriate. (1) Criteria (4) Criteria Criteria for limits on reactor internals . 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 response is avoided. The response should 14.2.12.1.52. also be sufficiently fast but with any aseillatory modes of response well damped. 14.2.12.2.13 Recirculation Flow Control usua11y wiib deeay ratios 1ess tban.25. Tbc overall response of the sptem, at all (1) Purpose levels of control, should be within design ~ requirements with respect to such standard To demonstrate that the stability and control system criteria as response time, t-Aanenimerit 15 14252 i l

ABWR mm Standard Plant rn n r nonlinearities or dissimilarities in systep( [) rise time, overshoot and settling time. (_) Also, the oserall $> stem performance should response at various conditions Ahliiso be in accordance with expectations for be demonstrated. The above testiug will anticipated transients. also seru to demonstrate overill core stability to subcooling changes. 142.12J.14 Fredwater Control (1) Criteria (1) Purpose Above all else the feedwater control system To demonstrate that the stabilit) and performance shall be stable such that any response characteristics of the (vedwater type of disergent response is asoided. The control system are in accordance with design response should be sulficiently fast but requirements for applicable system configurs-with any oscillatory modes of response well tions and operational conditions, damped, usually with decay ratios less than 0.25. Additionally, the open loop response (2) Prerequisites of the system should rneet design mquire. ments with respect to such 3tandard control The preoperational tests are complete and system criteria as response: time, rise time, plant management has reviewed the test oversboot, and settling time. Also, the procedure and has approsed the initiation of overall system response should b-as expect-testing, for each scheduled testing ed following major plant transients and i ite ration the piant shall be in the trips. appropriate operational configuration with all specified prerequisite testing complete. 14.2.12.2.15 Pressure Control This includes preliminary adjustments and O optimization of control system components, as (1) Purpose i appropriate. To demonstrate that the stability and (3) Description response characteristics of the pressure regulation system are in accordance with the Startup ph;se testing of the feedwater design requirements for all modes of control control system is intended. to demonstrate under expected operating conditions. that the ourall response and stability of the system meets design requirements sub-(2) Prerequisites sequent to controller optimization. Testing will begin during plant beatup for any The preoperational tests have been completed special configurations designed for scry low and plant managernent has reviewed the test feedwater or condensate flow rates and will procedure and has approved the initiation of m wha up thr ugh the normal full power testing. For each sche duled testing itera-k line up. Testir sWd include all modes of tion the plant shall be in the appropriate control and should encompass all expected - operational configuration with all Lpecified plant power levels and operational condi-prerequisite testing complete. This in-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-direct input of demand changes at various priate. g levels of control. System response SWd+ WII also be esaluated under transient operation. (3) Descriptioir - al conditions such as an unexpected loss of a feedwater pump or a rapid reduction in core Startup phase testing of the pressu.e con-flow and/or power lesel and after plant trips trol system is intended to demonstrate that such as turbine trip or main steam line the overall response and stability of the i f_) isolation. Proper setup of control system system meets design requirements, subsequent l ) 'V components or featurn designed to bandle the to control system optimization. Performance l Amendment 18 14 W l l

i ABWR m-Standard Plant mn shall be evaluated across the spectrum of the testing procedure and has approsed the O anticipated steam flows for both the pressure initiation of testing. Affected splems and regulation and load following modes of 2 equipment, including lower lesel control l cont rol, as applicable. Testing s splems such as RC&ls, recite flow control, demonstrate acceptable respac5e with either feedwater control and turbine control, as the turbine control sahes or bypass sahes well as monitoririg and predicting lunctio.is in control and for the transition between the of the plant process computer and/or auto-tw o. Testing will be accomplished by manual mation computer, shall base been adequately manipulation of controllers and/or direct tested under actu I operating conditions l D]synpa-LQmand changes at sarious lesels of f control itWAl also be demonstrated that (3) Description other affected parameters remain within acceptable limits during such pressure regu-A comprehensise series of tests will be per-lator induced transient mancusers. Oserall formed in order to demonstrate proper func. sptem response will be esaluated during tioning of the various plant automat.on and other plant transients as well. Addition. control features. This testing $ ball in-ally proper actup of components or features clude or bound a!! expected plant operat-designed to deal with the nonlinearities or ing conditions under all permissable modes dissimilarities in sptem response that may of control and shall also verify, to the ( s.ist under sarious conditions be extent possible, avoidance of prohibited or demonstrated. undesirable conditions os cotstrol modes. .m sLs tl ALF capabilities will be demonstrated under (4) Criteria control of the APR for both control rod snosements and core flow danges including /.bose all else, sptem performance shall be anticipated transition regions. Such stable such that any type of disergent re- !csting will include demonstration (s) that ense is avoidei The response should be t'nu dynamic response of the plant to design sufficiently fast but with any oscillatory load swings for the facility, including modes of response

• ell damped, usually with limiting step and ramp changes as appro-deca) ratios less than.25.

The oserall priate, is in accordance with design. The l response of the sptem, for each mode and ability of the PGCS to properly orchestrate level of control, should be within design automt.ted plant startup, shutdown and power requirements for such standard control sptem maneuvering will be shown. Also to be criteria as response time, rise time, oser-tested are sptem components or interfaces shoot and setting time, Also, the overall that perform monitoring, prediction, splem performance should be in accordance processing, validation, alarm, protection or with expectations for anticipated transients, control functions. 14.2.12.2.16 Plant Automallon and Control (4) Criteria l (1) 'Nrpose The PGCS, APR and other features and func. tions of plant automation and untrol shall To verify proper plant performance in auto-perform in accordance with the applicable l matic modes of control such as during auto-design and testing specifications. Auto-i matic plant startup or automatic laad fol-matic maneuvering characteristics of plant lowing (ALF) under the directier of the power and systems shall meet the appropriate re-l generation control sptem (POCS) and the sponse and stability requirements. Safety l tutomatic power regulator (APR), and protection features shall perform con-sistant with safety analysis assumptions and C) Prerequisites predictions. ^ The applicable preoperational tests have been completed and plant management has reviewed Ampdmem 1s ydu ~ _ _. _

ABWR

== Sandard Plant nr 9 dance mtb design requirements. (2) Prerequisites (2) Prercquisites The preoperational testine i complete and plant management has r..iewed Ibc test The prec.perational testin;; is complete and procedure and has approsed the initiation of plant management has resiewed the test pro-testing. For each scheduled testing itera. l edure and has approsed the initiation of tion the plant shall be in the appropriate l testing. For each scheduled testing itera. operational configuration with all specified i tion the plant shall be in the appsopriate prerequisite testing complete. Applicable operational configuration with all specified instrumentation bas been checked or prerequisite testing complete. Instrumenta. calibrated as is appropriate. tion bas been checked or calibrated, as is appropriate. (3) Description (3) Description Pertiner't parameters will be monitored throughout the feedwater systern, and con. Pertinent recirculation system and related densate system if appropriate, across th-parameters will b. monitored at a variet) of spectrum of system flow and plan: operating i power and flow conditions in order to demon. conditions in order to demonstrate that sys-strate that system operation is in accordance tem operation is in accordance with design. with design. Parameters to be monitored and Parameters to be monitored may include tem-evaluated should include RIP speeds, pump peratures, pressures, flow rates, pressure deck and core plate differential pressures, drops, pump speeds and developed heads, and pump efficiencies, maximum core flow capabil. general equipment status. Of special inte, it) and any number of other variables that rest will be data that serves to verift de. may indicate the status of the RIPS and their sign assumptions used in plant transient O shafts, motors, or beat exchangers. Data performance and safety analysis calculations shall also be talen and esaluated during tran. like maximum feedwater runout capabilities sient conditions such as pump trips and re. and feedwater temperature versus power lesel starts, and during off normal conditions such relationships. Steady state and transient as one pump out of service operation. Of par. testing will be conducted as necessary, to l ticular interest qbe the onset of re. assure that adequate margins exist between serse flow through idle pumps and tS cali. system variables and setpoints of bration of total core f ow indiciions during instruments monitoring these variables to both normal and off normal operating prevent spurious actuations or loss of conditions. u.11 system pumps and motor. operated vahes. (4) Criteria (4) Criter;a When applicable, measured parameters shall When applicable, measured parameters shall compare conservatively with safety analysis compare conservati$ely with safety analysis design ass imptions. Additionally, test data design assumptions. Additionally, test data should demonstrate tha* system steady state should demonstrate that system steady state and transient performance meets design re. and transient performance meets design quirements, r e quir e m e nts. 14.2.12.2.18 feed *ater System Performance 14.2.12.2.19 Main Steam System Performance (1) Purpose (1) Purpose To serify that the oserall feedwater system To serify that main steam system related operates in accordance with design require. performance characteristics are in accord-merts. ance with design requirements. Amcadroent 18 14 M S

ABWR .= = Sandard Pant m4 t e s ting. For each scheduled testing itera-(3) Dtscription p tion the plant sha!) be in the appropriate V operational conhguration with all prerequi-Startup phase testing of the RHR sptem is site testing complete. Apt cable instrumern intended to den onstrate the capabilities of li tation shall be checked or calibrated as is the sptem beyond what was possible during apprepriate. the preoperational phase due to insufficient temperature and pressure conditions. Pert-(.1) Description inent system parameters will be monitored in the suppression pool coohng and shutdown Pertinens sptem parameters, such as tempera. cooling modes to verify that overall system tures, pressures, and flows, will be moni-operation and heat removal capabilitic, are tored at sarious steam flow rates in order to in accordance with design requirements. An demonstrate that sptem operation is in ac-at t e m r4yhM be made to obtain results l cordance with design, The steam flow measur hwith flow rates and ternperatures near pro-ing desices that proside input to feedwate cess diagram values. However, due to the control and/or ler k detection treic Mie relatively low core exposures and decay hea; crouchecked to scrify th accuracy of design loads expected during the startup program, calibration assumptions. If appropriate, the care should be taken such that the limit on prenure drop det eloped across critical compo-vessel cooldown rate is not exceeded. l sMM be compared with design ulues. 6W The quality of the sicaa leaving the reactor (4) Criteria l 4.*M also be determined to be within design requirements (if not previously tested). Sptem performance, especially heat remosal capability, $ ball meet safety analpis re-(?) Criteria quirements. Additionally, measured para-meters should indicate that oserall sptem When appliub'a r casured parameters shall performance is consistent with design expec-s compare consemovely with safety analysis tations. dest;n assumptions. Additionally, test data should den onstrate that system steady state 14.2.12.2.21 Reactor Water Cleanup Sptem and transient perfermance meets design Performance r e q uir e me n'.s. (1) Purpose 14.2.12.2.20 Residual lleat Remosal Splem Performance To verify that reactor water cleanup system performance, in all modes of operation, is (1) Purpose in accordance with design requirements at rated reactor temperature and pressure cond. To verify that resideal heat removal sptem itions. performance is in accordarice with design for actual pLA operating conditions. (2) Prerequisites (2) Pretcquisites The preoperational testing is complete and plant management has reviewed the test pro-The preoperational testing is complete and cedure and has approved the initiation of plant management has reviewed the test pro-testing. For each scheduled testing itera. < cdure and has approved the initiation of tion the. plant shall be in the appropriate t e c in g. For each scheduled testing iter-operational configuration with the specified ation the plant shall be in the appropriate prerequisite testing cornplete. Instrumern operational configuration with all specified tica has been checked or calibrated a prerequitite testing complete. Instrumenta-appropriate. tion has been checked or calibrated as D appropriate. (3) Description n

AEWR nau m Standard Plant mn Startup phase testirg of the RWCU sptem is throttle pump discharge pressure in order to an extension of the preoperatior,al tests for simulate reactor pressure and the expected k rated temperature and pressure conditions. pipeline pressure drop. This testing is Splem parirreters will be monitored in the done to demonstrate general system sarious modes of operation at critical operability and to make most controller temperature, pressure and flow conditions, adjustments. Reacto' sessel injection tests will follow to complete the controller The perfermance of sptem beat exchangers and adjustments. Proper controller adjustment fdter/demineralizer units will be evaluated is verified by introducing small step at bot operating conditions. The ability of disturbances in speed and flow dernand and the splem to reject excess sessel insentory then demonstrating satisf actory system during plant beatup will be serified, Other response and stability. This will be done l sptem leatures Md be demonstrated as at both low RCIC pump flow (but abose [ 5hatl) appropriate. minimum turbine speed) and near rated RCIC pump flow conditions, and at reactor (4) Criteria pressures of 150 psig and rated, in order to d span the RCIC operating range. Splem performance should meet the specified design requirernents in all operating modes. After all controller and system adjustments have been made a defined set of demonstra-142.12222 RCIC Sptem Perfortnance tior.s will be performed with the final set-tings. This will include two consecutise (1) Purpose successful reactor vessel injections, by automatic initiation from the cold standby To serify proper operation of the RCIC sp. condition, to demonstrate sptem reliabil-tem oser its expected operating pressure and ity. Cold is defined as a minimum of 72 Dow ranges, and to demonstrate reliability hours without any kind of RCIC operation. ( in automuic starting from cold standby with Following these tests, sprem data will be the reactor at power. collected while operating in the full flow test mode to provide a benchmark fc,r compar-(2) Pierequisites ison wi h future surveillance tests. Addi-t tionally, a demonstration of extended oper-Tbc preoperational tests are complete and ation of up to two hours (or until the pump plant management has resiewed the test and turbine and their auxiliaries base sta-procedure and has approsed the initiation of bilized) of continuous operation at rated testing. For each scheduled testing itera. flow conditions will be performed. For all tion the plant shall be in the appropriate testing proper operation of the sprem and operational configuration with all specified related auxiliaries will be evaluated. prerequisite testing complete, All appli-cable instrumentation shall be checked or Additionally, proper funcioning of the RCIC calibrated as is appropriate. steamline isolation val +es will be verified at rated temperature and pressure and at (3) Description higher power levels if a;.propriate. This verification will inclu je proper valve The RCIC system will be tested in tv o ways, operation and acceptable cloture timing in through a full flow test line leading to the response to an isolation signal. Also, suppression pool and by flow injection sufficient operating data will be taken in l directly into the reactor vessel. The first order to verify proper setting of, or to set of tests will consist of manual and auto-adjust as necessary, the high RCIC steamline matic mode starts and steady state operation, flow trip setting of the leak detection and at 150 psig and near rated reactor pressure isolation system trip logic conditions, in the full flow test mode. q7 4 p During these tests an atternpt will be made to ) ~- l Also, any RCIC system testmg that was not performed during \\ Amedmem 18 / the preoperational test phase, due to the msufficiency of the 14 w temporary steam supply source utWzed will be completed as early in the program as is practicable. - ww ~~ /

ABWR n-Standard Plant PTV f} tendencies and should provide quick but 142.12.2.24 IIVAC Splem Performance d stable response. (1) purpose 14.2.12.2.:3 Plant Cooling /Ser3 ice Watrr Sptemm Performance To verify sarious HVAC systems performance for the loads present during reactor power (1) Purpose operation. To serify performance of the various plant (2) Prerequisites cooling /sersice water systems, including the reactor building cooling water system, the Tbc preoperational tests are complete and reactor service water system, tbc turbine plant management has reviewed the test pro. building cooling water sptem and the turbine cedure(s) and has approved the initiation of l service water sptem under expected reactor testing. For each sebeduled testing itera. power operation load conditions. tion, the plant shall be in the appropriate operational configuration with the soecified (2) Prerequisites prerequisite testing complete. All applicable instrumentation shall be checked The preoperational tests are complete and or calibrated as is appropriate. plant management has reviewed the test procedure and has apptraed the initiation of (3) Description testing. For each scheduled testing itera-tion, the plant shall be in the appropriate Power ascension phase testing of plant HVAC operational configuration with the specified systems is necessary only to the extent that prerequisite testing complete. All appli-fully loaded conditions could not be app-cable instrumentation shall be checked or roached during the preoperational phase. p calibt.ned as is appropriate. Pertinent paramete sk eH be monitt: J in f order to pr ' final verification of (3) Description Shall , er, flow balancing and cooler performance under near design or special Power ascension phase testi g of plant situation conditions, as is appropriate. cooling water systems is nec sary only to This w.ill include extrapolation sf results the extent that fully loaded c ditions could obtained under normal or test conditions as not be approachvi during th preoperational needed to demonstrate required performance l phne. Pertinent patameters be moni-at limiting or accident conditions. tored in order to provide a final verifica-tion of proper sptem flow balancing and heat (4) Criteria exchanger performance under near design or special conditions, as is appropriate. This System performance should be consistent with will include extrapolation of results design requirements. For systems that are obtained under normal or test conditions as taken credit for in the plant safety aceded to demonstrate required performance at analysis, performance shall meet the minimum limiting or accident conditions. requirements assumed in such analysis. (4) Criteria 14.2.12.2.25 Turblue Vahe Performance System performance should be consistent with (1) Purpose design requirements. For systems that are taken credit for in the plant safety analy. To demonstrate proper functioning of the sis, performance shall meet the minimum main turbine control, stop, and bypass requirements assumed in such analysis. valves during reactor power operation. r ib l Amendmem 18 14 MS I l l

l l l ABWR mn m Standard Plant pn 4 i steamlines downstream of the SRVs. Tailpipe The credible single f ailure or operator O sensors may include ternperature indications, error that has been indentified as resulting t ressure switches or acoustic monitors Down-in the largest feedwater temperature reduc-stream indications of SRV operation could be tion will be initiated at a significantly changes in such parameters as turbine sahe high power level, while considering the positions or generator output. Such changes esent analyzed and tbc predicted results. will aho be evaluated for anomalies which Core performance and overall plant respene rLay indicate a restriction er blockage in a will be observed in order to demonstrate particular SRV tailpipe by making sabe to preper integrated response and to compare N vahe comparirons. Tailpire backpressuret actual results with those predicted. This SM p A 14u aho be esaluated against any bounding comparison will take into account the dif-design assumptions. Additionally. during ap-ferences between actual initial conditions plicable plant tran*ient testing, where SRVs and observed results and the assumptious are expected to oprn, operability, opening used for the analytical predictions. setpoints. and reset pressures will be serified. (4) Criteria N) Criteria Resultant MCPR shall remain greater than the fuel thermal safety limit and measured There shall be a posithe indication of steam results shall compa,e conservathcly with diuhange during each manual sabe opening. design assumptions and predictions. The For automatic openings the relief setpoirts oserall plant rrspon.,e should be accoruing and rent pressures shall be within technical to design and testing specifications. specifi.ation limits. SRV open and close in-dications. including tailpipe sensors, should 14.2.12.2.29 feedwater Pump Trip function as designed. For manual openings the apparent steam flow through each SRV (1) Purpose O, should not sary significantly from the aser-age for all sabes. Tailpipe back pressures To demonstrate the ability of the plant to should be conmtent with design assumptions. respond to and survhe the loss of an ope-rating feedwater pump from near rated power 14.2.12.2.2M Lms of Fredwater lleating conditions. (1) Purp sse (2) Prerequisites To demonstrate proper integrated plant res-The preoperational tests are complete and ponse to a loss of feedwater heating esent plant management has reviewed the tesi pro-and to s erify the adequacy of the modeling cedure and has approved the initiation of and associated assumptions used for this t e stin g. The plant shall be in the trandent ir u.c plant licensing analysis. appropriate operational configuration with the specified prerequisite testing com-(2) Prerequisites plete. Applicable instrumentation shall be checked or calibrated as is appropriate. The pt: operational tests are complete and plant management has reviewed the test proce. (3) Description dure and has approsed the initiation of test-ing. The plant sball be in the appropriate From an initial reactor power level near operational configuration with the specified rated, one of the operatirsg feedwater pumps prerequisite testing complete. All appli-will be tripped and it will be demonstrated cable i strumentation shall be checked or that the overall plant response is such that cabbrated as is appropnate. a reactor trip is avoided. Specifically. it (q g 4*eks be serified that the ferdwater con-l (3) Deuription trol system is sufficiently responsive, in

IMNd more Standard Plant erv n (3) Description This test M be performed from a low Ow'd i e O i I ' O Ainendment 18 14:411 l

ABWR m u.. Standard Plant pix A o initial power level but from one that is suf-toom. Additionally, system

• md plant per-ficiently high such that a majority of plant form'ince shoula be consists < with design systems are in their normal configurations and testing specification requirements, for power operation. This test is as much a test of normal and emergency plant procedures 14 2.12 2.32 Loss of Turbine Generator and the ability of plant personnel to cartypdOITsite Power l

them out as it is a test of plant s) stems anQM equipment. Therefore, the test hv4d%e (1) Purpose performed using the minimum shift crew that would be asailable during an actual esent. To serify proper electrical equipment res. Additional qualified personnel will be avai-poose and reactor system transient perfor-labic in the control room to monitor the tro-mance during and subsequent to a turbine gress of the test and to re edablish control generator trip with coini. dent loss of all of the pl, int should an unsafe condition offsite power sources. desclop. These personnel will also perform predefined non safety related activities to (2) Prerequisites trotect plant equipment where such activities would not be requited during an actual emer. The preoperational tests are cotnplete and pency situation. The test will be initiated plant rnanagement bst re"iewed the test pro-b) simulating a control room esacuation and cedure and has approved the initiation of then tripping the reactor ty means outside of testing. The plant shall be in the appropri-the control room. Achiesement and mainte-ate operational configuration with all nance of the hot standby condition is then specified prerequisite testing complete. demonstrated through control of tessel pres. Applicable instrumentation shall be checked sure and water lesel. The ability to reach or calibrated as is appropriate. A suffi-celd shutdown is demonstrated by cooling the cient number of qualified personnel shall be O reactor down to where some form of residual available to handle the needs of this test U heat removal can be ar d is initiated by es. as well as those associated with normal tablishing a heat rejection path to the plant operation. vitimate heat sink, again by means entirely outside of the main control room. The cold (3) Description thutdown capability does not necessarily have to be demonstrated immediately following the This test eWd be performed at a relatne-l thutdown and hot standby demonstration as ly low power lesel early in the power ascen-long as the total integrated capability it, sien phase. but with the generator on line adequately demonstrated. Also, additional at greater than 10% load. The test will be personnel, oser and at.ove the minimum shift initiated in a way such that the turbine crew, may be uiiliced for the cold shutdown generator is tripped and the plant is portion of the test consistent with plant completely disconnected froin all offsite procedure and management's ability to assem-power sources. Tbc plant shall then be ble extra help at the plant site in emergency maintained isolated from offsite power for a situations. minimum of 30 minutes. During this time. appropriate parameters will be monitored in (4) Criteria order la verify the proper response of shh. plant systems and equipment, including the The remote shutdown test , as a rnini-proper switching of electrical equipment and mum, demonstrate the capability of plant per-the proper starting and sequencing of onsite sonnel, equipment, and procedures to initiate power sources and their respective loads, a reactor trip, to achieve and maintain hot standby conditions for at least 30 minutes, (4) Criteria and to initiate decay beat removal such that p coolant temperature is reduced by at least All safety related equipment and systems, t 500F, all from outside the main control and others judged to be important to safety i Arcandment 2 14 W

AOM UAn w. Stilpdard Plant r> ry n g for this esent, shall function a. designed in reactor trip Am4d also be rifie d. Owr. accordance with technical specifkation and speed of the main turbine M also be y safety analysis requitements. All other evaluated since the generator is unloaded sptems and equipment should perform censis-prior to complete shutoff of steam to the tent with applicable design and testing turbine. s p e cific ation s. For a turbine trip, the generator remains IJ.:.1:11.1 Turbine Trip and Grnerator loaded and there is no oserspeed. Hower.r, Load Pe,jection the dynamic revyonse of the reactor may be different if the steam shutoff ra'e is (1) Purpose different. If there is expected to be a significant difference, then it may be To serif > that the dynamic response of the necessary to perform a separate demonstra-reactor and applicab!t sptems and equipment tion and evaluation, similar to that is in acco, dance with design for pr ective discussed above, but initiated by a direct trips of the turbine and generator during trip of the main turbine. power operation. I turbint or generator trip should also be p) Prercquhites pe* formed 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 cap.tcity of the plant management has resiewed the test pro-bypass vah es. Reactor dynianic response is cedure and has arproved the initiation of not as important for this transient except testing. The plant shall 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 complett. All tion of proper integrated plant and system applicable instrumentation ihall be checked performance. p or calibrated as is appropriate. V (4) Criteria (3) Description The reacto. shall not scran during turbine from an initial power iesel near rated, the or generator trips initiated from power 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 plant response. The method for initiating direct scram trip on turbine stop salve l r*- should be chosen so that the turbine closure or control valve fast closure is .d to masimum oserspeed potential. e n a ble d. For high power turbine or l d. .t parameters such as sessel dome pres-generator trips, reactor dynamic response .d simulated fuel surface heat flux should be consis. tent with predictions monitored and compared with predic-based on expected system characteristics and i.cr., 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, surface heat flux. Safety related and main steam relief vahes, the reactor protec-essential equipment and systems shall tion sptem. and the feedwater and recircula-respond, as applicable, consistent with tion systems will also be demonstrated. The technical specification and safety analysis core flow coastdown characit:ristics should be require ments. Other plant systems and evaluated upon actuation of the recirculation equipment should perform in accordance with pump trip logic. The ability of the feed-the appro priate design and testing water system to control vessel lesel after a specifications. C lb Amedm.rt 11 14 M3

AI M mu Standard Plant pm 14.2.12.2.3J Reactor full isolation triate design and testing specifications. (1) Purpose 14.2.12 2.3! Off gas Splem To serify that the dynamic response of the (1) Furpose reactor and applicable systems and equipment is in accordance with design for a simulta-To scrify proper operation of the sarious creus full closure of all MSIVs from near components of the offgas system over tbc rated reactor power. expected operating range of the system. (2) Prere luisites (2) Prerequisites i The preoperational tests are complete and The preoperational tests base been coruple'ed plant management has reviswed the test proce. and plant management has reviewed the test dure and has apptosed the initiation of test-procedure and has approved the initiation of ing. Tbc plant shall be in the appropriate t e r, t i n g. For each scheduled testing operational configuration with all specified interation, the plant shall be in the prerequisite testing complete, All appli-appropriate operational configuration with I cable instrumentation shall be checked or the specified prerequisites testing l calibrated as is appropriate. complete. All applicable instrumentation shall be checked or calibrated as is i (3) Description appropriate. I A simultaneous full closure of all MSIVs will (3) Description be initiated from near rated power in order to serify proper reactor and integrated plant Proper operation of the offgas system will T response. Reactor dynamic response, as deter-be Cemonstrated by monitoring pertinent mined by such parameters as essel dome pres-parameters such as temperature, pressure, sure and simulated fuel surface heat flux, flow rate, humidity, hydrogen content, and will be compared with analytical predictions effluent radioactivity. Data hM be in order to verify the adequacy and conserva-collected at selected operating points sIcit f tism of the rnodels and assumptions used in that each critical component of the system 'g the plant safety and licensing analysis, is evaluated over its particular expec w Proper response of systems and equipment such operating range. Perfortsance hki >e as the MSlVs, SRVs, the reactor protection demonstrated for specific components such as system, and the feedwater and recirculation catalytic recombiners, and activated carbon systems will also be demonstrated. absorbers as well as the various beaters, coolers, dryers and filters. Also to be (4) Criteria evaluated are the piping, valving, instrumentation and control that comprise The reactor dynamic response should be con-the overall system. y l sistent with predictions based on expected system characteristics and shall be conser. (4) Criteria vative relative to safety analysis results based on design assumptions. Safety related lydrogen concentration and radioactivity and essential equipment and systems shall ru eIt'luents shall not exceed technical spond, as applicable, consistent with techni-specification limits. All applicable system cal specification and safety analysis require-and component parameters should be ments. Other plant systems and equipment consistent with design and testing should perform in accordance with the appro-specification requiremaats. y N Testing of the offgas system is also discussed in 113 9. j n s AmcMmem 1s 14 M4 l i

_ _ _.. _ _ _. _. _ _ _ __ __-._ _ =_._ _ _ _._. _ i l l O 14.2.12.2.36 Loose Parts Monitoring System Baseline Data (1 } Purpose To collect baseline data for the loose parts monitoring sy', tem 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 testirg. Tht, plant shall be in the appropriate operational configuration for the ccheduled te; ting. Applicable l instrumentation shall be checked or calibrated as is appropnate. -( 3 ) Description Loose parts monitoring system dato will be collected at appropriate power and tiow conditions to provide 6 baseline set of data indicative of normal plant operations. The daia rhtained will be used to help verity the adequbey of. or to facilitate needed changes to, initial atert level settings above normal levels. ( 4 ) Criteria { Sufficient baseline data shall be obtained so as to verify the adequacy of system alert level settings in accordance with design requirements, t 14.2.12.2.37 Concrete Penetration Temperature Surveys (1) Purpose To demonstrate the acceptability of concrete wall temperatures in the vicinity of selected high ten'perature penetrahans under norrnal plant operational conditions. (2) Pretequisites P The preoperational tests are complete and plant management has reviewed the test procedure and has approved the initiation of testing. The plant chall be in the appropr! ate operational configuration for the scheduled testing, Applicable instrumentation shall be installed and checked or cahbrated as is appropriate, i k O. l4.2 foi, I

~ -. -.. ~.. - -. - - - ~. - -.....~. - - - - -.- k 1 ( 3 ) Description Concrete temperature data will be collected, around selected high temperature penetrations, at various power level5 and system configurations in order to venty acceptable performance utider expected plJni operationan conditions. Penetrations and measurement locations selected for monitoring, as well as the test Conditions at which data is to be coll 6cted, shall be tufficiently comprehensive so as to include thr expected limiting thermal loading conditions on critical concrete waila and structures within the plant. ( 4 ) Criteria The temperature (s) cf the concrete at the monitored locations should be consistent with design predctior's and shall not exceed cesign basis tsquirements or assumoDons critical to associated design basis ana!yses. 14.2.12.2.38 Radioactive Waste Syt,tems Perfortnance ( 1 ) Purpose To demonstrate acceptable performance of gaseous and liquid radioactive waste processing, storage and release systems under normal plant operational O conditions. (2) Prerequisites The preoperational tests are complete and p! ant management has reviewed the I 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 checked or calibrated. Appropriate precautions shall be taken relative to activities conducted in thc 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, phase to demonstrate system operation is an accordance with design requirements. Operation and testing of liquid and gascous radioactive waste systems is discussed in detail in Sections 11.2 and 11.3, respectively. Testing specific to the main condenser offgas system is also ctiscussed deparately in subsection 14.2.12.2.35. O 14. 7. W 1 . ~ -.. -.

O (4) Oriteria Performance characteristics of the liquid and gaseous radioactive waste systems should be in accordance with the appropriate design and testing specifications, and as discussed in Sections 11.2 and 11.3, respectively. Handkng and release of radioactive wastes shall be in conformance with all applicable regulalions. 14.2.12.2.39 Steam and Power Conversion Systems Performance (1 ) Purpose Tc demonstrate acceptable performance of the various plant St9am driven auxiliaries and power conversion systems under expected operational cond'tions, particularly that equiptr.ent that could not be fully tested during the i preoperational phase due to inadequate steam flow conditions. i2) 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 g russary instrumentation shall be checked or calibrated. ( 3 ) Description Operation of steam driven plant auxiliatics and power conversion systems will be mcnitorec, and appropriate data collected, during the power ascension test phase to demonstrate system operation is in accordance with design requirsments. Systems to be monitored include the main turbine and generator and their auxiliaries, the feedwater heaters and moisture separator / reheaters, the main condenser and condenser evacuation system, and the main circulating water system Operation and testing of power conversion systems is discu; sed in detail in Chapter 10. The main turbine generator and related auxiliaries are discussed in section 10.2 and other power conversion equipment and systems are discussed in section 10.4. Testing specific to turbine valves is described in subsection 14.2.12.2.25 and plant transient testing involving the main turbine generator is described in subsection 14.2.12.2.33. ( 4 ) Criteria-Performance characteristics of the various systems monitored should be in accordance with the appropriate design and testing specifications, and as discussed in Sections 10.2 and 10.4. O W.2.-W,3

l ABWR nm,ws Standard Plant pix n 14.2.13 Interfaces The preceding discussion of preoperational ar J Startup tests were limited to those systems 1nd components within, or directly related to, ti:e AEWR Standard Plact Other testing, with respect to site specific aspects of the plant will be necessary to satisfy certain ABWR in-terface requirements. Testing of such systems and components should be adequate to demonstrate conformance to such requirements as defined throughout the specific chapters of the RSAR. Delow are systems that may requite such trst ng: (1) electrical switch >ard and equipment; j (2) the site securit) plan; (3) personnel monitors and radiation surse) instruments; and (4) l'i automatic dispatcher con ol system (if applicable). / Also to be sup{ plied by the a;plicant referencing the ABWR design is the startup administration manual described in Section O 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 next te. ting plateau. 9< [z w a c m,~um.o A Nom %.] j O AmeM~ent 18 14 M s

i 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 exempt from operating license conditions requiring NRC prior approval for major test changes. Such tests are those which are not essential to the demonstration of conformance with design requirements for structures, systems, components, and design features which meet any of the following criteria:

a. - Those that will be used for safe shutdown and cooldown of the reactor under normal plant conditions and for maintaining the reactor in a safe condition for an extended shutdown penod; b.

Those that will be used for safe shutdown and cootdown of the reactor under transient (infrequent or moderately frequent events) conditions and postulated accident conditions and for maintaining the reactor in a safe condition for an extended shutdown period following such conditions; c. Those that will be used for establishing conformance with safety limits or limiting conditions for operation that will be included in the facility technical specifications; i d. Those that are classified as engineered safety features or will be used to support or ensure the operation of engineered safety features within design limits; e. Those that are assumed to function or for which credit is taken in the accident analysis for the facility, as described in ths FSAR; or O f. Those that will be used to process, store, control, or limit the reitiase of radioactive materials. Of the fests described in Section 14.2,12.2 for the ABWR Standard Plant the following tests, or designated portions thereof, meet the above criteria:

1) 14.2.12.2.13 Recirculation Flow Controt ercept for those features intended to limit maximum core flow; 2 ) 14.2.12,2.21 Reactor Water Cleanup System Performance;

3) 14.2.12.2.23 Plant Cooling / Service Water System Performance those portions pertaming 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 system;

5) 14.2.12.2.29-Feedwater Pump Trip; and

6) 14.2.12.2.39 Steam and Power Conversion Systems Performance.

O + .W.2-d.l b. .__~,_..._.-__._-_.._,,._..2. ..---.---u..

I ll. l' m 1 e g a p m P a w s ., w i e r p b ( g n w e n o w I m e, P . 's v ,.R n 5 o g 4 3n h f g 4 s >4 _ m H 3 ,w g p r = I r o. e g n .t e p p . d. u N v a. e ,f 4 e = , 1, = r en e Lf e, , t ea m e r a u n m h e a w . 4 r ie h u m.m i e r i f r. t e + m w w w m a.._hs m P w c i r 4 a h 3 ,. d e s g 4 e v d. m =. M Im 1 h. i s.p a A . o

• m

= a X m s W 4t t P I i R jkl!i{ l. l T M A t' V V V / / 'c i M f l ,l, e I t id M I M V V V V / / t o I e r l I e N A l .{ w l o O l' V / V V 'e P 1 G G w I f N l o M I' 1 L S N 1 / / V / V / V i 1 e s e I A I !V P l fil l R L E W / V / V V V / V V / e t t V l:l VI +f:l l gi l-O P pu ta e s s t t m H n n r T e e u a S m g m e t k-a E r i r s g o n e n t c c s r u n u a l m n m N m s o s t N a r a e g e o e m e m t r = O M n n m e m w M f s r U I im u e D a t a l' e

• r tn S

l k c e r m m H N. k i g n f l m u m m g g F e r W A e g o m m m m c a r s n e r f r m m y m m e u D e u M u M

• c ts t

g a r r a r r y o s h F e e n r r A m u o s a T T I u a. m. le e o e e e Dt n m m / a u e m m fr r a g m m R R d e a P ta u g S-k t a u e i M r a t / f r. n v M E a t a l as o 2 O e S d ta p e ia d n V m S i d r s W R r s d r o r w a a A m e-e n t T e 1 t. y e c se N N n R e v l u V a i l t t g g O e h n e w ic n g R - r M S -r e r S o r F n 4 l' m n l C m h l' G n l im - S S s rh m a a s o e r s y i i 1 t a p e d m m y di m i i e a a a h a re b n se l O O R u a ll m lA d h e n v r a t h a l i l e C t e n m t t e S S t O m r e e t e t m u r u = a lb e S h S S d r l C T M a h a u i r= - F F l I V T C R F h M O l -x fe e&.& !1!tllllllIf' tl ff l[ llf ll [ijf f il ll}j' l ,l 1,i

i i!f' ll-.L ! i;ft[ f [r [ [,' l Ir l, l ([l. [p[r L[t}' t;! t!; (!!!! 2 e g t. m h a P w u 'm U 1 I w m ~ T o f n 4 t s i w i e 8' m1 e o 1

• i1 l

wn l P r R M a l e h t g S e an H t op n m en. m E e = I w s P O i n t. e H N h r, h f'c e a v r en v r .i s s n. t =. w' s n t m ,n a = e guw .r. r ~ ea. eu h e d 1, 8 t w n" I dt P r = m i P r o i I v at nn a " u d st '.t M 8P a.p 4 4 v n dy X N fmf On ^ t 3' r = a I P R l t T M A P V V V V V V V V V v V V V V I M 1 U l l l is A P E V V V V V V V V V V V V V t 1 T T 5 re W A. w f I K l' P o V V 'e V V V V V V 'e V V V V P S i G N w N o l '} E I I VV V V / V V V V V V V V / V L C I 1 1 S S = 1 A E P l l I R V L EW U V / V O l l l.lg l l ] P pu t ta ne e m H k r T c e t r ) a t e S n u n h d lce E a a w C n u s e t m e n e n l s s e n e u e n o M N e g m g m n e N n o it r a a m e e u r c = f O w e p e s R r e r r s r r t e s s r r n s U u u a u t e g I t f g o ta a M m n n e S P p o s e f e n O H o R t n i r e e N n p y p / O P im o e / t m e r r s n m n E ie s s a n m g s p M t e o n n e e C r u M e i n m s R R R e e ir a s e w n a s I o u m r t l t S y / s e d u e a S / / / m ts A n n n s r r n s a E ir a a a ig S i c u c T r o e a n bi le n y o g o o o t r i M e o r t o F n n I b t V R n i u i r n r r M p t t r a r h n n n lA e o P S P l t s s s e a o t W to r r r e l 1 t o C p n o e a s b b b u M n A u r o I i r a s s e t t R n e 2 O i h h i m p o i n n e C W w a a r V n la e n m d C n a a l a i t t o l r S n e s u a R r u o p 4 P C C C t n ) n s e b t M r r o k o o H e n e u r c e m y r t t I' o a Vi y i / f I 1 M M M S C i d p s I o M e r c c e p W t W P a a a r l n n r p a O le o N R R P ss p u i3 n e u s se ic a o u c e e o m u R P. P e r r t I ) = N A R e i R R C e S A T 1 c b i S S ~ a t I I r t t o V t s a r r a y y e T N P C N S S R O e v.eP

• t j

1l ,{ i

>lil il

.j lj

F 3 e t g e t w a P r p y ma et whh. ~w r e. .a 1 p w c t re as o pm e e P u. al a r== h s i g f w = ie vr at H t S e t r =

• h t

r dt t t a P o s e a we N be e H r eb a s r ah b e f O s l c a,n pe e a hw w e m r h m. h m. e tms w w.. n o x w lee P mte d w d o d e. e t n n i i M s

• v yaw

= a X f t As Mir IR P lg T M l' M V V V V / V / V V V V V _/ l I P. I T L l l l S A P E T M V V V V V / V V V T I re N A OO f l l l w I o P I'. V V V V V V V P S C. 1 N w N l l l f l o EC U L l V V V V V V V / i l S S = I A F R T l l l P f V t E O VO l ll P pu ta n m n e o e o e H I' t i u e n m i t a o a a a a r S m m m m u m e r r r a a r F f r if m i f d i n o u T m m n r o o m N re N G G C f r r e P = e O / t I t / / e S n n n l P e m m U t t e a c o D a r n m e n e m e te g H e e e N l ts tm m te = tn a m e m m m w s s t a a o o S lm s m r y E o t f a o C u u u Gd r l i e S m o m m la o t j j f t S m c d s d u r e r r f e C g f r P v A i h n o i P t t e o u o o l i l C A A A n n o f f f R a S i e r e n e l' e P x. s m g t r i r o m m x l e r w m o m l e m / n l P k. l e r a s m P u T. o e r ts t e p e u o t e R ts R G s 1 r m t u u m e M l t t t c te f ts y tu m v r m e a f s n s S' i t 2 O n S o S m S y y t y t l i S u R S u m S I s w n s a a w n V t r p u e S r l t d o r o G l m u co 4 P o l C c s t t I e l o o S r a e o e R y O y m y l p tu O 1 I t d i p te d e r d p lu m te t e a r r r d u t t t r a a a i S a t a a o P m s a n r n A n s t u w te a r u p le t tr I P d S M n w o m o n c u h = c a e i o l S S i, G C s C n t r t b r S R m m l e c e 1 i a a V a e r M R O T R E P I' R /I ~c lhE".4 l 1 ,i '* ,1

l' 1;lllI l g 4 _ e . n.- e . r n g s a P P . p 1 'm n x r. u 'e 4 w n o e w s, P s. r t h r m, I 4 k l S i. u, r g c. es u. s i t l p m. r o s = 1 e 8 o. s O. tp P( r' 1 m O n' N o r t. r a. I p u I 6 n. c u r t s t e a .c w i e i. p l s) i I. al r s t< s ec tp 3 ra n a r en r r s e = pw te n sp r r e. t = e g e w o. tei e n o o n I m. i i it a e P s s n s a t e n s t. n w p ~ g s 4 i, i g

r h

b. ie g l t . t n M rl m t h n, I. mp ir o s 'e = "e p m IX h R I In. t P h 4I r t t je Ig l f T [ M A 1' V / V v / / v 1 M e I T U S A l' E E / V v / c M T I r l f e N A w O l' l. / V ~~ / / / V v P 1 I o S G I N w N I l o EC U t I / / V / v / v / "r / / / V I I S S = I A F R T P l V L EW o O f P I c p r u u a 'a e m e i m o r l r fr t r a a s m e k E P r I' o g cu m m N fr N e is r m o c s s P O m n. i g 2 = y I' g t m S ta te m i r H u n a U IS e c a / m m c a s I r N e c r e i u n t r E y n e-ta p s e e c r I c u ~ t e n p s c M e s S a O m n s / c V W O m C t n e S p m a r r a o e n r a u a i m s m lC u F in m u s t c r it r u g A u r m r ia o n s s S e a r c. f s e n r s e s w e s r o r o i r e e n m o e r k c V o e R a r e r P n o p r c p r 1 v e le f f l f P e P e P e n 5 C c l E P j l a re r iu S O P O P p s C e m a 1 W e R M e n V O s r o Q / e a P o e la e m n a e r t r l t t 2 e u y f m ta v r a ) t g a o l r V t u m l m i. m c a d n 4 N t S r r e e o h S tr t m la o u r u n a u I a e l S a o e ts R a e f l W P R C n y i s i V h o di m pe 1 y t o S ly w y r r a e D S m g n C m S l i f d n e t y h / n r v e P h e r o O a e o i i n c v o ie f C tr f b V n ir P d tu a n S O A S O e t n / O r b I t lb t n = i A S I F I I i c V I I t I a l a e C a V u S V r R l M S O T R R P I I I 14 g _ !l ll!lll!I fll!lli t l}ll1Iil l l1f l( l iff lili 1

ll'j l'l I1 5 ega P r eeP t h i t g m. H sE = c. g t P o H N b t w t r s e r t a e w = w -p l u r. ut hi bt e e e r n t r w c m, t t es t t i e o e r M te P T e f r T. W d c r f r a A a W t t'w e w e 1 i M t n t n X s A A A A A A s t t i s = I P R (f l l l T l l l l M A P v v / V / v / / v V v I M I T U l l l j S 3 P V V v V v V V E 1 1 T I r N S e lf l:l l w O P P o V V V v v V v P G G I w t N l o E 1 i L C i 1 S N v v V 1 = 1 A l l-I R ~ P 1 E W L W ( O l l l l l P ou ta r a e t e n. e a H m w D y o m r m a I t S w P a e e i x c e e m m R e y a l a k a r. l m lc I t r p T u r f C w a s o I J m N tn f t a O o f. r t a s e I r = s P o n a f o l S C u i p m U I t r y m n c r H r N e o B u c e is l' a r E g h r ta i p m y t a o n n s S t C p p m r t r a S u i e a c h iug i t g m n e r a d rc n t e A r ip T i n e wi R m r r s s l r o E t r v T p u e C d ta e R u f o m a r n t S le I m p O C d r E i W m P ip ip r t I t P m in i s n c s e p u c n u p 1 T m m x r I r t o s a r r a v r a e i 2 O w u r 1 e r t I I R f b p y T e l m T 1 P o M w V P m e f 4 P P P I r i c c w l is c v s d n r y r r f t l R R e n T R n o u m t u p r a T a P F y a a R F e a r = c d b l r S C P a u e o w n u r i C f le o w k o n a r lu t a r o s b u t c n w h t m e w n = n i O r s s t T F c g u I 1 t ~ u r a m o I a o e e h u e 0 e n vi V T R 0 P O T F R S I I I I 2h 7. !l I l l l l!lt f(ljf lIlIllll; lL 1l.

j Figure 14.2 1 Power Flow Operating Map and Testing Plateau Definitions i 7 l l l I l l 1 1 1 1"' i vi i rran, enue serin O Natt.n At Cinuf t At 80N O, T) tio j g { If, tocoows n. ms uni e ,,o IE ion a tow. iis i onA, ..llik ..a c$*}'"~ a im m i o.,=,- g , gipif = ei nous noo unt 3 (' f / 9gg .w i ro c en i me r.n 1 r/ h l -- f' O 4:lli E po e riei..u . n f M:dd a l i il g ziu s /, si (y n"1til f ro i,U,**hi, sie Au $rcanaton vuit t vcicat in r,i A H l { sp i 1 -- I / I I i i t I 1 i O o o ,o o, .,o .o so eo ,o .,o i. i o, in Pf nCE NT CORf ILCW lastina Plateau Descrint!cn (1). Open Vessel (OV) With the RPV head removed, from initiation of fuelloading to cold conditions with a fully loaded core Nuclear Heat Up (HU) During nuclear. heat up, from ambient conditions and 0 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 pumps (RIPS) within 10% of minimum speed Mid Power (MP) Between approximately the 50% and 75% power rod lines, with the RIPS operating between minimum and rated speeds, with the lower power corner within the capacity of the bypass valves. High Power (HP) Along and just below (+0 5%) the 100%' power rod line, from minimum RIP speed to rated core flow F (1) Descriptions of testing plateaus are offered for illustrative purposes and general guidance only, as some tests are intended to be conducted outside the general testing plateaus described. Neither tne above descriptions, nor the corresponding boundary lines on the power flow map, are meant to be absolute timits, Any operating limits will be specified in the plant license iny other O testing restrictions will be specified either within the plant administrative procedures covering the power ascension test program or within the individual test proc 9 dure for a given test. I. i l (4.1 - (;4 l ~

u AIMR utomar Standard Plant RKil RESPONSE 430Js The plant protection signals that automatically isolate the secondary containment and activate the SGTS are: !1i Jecondary containment high radiation sipal. (. Refueling floor high radiation sipal. 1 (3) Drywell pressure high sipal. Reactor water level low sipal. dary containment HVAC supply / exhaust fans stop, Ne secondary contaiorent is accomplished by c!csure of the secondary con'ainment e .ust line ducts which pass through the secondary containment boundary. The HVAC e ceasist cf two valves in series in each of the supply / exhaust lines. These valves w t are t . A ncrmally-open, fail closed butterfly vales. Futhe - ss are prosided in Subsection 6.2J,9.4.5.1 and Section 6.5 OUE! i ION 430.32 .Id..ntify and tabulaie by size, piping which is not provided with isolation features. Provide an ar.alycis to demonstrate the capability of the Standby Gas Treatment System to maintain the design nc-em guive pressure following a design basis accident with all non isolated lines open and the event of ( the worst sing!c failure of a secondary containment isolation valve to close. (6.2) RESPONSE 43032 ub is e.w el ej,wv4m 42 s dseekon G. S. t. 3. ) Res p om e 4c,4b s s b b s = ch, a dedin ;.p=.:c :.mc.d=enh -Reverne4edhisteesl ion + be- . 'G.5 5.L. om d ^ c. w QUESTION 43033 Discuss the design provisions that prevent primary containment leakage from bypassing the secondary containr ent standby gas treatment system and escaping directly to the environ: +nt. Include a tabulation of potential bypass leakage paths, including the types of information indicated in Table 618 of Regulatory Guide 1.70, Revisiou 3. Provide an evaluation of potential bypass leakage paths considering equipment design limitation and test seroitivities. Specify and justify the maximum allowable fraction of primary containment leakage that may bypass the secondary containment structure. The guidelines of BTP 6-3 should be addressed in considering potential bypass leakage paths. (6.2) MSPONSE 43033 The secondary containment compleely surrounds the primary containment except it the basemat. In addition the lower third of the secorsary containment is surrounded by soil, thereby reducmg leakage paths. No measurable leakage is expected t': rough its walls except at penetrations. The secondary containment will be maintained at subatmospheric conditions to prevent leakage from bypassing the l seconJary containment. Only valve leakage through process piping can bypaz.s the secondary containoent. This leakage will be tuonitored via ti.e containment leakage test type C on the octboard l ) containment isolation valves, The secondary containment leak rate calculation is provided in the v' response to Question 430.52c. Amendment 12 lLe

ABWR m,im, Standard Plant uva 0 AC ATMOSPHERIC CONTROL ^U lO lA INSTRUMENT AIR f 's$ SA SERVICE AIR )

1. "O HPIN HIGH PRESSURE k@

NITROGEN AO 3 T31 F041 l l l X-BO T31 F002 T31}O25 HVAC" ' Ac PRIMARY b # CONTAINMENT AO g l l l X-240 HVAc i T31 F001 T31 F003 A Q}f: N2 BOTTLES DIV. i HPIN rs m u MSRVs L ;;l [2[ X-71A M P54-FOO3A P54 F007A ~; P54-F00BA v U MO c-g AC 3 4 HPIN lMo{ 754-F012A AO M X-72 1Y -~ N T31 F042 P54 F203 P54 F200 j; pSSF2LB L o-n MO ?- O lMOl P3 F0128 h AC P54 F0088 g [T[ X-71B M P54 F003B P54 F0078 MSRVs v N2 BOTTLES f DIV.2 HPIN g D MSIVs pga.F216 ( M N d x-70 N ((h\\ _PS2 F277 ) PS2 F270 PS2 F271 PS2 2276 r. HPIN +4-I A hj Wgc ->- AC bJ VACUUM h ~~ BREAKERS )2[ bl IA PS2 F257 PS2 F258 f W SA O d IA Sh ria 4 - > TIP l >;4 N2 PURGE O St. ( Figure 20,3 - 55 COMPRESSED G A!:, SYSTEMS INTERCONNECTIONS l (Response tu Question 430.217) 20 3 354 30 Amendment 16}}