ML20059B788
| ML20059B788 | |
| Person / Time | |
|---|---|
| Site: | 05200004 |
| Issue date: | 10/16/1993 |
| From: | Wilhelmi F GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20059B690 | List: |
| References | |
| 25A5013, NUDOCS 9310290098 | |
| Download: ML20059B788 (43) | |
Text
{{#Wiki_filter:- _. . . h GE Nuclear Energy 1sasons REV B su uO.1 HEVISION STATUS Sill;t:T DOCUM1Wr TITLE ISOLATION CONDENSER SYSTEM LLGliNLtDRDLSCRit'110NDEDliGU15 . 'IYPE: DESIGN SPEC FMF: SBWR MPL ITEM NO: 1132-4010 RHVISIONS C A PRELIMINARY ISSUE DMH 5088 10/1U91 B E Mi ptp, O I Y @3 DMil 6113 ft, ' d O 0yks f{FE$1 YlELMI FE COOKE 781KLU I e I'RINTS TO MADDDy APPROVALS IO/IMI GENER AL ELECTRIC COMPANY .; 175 CURTNER AVENL'E 4 iU Wil,HEi.MI u13/91 TE COOKlVM DRUZ7,0NE srn josa, ca 95325 ! CllKl > B y IS$UED 1 -; IE W11.Illil.MI 10/1991 " GA B AYLIS 10!!6/91 . . 6.5 l 1 it OltTIZ 16-OCT.93 09:54:02 'PICKUl"
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TABLE OF CONTENTS Page l
- 1. SCOPE 4 1.1 Purpose 4 .
1.2 Use 4 i
- 2. APPL.ICARI.E DOCUMENTS '4 !
2.1 Supporting and Supplemental Documents 4 2.1.1 Supporting Documents .4 - 2.1.2 Supplemental Documents 4 2.2 Codes and Standards G-2.2.1 American Society of Mechanical Engineers (ASME) Boiler and Picssure Vessel Code 6 2.2.2 Institute of Electrical and Electronic Engineers (IEEE) 6 2.2.3 Standards of the Tubular Exchanger Manufacturers Association (TEMA) .6 2.3 12ws and Regulations 6 2.3.1 NRC Regulations 6 2.3.2 Regulatory Guides 6
- 3. DESIGN DESCRIPTION 6 :
3.1 Summary Description 6- j' 3.2 Detailed System Description 7 3.3 System Boundaries 10 3.3.1 Includes 10 3.3.2 Excludes 10 3.4 System Operation -10 3.4.1 Normal Plant Operation 10. . 3.4.2 Plant Shutdown Operation .11 ~l 3.4.3 Isolation Condenser Operation 11 i 3.5 System Interfaces 12 3.5.1 Nuclear Boiler Systern (NBS) (B21) 12 .i 3.5.2 Leak Detection and Isolation System (LD&IS) (C21) 12 i S.5.3 Fuel and Auxiliary Pools Cooling System (FAPCS) (G21) 12 3.5.4 Make-up Water System (MWS) (P10) . 13 3.5.5 High Pressure Nitrogen Supply System (HPNSS) (P54) 13 3.5.6 Passive Containment Cooling System (PCCS) (T15) - 13 3.5.7 Direct Current Power Supply (R42) . . 13 3.5.8 Safety System Logic and Control (SSIL) (C74) 13 3.6 Instrumentation and Control 13-3.6.1 Instrumentation 13 3.6.2 Control Logic and Interlocks 14 l r 7 m o x? p v ate; I It OltTIZ 18.OCT.93 Oth.M02 'PICKUl" l
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Page 15;
- 4. FUNCTIONS AND REQUIREMENTS 4.1 Functions .
15 4.2 General System Level Requirements 16 4.2.1 Performance Requirements 16 4.2.2 Configuration and Arrangement 118 4.2.3 Safety 19 ' 4.2.4 Design Life 20. 4.2.5 System Interfaces 21 , 4.2.6 Instrumentation and Control 21 4.2.7 Availability 22' 4.2.8 Environment 22 4.2.9 Maintenance 22 4.2.10 Surveillance Testing and Inservice Inspection. 23 4.3 Specific Requirements for Components 24 4.3.1 Isolation Condenser 24 4.3.2 holation Condenser Pool 25 4.3.3 Isolation Vahrs (F001, F002, F003, F004) 26 4.3.4 Condensate Return Valves (F005, F000) , 28 ; 4.3.5 Vent Valves (F007, F008, F009, F010, F011, F012) 29 4.4 Quality Anurance 30 4.4.1 - General 30 4.4.2 Tests and Examination 30 APPENDICES
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10 SWTEM TECliNICA1, SPECIFICATIONS 35 23 SWTEM OPERATING CONDITIONS 39 i l i i l I a.toormvan; l It OltTlZ '18-OCT-93 09:M:02 'PICKUI" 1
&) GE Nuclear Energy 25A5013 ncy B m.4
- 1. SCOPE 1.1 Purpoic. This specification defines the requirernents for the design, performance, con 0guration, and testing for the Isolation Condenser System (BS2). It air.o dennes the interface requirements with other systems in the complete nuclear system and with the balance of plant.
1.2 Bc. The use of this dceign specification is applicable to the Simplified Boiling Water Itcactor (S!! Wit) Project only.
- 2. APPI.lCABl.E DOCUMENTS 2.1 Etpporting and Supplemental Documents. The following documents form a part of this speciGration to the extent speciGed herein.
2.1.1 Supporting Documents MPI, NO.
- a. Isolation Condenser System PkiD (107E5154) B32-1010 (ANSA 1.DO document number: SBW5280DNJXN012001/2)
- b. Isolation C<mdenser System Process Diat; ram B32-1020 (ANSA 1.DO document number: SBW5280DNIXN011001/2)
- c. Isolation Condenser System Logic Diagram (137C9292) B32-1030 (ANSAI.DO document number: S!1W5280DNRX013000)
- d. Isolation Condenser System PklD Data B32-1010
- c. Isolation Condenser System Data Sheet B32-1010
- f. Reactor Cycles (107E6372) 1111-3040 2.1.2 Supplemental Documents 2.1.2.1 Documents under the following identities are to be used in conjunction with this spccification:
MPINO.
- a. Nuc1 car lloiler System Design SpeciGcation B21-4010 (ANSAi.DO document number: SBW5100SNPXN001000)
- h. Nuclear Boilcr System PikID B21-1010 (ANSAl DO document number: SBW5100DNJXN001001/6) w.o w meaw
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2.1.2.1 (Continued) .
- c. Passive Containment Cooling System Design Specification (25A5020) T15-4010 (ANSAI.DO document number: SBW5280SNPXN003000)
- d. Passive Containment Cooling System PalD (107E51GO) T15-1010 (ANSAI.DO document number: SBW5280DNJXN014001)
- c. Icak Detection and Isolation Sysicm Design Specification C21-1010
- f. Fuel and Auxiliary Pools Cooling System Design SpeciGcation (23A6921) G21-4010
- g. Fuel and Auxiliary Pools Cooling System P&lD (103E1581) G21-1010 l
- h. Mateup Wates System Design SpeciGcation P10-4010
- i. System Design SpeciGcation Standard (23A6857) A00-3050
- j. Pressure Integrity of Nuclear Components (25A50GI) Al 1-2029
- k. Source Terms A11-2052 i
- 1. Process In strumen tation A11-4001
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- m. Procedure for Preparation of System Man-hfachine Interface Requirements A32-1034
- n. Reliability, Availability & Maintainability '
(RAM) Criteria (23A6899) A18-1020
- o. F.quipment Emironmental Data Al 1-2020 2.1.2.2 The following documents are to be used in conjunction with this speciGcation to the ;
extent speciGed herein: .i
- a. Composite Design SpeciGcation (23A6723) All-5299 l
- b. Generic Operations and Maintenance (23A6822) ASGS9010 Requirements SpeciGcation
- c. Plant Tran sient/ Stability Perfonnance Requir ements (23A6918) All-3006 l
- d. Composite Design SpeciGcation Data Sheet (2SA6723AC) All-5299 !
- c. hiaterials and Process Control Al1-2043 i
- f. SBWR Design and CertiGcation Program Quality Assurance Plan NEDG-31831 1
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i 2.2 Codes and Standards. The following codes and standards form a part of this specification to i the extent specified hercin. The applicable code and standard edition dates together with exceptions to code and standard requirements are defined in reference 2.1.2.2.d for those specified herein. 2.2.1 American Society of hicchanical Encineers (ASME) Iloiler and Pressure Vessel Code
- a. Section Ill: Nucicar Power Plant Components
- b. Section XI: Rules for Inservice inspection of Nuclear Power Plant Components 2.2.2 In5lilute of Electrical and Electronic Engineers (IEEE1 l
2.2.3 Standards of the Tubular Exchanger Manufacturers Anneiation (TEhfM 2.3 I.aws and Regulations. The followinglaws and regulations form a part of this specification to the extent specified herein: t 2.3.1 NRC Reculations !
- a. None specified as part of this specification.
2.3.2 Ergu!atory Guidu [
- a. None specified as part of this specification.
- 3. DESIGN DESCRIl1 ION 3.1 Summary Devription. The Isolation Condenser System (ICS-1132) basically consists of three totally independent loops, each containing a heat exchanger that condenses steam on the tube side and transfers heat to water in a large pool (IC/PCC pool) which is vented to atmosphere. ;
T he condenser, connected by piping to the reactor pressure vessel,is placed at an elevation i* above the source of steam (veseel) and,when the steam is condensed, condensate is returned to the vessel sia a condensate return pipe. The steam side connection between the vessel and the 1C is normally open and the condensate l line is normally clored. This allows the isolation condenser and drain piping to fill with condensate which is maintained at a subcooled temperature by the 1C/PCC pool water during i normal reactor operation. , The isolation condenser is star ted into operation by draining the condensate to tlie reactor, thus i ! causing steam from the reactor to fill the tubes which transfer heat to the cooter pool water. s I f , esto at ettv 4ms, i I b I. .
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arv IT a 5.2 D.cuilnUbitern Desn.iplnu. i The Isolation Condenser System (ICS) limits reactor pressure I and temperature within an acceptabic range so that safety /reliefvalve operation is limited and i automatic reactor depressurization will not occur when the reactor becomes isolated during -! power operations. , The ICS consists of three, high-pressure, totally independent loops, each containing a steam isolation condenser (IC) as shown on the ICS P&lD (ref. paragraph 2.1.1.a). The ICS P&lD j defines piping system interconnections, valves, instruments, special arrangement requirements, '
.. manually operated controls and system input sources and outputs.
Each IC is designed for S0 MWt capacity and is made of two identical modules. i The units are located in the IC/PCC pool positioned above, and outside, the SitWR ; containment (drywell). ! The IC is configured as follows. l The sicam supplyline (properly insulated and enclosed in a guard pipe which penetrates the l w tainment roof slah) is vertical and fecds two horizontal headers through four branch pipes. Each pipe is provided with a built-in flow limiter, sired to allow natural circulation operat on of the IC at its maximum heat transfer capacity while addressing the concern ofIC breaks downstream or the steam supply pipe. Steam is condensed inside vertical tubes and is collected in two lower headers. Two pipes, one from each lower header, take the condensate to the , common drain line which vertically penetrates the containment roorslah. A vent line is provided for both upper and lower headers, to rernove the noncondensable gases , away from the unit, during IC operation. The vent lines are routed to the contaimnent through a single penetration. A purge line is provided to assure that, during normal plant operation (ICS standby conditions), ; the excess of hydrogen (from hydrogen water chemistry control additions) or air from the - ! feedwater will not accumulate in the IC steam supply line, thus assuring that the IC tubes will' not be blanketed with noncondensables when the system is first started. Two fail as-is isolation valves in series (F001, nitrogen rotary motor-operated and F002, motor. . operated) are located in the run of steam supply piping inboard of the containment boundary.- They are used to isolate that part of the ICS which is located outside the containment. Two ' dillerent vahc actuator types are used to assure flow path closure. . On the condensate-return piping, two fail as-is isolation valves in series (F003, motor-operated ! and F004, nitrogen rotary motoroperated) are prcnided, also locaterl both inhoard of the containment boundary. They are also used to isolate parts of the ICS outside the containment, ; and two different valve actuator types are used to assure flow path closure. ; Located on the condensate return piping,just upstream of the reactor entry point,is a loop seal ' j and a parallel-connected pair of valves: a condensate return valve (F005, motor-operated, fail as. ; is) and a condensate return bypau vahc (F006, nitrogen piston operated, fail open). These two i valves are closed during normal station power operations. Since the steam supplyline valves arc ! normally open. condens. ate will form in the IC and will develop a level up to the steam ] wr m erv m, It OltTIZ 18-OCT.93 0944:02 'I'IC K U P'
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I GE Nuclear Energy 25As01s -a l ncy 11 l S.2 (Continued) ,, l distributor, above the upper headers. To start an IC into operation, the motor-operated condensate return vahe (F005) is opened, whercupon the standing condensate drains into the , reactor and the steam-water interface in the IC tube bundle moves downward, below the lower ' headers, to a point in the main condensate return line. The fail open nitrogen piston operated condensate return bypass valve (F006) opens if the 125 V DC power is lost or on reactor water leset signal (below L2). System controls allow the reactor operator to remote manually open both of the condensate return valves at any time. The loop seal assures that condensate valves do not have 285*C (545'F) water on one side of , disk and subcooled water (as low as 10'C (50*F)) on the other side during normal plant operation, thus affecting 1cakage during system standby conditions. Furthermore, the loop sea! , assurcs that steam continues to enter the IC preferentially through the steam riser, irrespective I of water !cvel inside the reactor, and does not move counter-current back up the condensate-return line. l>uring ICS normal operation, any noncondensable gases collected in the IC are vented, from the IC top and bouom headers, to the suppression pool. Vcnting is controlled as follows:
'I wo nor mally closed, fail closed, solenoid operated valves (F009 and F010) are located in the ven: line from the lower headers. They can be actuated both, automatically (when RPV prcasure is high and clihcr of condensate return valves is open) and manually, by the control roorn operator.Two bypau motor operated valves, F011 and F012, (normally closed) allow the j operator to vent noncondensable gases in case of F009 and/or F010 failure.
The vent line from the uppcr headers with two normally closed, fail closed, solenoid operated valves (P007 and F008) is provided to permit opening of this noncondensa1>1e gas flow path by the operator, if nerenary. All the vent valves arc located in a vertical pipe run near thd top of the drywell.The vent piping minimum slope to the suppression pool is equal to or greater than 1/25, to prevent stearn-condensate induced water hammer. A catalytic converter is provided to recombine noncondensabic gases (hydrogen and oxygen) under normal plant operation (ICS standby condition). The hydrogen recombiner is a plating of platinum, palladium and rare earth oxides onto metal surrece that has about 35'/o nickel (Ni) such as " Carpenter 20" or "330 stainicss stecl*, ! The catalytic converter is located on the steam distributor cover, at the top end of the steam supplyline to the 1C.
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3.2 (Continued) As a backup to the catalyst and to discharge hydrogen excess (SBWR has hydrogen water chemistry) or air, a vent is prosided that takes a small stream of gas from the top of the IC and vents it downstream of the RPV, on the main steam line, upstream of the MSIVs. - ' Each IC is located in a subcompar tment of the IC/PCC pool and all pool subcompar unents , communicate at their lower ends to enabic full utilization of the collective water inventory, i independent of the operational status of any given IC subloop. A valve is provided at the bottom of ; each IC/PCC pool subcompartment that can be closed so the subcomparunent can be emptied of water to allow IC maintenance. Pool water can heat up to about 10l*C (214*F); steam formed, being nonradioactive and hasing a slight positive pressure relative to station ambient, vents from the steam space above cach IC where it is released to the atmosphere through large-diameter discharge vents. A moisture separator is installed at the entrance to the discharge vent lines to preclude excessive , rnoisture carryover. , IC/PCC pool make-up clean water supply for replenishing Icvel is provided frorn the Makeup Water System (MWS) (ref. 2.1.2.1.h). Pool level control is accomplished by using an air-operated vahe in the make-up water supply line.The valve opening / closing is controlled by a water level signal sent by a level transmitter sensing water 1cvelin the IC/PCC pool. Coolitig/cican-up ofIC/PCC pool water is performed by the Fuel and Auxiliary Pools Cooling
- System (FAPCS) (ref. 2.1.2.1.f and g). Several suction lines, at different locations, draw water fiom the sides of the IC/PCC pool at an elevation above the minimum water level that is .
required to be maintained during normal plant opera' ion The water is cooled / cleaned and is .i returned back to the pool. A safety-related independent FAPCS IC/PCC pool makeup line is provided which is routed to the pool from a valved connection located in the yardjust outside the reactor building. Four radiation monitors, shicided from all radiation sources other than the flow passing through the specific IC loop exhaust passages, are installed in the IC/PCC pool exhaust passages to atmosphere to dctcct any IC tube Icakage. Detection of a low-Ictel leak (radiation lesel alue background -logic 2/4) shall result in alarms to the operator. At high radiation levels (exceeding site boundary limits -logie 2/4), isolation of the Icaking isolation condenscr will occur automatically (closure of the isolation valves F001 through F004). Four sets of di!Terential pressure instrumentation are bcated on the steam line and another four ! sets on the condensate return line; detection of excessive flow in the steam supplyline or in the ' l i condensate return line (logic 2/4 aigr,ials) will result in alarms to the operator, plus automatic l isolation of both steam supply and condensate return lines of the affected IC loop. : I i M O W (qlv4 % ! l It OltTIZ 18-OCT-93 09:.11:02 'I'ICl{ Ul" i 1
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' 3.3 System Boundaries 3.3.1 Includes. The ICS design scope includes the following:
- a. Outside vent to atmosphere.
- b. Steam dryers in the pool vent Cow path.
- c. IC/PCC pool subcompartment interconnections (pipes and valves).
3.3.2 bIl dg. 3 The ICS design scope excludes the following:
- a. IC/PCC pool.
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- b. Pool makeup and water recirculation systems.
- c. Pool instr umentation. '
r!. Radiation monitors. S.4 System Oncr ation , 3.4.1 Normal Plant Operation. l>uring normal plant operation, the IC subloop is in " ready standby",with both steam supply isolation valves and both isolation valves on the condensate return line in a normally open position, condensate level in th_e IC extending above upper , headers, condensate return vahc. pair both closed, and with the small-vent lines from the IC top ! and bottom headers to the suppression pool closed. A hydrogen recombiner, located inside the IC, on the steam distributor, at the main steam supplyline top end, recombines the small !i quantity of noncondensable gases. Steam flow is induced from the steam distributor through the i purge hne by the pressure differential caused by main steam I ne flow. .j l The valve status, failure mode, actuation rnode, pipe sire, valve type and line are as follows: Valve Staim Failure mode Actuatorm Valve Number 11.) .(2) 111 fjte Iype Location j F001 NO Al NMO 12" gate steam line l F002 NO Al MO 12" gate steam line FD03 NO Al MO 6" gate condensate to RPV l F004 NO Al NMO 6" gate condensate to RPV l F005 NC Al MO 6" gate condensate to RPV l F006 NC FO NO G" glotic condenute to RPV F007 NC FC SO 3/4" globe vent line to SP F008 NC FC SO S/4" globe - vent line to SP F000 NC FC SO S/4" globe vent line to SP j F010 NC FC SO 3/4" globe vent line to SP ; no w puun 11 OltTIZ 18-OCT.93 09:54:02 'l'I C Kill"
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t 3.4.1 (Continued) .l Vahe St at us Failure mode Actuator _typs Valve *
. Number ID R.) fil fits type laatio_n F011 .NC Al hio 3/4" globe vent line to SP-F012 NC. Al MO 3/4" - globe vent line to SP F013 NO Al MO 3/4' globe purge line t. MSL .
legend: (1) NO - norinally open: NG = normally closed; ' (2) Al = as is: FO = fail open; FC - fait closed; (3) Nhf 0 - ni rogen t rotary motor operated: SO = mlenoid operated: NO = nitrogen piston operated: MO - electric motor operated. 3.4.2 Plant Shutdown Operation. During refueling. the IC is isolated from the reactor,with all , isolation valves closed (F001 through F004). The vent valves (F007 through F012 ) are also closed. ; 3.4.3 Isolation Condenser Operation. Any of the following sets of signals will generate an actuation signal for ICS to come into operation (see also ref. 2.1.1.a & c) to implement the , control requirements of ref. 2.1.2.2.c: a MSIV valve position on MSL A $ 90% open, , plus MSiv valve position on MSL15 s 90% open, (Reactor Mode Switch in "RUN" only); ; 1 (Note: 90% open is the nominal setpoint value; the MSIV position minimum plant safety analytical limit is 85% open) , or:
- b. RPV pressure 2 7.447 MPag (1080 psig) for 10 seconds; c::
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- c. Reactor water level below level 2; )
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- d. Operator remote manual initiation. -
When one of these ICS initiation 3,ignals occurs, the condensate return valves F005 and/or F006 open within 30 seconds; that starts IC operation. If the IC does not operate, the RPV pressure i will peak and gradually increase to the SRV setpoint of 8.619 MPag (1250 psig). The isolation- -; valves are signaled to open to assure that they are opened during or after a test closure of the ' valvet
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GE Nuclear Energy 2bA501S m 12 Rcv D S.4.3 (Continued) If, during IC operation and after the initial transient, the RPV pressure increaws above 7.516 hiPag (1090 psig), the bottom vent valves F009 and F010 automatically open; when the RPV pressure decreases below 7.447 MPag (1080 psig) (reset value) and after a time delay to asold too many cycles, these two valves close. After reactor isolation and automatic ICS operation, the control room operator can control the venting of noncondensable gases from &c ICs to enabic them to hold reactor pressure below safe shutdown limits. 3.5 System Interfacc3. The document listed in paragraph 2.1.1.a shows the mechanical interfaces ofICS with other systems. The following paragraphs describe all ICS interfaces with other systems. S A1 Nuclear 1%iler System (NRS) (B21). The steam to be condensed is directed to the ICs from RPV stub tubes which are part of the NBS. The RPV stub tube nonle locations are shown on the ICS P&lD (ref. paragraph 2.1.1.a). Another physical and functional interface t.ctweca NBS and ICS is the vent line that purges noncondensabics downstream of the RPV, during normal plant operation. The IC loop purge line is connected to both NBS main stcam lines, upstrearn of the MSIVs. Nits and ICS cach also have certain instrumentation interfaces: MSIV limit switches and reactor pressure sensors that actuate ICS (see ref. 2.1.1.c and ref. 2.1.2.1.b). 3.5.2 Lcak Detection and Isolation System (I D&lS) (C11.1. The LD&lS willisolate each IC loop indisidually on high pool radiation or on high flow (as measured by high dilTerential pressure) in the steam supply line or the condensate return line (sec Paragraph 3.2 for detailed system description). 3.5.3 Fuc1 and Auxiliary Pools Cooline System (FAPCS) (G21L This system performs a cooling / cleanup of IC/PCC pool water. Scseral suction lines, at different locations, draw water from the sides of the IC/PCC pool at an elevation above the minimum water Icvel that is required to be maintained during normal plant operation. The water is cooled / cleaned and is returned back to the pool at sescral different locations. There is a separate supply pipe to the IC/PCC pool with a connection through which, under an emergency, water can be supplied from fire or tanker trucks. wceannw
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1 3.5.4 Makeup Water System (MWS) (P10h This system provides IC/PCC pool makeup clean j water supply for repicnishing level. j Irvel control is accomplished by using an air-operated valve in the makeup water supply line. The valve opening / closing is controlled by a water level signal sent by a level transmitter sensing , water level in the IC/PCC pool. ! 3.5.5 liigh Pressure Njnogen Supply System (HPNSS) (P541. The valves F001 and F004,' nitrogen rotary motor operated, and the valve FD06, nitrogen piston operated, alllocated inside containment, utilire clean nitrogen gas, supplied by this system,if availabic. , During abnormal conditions, (i.e., emergency) the valves are fed by pneumatic accumulators ! (nitrogen charged). , 3.5.6 Palve Containment Cooline System (PCCS) (Tl 5h The ICS and the PCCS do not have ; any functional interfacc. But all ICs and PCC Condensers will be located in the common IC/PCC pool (but in separate subcompartments) and thus will use the same water. 3.5.7 Diisct Current Power Supply (R421.125 V DC Power (divisions I,Il and III) shall be used for solenoid operated and motor operated valves as defined by ref. paragraph 2.1.1.c. 318 Safety System I ngic and ControIISSI .C) (C74L The logic defined by ref. paragraph 2.L1.c shall be incorporated into the SSLC. 3.6 Lnstrumentation and Ce ntrol. The ICS instrumentation is shown in the document 1isted in paragraph 2.1.1.a. Control logic for the system is given in the document listed in paragraph 2.1.1.c.The following paragraphs give a brief description for the system instrumentation and - con ti ot logic. 3.G.1 Instrumentation. Four radiation sensors are installed in the IC/PCC pool exhaust . passages to the outside vent lines that vent the air and evaporated coolant (vapor) to the environment. These sensors are part of the LD&IS (ref. paragraph 2.1.2.e). On high radiation signal, coming from 2-out-of4 radiation monitors installed near each IC compartment, all the lines from/to the IC are isolated. This means closure of the isolation valves F001 F002, F003 and F001. The high radiation can be due to a Icak from any IC tube and a subsequent release of noble gas to the air above the IC/PCC pool surface. Four sets of differential pressure instrumentation on each steam supplyline and another four ' sets on each condensate return line are used to detect a possible LOCA. , liigh dPT signal coming from two of four dPT on the same line (steam or condensate) closes all isolation valves and therefore renders the IC inoperable. The operator cannot ovenide either the high radiation signals from the 1C atmosphere vents or the high differential prcssurc IGisolation signals.
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3 61 (Continued) A temperature element is provided in each vent line, at the downstream of the valves, to confirm vent valves function. Each temperature element is connected to a temperature recorder located in the main contro1 room. , A temperature element is prosided in each condensate return line, downstream ofisolation valve IV04. Each temperature clement is connected to a temperature recorder located in the - ruain control room.This temperature recorder, together with the difTerential pressure recorder which get the signal from one of the dPTs located on the condensate return line, allows . operators to conduct the five > car heat removal capalaility test on the IC. ! A test connection with an end cap is provided at the upstream side of the outer isolation valve, F002 on the steam supply line, to perform leak tests on isolation valves F001 and F002; A test connection with an end cap is proviiled at the downstream side of the outer isoladon valve, on the condensate return hne, F003, to perform leak tests on isolation valves F003 and , F004. A test connection with an end cap is provided upstream of the motor operated valve F013, on the purge line, to perform leak tests on excess flow valve F014. 3.6.2 Cnntrol I ocic and in(erlocks t 3.6.2.1 The initiation signals which actuate all three ICS loops at the same time, opening the valve F005, are describcd as follows;
- a. Inhoard or outhoard MSIV's position s 90% open on MSL(A) and inboard or outboard MSIV's position s 90% open on MSL(B) and the reactor mode switch in RUN".
There are two MSIVs on each main steam line. The logic is: 1-out-of-2 limit switches of either MSlVs on the same line plus 1 out-of-2 limit switches of either MSIVs on the other line (logie ; icut-of-2 twice). Both MSI 5 must be closed for IC actuation. Ilowever, during MSIV testing, one MSL is temporarily out of service. During these conditions , a 1-out-of 2 signal coming from the limit switches of the operational MSLwill cause ICS operation.
- b. RPV pressure (with logic 2-out-of-4) 2 7.447 MPa(g) (1080 psig) for 10 seconds. !
- c. Operator Manual initiation.
T he MSlV position switches for ICS control are electrically separate from similar switches that feed position signals to the RPS. When the RPV pressure decreases below a reset value 5.516 MPa(g) (800 psig), the operator is ahic to stop ICS loops individually, by overriding the signal coming from MSIV's closure, no v etv m It OltTIZ 16 OCT-!G Oth.~>4:02 'I'IC K U I" i
& GE Nuclear Energy 2sAs01s n a 11 m m. 15 ;
3.6.2.2 Condensate return valve F006 opens, automatically,in a loss of the two feeding electrical power divisions, or if the reactor level drops to 1.2, or, manually, by operator action. - S.6.2.3 Automatic actuation for the vent valves (F009 and F010, located in series) is provided by high RI'V pressure (above system actuation value) and either of condensate return valves not
- fully closed (with time delay to avoid vent opening during the initial transient). The valves close, preventing loss ofinventory, when the RPV pressure decreases below a reset value. -
S.6.2.4 Closure of the isolation valves (F001 through F004) and alarms shall be automatic on the . following signals coming from their own loop (logic 2/4): l
- a. 11igh mass flow in the IC steam supplyline; or i
- b. Iligh mass flow in the IC condensate return line; or
- c. liigh radiation in the pool steam flow path.
- 4. FUNCTIONS AND REQUIREMENTS '
4.1 Functions. The ICS shall automatically limit the reactor pressure and prevent SRV-operation when the reactor becomes isolated following scram during power operations. Fur thermore, the ICS. together with the water stored in the RPV, shall conserve sufficient reactor coolant volume to avoid automatic depressurization caused bylow reactor water Icycl. It must also, over a longer duration, remote excess sensibic and core decay heat from the reactor,in a passive way and with minimal loss of coolant inventory from the reactor, when the l normal heat removal system is unavailabic, following any of the following events:
.1
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Sudden reactor isolation from power operating conditions: Station blackout (i.e., unavailability of all AC power) for 72 hours; j Anticipated Transient Without Scram (ATWS). I To accomplish these functions, the minimum heat removal capacity of the ICS shall be 60 MWt F 1 at a reactor pressure of 7A20 MPa(g) (1050 psig) and the condenute return valve stroke <> pen 1 j time shell be 30 seconds with a logic delay time not to exceed 1 second after opening setpoint is o reached. The ICS is not an *Enginecred Safety Feature" (ESFis defined in reference 2.1.2.2.a.) because other ESFs provide piotection if the ICS is not available; however, the ICS is designed as a safety- : related system to remove reactor decay heat following reactor shutdown and isolation and to prevent unnecessary reactor depressurization and operation of ESFs which can also perform this - i fun c tion. ' wt o w p4 v ess; 11 OltTIZ .18-OCT-9'l 09: Tut:02 'I'IC K U I
, .. . _ . _ - _ _m . (h' GE Nuclear Energy 25r501s nev 11
.no. 1 s 4.2 fkatrsi.r System-Level Reouirements. The ICs shall be capabic of removing post-reactor ,
isolation decay heat with 2 out of 3 ICs operating and to reduce reactor pressure and I temperature to safe shutdown conditions (2.068 MPa (g) (300 psig and 215'C (420 F),in 36 hours, with occasional venting of radiolytically generated nonconde)nsable gases to the pr suppression pool. 4.2.1 Performance Remiirements. For operating temperatures and pressures, system operating modes and performance requirements, see paragraph 3.4 and the document "ICS Process Diagram" (ref. paragraph 2.1.1.b). The IC may have a steady state condensing enacity as high as 140% of nominal rating when new and unfouled. Therefore, the ICS shall be designed such that IC tubes are completely drained at 140% of nominal rating to minimize cyclic operation due to intermittent tube e flooding. , The system and equipment duty cycles are as follows (refer to document paragraph 2.1.1.f for - eveni descriptions): 4.2.1.1 Normal (Planned Operation) andjJpzLCanditions (Moderately Frequent Transientd
- Occurr ences ' !
- a. lleatups: 525 cvent 3 (405 cycles); events 10 and 11 (60 cycles);
cvent 20 (60 cycles).
]
Steam heatup cycles, starting from - cold conditions of 10"C, O MPa(g) to 289 C,7.240 MPa(g) (50 F,0 psig to 552 F,1050 psig) at 55'C/hr (100"F/hr) max.
- h. '
Cooldown n without IC opera tion: 403 cvent 15 (395 cycles); event 21 (8 cycles). Cooldown cycles starting from steam saturation - temperature of 289^C,7.240 MPa(g) to 10*C, O MPa(g) (552*F,1050 psig to 50*F,0 psig) at 55.5 C/hr (100'F/hr) max. 1 I I I at 0 sof ptt v e.w, i I
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it OltT12 18-OCT.93 09:54:02 'PIC H U P' -I
& GE Nuclear Energy 28x501s nu Il eno. 1, 4.2.1.1 (Continued)
Qccurrence3 c) Isolation condenser operations: 135 event 10 and i1 (60 cycles); event 12 (13 performance test cycles); event 20 (60 cycles); event 23 (2 cycles). > Starting from the IC standby conditions, the condensate return valve is opened and 10*C (50*F) condensate is replaced by 301.7 C (575"F) steam inside the IC tubes. After two hours, when the operator c. loses the valve F005, the temperature ofIC tid >cs and condenute return line decreases to 10*C (50 F). For onc event the valvc F005 is supposed to be closed after 72 hrs ofIC operation. d) OllE (Operating Basis Earthquake) 10 Dynamic analysis including OllE shall be based on the floor response spectra of figures 4.1 and 4.2. 4.21.2 Fmergency Conditions Unfrennent incident 0 a) ATWS (Anticipated Transient Without Scram): <10E-02 events / year crent 2V. Starting from the IC standby conditions,in 0.5 minutes the pressure rise up to 9.5 MPa(g) (1378 psig). Then the steam supply pressure remains constant for an indefinite penod of time (until thermal equilibrium is reached).Then, the temperature decreases to 10*C (50"F) at 55.5"C/hr (100'F/hr), 4.2.1.3 Fanited Conditions (Postulated Accidents) a) Large 1,0CA (Loss of Coolant Accident): <10E-04 cvents/ year event 27. Starting from the IC standby conditions. in one minute the temperature .iscs up to 301.7 C (575'i') and the pressure increases to 8.619 MPa(g) (1250 psig), with the condensate rernaining at 10*C (50 F) Then there is a 3.3 minute depressuri7ation to 1.103 MPa(g) (160 psig), then exponentially to 0.1 MPa(g) (15 psig) (10 minutes is the total time). utow m a, I n_ . . . . . It OltTIZ 18-OCT413 0954:02 'I'IC K U I"
& GE Nuclear Energy 2sas0ns acv B n as. , 4.2.1.3 (Continued)
Occurrences b) SSE (Safe Shutdown Earthquake) <10E-04 events / year , Ihnamic analysis in_cluding SSE shall be based on the Door response spectra of figures 1.3 and 4.4
- 4.21.4 Test Conditions a) Primary Side Hydrostatic Test 10 Test pressure = 1.25 design pressure test temperature: see '
ASME Ill App. G temperature limits apply to assure adequate fracture toughness. b) Tube I cakage Test (later) - (Test requirements to be defined) c) Others (la ter) For the isolation vahes oper ational readiness tests,240 full stroke closures tests in 60 years shali also be considered. The tests are donc during normal plant operation at 7.240 MPa(g),' 10*C (1050 psig,50 F) (for valves on the condensate return line) or 287.8'C (550 F) (for valves on the steam supply line). Full stroke closure is needed so the isolation condenser will not operate when the condensate return valves (F005 & F006), which are in series wi th these isolation valves, are opened during their operational readiness tests. For the condensate return valves operational readiness tests,240 open-close tests in 60 years shall be considened. The tests are donc during normal plant operation at.7.240 MPa(g) (1050 psig) and 10*C (50'F) minimum. Isolation valves F003 and F004 must be closed prior to opening these condensate return valves, : so the isolation condenser will not operate when F005 and/or F006 are opened, during operational readiness testing. 1.2.2 ConDguration and Anangement 4.2.2.1 The demtion difference between the IC pool bottom and the Reactor Pressure Vessel level B shall be equal to or greater than 6.5 meters. According to this elevation difference, the isolation condenser loop pressure drop (piping, cibow, valves and heat exchanger) shall be limited to 41.5 kPa (6 psi) at the maximum flow rate. i ed[O k1 lFilV 4Sfy l It OltT17. 18-OCT.93 09:5 4:0'.! 'PICKUI" ! l
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l h) GE Nuclear Energy 28A5ons ncy n en .19 i 4.2.2.2 After thermal expansion the steam supplyline piping minirnum slope toward the , Reactor Pressure Vessel shall be equal to or greater than one unit length elevation drop per one hundred uni tlengths of horizontalline run (i.e.,1/100) and the condensate return line minimum slope shall be 1/25; the only exception is the loop seal piping located at an elevation below the RPV noule. The loop seal is needed so there is not a high temperature difference between the two sides of the condensate return valves disk, and so that back flow through the condensate return line is avoided. The loop seal shall be made by providing a reduction in the pipe line elevation of 0.5 meters (minimum) below the RPV noule cicvation. 4.2.2.3 The vent valves (F007 through F012) shall be located near the top of the drywellin a scrtical pipe run. The piping minimum slope to the suppression pool shall be equal to or greater than 1/25, to prevent steam condensate induced water hammer. 4.2.2.4 The piping minimum slope toward the main steam line shall be, for the purgc line, equal to or greater than 1/25. 4.2.2.5 The straight length ofIC piping upstream and downstream of the elbow taps shall be (later from test) minimum. This length shall be suflicient to give a repeatable differential pressure at the highest flow rate. 4.2 2 6 The instrument piping which connects to the condensing chamber for difTerential pr essure measurement shall be routed downward with a continuous slope equal to or greater than 1/25. 4.2.2.7 System configuration shall permit insenice inspection. The physical arrangement and access of piping and valves for insenice inspection is defined in ref. paragraph 2.1.2.2.b. 4.2.2.8 System configuration shall permit component senicing in accordance with the plant operation and maintenance requirements (ref. 2.1.2.2.b.). 4.2.3 Safety 4.2.3 i The ICS is used to transfer decay and rcsidual heat from the reactor after the reactor is shutdown and isolated. 'I his function can also be performed by the Engineered Safety Features of A!)S, PCCS, and GI)CS. 7 he ICS shall be designed and qualified as a safety-related system to comply with 10CFR50 Appendix A, Criterion 31. Its function is to avoid unnecessary use of thee I.SFs for r(sidual heat remenal, but it is not an Engineered Safety Feature (see Appendix 10 Figure 10-1 which shows plant operationallogic as it relates to the several systems, including the ICS, which can be used to remove decay heat after reactor isolation).
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h) GE Nuclear Energy 95Asols ncv B m ,c. 90 4.2.3.1 (Continued) The ICS parts (including isolation vahes) which are located inside the containment and out to the IC flow restrictors shall be designed to ASME Code Section III, Class 1 Quality Group A.The ICS parts which are located outside the containment downstream of the flow restrictor shall be designed to ASMl; Code Scction Ill, Class 2 Quality Group IL The electrical design shall comply with IEEE Class 1E, and the entire system shall be designed to Seismic Category I. (See ref. 2.1.2.2 a for quality group, cicctrical, and seismic classifications).
'Ihe common cooling pool that ICs share with the PCC Condensers of the PCCSis safety related.
4.2.3.2 Two out of threc ICS loops are initially needed to remove post reactor isolation decay beat, after sustained reactor operation at 100% power (see Appendix 10 for ICS operational requirements). 4.2.3.3 As protection from missile, tornado and wind, the ICS parts outside the containment (the IC itstif) are located in a subcompartment of the safety related IC/PCC pool to comply with 10CFR50 Appendix A, Criteria 2,4 and 6. The IC steam supply pipes include flow restrictors, and the 1C condensate drain pipes are oflimited area so that an IC piping or tube rupture in the safety-related IC/PCC pool will limit flow-induced dynamic loads and pressure buildup ia the IC/PCC pool. Also guard pipes and special transition fittings are used at the locations wherc thc IC steam supply and condensate return pipes enter the pool at the containment pressure boundary. 4.2.3.4 Tbc valve actuators shall be qualified for senice inside the drywell for continuous senice under normal conditions and to be operabic for 4 hours with a steam environment. Thereafter, the valves are required to remain in their last position. 4.2 3.5 The ICs shall not fail in a manner that damages the safety related IC/PCC pool as a resul' of dynamic loads, including combined seismic, DPV/SRV or LOCA induced loads. 4.2.4 I!nign Iife. Material and equipment sclection for the system components shall be based on a usefullife of f,0 years. Therefore cach IC unit shall be designed for 60 years life and, if necessary, repair operations will be performed during refueling. However,in case of major damage of some component part, the module shall be casily removahic.
'Ihe electrical and pneumatic devices for the valves shall have a design life of 10 years (minimum).
Valve seals, gaskets and lubricants shall be based on a minimum 5 years' life. i w w w w. l l m -
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& GE Nuclear Energy 25A501a ncy B m ,c. 21 4.2.5 System 1nterfaces !
4.2.5.1 liuclear Boiler Sgem (Nils) (B21). Sec paragraph S.5.1. 4.2.5.2 Irak Detection and Isolation Sntem[LD&iS) (C21). See paragraph S.2. 4.2.5.3 Fuel and Auxiliary Ponis Cooline System (FAPCS) (G2D. 'l Description Duration ,
- Cooling and clean-up Intermittent ofIC/PCC pool 4.2.5.4 Mate.up_ Water sy2tsm (Mws) (Plo). ;
Description Duration Water to maintain IC/PCC pool Intermittent
- lesci 4.2.5.5 Hjgh Pressure Nitrogen Sugg}y System (HPNSS) (P54).
Description Duration Service in 21"C to 57*C (70 F to Continuous 135"F) max.,40% to 90% relative humidity 4.2.5.6 Passive Containment Cnoling System (PCCS) (Ti5). See paragraph 3.5.6. ' 4.2.5.7 Diret t Current Power Supply (R42) 7 De<<rintion Duration 125 V DC Continuous 4.2.5.8 Safsly_Syntm leagic_and control (SSi,C) (C74). See paragraph 3.5.8. 4.2.6 Instrumentation and Control 4.2.6.1 Instrumentation Requirement.s. The document Isolation Condenser System P&iD i Data" (reference parage aph 2.1.1.d) -later - speciGes system instrumentation requirements and - i , settings.
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&1 GE Nuclear Energy 25Asols w w>. 22 new 1.
4.2 6.2 Control Heouirernens. The document *1 solation Condenser System 1.D'(refcrcnec paragraph 2.1.1.c) specines requirements for system control logic. On this rnatter, see also i paragraph S.6.2. 4.24.3 Man. Mar hine in_tcrface Requirements. The system man-machine interface requirements will be descloped later, in conformance with the document listed in paragraph 2.1.2.1.m. 4,2.7 Availability 4.2.7.1 The ICS contribution to the total plant unavailability (plant forced outage time) shall be equal to or less than 0.17% according to the document 1isted in paragraph 2.1.2.1.n. 4.2.7.2 The system maintenance has to be performed during refueling. (The maintainability criterion for SitWR is that regular refueling and planned plant maintenance can be accomplished in one 5May outage every two years). 4.2 7.3 From the point ofview of refueling outage time, the ICSis not in a critical path. 4.2 7.4 The mean time between failures shall be, as an objective, two years: valve gaskets 25 yean; pressure retaining parts >60 years.
.+
4.2.7.5 The mean time to repair (M'ITR) of a failed component shall be low such that the repair has minimal impact on system availability and on equivalent availability factor (EAF). 4.2B Fmironment : 4.2.8.1 ICS components required to function under upset conditions shall be designed to remain functional under the abnormal crwironmental conditions in addition to the normal condidons denned in document paragraph 2.1.2.1.o. 4.2.8.2 For purposes of radiation shiciding design," Source Terms" document (see paragraph . 2.1.2.1.k) shall be used. 4.2.8.3 The ICS stearn supply and steam purge line piping and valves plus the drain line within shield wall and structural penetrations shall be provided with thermalinsulation,which limits beat loss to 252 W/m 2 (80 Btu /hr-f 2t ) of piping surface area during normal reactor operation. Inmlation shall contain no chlorides and shall retain no moisture if wetted. Insulation shall be simply removable to permit insenice inspection of piping. The remainder of'hc IC drain and vent lines that connect to d, bottom and top of the IC and are flooded durkg normal operation need not i e insulated. , 4.2.9 Maintenanc.c. No preventive maintenance actions are expected to be performed during normal plant operation. , Corrective maintenance for IC tube plugging following tube leak dctcction can be performed during refueling. I ucw eu w, ,
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H OltTIZ 18-OCT-93 OthM:02 ' PICKUP'
& GE Nuclear Energy usas01s to B wo. 2a 0 4.2.9 (Continued) 1' After closing the isolation valves to/from the IC and after emptying its pool subcompartment (see paragraph 4.3.2.2), plugging of the leaking tube can be performed by personnel operating t from the refueling floor. Maintenance will be performed from upper and lower end, after removal of the header covers. A remotely operated tool shall be used. -
If there is considerable damage to some component part of the IC, each module ofIC unit'shall be easily removable, af ter cutting the feed, drain and vent lines. The pool water in the isolation condenser subcompartment shall be removable without emptying the entire IC/PCC pool. 4.2.10 Smveillance Testing and insenice Inspection. 4.2.10.1 During plant outages routine ISI is required for the isolation condenser, piping , contr.inment penetration sleeves, and supports according to ASME Code Section lit and Section XI (requirements for design and accessibility of welds). IC removal for routine inspection is not required. Ultrasonic inspection is required for IC tubes / headers welds. , IC tubes shall be inspected by the eddy current method. .! 4.210.2 IC five year heat removal capability test is required.This test'is accomplished with data , derived from the temperature sensor located downstream ofisolation valve F004 together with the LD&lS differential pressure transmitter registering dilTerential pressure on the condensate return line. ;
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4.2.10.3 During plant normal operations, quarterly surveillance testing of normally-closed' valves F005 and F006 on each IC condensate line to the RPVis expected to be perfonned. ' a The test procedure for these condensate return valves starts after the condensate return line ; isolation valves F003 and F004 are closed; this avoids subjecting the IC to unnecessary thermal heat up/cooldown cycles. , Iv>1ation valves on the steam supply line (i.e. F001 and F002) shall remain open to avoid IC depressuriution. The test is performed by the controt room operator via remote manual switches that actuate the isolation valves and the condensate return vahes; the opening and closure of the vahesis scrified by their status light. I i 4~C W My e% I
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.R OltTIZ IS OCT !G 0M4:02 'I'lCKUI" l
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& GE Nuclear Energy 25r501s na B
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4.2.10.3 (Continued) ; The procedure is as follows: close F003 and F004 valves; , fully open, and subsequently close, valve F005 and then F006: re-open isolation valves to put the 1C in stand-by condition. 4.2.10.4 The isolation valves (F001, F002, F003, F004) shall be tested, quarterly, one at a time. If a splem actuation signal occurs during test, all the valves arc aligned automatically to permit , the IC to start operation. 4.2.10.5 Each vent valve (F007 through F012) shall be tested quarterly.
- The vahes which are located in scrics, shall be opened one at a time during normal plant opeiation. A permissive is provided such that the operator can open one vent valve if the other one in series is closed.
4.2.10.6 The purge line root valve F013 shall be tested quarterly. 4.3 Spnific Reauirements for Components 4.3.1 Ig,1ation Condenwr 411.1 The IC shall be designed for 30 MWt capacity. 4.3.1.2 Design pressure and temperature: 8.619 MPa(g) (1250 psig), , 302*C (575'F). ' 4.3.1.8 The IC is an extension of the reactor coolant pressure boundary . ASME Code Section III Class I (for parts through the containrnent boundary) and Class II (beyond the containment boundary) and TEMA Class R apply. ASME Code Section XI i requirements for design and accessibility of welds for inservice inspection apply, i 4.3.1.4 Tube surface (heat transfer area) is to be defined with 7.240 MPa(g) (1050 psig) ! satoraled reactor steam in the tubes and 100*C (212*F) pool water temperature. Fouling factor shall be considered only on the shell side, and a value to be used is 0.00000 mt*C/W (0.0005 fit*F-h/ Btu). M O act (8V W 41Wh ' f
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It OllTIZ 16-OCT 33 09:54:02 'PICHUI"
& GE Nuclear Energy usrsons ncv B s n 2s 4.3.1.4 (Continued)
A margin of 5% for tube plugging shall be included. Other additional margins used for defining heat transfer sus face shall not be included. 4.3.1.5 Material shall be nucicar grade stainless steel, or inconel, or other material which is not - susceptibic to 1CSC (Intergranular Stress Corrosion).- The specia1 requirements of reference 2.1.2.2.c apply. 4.3.1.6 Pressure losses shall bc limited to 20.68 kPa (3 psig) from the steam line penetration to the main drain line penetration (top of drywell top slab) at maximum expected steady state IC condensing capacity (140% of nomma1 capacity), 4.3.1.7 The acceptable rate of heat loss from an IC heat exchanger and its piping is 0.06 MWt. 4.3.lE The IC modules must be removabic for replacement,if nccded, during plant shutdowns. 4.3.1.9 The IC shall be provided with an appropriately mounted (in the high point above the water level) catalyst for hydrogen and oxygen recombination, during normal plant operating _ conditions.
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l As a backup to the catalyst and for long term assurance in the hydrogen water chemistry - ! condition case, a vent shall be provided that takes a small sucam of" gas
- mixture (steam and
, noncondensahics) from the top of the IC and vents the mixture downstream of the RPV. -i 4 4.3.2 Isolation Condenser Pool 4.3.2.1 Both the ICs and the PCC Condensers are located in a large water pool, positioned ; above the drywell. The large IC/PCC pool is partitioned but cach IC and PCC must be able to draw water from the entire pool. The pool air / steam space also is open. 4.3.2.2 The pool subcompartmentinterconnections shall be as follows: except for the IC and PCC pool compartments, all other pool subcompartments shall be interconnected below pool water lescl; the IC and PCC pool subcompartments shall be connected to the other pools below . the water level by locked open valves, one for each subcompartment, which can be closed to imlate and empty, using a portable pum ), the individual pardtioned subcompartment for maintenance of the unit (see ref. 2.1.1.a . 4.3.2.3 The water volume above the top of the IC tubes shall be such as to guarantee the ! required performance over a duration lasting 72 hours after reactor isolation, and to remove- l ,
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reactor system stored heat during station blackout (ref. 2.1.2.2.a). 4.3.2.4 1,ocked open subcompartment valve remote handwhccis shall be extended above water lescl. to locations which arc accessibic to the operator. l' i uco w w <n L- . _ It Oll'l IZ 18.OCT-93 09:M:02 'I'IC K U l" l
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& GE Nuclear Energy 'a rs013 acv 11 w w. 2s 4.3.2.5 The walls which contain the airspace flow path shall extend above the normal water -
level, 'Ihis enhances the Dow stability and heat removal of the condensers by establishing a flow path for the makeup water through the lower pipes. 4.3.2.6 The vent flow path area shalllimit the pool pressure to 34.4 kPa(g) (5 psig) (maximum) under postulated IC pipe rupture flow conditions (critical flow through an area equivalent to two 3" pipes plus one 4" pipe). 4.3.2.7 For the leak detection systems located in the IC/PCC pool see paragraph 3.2. 4.3.2.8 For IC/PCC pool instrumentation see ref. paragraph 2.1.2.1.f and 2.1.2.1.g. 4.3.2.9 For IC/PCC pool makeup see paragraph 3.2 and ref, paragraph 2.1.2.1.h. , 4.3.2.10 Steam dryers are needed to remove carryover moisture from the steam leaving the IC/PCC pool before this steam is released to the atmosphere. The moisture content of the steam leaving the vent pipe shall not exceed 2% of the mass flow of the steam generated in the IC/PCC pool. The inlet vane face area required is 4.5 square meters for each unit (13.5 square meters total). The required minimum elevation of the dryers above the pool water levelis equal to the head loss due to the flow through the flow path, from the pool water surface to downstream the steam dryers. 4.3.3 Isolation Valves (F001. F002. F003. F004). Two isolation vahes in series are located both-in the steam supply line and in the condensate return line ofeach loop. The inner valves (F001,~ F001) are nitrogen-motor-operated and shall be Div. II, DC, power operated; the outer valves (F002 F003) are motor-operated and shall be Div. I, DC, power operated. Gate type valves are required for low pressure losses. Double disk wedge gate type (or equivalent) which apply axial seating force after the paralle1 disks are in the closed position are preferred to prevent sticking closed when signaled to open. The isolation valves shall be both automatically and remote manually actuated with automatic closure overriding manual opening. The isolation valves shall be signaled to open if the initiation signal occurs during the test of , normally closed condensate return valves. , A remote manual closure switch position is provided for the isolation valves to permit the operator a means to isolate the IG.
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l It OltTIZ 18-OCT 93 09:M:02 TIC 1(111"
& GE Nuclear Energy 2srsals ncv B s . 2, 4.3.3 (Continued)
Closure of the isolation valves to any IC unit, and alarms, shall be automatic by an electrical signalinitiated by any 2 of 4 of the following signals, coming from the respecuve loop: 11igh mass flow in the IC steam supply line; Iligh mass flowin the IC condensate return line; High radiation in the pool vents. The position of the isolation valves shall be indicated in the control room to permit the operator to evaluate the effectiveness of drywell and containment isolation. Isolation valves shall close at a nominal rate of 30.5 cm (12 inches) of stem movement per minute (one minute maximum) with critical flow through the valves or in an adequate time such as to limit offsite doses below the limit values in case of IC pipe break, assuming the reactor coolant contains radioactivity at the limiting value for continued power operation, as specified in technical specification operating limit. Each nits ogen-motor-operated valve shall be provided with a pneumatic accumulator which is sired to provide sufficient capacity to ensure adequate supply pressure to the valve actuator to close, re.open and re-close the valve while the discharge pressure is at containment design pressure. The accumulator shall be charged by the HPNSS (ref. paragraph 4.2.5.5) which shall aho provide makeup for valve actuator system Icakage. , 1 The accumulator shall be of corrosion resistant material and be provided with low point drain. I Pocumatic inlet and outlet piping shall be arranged to permit the accumulator to act as a crud trap. The fittings and pipe between the accumulator and the valve actuator should be austenitic stain 1 css stcc1 piping or flexible tubing. A check valve of corrosion resistant material shall be provided on the line supplying the nitrogen accumulator to prevent leakage of gas out of the accumulator in the event of a gas
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supply failure. The ci eck vahe shall have a resilient seat and be spring loaded. The IC pneumatic system (piping and equipment) leakages and accumulator volumes shall be established as input to containment pressure determinations. o.o w n v os.
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. us l 4.3.4 Condensate Return Vahes (F005. F006) l 4.3.4.1 Condensate Return Valve (F005). This vahc shall be a motor-operated, double disk wedge gate type valve, ON/OFF, and designed to fail as-is on loss of essential 125 V DC power.
For the dilTerent loops the valve shall be powered as following: loop A. Div. I; loop B, Div. II; loop C, Div. !!I. A gate type valyc is required for low pressure losses. Doubic disk wedge gate type (or equivalent) whkh apply axial seating fone after the parallel dists are in the closed position is needed to minimlic icakage and to prevent sticking closed when signaled to open. A device or small pauageway shall be provided to relieve bonnet pressure to the upsticam end (IC side) of the valve. T his is to prevent locLup of the valve due to thermal expansion of water inside the bonnet and between the disks. ICS automatic actuation is prosided by the following signals:
- a. MSIV valve position on MSL A s 90% open, plus MS!V valve position on MSL B s 90% cpen, (Reactor Mode Switch in *run" only);
- b. RPV pressure 2 7.447 MPeg (1050 psig) for 10 seconds;
- c. operator roanual initiation.
The logic shall be arranged so as to actuate all three loops at the same time. A stroke-open time of 30 seconds is required to meet system performance requirements. The operator shall be abic to stop any individua11CS loop whenever the RI'V pressure is below a reset value of 5.516 MPeg (800 psig), overriding TCS automatic actuation signal coming from MSIV's closure. Automatic reset of this override is provided when the pressure increases above the stated rewt value. The RPV high pressure automatic signal shall not have an override. 4.3 4.2 Cerdennit}<eturn B pmGdxc_EQDO). 3 This valve shall be a spring-loaded, pnenmatic, piston-operated globe valve, designed to fail open on loss of pneumatic pressure to the valve actuator. This valve shall also be signaled to open when reactor water levci drops to 1.2.
'I he vahe shall be piloted by two DC solenoid-operated pilot valves, supplied from two separated source of safetygrade (Clau 1E) hattery powcr (loop A, Div.1,2; loop 11 Div. 2,3; knop C Div. 3,1).
A pneumatic anumulator shall be located close to the valve to provide pneumatic pressure for the purpose of assisting in valve closure when both pilots are energiicd or in the event of failure of pneumatic supply pressure to the vahe operator. ne o m n nu,
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h GE Nuclear Energy 25A501S m.v B eum 29 9 4.3.4.2 (Continued) The valve actuation system and the actuation pressure source shall be piped in such a way that : when one or both DC solenoids are energized, the accumulator shall pressurize the valve operator to close the valve, overcoming the opening force exerted by the spring. When both solenoids are de<nergized, as in a loss of two divisions of electrical power supply or manual switch in the open position, the accumulator path shall be closed and the nitrogen in the valve operator shall be vented, so that the spring opens the valve. 4.3.5 Vent Valves (F007. F008. F0&A F010. F011. F012) 4.3.5.1 Too Vent W1ves (F007. FD0m, Two valves in series are located in the ventline from the top heades. . Normally closed, fail closed, solenoid-operated, globe type, these valves can be opened by the control room operator via remote manual switch (onlyif either of the condensate return valves . is not fully closed) if discharging noncondensabic gases also from the IC top is necessary. During plant startup the valves shall be opened by the operator (a permissive is prosided for that) to dischargc air from the IC and ICS piping. The valves can also be opened, one at a time, during nor mal plant operation, to perform a i quarterly test. 1 Both valves for loop A, B and C shall be Div. 1,2,3125 V DC power operated, respecthcly. ; 4.3.5.2 [bttom Vent Valves (F009. FOl0. FOI 1. F0121. The bottom vent valves F009 and F010 , f shall be normally closed, globe type, solenoid-operated valves, designed to fail close on loss of 125 V DC powcr. Automatic actuation for these two series vent valves (F009, F010),is provided by the following , signals: high RPV pressure of 7.516 MPa(g) (1090 psig) and either of the condensate return or ; condensate return bypass valves not fully closed, with time delay, to avoid vent opening when the IC enters in operation This time delay shall be chosen so that the peak transient reactor pressure will have dropped below the automatic vent set pressure after the condensate drain valves are opened. When the RPV pressure decreases below a reset value and after a time-delay ; to avoid too many cycles, these two vent valves close, preventing loss ofinventory to the i supprenion pool. During norrnal plant operation the valves F009 and F010 can also be opened by the operator, only if either of the condensate return or condensate return bypass valves is not fully closed, and, one at a time, to perform a quarterly test. The vent bypass motor <>perated valves (F0ll, F012) permit the operator to open a noncondensable gases flow path (only if either of condensate return vafves is not fully closed), . in case of F009 and/or F010 fail to open. .) 1
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APPENDIX 10 SWTEM TECHNICAL SPECIFICATIONS
-l The attached figure 10-1,
- Operational logic Diagram", defines the required IC loop operational .
status together with other systems and ESPs (Engineered Safety Features) which are needed to 1 operate the reactor at 100%, and lower power, including hot and cold, shutdown. - A given ICS loop shall be considered operabic if: i isolation vahes closure are successfully tested, at Icast once every 3 months: condensate return valves are successfully tested, at least once every 3 months; vent vahEs are successfully tested, at least once every 3 months; 1C thermal performance is acceptable (successful test every 5 years); DC power division 1,2 and 3 are available (for ICS vahrs operability); { High Pressure Nitrogen Supply System is availabic (for nitrogen operated valves operability); 1 IC/PCC pool water level is nonnal; ; instruments, logic and control are operational. ,I 7 he figure 102 *ICS Technical Specifications I,ogic Diagram" which is an abstract of the l
- Operational Logic Diagram" shall be used to define Technical Operating Specifications for the Pla n t. ,
The figure 10-3 *1CS Technical Specification Flow Chart"is a simplified version of figure 10-2 for use by the operator. i j l l r sof.O kJF (PV V 414, t it OltT14 1S-OCT-9:5 OthM:02 'I'IC K U l"
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~. so APPENDIX 20 l
SWTEM OPERATING CONDITIONS l The operating conditions which arc described in the paragraphs which follow are: l l
- a. Startup ,
(1) Cold stasi : i (2) llot restart
- b. Normal Plant Operation ,
- c. Shutdown
- d. Refueling
- e. Isolation Condenser normal operation (upset conditions) 20.1 Startuo - Cold Start, This paragraph covers start from atmospheric pressure and low o
temperatures. The initial conditions are as shown on the Isolation Condenser System P&ID (ref. 2.1.1.a), except the top vent valves (F007 and F008) are opened to warm the IC steam line and purge noncondensables during startup heating. In addition:
- a. Allinstruments are in operation.
- b. All accumulators are at normal pneumatic pressure.
- c. Reactor Mode Switch is in STARTUP mode.
20.2 Startup-Ilot Restart. This section covers starts with the reactor pressurized and hot.The initial conditions are as shown on the Isolation Condenser System P&lD;in addition:
- a. All insu uments are in operation. ,
I
- b. All accumulators are at normal pneumatic pressure.
- c. Reactor Mode Switch is in STARTUP mode.
20.3 Normal Plant Operation. Normal operation !ncludes ste >dy-state operation at a given power level up to rated power. The initial conditions are ,, snown on the isolation Condenser : System P&ID. In addition: j k i
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- <0 20.3 (Continued)
- a. All instruments are in operation.
- b. All accumulators are at normal pneumatic pressure.
- c. Reactor biode Switch is in RUN position.
Normal operation is the condition at the end of Startup followed by switching the Reactor biode Switch to RUN position or the condition following a planned or unplanned transient which does not scram the reactor. In case oflarge leak, no operator action is needed. The affected IC loop is automatically isolated , (closure of the vahes F001 through F004) by the signals coming from the Leak Detection and Isolation System. On the purge line, the excess flow valve perfonns the isolation. The existence of smaller leaks that cause radiation in the exhaust line that exceed background radiation when the IC units are not in operation is detected, and alarms are generated. . The purpose of the alarms is to alert the operator that there may be an IC leaking and that a further check is needed to confirm the Icak. This forther Tzak check is done by the operator, isolating each IC loop, onc at a time, to . determine whether the leak can be stopped. The size of a leak cannot be cortclated with the ' characteristics of the alarm signals, therefore the affected IC toop shall remain out of service if the leak indication returns to normal (alarm stopped) when the affected ICis isolated (the afTected IC loop shall remain ir.otated untilit is repaired during plant shuidown), . The operator shall close the valve TOIS of the leaking loop, to completely isolate the affected isolation condenser frcm the primary side (the excess flow valve is not efTective to prevent back ' flow through the purge line in case oflow flow). 20.4 Shutdown. Shutdown starts from the reactor in Hot Standby with all contro1 rods inserted and all conditions correspond to this. The Reactor hiode Switch in S11UTDOWN mode and the isolation Condenser System is " ready. _s to start" as during normal plant operation. 20.5 Refueline. During refueling allIC system valves (F001 through T01 ; are closed. Then maintenance can be performed. ' 3 l i wo w ny m, l It OftTIZ 18 OCT.93 09:.% 02 TICKUl"
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GE Nuclear Energy 28xs013 . ~a. < n ncv B FINAL 20.6 liel;tl ign Condenser Normal Operation (unset condition 0 During IC normal operation the valve suntus is as follows: Valve , number Status . F001 Open - F002 Open F003 Open F004 Open F005 Open (closed if failed) F006 Closed (open iflevel $1.2 and/or , station blackout with loss of safety grade battery power) F007 Closed These vent valves open, automatically (F0@/10) or F008 Closed rnanually (F007 through F000 Closed F012), when venting to the F010 Closed suppression poolis needed. F011 Closed F012 Closed F013 Open (the valve can remain open, ,
.. because hfSIVs are closed)
After the ICS loops start into operation no actions are needed by the operator. .The condensate ,
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return vahts can remain opened without reaching RPV level 1. The operator can reclose the condensate return valves only when the RPV pressure is below 5.516 h1 Pag (800 psig). k
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