ML20059B823

Rev C to Passive Containment Cooling Sys

ML20059B823
Person / Time
Site:	05200004
Issue date:	10/16/1991
From:	Wilhelmi F GENERAL ELECTRIC CO.
To:
Shared Package
ML20059B690	List: ML20059B687 ML20059B717 ML20059B739 ML20059B788 ML20059B823 ML20059B834 ML20059B946 ML20059B967 ML20059B981 ML20059B993
References
25A5020, NUDOCS 9310290108
Download: ML20059B823 (23)

Text

-

GE Nuclear Energy 2sAso20 su no. ,

REV C '

RD1SION STATUS SHEET DOCUMINI Til1Ji PASSIVE CONTAINMENT COOLING SYSTEM  !

1 LTD11ND 011 DESCRIl710N OF GROUPS TYPE: DESIGN SPECIFICAT10N -

INF: SBWR  ;

MPLITEM No: T15-4010 REVISIONS l C-PREl,IMINARY ISSUE

^ DMH5088 10-16-91  ;

B FE WILHliLM1 11-12-91 GAD -

DMH5361 CKD BY:  :

FE WILilELMI FE COOKE C d[ h.M1 p t.g 0 1 W g i

781KLB DMil6113 '!

~i CKD BY: ~

Dfa / L #8 FE NILI El.M1 FE COOKE C&& "

l

.j i

PRINTS TO MADEBY APPROVALS GENER AL ELIClRIC COMPANY 10-16-91 175 CURTNER AVENUE FE WILHEt,Mi 62491 FE COOKE/M DRUZZONE SAN mSE CA 95175 CitKO DY JSSUED FE WILHELMI 10 16-91 0" " #

GA DAYI.lS 10-16-91 ,

I hM ,

i  !

__. - ~ ~

9310290108 93101904 Di PDR ADOCK 052 ij i

a::

eu!

GENuclearEnergy &j 25A5020 rmo. 2 2r ncy C Y

.[$]

a TABI,E OF CONTENTS fi L:'

=zu Page: .

. .m. 2 .

1. SCOPE 4 -

1.1 Purpose 4 1.2 Use 4-

2. APPLICAlli,E DOCUMENTS 4-2.1 Supporting and Supplemental Documents 4 2.2 Codes and Standards 5 --

2.3 I2ws and Regulations .5 - '

3. DESIGN DESCR11' TION 6-3.1 Surnmary Dextiption 6 S.2 Detailed System Description 6 ,

3.3 System Boundaries 8 3.4 System Operation 8 3.4.1 Normal Plani Operation B 3.4.2 Plant Shutdown Operation 8' 3.4.3 Passive Containment Cooling Operation R -i 3.5 System Interfaces 9 '

S.5.1 Gravity Driven Cooling System (GDCS) (E50) 9 t 3.5.2 Dr)well Gas Recirculation System (DGRS) T55) 9 t 3.5.3 Fuel and Auxiliary Pools Cooling System (FAPCS) (C21) 9 3.5.4 Make-up Water System (MWS) (P10) 9 3.5.5 Isolation Condenser System (ICS) (1132) 9 3.5.6 Containment System (CS) (TIO) 9 .

S6 Instrumentation and Control 9

4. FUNCTIONS AND REQUIREMENTS 10~

4.1 Functions 10 ,

4.2 General System-level Requirements ' 10 4.2.1 Performance Requirements 10 ,

4.2.2 Configuration and Arrangement 11 -

4.2.3 Safety 12 4.2.4 Design Life 13 4.2.5 System Interfaces _

13 .

4.2.6 Instrumentation and Control 13 4.2.7 Availability 13 4.2.8 Environment 14 1 4.2.9 Main. nce 14 4.2.10 Suncihance Testing and In-Scrvice Inspection 14  ;

4.3 Specific Requirem ta for Componena .15-

~

4.3.1 Passive Containment Cooling Condenser 15 ,

4.3.2 IC/PCC Pool

15-wro m po tw; l

l

.- _ l h

l M me o p-.aw -

w _ - - + . - - - - - - - --

GE Nuclear Energy Q,- 25A5020 anc. S ncy C TAllLE OF CONTENTS Page 4.4 Quality Assurance 16~

4.4.1 General 16 4.4.2 Tests and Examination 16' APPENI)1X 10 SWTEh! TECHNICAI, SPECIFICATIONS 22 e

i t

I t

i n

NC0E7PEV4M)

'h - ._

GE Nucicar Energy

- 25A5020 sm 4 ntv C

1. SCOPF, 1.1 Putpmst. This speciGcation de Gnes the requirements for the design, performance, conGguration,and testing for the Panive Containment Cooling System (T15). It also dennes the interface requirements with other systemsin the complete nuclear system and with the balance of plan t.

l.2 l!g. The use of this design speciGration is applicahic to the SimpliGcd Boiling Water Reactor (SilWR) Project only.

2. APPL.lCABLE DOCUMENTS 2.1 Supporting and Supplemental Documents. The following documents form a part of this speciGcation.

2.1.1 Suppordng Documents.

MPL NO.

a. Passisc Containment Cooling System P&lD (107E5160) T15-1010 (Ansaldo document number: SilW5280DNJXN014001)

b. Pessive containment Cooling System Process Diagram (107E6072) T15-1020 (Ansaldo document number: SBW5280DNJXN015001) 2.1.2. Egpplemental Documents 2.1.2.1 Documents under the following identities are to be used in conjunction with this speciGcation:

MPL NO.  :

1

a. Isolation Condenser System Design SpeciGcation (25A5013) B32-1010 l (Ansaldo document number: SBW5280SNPXN002000) l

b. Isolation Condenser System P&ID (107E5154) B32-1010 (Ansaldo document numbcr: SBW5280DNJXNO12001/2)

c. Gravity Driven Cooling System DS E50-4010 (Ansaldo document number: S15W5240SNPXN001000)

d. Fucl and Auxiliary l'ools Cooling System Design SpeciGcation (23A6921) G21-4010 j

e. Fuel and Auxiliary Pools Cooling System P&ID (103E15,81) G21-1010 ed O E 7 Fiv 4 9a; ,

.n.

',.1 .,'1 ! .} . . .cf '(.'. .{ l , 7

• I iD'. . j '.'. '

. / j l .. .. ' . ...

.[ ' . . . [ ,, , ;' ' 'J

's,' . -

)

GENuclearEnergy

- 25A5020 rd 5 ncv C

f. Make-up Water System Design Spec. PI(M010

g. Systen Design Specification Standard - (23A6857) A00-3050

h. Pressure Integrity of Nuclear Components A11-2029 ,

i. Drywell Gas Recirculation System P&lD .TS M 010

j. Reliability, Availability & Maintainability (RAM) Criteria (23A6899) A18-1020 k Equipment Environmental Data . A l 1-2020

1. Source Terms A11-2052 2.1.2.2 The following documents are to be used in conjunction with this speci0 cation to the extent specified herein:

a. Composite Design Specification (2SA6723) All-5299

b. Generic Operations and Maintenance Requirements (2SA6882) A80-8010 Specincation

c. Composite Dcsign Specification Data Sheet (23A6723AC) A11-5299

d. Mechanical Equipment Separation for Engineered (23A6932) Al1-2018 Safety Feature (ESF) Systems 2.2 Codes and Sta.n_Ilards. The following codes and standards form a part of this speciGcation to -

the extent specified hercin. The applicahic code and standard edition dates together with exceptions to code and standard requirements are defined in reference 2.1.2.2.c.

2.2.1 American Sorkb ofMerbankalEnghtern.(ASME) Boiler and Pressure Vesgl Cody

a. Section Ill: Nuclear Power Plant Components

b. Section XI: Rules for Inservice Inspection of Nuclear Power Plant 2.2.2 Institute of Eltriticaland_Elegir.onic Engineers (IEEE). None speciGed as part of this ,

spccincation, 2.31.aws and Reculations The following laws and regulations form part of this speciGcation to the extent specined herein:  ;

2.3.1 ERG.Erguliulon3. Nonc specined as part of this specification. ,

2.S.2 Regulatory Guides. None specified as part of this speci6 cation.

. NIO 907 $[ V 4%B.-

...s.. , , ,

GENuclear Energy

&) 25A5020 ntv C m.). 6

3. DESIGN DFSCRil" TION 3.1 Summary Descrip1!2n. The Passive Containment Cooling System (PCCS-Tl5) basically cnnsist.s of three totally independent 1 oops, each containing a heat exchanger that condenses steam on tube side and transfers heat to water in a large pool which is vented to atmosphere.

The PCCS operales by natural circulation. Its operation is initiated by the difference in pressure between the dr)well and the wetwell, which are parts of the SIMR pressure suppression type con tainment system.

The condenscr, which in open to the primary containment, can receive a steam-gas mixture supply directly from the drywell. The condensed steam is drained to the GDCS (Grasity Driven Cooling System) pool and the gas is vented through the line which is submerged in the pressure suppression pool.

A DGRS (Drywell Gas Recirculation System) suction line is connected to the PCCS vent line to recirculate reactor containment gas and steam, during post-LOCA recovery, increasing PCCS e fIcc t heness.

1 he PCC loop does not base valves which must operate to allow the PCC to function, so the system is always in ' ready standhy" 3.2 Dclailg1LSystem Dqst.iption. The Passive Containment Cooling System (PCCS) maintains the Containment within its pressure limits for design basis accidents. The system is designed as a pacive system with no components that must actively function, and it is also designed for conditions that equal or exceed the upper limits of containment reference sescre accident capability.

1 he PCCS consists of thrce, low-pressure, totally independent loops, each containing a sicam condenser (Passive Containment Cooling Condenser) as shown on the PCCS P&lD (ref. paragraph 2.1.1.a). The PCCS P&TD defines piping system interconnections, special arrangement requiren ents and system input sources and outputs.

Each of the three PCC Condenscrs is designed for 10 MWt capacity and is made of two identical rnodules. The three condensers limit containment pressure to less than its design pressure for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after a LOCA.

The units are located in a large water pool positioned above, and outside, the SBWR primary containment (drywc!!).

The PCC Condenser is configured as shown on the diagram (reference Paragraph 2.1.1.a)as follows:

A central steam supply pipe is provided which is open to the containment at its lower end, and it feeds two horizontal headers through two branch pipes at its uppen end. Steam is condensed inside ser tical tubes and the condensate is collected in two lower headers M O F 7 (f4v 4%43 i

,. ., '. e..

e ..a

\' s " . ,

l

i GE Nuclear Energy l 25A5020 s>oo. 7 ncy C -

- i The sent and the drain lines from cach lower header are routed to the drywell through a single l containment penetration as shown on the diagram (reference Paragraph 2.1.1.a). j The condensate drains into an anular duct arounti the vent pipe and then unws in a line which c.onnects to a large common drain line which also receives Dow from the other header, The PCCS loops receive 'a steatu-gas mixture supply directly from the drywell. The PCCS loops are initially driven by the pressure difference created between the containment drywell and the suppression pool during a LOCA and then by gravity drainage of steam condensed in the tubes, so they require no sensing, control, logic or power-actuated devices to function.

A branch line from the PCCS vent line is connected to the DGRS which can be used to recirculate the drywell gas by drawing the gas through the PCCS and blowing it back into the dr>well during post accident recovery operations.

The DGRS pipeline extension from the PCC vent line contains two locked closed shut off vah es in series plus one check valve (as shown in ref. document 2.1.2.1.i) to assurc that drywc11 gas docs not bypass the PCCS during a LOCA.

The PCCS loops and the DGRS loops are an extension of the safety-related containment and do not have containment isolation valves.

Spectacic flange 4 are included in the drain line and in the vent line to conduct post maintenance l leakage tests separately from Type A containmentleakage tests.

l.ocated on the drain line, downstream of the spectacle Danges, two smalllines are provided: they supply condensate to the vacuum breakers water seal. The two lines feed different vacuum breakers and each vacuum breater recch'es condensate from two separate PCCS units.

1 ocated on the drain line and submerged in the GDCS pool,just upstream of the discharge point,-

is a loop scah it prevents back flow of steam and gas mixture from the drywell to the vent line, which ,

would otherwise short circuit the Dow through the PCC heat exchanger to the vent line. It also provides long ter m operational assurance that the PCC condenser is fed via the supplyline.

Each PCC condenser is located in a subcompartment of the IC/PCC pool, and all pool subcompartmentS communicate at their lower ends to enable full utilization of the collecthe water inventory, independent of the operational status of any given IC/PCC subloop. ,

A valve is prosided at the bottom of each PCC subcompartment that can be closed so the subcompartment can be emptied of water to allow PCC condenser maintenance.  !

Pool water can heat up to about 10l*C (214*F); steam formed, being nonradioactive and having a  ;

slight positive pressure relathe to station ambient, vents from the steam space above each PCC +

Condenser segment where it is released to the atmosphere through large<liameter discharge vents.

A moisture separator is installed at the entrance to the discharge vent lines to preclude excesshe moisture cariyoser and loss ofIC/PCC pool water. y mm us k

l

,.,,y,,. _ ,,. -,--r --r,- -- ,,- -

GE NuclearEnergy -

- - 25A5020 sm 8 l nu C i IC/PCC pool make-up clean water supply for repicnishing levelis provided from *Make-up Water l Sys tem" (r ef. 2.1.2.1.1).

Ievel con trol is accomplished by using an air-operated valve in the make-up water supply line. The valve opening / closing is contro, led by w:.ter level signal cent by a level transmitter sensmg water Icvel in the IC/PCC pool.

Cooling / clean-up of IC/PCC pool water is performed by " Fuel and Auxiliary Pools Cooling System" (rcf. 2.1.2.1.d and c). Several suction lines, at different locations, draw water from the sides of the IC/PCC pool at an elevation above the minimum water level that is required to be maintained during normal plant operation.The water is cooled / cleaned and is returned back to the pool, I I

On the return line for IC/PCC pool water recirculation flow, there is also a post-LOCA pool water l make-up connection.  ;

l 3.3 Sn!rm Iloundaries 3.3.1 Includes. The Passive Containtnent Cooling System design scope includes the following:

a. PCC pool subcompartment interconnections (pipes and valves).

3.3.21%cludn The Passive Containment Cooling System design scope excludes the following;

a. IC/PCC Pool.

b. Poo1 in strumen tation.

l

e. 0;itside vent to atmosphere. j

d. Steam dryersin the pool vent flow path.

c. Pool make-up and water recirculation systems.  !

SA Svstem Op.nrarion.

3A.1 Entmal Plant Op_cration. During normal plant operation, the PCC suhloop is in

• ready standlay".

SA.2 &nt Shutdown Opr.ra_tian. During refueling, the PCC heat exchanger maintenance can be performed, af ter closing the locked open valve which connects the PCC pool subcompartment to the common parts of the IC/PCC pool, and drying the individual partitioned PCC pool.

SA.3 Pauive Containment Cooling Operation. The PCCS recchc a steam-gas mixture supply dirc< tly from the drywell;it does not have any vahe, m it immediately starts into operation, folio ving a LOCA event. Non condensables together with steam vapor enter the PC Condenser; steam is condensed inside PCC Condenser vertical tubes, and the condensate, collected in the h>wer headers,i; discharged to the GDCS pool. The uncondensables are purged to the wetwell through the ven t line. l en a s:mu an, J

y. L ..

y . .

l

-. . ~ - -

~

GEhuclearEnergy 25A5020 cm.o. 9 nty C 3.5 System interfaces. The document listed in paragraph 2.1.1.a. shows the mechanical interfaces of PCCS with other systems.The following paragraphs describe all PCCS interfaces with other system s.

3.5.1 Gravby Driven Cooline System (GDCS) (E50). The GDCS pool receives a steam condensed from the PCC Condenser.

The drain line for PCC system "A" shall go to the GDCS pool at 90 reactor building azimuth, and the drain line for PCC systems "B" and "C" shall go to the GDCS pool at 270* azimuth.

3.5.2 Drywell Gas Recirculation System (DGRS) T55). This system can be used to recirculate the dr)well gas by drawing the gas through the PCCS and blowing it back into the drywell, during post accident recovery operations, to depressurire the containment.

Operation of this system is manually initiated after opening locked closed shut ori valves.

. 3.5.3 Fuct and Auxiliary Pools Cooline System (FAPCS) (C21). This system performs a ,

cooling /cican-up of IC/PCC pool water.

Several suction lines, at difTerent locations, draw water from the sides of the IC/PCC pool at an elevation above the minimum water level that is required to be maintained during normal plant operation.The water is cooled / cleaned and is returned back to the pool.

On the return line for IC/PCC pool water recirculation flow, there is also a post-LOCA pool water make-up connection.

3.5.4 &k -upEalcLSyMGIL(MWS1(PIO) t This system provides IC/PCC poot make.up clean water supply for replenishing level, l evel control is accomplished by using an air-operated m1ve in the make-up water supply line.The ,

salve opening / closing is controlled by water level signal sent by a level transmitter sensing water levelin theIC/PCC pool.

3.5.5 IsolatinnSondenser Sptem (ICS) (B32). Passive Containment Cooling System and Isolation Condenser System du not have any functional interface. However, the PCC Condenser and Iselation Condenser will be hxated in a common pool (but in separate subcompartments) and will share the same poof water and steam discharge vent to atmosphere.

3.5.6 Containment System (CS) (TIO). Two smalllines, located on the drain line downstream of the spectacle flange, supply condensate to the water scal on the vacuum breakers: as long as the PCCS units are condensing steam, a relatively constant source of water is available for the water seal. l 3.6 inMIumentalicantiCuttiud. This paragraph is not applicable: PCC System does not have insti umentation, and control logic is not needed for its functioning (no sensing, no power actuated i valves and,in general, no power-actuated devices).

ht o 69 (% v 4W3 )

I i

? 7-- j 4 + , , . - -w- mw, - - ex- - - - -

e ur- + y e ~g es 7 m - - - - -

t--- y y q

G GE NuclearEnergy 25A5020 ncv C m w3. 10

4. FUNC1'lONS AND REQUIREMENTS 4.1 Functions. The Passive Containment Cooling System, siicd to rernove the core decay heat rejected to the containment at approximately one hour after a LOCA, shall proside containment cooling for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> post-I OCA,with containment pressure never exceeding its design pressure limit of 379.2 kPa(g) (55 psig), and with IC/PCC pool inventory not being replenished.

'I he PCCS is an *Enginecred Safety Feature" (ESF), and it is a safety related system.

4.2 Gencral Svitem-1 rvel Recuirements. The PCC Condensers shall be sized to maintain the Containment within its pressu're limits for design basis accidents. The PCCS shall be designed as a passive system without power actuated valves or other components that must actively function and shall be cotutructed of steel to design pressure, temperature and environmental conditions that equal or exceed the upper limits of containment system reference severe accident capability.

4.2.1 l'sIformance Reoviremttm. For operating temperatm es and pressures, system operating modes and performance requirements, see paragraph 3.4 and the document *PCCS Process Flow Diagram" (ref. paragraph 2.1.1.b).

The sptem and the heat exchanger shall be designed for the following thermat, pressure,sibration and dynamic load (including scismic) cycles:

4.2.1.1 Normal Condition (Planned Operation). Continuous operation at containment conditions of 013.8 LPa(g),10*C to 06C (0-2 psig,50cF to 140*F) air or nitrogen with 50% relative humidity in tubes, and 10*C to 60*C (50*F to 140*F) pool water outside the tubes.

4.2.1.2 Upset Cnnditions (Moderately Frequent Transient =). ASME Code Section 111, Class 2, Ievel li Sersice Condition limits apply for the following:

a) Two steam and gas misture (steam, nitrogen, oxygen and hydrogen) hcatup cycles where presmre and temperature in the tubes increases to 379.2 kPa(g),150.5'C (55 psig,303 F) (sec Ogure 4.1 for pressure versus time plot).

Pool watcc coolant temperature outside the tubes rises from 10*C to 1000C (50cF to 212*F) in 10 minutes or more.

The rationale for two cycles is: automatic depressurization occurs then the plant operation is resumed with a 1 cycle allowance tojustify continued operation.

b) 10 equivalent dynamic load excitation input cycles (including scismic) with 10 response acceleration cycles per excitation cycle (sec Ogures 4.2 and 4.3),

w cvm ,

t

.g.

t GE NuclearEnergy G- 25A5020 ncy C m wa. 11 .

7 4.2.1.3 Entlicdfondidgni. (Postulated Accidents) - Case 1. The following conditions shall be analy/cd (but not tested) for the following: maximum combined SSE, DPV/SRV, and LOCAloads .

(see figures 4.4 and 4.5) concurrent with a pressure and a temperature of 379.2 kPa(g),150.5*C (55 psig,303*F) (ASME Section III, Class 2, level C Service Condition streu limits apply for this load combination). ,

Occurrences:less than or equal to 10FA)G events / year.

i 4.2.1.4 Faulted Conditions (Postulated Accidents)- Caft.2. The following conditions shall be analyicd (but not tested) for the following: the steam and gas rnixture (steam, nitrogen, oxygen and .

hydrogen) pressure and temperature in the tubes increases as in the cycle above during the inidal

. 380 seconds (see figure 4.1 for pressure versus time plot); thereafter, the pressure and temperature in the tubes increase to 758.5 kPa(g),171.1*C (110 psig,340*F) in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (ASME Section Ill, Class 2, Service Level C stress limits shall apply for this load combination).

Pool water coolant temperature outside the tubes rises from 10'C to 100*C (50#F to 212'F) in 10 minutes or more.

Occur:ences:1 css than or equal to 10E-0G cvents/ year.

4.2.1.5 Test f hnditions -

Occurrences a) Containment pneumatic preuore test cycles at 448.2 kPa(g) -5 ambient. 48.9'C max. (65 psig ambient 120'F max.) temperature, b) Containment pneumatic leakage tests (10CFR50, 30 AppendixJ, Type A tests) at 379.2 kP4(g) ambient.

48.9'C max. (55 psig, ambient 120*F max.) temperature.

l c) ost maintenancc lcakage tests at 60 PCC pncumatic p'C (110 psig, ambient 140*F max.).

758.2 kPa(g),60 4.2.2 fonfieuration and Arrancement.

4.2.2.1 The elevation difference between the IC/PCC pool bottom and the GDCS pool water surface shall be equal to or greater than that specincd m supporting document paragraph 2.1.1.a. ,

4.2.2.2 The vent line submergence is denned by stipporting document paragraph 2.1.1.a. The value is based on two opposite aspects: deep vent h,ne end to avoid stratification phenomena, but not so deep that it stops the PCCS venting function.

4.2.2 3 The elevation diflerence between the vent line end and the top of the horizontal vents

(

(DW.%W) is defined by supporting document paragraph 2.1.1.a.

NLO W lM d4 %

1 1

1 GE Nuclear Energy 25A5020 sma 12 - 1 uv C ,

4.2.2.4 According to the above elevation difTerence, the passive containment cooling loop pressure  ;

drop (hcat exchanger and vent line piping and cibow) shall be limited: < 850 mm of water at j suppression pool temperature, at the flow rate defined in " mode C" (Post LOCA Quasi Steady State i conditions) of the ref. doc. 2.1.1.b. At this pressure drop nlue, bypassing of tbc PCC Condenser thr ough the DW-WW hori/ontal vents can occur.

4.2.2.5 Ventline piping minimum slope to the suppression pool shall be equal to or greater than 1/25.

4.2.2.6 The drain line from the PCC shall not penetrate the GDCS pool below the GDCS water surface so drain line failure will not drain the GDCS pool.

The loop seal has to be 250 mm below the water level, during normal plant operation. Its length shall be at least 2500 mm to prevent the backflow of steam and gas mixture from the drywell to the vent line.

4.2.2.7 The 1/4 inch lines connections have to be made at the bottom of the horizontal run,in the 6" pipe, for condensate drainage.

4.2.2.8 System configuration shall permit inservice inspection. The physical arrangement and access of piping for inservice inspection is defined by reference 2.1.2.2.b.

4.2.2.9 System configuration shall permit component servicing in accordance with the plant servicing system requirements.

4.2.3 Safety.

4.2.3.1 The Passive Containment Cooling Condenser is an extension of the containment (dr)well) pressure boundary and it is used to mitigate the consequences of an accident. This function classifics it as a safety related Engineered Safety Teature (ESF) per reference Paragraph 2.1.2.2.a.

Therefore, ASME Code $cction Til, Class 2 and Section XI requirements for design and accessibility of welds for in service inspection apply.

The system shall be designed to Scismic Category 1.

The sptem shall also be arranged / protected as required by reference document 2.1.2.2.d, which includes protection against mechanical damage, fire and flood.

4.2.3.2 The common cooling pool that PCC Condensers sharc with the IC's of the isolation Condenser System (1132) is a safety related Engineered Safety Teature (ESF), and it shall be designed such that no locally generated force (such as an IC system rupture) can destroyits function. The requirements of reference document 2.1.2.2.d which include arrangement / protection requirements against mechanical damage, fire and flood apply to the common IC/PCC pool.

Def 0 W (NEv 414)

)

r

.\

& GENuclear Energy 25A5020 uv C eme, j 3 4.2.3.3 As protection from missite, tornado and wind, the PCC System parts outside the containment (the Passive Containment Cooling Condenser it.self) shall be located in a subcompartment of the safcty related ICS/PCCS pool.

1 4.2.3.4 The PCC Condensers shall not failin a manner that damages the safety related ICS/PCCS l po >l as a result of dynamic loads, including combined scismic, DPV/SRV or I.OCA induced loads.

4.2.4 liesign Life. Material and equipment selection for the system components shall be based on a useful hfe of 60 years.

Thcrcfore cach Passive Containment Cooling Condenscr unit shall be designed for 60 years life and, if necessary, repair operations will be perform during refueling. However,in case of major damage of some component part, the module shall be easily removable.

4.2.5 Sptem Interfaces.

4.2.5.1 Gravity Driven Cooling Sptem (CDCS) (E50). See paragraph 3.5.1.

4.2.5.2 DrywclLGaLReckculatiottSystendRGKS11Md. See paragraph 3.5.2.

4.2.5.3 fuel and Auxiliary Pools Cooling. System (FAPCS) (G21).

Description Duration Cooling and clean-up Intermittent ofICS/PCCS pool 4 *25.4 hials .upEMsLSuisndMM'SLIPlHl.

D.cniption Duration Water to maintain Inter mittent ICS/PCCS pool level 4.2 5.5 Im13 tion Condenter System (ICSLfit32). See paragraph 3.5.4.

4.2 5.6 Contamment System (CS) T10). See paragraph S.5.6.

4.2 6 Innranntniation ansLContro]. This paragraph is not applicabic: see paragraph 3.6.

4.2.7 Mailahiluy.

4.2.7.1 Since the plant aserage availability has to be no less than 87%, the allowable PCC system contribution to the total plant unavailability (plant forced outage time) shall be equal to or le<.s than 0.02%, according to the document listed in paragraph 2.1.2.1j.

4.2.7.2 The system maintenance has to be performed during refueling. (The maintainability criterion for SliWR is that regular refueling and planned plant maintenance can be accomplished in one 50 day outage every two years).

Nt D V 1 Itt v Ott n .. ..

, ,_, *a, . ' '9-' ,- .

'1* , . _

', ' "'. . s ' ' . ,

=.- - - - ,

4 Q GENuclear Energy 25A5020 ncy C em 14 i l

l 1

4.2.7.3 From the point of view of refueling outage time, the PCCS is not in a critical path.  :

1

- 4.2.7.4 The mean time between failurcs shall be, as objective,60 years.

4.2.8 Dniinutttnti.

4.2 8.1 Passive Containment Cooling System components (hcat exchanger and piping) are required to function under emergency and faulted conditions. Therefore,it shall be designed to remain functional under the abnormal environmental conditionsin addition to the normal '

conditions defined in document paragraph 2.1.2.1 k.

t 4.2.8.2 For purposes of r adiation shiciding design, Source Terms document (see paragraph 2.1.2.1) shall be used.

4.2.8.3 Passive Containment Cooling System is not prosided with thermal insulation.

4.2.9 Maintenancs. No piesentive maintenance actions are expected to be peiformed during normal plant operation. ,

The PCC Condenscr headers, PCC pool and piping shall be arranged so that the heat exchanger tubes can be plugged,if needed. Plugging will be donc during plant shutdown.

If theic is considerable damage to some component part of the PCC Condenser, each module of the unit shall be casily removabic, after cutting the feed, drain and vent lines.

The pool water in the PCC condenser subcompartment shall be removabic for PCC condenser cleaning, inspection and testing without emptying the entire ICS/PCCS pool.

4.2.10 Surreillantelesingand In-Scrvice inspection, .

4.2.10.1 During plant outages routine ISI is required for the Passive Containment Cooling Condenser, piping, supports, and containment penetration sleeves according to ASME Code Section !!! and Section XI (requirement.s for design and accessibility ofwelds).

PCC condenser removal for routine inspection is not required.

Ultrasonic inspection is required for PCC Condenser tubc/ header welds.

PCC Condenser tubes shall be inspected by the Eddy current method.

Inspection and leak testing will be donc during refueling outages.

4 ser o at 7 int v (ta; 1_ I

GE Nuclear Energy Q' - 25A5020' nty C emo. 15

3 4.3 Specific Requirements for Comoonents. 'I 4.3.1 Passive Countinment Cooling..Condennr.

4.3.1.1 The Passive Containment Cooling Condenser shall consist of 3 units. Each unit may be made of two identical modules and shall be designed for 10 MWt capacity, nominal, at the following conditions: ,

pure saturated steam in the tubes at 3.04 ata (absolute) and IS4*C; pool water temperature at atmospheric pressure and 102 C. ,

4.3.1.2 Design pressure and temperature:

758.5 kPa (g) (110 psig),

171 C (310*F). .

The temperature design value is based on the drywell response to a design basis loss-of-coolant accident.

4.3.1.3 The PCC Condenser is an extension of the containment (drywell) pressure boundary.

Therefoie, ASME Code Section Ill Class 11 and TEMA Class R apply.

4.3.1.4 Material shall be nucicar grade stainless steel or other material which is not susceptible to IGSC (Intergranular Stress Corrosion).

4.3.1.5 Pressure losses for condenser and vent line shall be limited: <850 mm of water at suppression pool temperature at the flow rate defined in " mode C" (Post-LOCA Quasi-Steady State Conditions) of the ref. document 2.1.1..b..

4.3.1.6 The PCC Condenser modules must be removable for replacement,if needed, during plant shutdown s. ,

4.3.2 IC/PCC Pool.

4.3.2.1 110th the Passive Containment Cooling Condensers and the Isolation Condensers are located in a large water pool, positioned above the drywell.

The large IC/PCC poolis partitioned but each IC and PCC Condenser must be able to draw water from the entire pool; the pool air / steam spaces and vent system to atmosphere are commonly used by all IC and PCC units.

4.3.2.2 The pool subcompartment interconnections shall be as follows: except for the IC and PCC '

pool compartments, all other pool subcompartments shall be interconnected below pool water level; the IC/PCC pool subcompartments shall he connected to the other pools below the water level bylocked open vahes, one for each subcompartment, which can he closed to innlate and empty it, using a portahic pump. Emptying the subcompartment allows maintenance of the unit during refueling (see ref. paragraph 2.1.1.a).

imn ec e m.

, ,c. .

1 Q GE Nuclear Energy 25A5020 av C rse. 16 j

i l

4.3.2.3 The location of the PCC Condenser tubes in the PCC pool shall be such as to guarantee the ,

required performance for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> minimum. The requirement for IC System is more limiting for l pool design (see ref. paragraph 2.1.2.1.a). I 4.3 2.4 locked open valve tcmnte handwhcch shall be extended above water level, to locations which are accessibic to the operator.

4.3.2.5 The walls which contain the airspace flow path shall extend above the normal watcr level; this enhances the flow stability and heat removal of the condensers by establishing a flow path for the male-up water through the lower pipes.

4.3.2.6 For IC/PCC pool insirumentation, see ref. paragraph 2.1.2.1.d and 2.1.2.1.c.

4.3.2.7 For IC/PCC pool make-up, see paragraph S.2 and ref. paragraph 2.1.2.1.f.

4.3.2 R Steam dryers are required to remove carryover moisture from the ICS/PCC pool before it is released to atmosphere, The moisture content of the steam leaving the vent pipe shall not extced 2% of the mass flow of the steam generated in the ICS PCC pool.

4.4 Quality Anurance.

4.4.1 General.

1.a t e r.

4.4.2 Tests and thamination.

I.a t e r.

-, n., ,

I i

j l I

.h,, .;..h.,.

,b-. ,. a v- . . , ,

<c , _..,.p ., .,

'j GENucIcar Energy A 25A5020 sn eo. 17 .

REV C ,

~ .1 l

J l

s

'I e

'h y -.

SBWR M$tB DW AND WW PRES $URE TO LESS THAN 379.2 kPa (g) -i (55 pats) AT 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> rAYWELL AND PCCS ' M MPEMTunt: 151*C (3C3*F)) ,

u , conotustn ene ssunc .?

A Y k 3

F.

y ' WETWCLt PRELSURE ,

b N

tr L

l NOT E ' TE MP[RATyA[ Cf PCC (CND[$d$[$4 POOL $U0CouPAnf uCNT WATE A OUlstDE PCC5 CCWDENSER RCMAINS AT 10*C FOR TH;S TiUT PERIOD AND TwtN Af$($10101*C  ;

e  ! I f  !

o ro oc sc

l J

1

~~

V l

l

- ,. , . - . . .. . - . , . - ,, , , - . - - , . -- . . . . , . ~ . . . . -

i l

' l GE NuclearEnergy =

25A5020 sem. 18' scv C <

l l

l l

.l l

l l

i 5 . _ _ . _ . .

q..g. .

l .f I.. '

i i

' P( ', ' ,

.. 4,5 - -

3-

\ '

4 _ . . _ _ ____ . . . .. , . .

i 3,5 - -

j - - - - - - - - - -

l y 3-  : -

h  ! .  !

& P,5 i 1 m  ;

. 1 i ,

g i o I i ,

l y p - {q

). ,

. i . .*

I i . t

(

i 1  ;

i i

'r i

, i l .

1.5 - 5 jj  ;  ; . i ;.

! i ,

, i e' j. --

1 -- -

4 I  : .

j l l t i' n ': '

O.5 1 -

' - 6 l

0 -1 j

t' ii

+- .

I li ii>

i .

.i 0,1 1 10 100' FREQUENCY.cpb l

i

.i

.l 1

FIGURE 4-2. UPSET CONDITION Dm'AMIC LOAD RESPONSE SPECTRA HORIZONTAL i wr o w gv v see;

)

~~. .

1

. l

.. .- - - - - - - 1

.l

' GE Nuclear Energy .

@ 25A5020 ncy C sm.o. 19 i

1 l

q l

. / . . l

..f i,s _ .

.j _ _. _

j.

/ .__ _ _ _ _ .

,,e - . . . . .

/(. - . . . .-

Y

• 1,2 - - - - -- - - - - -- - -- - - - - - -

6

)3 ,_ .~/ .

5 ,

g I l 4 W o.e - 3- }- j l, ,

l e,e - q ,

l t 1

-f 0,4

}-

3 _

I i l l c,a d -  ! ,-] I, 5

! , l !l' f l j l l i .l i 4 I}l,

.. . . i .;

o .4 .l .

o,1 1 to te j I

F ntOut HCV- ces l

1

-l FIGURE +3 UPSET CONDITION DW'AMIC LOAD RESPONSE SPECTRA VERTICAL wo w ei v m, h

1 j

.. q

P y' GENucIcar Energy 25A5020 v ma. 20 ncy C 7

7 ,

r--

s_ . _ . . _ . _ . _ _

• l Ee _.

.l _

F I >

y 4 i l I l

3 I i l l

5*-

4 i

i l l i

l 1i i i ll . l l 2 -

1,, t r li: -

! l  !

l l

i

l l l l  !

l . I -

l l  ! l l i

' I i; i  ! '

1 ~

+

i

' , t  ! l I

'- i 1 i e1i j i >

J .__ L _

' +

ih.

o  ! il l l 1 ll t I !}I' C,1 1 10 100 f 54CCUENCY ces FIGURE 4-4. FAULTED CONDITION DYNAMIC 1.OADING IIORI7.ONTAI,

• Senice Ievcl C Limits Apply for the PCCS N[ O 07 (Ri V AM he

.#'# ., ', , ., 'a -

. , ,_,4 .

, i, ' ._ _ '

. s e

1

}.. .

GE Nuclear Energy

) 25A5020 s m . 21 ncy C l.

.I I

['

l

' f.

l

~l^ l 1

g . . . . . . . _ - ~---

---. 333 -

l 4

N 2 - ~' '- \

r j s 7 ,. . . _ .. .

r If

,- - 3

i. y t v" '

l:

S .

l l5 I '

' l; il d

o l' l t y _ f  ! '

[

g , j i

! f .

. t- i t l <

l 0,5 * - i

.' 'i 'I

• I l  !

l l l ,.

l; i

ij f

.r I *

! ! f*

k '

1 l I I

.; i l; l Dd I J J J' ' 8 5 -

i

! O,1 1 10 #

1

{ fRLOVENCV.tp6 j I l

-l i

FIGURE 4-5. FAULTED CONDITION DiNAMIC LOADING VERTICAL ]

• Service Level C Limits Apply for the PCCS

l. N[O E7 F4 W 4%Ja i

p  !

L..

I

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

GENuclearEnergy l Q'r -

25A5020 sine. 22 I uv C HNM, l l

APPENDIX 10 S) STEM TECHNICAI. SPECIFICATIONS The objective is to preserve the capability of PCCS to perfonn its function, j 1.imiting Conditions for Operation (LCO):  ;

l l

3 PCCS subsystems shall be available during operation at full reactor power; 2 PCCS subsystems shall be available during operation at 565% power; 1 PCCS subsystem shall be availabic during startup and during operation at 30% power; and ,

in case oflow suppression pool water Icvel, take action according to

• Suppression Pool Water Icvel ICO*;

in case oflow IC/PCC pool water level, take action according to "lC/PCC pool Water Level 100".

1 j

l l

i i

l l

. MO D9 M V 4M; 1

l

_ . . . . . . . .