34
SI-HITACHI GE Hitachi Nuclear Energy James C. Kinsey Vice President, ESBWR Licensing PO Box 780 M/C A-55 Wilmington, NC 28402-0780 USA T 910 675 5057 F 910 362 5057 [email protected] MFN 06-249 Supplement 2 Docket No. 52-010 February 18, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Subject: Response to NRC E-mail Request for Additional Information Related to ESBWR Design Certification Application, Component and Subsystem Design, RAI Number 5.4-32 S02 Enclosure 1 contains GEH's response to the subject NRC RAI transmitted via e- mail on May 7, 2007. The previous response was submitted to the NRC via Reference 2 in response to Reference 3 (RAI 5.4-32 S01). The initial request was received from the NRC via Reference 5 (RAI 5.4-32), to which GEH responded via Reference 4. If you have any questions or require additional information, please contact me. Sincerely, )ames C. Kinsey Vice President, ESBWR Licensing ýDcýý'ýý "VIC

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Page 1: GE Hitachi Nuclear Energy SI-HITACHI

SI-HITACHIGE Hitachi Nuclear Energy

James C. KinseyVice President, ESBWR Licensing

PO Box 780 M/C A-55Wilmington, NC 28402-0780USA

T 910 675 5057F 910 362 [email protected]

MFN 06-249Supplement 2

Docket No. 52-010

February 18, 2008

U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555-0001

Subject: Response to NRC E-mail Request for Additional InformationRelated to ESBWR Design Certification Application,Component and Subsystem Design, RAI Number 5.4-32 S02

Enclosure 1 contains GEH's response to the subject NRC RAI transmitted via e-mail on May 7, 2007. The previous response was submitted to the NRC viaReference 2 in response to Reference 3 (RAI 5.4-32 S01). The initial requestwas received from the NRC via Reference 5 (RAI 5.4-32), to which GEHresponded via Reference 4.

If you have any questions or require additional information, please contact me.

Sincerely,

)ames C. KinseyVice President, ESBWR Licensing

ýDcýý'ýý"VIC

Page 2: GE Hitachi Nuclear Energy SI-HITACHI

MFN 06-249, Supplement 2Page 2 of 2

References:

1. Request for additional information, E-mail from the NRC (ShawnWilliams), requesting that GEH provide, in the DCD, a detailed descriptionof how the nitrogen rotary motor operated valve (NMOV) and thepneumatic piston-operated valve (NO) valve operate, specifically theactuator, dated May 7, 2007

2. MFN 07-192, Letter from James C. Kinsey to U.S. Nuclear RegulatoryCommission, Response to Portion of NRC Request for AdditionalInformation Letter No. 26 - Isolation Condenser System - RAI Numbers5.4-22 S01, 5.4-29 S01, 5.4-32 S01, 5.4-41 S01, 5.4-42 S01, and 5.4-52S01, dated April 20, 2007

3. Request for additional information, E-mail from the NRC (ShawnWilliams), requesting that GEH provide a detailed description of how thenitrogen rotary motor operated valve (NMOV) and the pneumatic piston-operated (NO) valves operate, dated February 5, 2007

4. MFN 06-249, Letter from David Hinds to U.S. Nuclear RegulatoryCommission, Response to Portion of NRC Request for AdditionalInformation Letter No. 26 Related to ESBWR Design CertificationApplication - Isolation Condenser - RAI Numbers 5.4-21, 5.4-23 through5.4-26, 5.4-28 through 5.4-30, 5.4-32 through 5.4-35, 5.4-38, 5.4-41, 5.4-42, 5.4-44 through 5.4-46, 5.4-48, 5.4-50, and 5.4-52, dated August 1,2006

5. MFN 06-141, Letter from the U.S. Nuclear Regulatory Commission, toDavid H. Hinds, Request for Additional Information Letter 26 Related toESBWR Design Certification Application, dated May 3, 2006

Enclosure:

1. MFN 06-249, Supplement 2, Response to NRC E-mail Request forAdditional Information, Related to ESBWR Design CertificationApplication, Component and Subsystem Design RAI Number 5.4-32 S02

cc: AE Cubbage USNRC (with enclosure)GB Stramback GEH/San Jose (with enclosure)RE Brown GEH/Wilmington (with enclosure)DH Hinds GEH/Wilmington (with enclosure)eDRF 0000-0065-4743, Rev. 2

Page 3: GE Hitachi Nuclear Energy SI-HITACHI

Enclosure 1

MFN 06-249, Supplement 2

Response to NRC E-mail Request for

Additional Information Related to

ESBWR Design Certification Application

Component and Subsystem Design

RAI Number 5.4-32 S02

Page 4: GE Hitachi Nuclear Energy SI-HITACHI

MFN 06-249Supplement 2Page 2 of 4

NRC RAI 5.4-32

Explain how the nitrogen rotary motor operated (NMO) and the Nitrogen piston operated (NO)valves perform their function.

GE Response

Nitrogen Rotary Motor Operated Valve (NMOV)

The purpose of the NMO valve is to protect against loss of pressure boundary integrity of theoutside containment portion of the ICS.

The NMO valve closes upon either a signal of excess flow (high DP) in the IC pipeline or asignal of high radiation in the IC/PCC pool vent line to the atmosphere.

Pneumatic Piston-Operated Globe Valve (NO)

The NO valve provides diversity of actuator type (mounted in parallel with F005); actuator holdsvalve closed; valve is opened by spring on shutoff or loss of pneumatic pressure/electrical signal.

The NO valve is normally closed; one of two IC condensate return valves in parallel; opens uponinitiation of the IC system to permit return of condensed reactor steam back to the reactor vessel.

DCD change is not required.

Page 5: GE Hitachi Nuclear Energy SI-HITACHI

MFN 06-249Supplement 2Page 3 of 4

NRC RAI 5.4-32 SO0

GE's response to 5.4-32 (AMFN 06-249) states the purpose and actuation logic but it does notdescribe how the nitrogen rotary motor operated valve (NMOV) and the pneumatic piston-operated valve (NO) valves operate. Since these valves are not the standard valves, provide adetailed description of the valve operation. 5.4-41 and 6.3-18 through 6.3-25 (MFN 06-249,MFN 06-241) Your response to several ITAAC related RAIs stated that there are ongoingdiscussions with the industry and the NRC as to the content that is required in Tier 1. Whensuch requirements are settled upon, each system in Tier 1 may go through a thorough review tosatisfy the agreed upon requirements. Please provide revised responses to these RAIs to addressthe original questions. There may be additional RAIs with similar responses. Those responsesshould also be supplemented.

GE Response

Valve operation for Isolation Condenser System (ICS) nitrogen rotary motor operated valves(NMOVs) and pneumatic piston operated valves (NOs) are described in detail in DCD Tier 2,Revision 3, Tables 6.2-23 through 6.2-30. These tables identify the valve type, actuation signal,valve position, and other design information, for each IC train valve.

ITAAC related RAI for the ICS have been revised and updated in Revision 3 of the DCD Tier 1Table 2.4.1-1. Specifically, RAI 5.4-41 was addressed specifically in DCD Tier 1 Table 2.4.1-1Items 18 and 19.

Resolution of RAI 6.3-18 though 6.3-25 is addressed in the response to RAI 6.3-18 SO0 (MFN06-241 Supplement 2).

DCD Impact

No DCD changes will be made in response to this RAI.

Page 6: GE Hitachi Nuclear Energy SI-HITACHI

MFN 06-249Supplement 2Page 4 of 4

NRC RAI 5.4-32 S02

Email/from Shawn Williams:

GE's response to 5.4-32 (MFN 06-249) states the purpose and actuation logic, but it does notdescribe how the nitrogen rotary motor operated valve (NMOV) and the pneumatic piston-operated valve (NO) valve operate. Since these valves are not the standard valves, pleaseprovide a detailed description of the valve operation, specifically the actuator, in the DCD.

GEH Response

In DCD Revision 4, valves B32-F002 (ICS steam supply line containment isolation valve), B32-F003 (ICS condensate return line containment isolation valve) and B32-F006 (ICS condensatereturn line bypass valve) were shown as having nitrogen-operated (NO) actuators. Theseactuators are similar to air-operated piston actuators, except nitrogen is used instead of air todrive the piston. B32-F002/F003 will have double-acting actuators for fail-as-is operation, andB32-F006 will have a single-acting design that will fail open.

Valves B32-FOO1 (ICS steam supply line containment isolation valve), B32-F004 (ICScondensate return line containment isolation valve) and B32-F005 (ICS condensate return linevalve) were shown as having nitrogen motor-operated (NMO) operators. These operators aresimilar to a standard electric motor operator; however, a pneumatic motor is used in place of theelectric motor. Pressurized nitrogen drives the motor, which results in either thrust or torquebeing applied to the valve stem through a reduction gear set, a worm gear and a stem nut.Nitrogen is supplied from accumulators.

However, the NMO actuators on these in-containment valves are being changed to an electro-hydraulic, fail as-is design because of the nitrogen volume demand of the NMO operators. Theelectro-hydraulic actuators use a low-voltage electric motor-driven pump to drive a double-acting piston operator. The low-voltage power requirement permits operation of the electro-hydraulic actuators from available battery-supported safety-related power supplies.

DCD Impact

DCD Tier 1 Table 2.4.1-1 and Figure 2.4.1-1, and Tier 2 Section 5.4.6.2.2, Tables 3.9-8, 6.2-15,6.2-23, 6.2-25, 6.2-27 and 6.2-29 and Figure 5.1-3 will be revised as shown on the attachedmark-up.

Page 7: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AR Rev. 05ESBWR Design Control Document/Tier 2

5.4.6 Isolation Condenser System (ICS)

5.4.6.2 System Description

5.4.6.2.2 Detailed System Description

The ICS consists of four high-pressure, independent trains, each containing a steam IC as shownon the ICS schematic (Figure 5.1-3 and 5.4-4a & b).

Each IC unit is made of two identical modules (see Table 5.4-1). The units are located insubcompartments adjacent to a large water pool (IC/PCC expansion pool) positioned above, andoutside, the ESBWR containment (drywell).

The IC is configured as follows:

* The steam supply line (properly insulated and enclosed in a guard pipe which penetratesthe containment roof slab) is vertical and feeds two horizontal headers through fourbranch pipes. Each pipe is provided with a built-in flow limiter, sized to allow naturalcirculation operation of the IC at its maximum heat transfer capacity while addressing theconcern of IC breaks downstream of the steam supply pipe. Steam is condensed inside135 Inconel 600 vertical tubes and condensate is collected in two lower headers. Twopipes, one from each lower header, take the condensate to the common drain line whichvertically penetrates the containment roof slab.

* A vent line is provided for both upper and lower headers to remove the noncondensablegases away from the unit, during IC operation. The vent lines are routed to thecontainment through a single penetration.

" A purge line is provided to assure that, during normal plant operation (IC system standbyconditions), an excess of noncondensable gases does not accumulate in the IC steamsupply line, thus assuring that the IC tubes are not blanketed with noncondensables whenthe system is first started. The purge line penetrates the containment roof slab.

" Containment isolation valves are provided on the steam supply piping and the condensate* return piping. The valve designs are the same for all four valves - either gate valves orquarter-turn ball valves. For two of the valves (one per line), the actuators are nitrogen-powered piston operators, which are similar to piston air operators. Nitrogen is suppliedfrom accumulators. For the other two valves, the actuators are electro-hydraulicoperators, which use an electric motor-driven pump to drive the piston.

* Located on the condensate return piping just upstream of the reactor entry point is a loopseal and a parallel-connected pair of valves: (1) a condensate return valve (nitrogen-operated, fail as is) and (2) a condensate return bypass valve (nitrogen piston operated,fail open). Two different valve actuator types are used to ensure open flow path byeliminating common mode failure. Therefore, the condensate return valves are singlefailure proof for each unit. Because the steam supply line valves are normally open,condensate forms in the IC and develops a level up to the steam distributor, above theupper headers. To start an IC into operation, the nitrogen motor-operated condensatereturn valve and condensate return bypass valves are opened, whereupon the standingcondensate drains into the reactor and the steam-water interface in the IC tube bundle

Page 8: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AR Rev. 05ESBWR Design Control Document/Tier 2

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 opens if the DCpower is lost.

* System controls allow the reactor operator to manually open both of the condensatereturn valves at any time.

* Located on the condensate return line, downstream from the second inboard containmentisolation valve is an in-line vessel. The inline vessel is located on each ICS train toprovide the additional condensate volume for the RPV. The volume of each vessel is noless than 9m 3 (318 ft3). The added inventory the inline vessel supports:

- Use of a single level logic for ECCS initiation, and

- Reactor vessel level that does not fall below the Level 1 setpoint during a loss offeedwater or loss of preferred power.

* The dryer/separator pool and reactor well are designed to have sufficient water volume toprovide makeup water to the IC/PCC expansion pools for the initial 72 hours of a LOCAresponse. This water is be provided through ICS connections between the dryer/separatorpool and IC/PCC pools. These connections open passively when the level in the IC/PCCpool reaches a low set point relative to the level in the Dryer/Separator pool.

* A loop seal at the RPV condensate return nozzle assures that condensate valves do nothave superheated water on one side of the disk and subcooled water on the other sideduring normal plant operation, thus affecting leakage during system standby conditions.Furthermore, the loop seal assures that steam continues to enter the IC preferentiallythrough the steam riser, irrespective of water level inside the reactor, and does not movecounter-current back up the condensate return line.

During ICS normal operation, noncondensable gases collected in the IC are vented from the ICtop and bottom headers to the suppression pool. Venting is controlled as follows:

* Two normally closed, fail-closed, solenoid-operated lower header vent valves are locatedin the vent line from the lower headers. They can be actuated both automatically (whenRPV pressure is high and either of condensate return valves is open) and manually by thecontrol room operator. Two normally closed, solenoid-operated lower header bypassvent valves allow the operator to vent noncondensable gases in case of failure of theautomatic lower header vent valves.

* The vent line from the upper headers is provided with two normally closed, fail-closed,solenoid-operated upper header vent valves is-fevided -to permit opening of thisnoncondensable gas flow path by the operator, if necessary.

* All the vent valves are located in vertical pipe run near the top of the containment. Thevent piping is sloped to the suppression pool to prevent accumulation of condensate in thepiping.

The cross-tie between IC steam line and DPVs in the ESBWR produces no significant negativeimpact on the loads and safety margins. The key details are as follow:

* During a LOCA event, the peak operation of ICS occurs during the early part of thedepressurization and before the DPV openings.

Page 9: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AR Rev. 05ESBWR Design Control Document/Tier 2

" At the time of first DPV opening, there is no subcooled water inside the IC drain line andin the downcomer region. The total dynamic head (DPV flow + IC steam flow) insidethe stub tube is small and does not induce back flow into the IC tubes.

" Failure of one IC drain valve or one DPV valve does not prevent the operation of theother system connecting to the common stub line.

* Based on first and third bullets above, the common-tie between the ICS and DPVs on thestub line has no significant impact on the safety margins [refer to fifth bullet below].Therefore, the physical separation of these two systems is not necessary.

* Parametric studies were performed with and without the function of the IC heat transfer(i.e., no IC condensation). The results indicate that the long-term containment pressure isslightly higher for the case without the function of IC heat transfer.

During ICS standby operation, discharge of excess hydrogen or air is accomplished by a purgeline that takes a small stream of gas from the top of the isolation condenser and vents itdownstream of the RPV on the main steamline upstream of the MSIVs.

Each IC is located in a subcompartment of the Isolation Condenser/Passive Containment Cooling(IC/PCC) pool, and all pool subcompartments communicate at their lower ends to enable fullutilization of the collective water inventory, independent of the operational status of any givenIC train. A valve is provided at the bottom of each IC/PCC pool subcompartment that can beclosed so the subcompartment can be emptied of water to allow IC maintenance.

When the heat exchanger goes into operation, the pool water can heat up to about 101 °C (214'F)and start to boil; steam formed, being nonradioactive and having a slight positive pressurerelative to station ambient, vents from the steam space above each IC segment where it isreleased to the atmosphere through large-diameter discharge vents.

A moisture separator is installed at the entrance to the discharge vent lines to preclude excessivemoisture carryover.

IC/PCC pool makeup clean water supply for replenishing level during normal plant operationand level monitoring is provided from the Fuel and Auxiliary Pools Cooling System (FAPCS)(Subsection 9.1.3).

A safety-related independent FAPCS makeup line is provided to convey emergency makeupwater into the IC/PCC expansion pool, from piping connections located at grade level in thereactor yard external to the reactor buildings.

Four radiation monitors are provided in the IC/PCC pool steam atmospheric exhaust passages foreach IC train. They are shielded from all radiation sources other than the steam flow in theexhaust passages for a specific IC train. The radiation monitors are used to detect IC trainleakage outside the containment. Detection of a low-level leak (radiation level abovebackground - logic 2/4) results in alarms to the operator. At high radiation levels (exceeding siteboundary limits - logic 2/4), isolation of the leaking isolation condenser occurs automatically byclosure of steam supply and condensate return line isolation valves.

Four sets of differential pressure instrumentation are located on the IC steam line and anotherfour sets on the condensate return line inside the drywell. Detection of excessive flow beyondoperational flow rates in the steam supply line or in the condensate return line (2/4 signals)

Page 10: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AR Rev. 05ESBWR Design Control Document/Tier 2

results in alarms to the operator, plus automatic isolation of both steam supply and condensatereturn lines of the affected IC train.

Page 11: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AR Rev. 05ESBWR

-- -------------------------- ------- - -- -- ---------- - -.. - I.-.-.---.-.------.--

I I ISOLATION CONDENSER

,~I I

I- - - - I - - - I ' I I i

Design Control Document/Tier 2

ATMOSPHERICI IVENT

I /

EH

TRAINA

Figure 5.1-3. Isolation Condenser System Schematic I

Page 12: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

Table 6.2-15

Legend For Tables 6.2-16 through 6.2-452

(a) Termination Region of the leakage through packing/stem only for outboard valves:al = Reactor Buildinga2 Main Steam Tunnel

(b) Termination Region outside containment of the leakage past seat:bl = Pool open to reactor buildingb2 = External environmentb3 = Main Condenserb4 = Isolation Condenser poolb5 = Reactor buildingb6 Close loop outside containmentb7 = Radwaste System

(c) Value Operator Types':AO/AcAONO/AccNONMO/AccNMOMOSOPMEH

= Air-operated valve with accumulator= Air-operated valve without accumulator= Nitrogen-operated valve with accumulator- Nitrogen-operated valve without accumulator= Nitrogen-motor operated valve with accumulator= Nitrogen-motor operated valve without accumulator= Motor-operated valve= Solenoid-operated valve= Process-medium operated valve= Electro-hydraulic operated valve

(d) Isolation Signal Codes:B Reactor vessel low water level - Level 2C Reactor vessel low water level - Level ID Main steamline high flow rateE Turbine inlet low pressureF Main steamline tunnel high ambient temperatureG Turbine area steamline high ambient temperatureH High DW pressureI IC/PCC pool high radiationK IC lines high flowL Low main condenser vacuumM High flow in the RWCU/SDC loopN Standby Liquid Control System operating

The operator types listed embody certain functional characteristics, such as those that fail-safe vs. fail as-is, orthose that have a stored energy source (spring, fluid accumulator) to permit completion of function or repeatperformance of functions upon loss of normal power supply. The actuator type listed for any valve application isgenerally based on historical BWR design. Alternate valve-&-operator combinations that provide equivalentfunctional capability and performance are pennissible.

Page 13: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

P Remote manualQ Process actuatedR Local manual (By Hand)S High radiation in DW sump lineT High HVAC radiation exhaust from refueling area or from Reactor Building.U Feedwater lines differential flow

(e) Valve Types2:

OS&Y Outside stem and yoke, typical of gate and globe valve designs that have anexternally exposed rising or non-rising stem that connects a yoke-mounted actuator (anytype) to the internal disk assembly, and includes a stem sealing gland (with or without ahermetic disk-to-stem internal seal such as a metal bellows or diaphragm).

Gate (GT) Any of several styles of valve where the disk is formed as a plate whichtransits the fluid flow stream with an orthogonal motion. The seating surface of the valvebody is also manufactured to be at a slight angle to or set orthogonal to the flow stream. Thedisk can be wedge-shaped in either solid or split/flexible form, or as two plates mountedback-to-back or similar form (e.g., parallel-slide or double-disk gate), matching the seatconfiguration. Additional variants include shutter type and rotating-slide type gate valves.

Globe (GB) Any of several styles and configurations of valves where the disk is formedeither as a truncated cone or curved section (spherical, elliptical, parabolic, etc.) with orwithout a following structure to support and guide the disk-&-stem motion. The body seat iscentered around the flow stream and the disk-&-stem motion axis is perpendicular to the seat(i.e., axially concentric with the flow stream at the seat orifice plane). Body variations arebased on the angle of the inlet-to-outlet nozzles and/or the angle of the stem to the inlet oroutlet nozzle. Stem and disk assembly may be unconnected to permit a combined check andstop valve function (floating-disk stop, non-return check, etc.).

Quarter-turn (QT) Any of various types of butterfly (QBF) and ball (QBL) valves where thestem/shaft is mounted across the flow stream and the pallet, ball or plug (disk) is rotatedthrough a 90 degree arc from full-closed to full-open. The actuator mechanism is typicallymounted directly to the valve bonnet and there may be no exposed stem. The butterfly valvepallet remains in the flow stream when the valve is open whereas the plug and ball valvesprovide either a reduced or full pipe diameter flow orifice and shield the valve and diskseating surfaces when opened.

Axial-flow (AF) A variant of globe valves with the valve bonnet and disk-stem assemblyrotated to be completely internalized and concentric with the fluid flow axis through thevalve. There may be no external exposed stem or sealing gland, depending on designfunction(s) and selected actuation option. Based on specific product design, the flow path is

2 Valve type(s) listed for each containment isolation valve number in Tables 6.2-16 through 6.2-42 indicates either

the specific design characteristics of a type or the range of types with suitable equivalent design characteristicscapable of performing the intended function(s) for each application. The first type listed is generally based onhistorical selection from previous BWR designs.

Page 14: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

typically formed as either an annular nozzle in a wafer-style body or as annular venturi in ateardrop-style body.

Check (CK) A valve operated by process flow (opens on forward flow, closes on reverseflow and gravity) with a pallet style disk that is connected by a hinge bracket or arm to ashaft (or hinge end pins). The shaft is aligned in the horizontal plane with its rotation centertypically set above the main fluid flow path so that the pallet swings up and out of the mainflow on valve opening. A variant is the tilting disk pattern wherein the shaft is set closer toflow center and the hinge point is mounted directly behind the pallet (similar to a butterflyvalve). Check valves may have spring-return closure (closure-assist) either internally orexternally mounted. Globe and axial-flow valve variants are also designed to perform thecheck valve function.

Relief (RV) A variant of globe valves operated by process pressure most commonly builtin spring-closed pressure-under-seat/pressurize-to-lift pattern (also referred to as direct-acting). There are also piloted relief valve versions, using a piston and process pressure tomove the main disk off its seat, that are either depressurize-to-operate or pressurize-to-operate designs. The control pilot that operates the piston is typically a small version ofdirect-acting pressure relief valve.

Page 15: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

Table 6.2-23

Containment Isolation Valve Information for the Isolation Condenser System Loop A

Penetration

Identification B32-MPEN-0001 3 B32-MPEN-0005

Valve Number F001A F002A F003A F004A

Valve Location Steam Supply Steam Supply Condensate CondensateReturn Return

Applicable Basis GDC 55* GDC 55* GDC 55* GDC 55*

Tier 2 Figure 5.1-3 5.1-3 5.1-3 5.1-3

ESF Yes Yes Yes Yes

Fluid Steam Steam Condensate Condensate

Line Size 350mm 350mm 200mm 200mm

Type C Leakage Test Yes Yes Yes Yes

Pipe Length from Cont. to COL holder to COL holder to COL holder to COL holder toInboard/Outboard Isolation provide provide provide provideValve

Leakage Through N/A N/A N/A N/APacking(a)

Leakage Past Seat(b) b6 b6 b6 b6

Location Inboard Inboard Inboard Inboard

Valve Type(e) QBL, GT QBL, GT QBL, GT QBL, GT

Operator(c) NMO/AeeFH NO/Acc NO/Acc NMO/AccEH

Normal Position Open Open Open Open

Shutdown Position Open Open Open Open

Post-Acc Position Open 5 Open 3 Open 3 Open3

Power Fail Position As is As is As is As is

Cont. Iso. Signal(d) I,K I,K 1,K I,K

Primary Actuation Automatic Automatic Automatic Automatic

3Two in series valves4piping of IC Quality Group B Design5 Except on IC pipe or tube failure

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26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

Table 6.2-23

Containment Isolation Valve Information for the Isolation Condenser System Loop A

Penetration

Identification B32-MPEN-0001 3 B32-MPEN-0005

Valve Number FOOIA F002A F003A F004A

Secondary Actuation Remote Remote manual Remote Remotemanual manual manual

Closure Time (sec) < 60 < 60 <35 < 35

Power Source Div. 1, 3 Div. 2, 4 Div. 2, 4 Div. 1, 3

With respect to meeting the requirements of US NRC 10 CFR 50, Appendix A, GeneralDesign Criteria 55, the closed loop safety-related IC loop outside the containment is a"passive" substitute for an open "active" valve outside the containment. The combination ofan already closed loop outside the containment plus the two series automatic isolation valvesinside the containment comply with the requirement of the isolation guidelines of 10 CFR50,App.A, Criterion 55 and 56.

Note: For explanation of codes, see legend on Table 6.2-15.

Page 17: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

Table 6.2-25

Containment Isolation Valve Information for the Isolation Condenser System Loop B

Penetration

Identification B32-MPEN-0002 6 B32-MPEN-0006 7

Valve Number FOOIB F002B F003B F004B

Valve Location Steam Supply Steam Supply Condensate CondensateReturn Return

Applicable Basis GDC 55* GDC 55* GDC 55* GDC 55*

Tier 2 Figure 5.1-3 5.1-3 5.1-3 5.1-3

ESF Yes Yes Yes Yes

Fluid Steam Steam Condensate Condensate

Line Size 350mm 350mm 200mm 200mm

Type C Leakage Test Yes Yes Yes Yes

Pipe Length from Cont. to COL holder to COL holder to COL holder to COL holder toInboard/Outboard Isolation provide provide provide provideValve

Leakage Through N/A N/A N/A N/APacking(a)

Leakage Past Seat(b) 7 b6 b6 b6 b6

Location Inboard Inboard Inboard Inboard

Valve Type(c) QBL, GT QBL, GT QBL, GT QBL, GT

Operator(c) NMO/AeeEH NO/Acc NO/Acc NMO/AeeEH

Normal Position Open Open Open Open

Shutdown Position Open Open Open Open

Post-Acc Position Open 8 Open9 Open 9 Open 9

Power Fail Position As is As is As is As is

Cont. Iso. Signal(d) I,K I,K I,K I,K

Primary Actuation Automatic Automatic Automatic Automatic

6 Two in series valves7 Closed barrier outside containment (Piping of IC8 Except on IC pipe or tube failure

Quality Group B Design)

Page 18: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

Table 6.2-25

Containment Isolation Valve Information for the Isolation Condenser System Loop B

PenetrationIdentification B32-MPEN-0002 6 B32-MPEN-0006 7

Secondary Actuation Remote Remote Remote Remotemanual manual manual manual

Closure Time (sec) < 60 < 60 <35 <35

Power Source Div. 1, 3 Div. 2, 4 Div. 2, 4 Div. 1, 3

* With respect to meeting the requirements of US NRCDesign Criteria 55, the closed loop safety-related IC

10 CFR 50,loop outside

Appendix A, Generalthe containment is a

"passive" substitute for an open "active" valve outside the containment. The combination ofan already closed loop outside the containment plus the two series automatic isolationvalves inside the containment comply with the requirements of the isolation guidelines of 10CFR50, App. A, Criterion 55 and 56.

Note: For explanation of codes, see legend on Table 6.2-15.

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26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

Table 6.2-27

Containment Isolation Valve Information for the Isolation Condenser System Loop C

PenetrationIdentification B32-MPEN-0003 9 B32-MPEN-000713

Valve Number FOO1C F002C F003C F004C

Condensate CondensateValve Location Steam Supply Steam Supply Return Return

Applicable Basis GDC 55* GDC 55* GDC 55* GDC 55*

Tier 2 Figure 5.1-3 5.1-3 5.1-3 5.1-3

ESF Yes Yes Yes Yes

Fluid Steam Steam Condensate Condensate

Line Size 350 mm. 350 mm. 200 mm 200 mm

Type C Leakage Test Yes Yes Yes Yes

Pipe Length from Cont. to COL holder to COL holder to COL holder to COL holder toInboard/Outboard Isolation provide provide provide provideValve

Leakage Through Packing(a) N/A N/A N/A N/A

Leakage Past Seat(b) 1o b6 b6 b6 b6

Location Inboard Inboard Inboard Inboard

Valve Type(c) QBL, GT QBL, GT QB, GT QBL, GT

Operator(c) NMO/AceEH NO/Acc NO/Acc NMO/AceEH

Normal Position Open Open Open Open

Shutdown Position Open Open Open Open

Post-Acc Position Open'' Open 15 Open15 Open 15

Power Fail Position As is As is As is As is

Cont. Iso. Signal(d) I,K I,K I,K 1,K

Primary Actuation Automatic Automatic Automatic AutomaticSecondary Actuation Remote Remote Remote Remote

manual manual manual manual

Closure Time (sec) < 60 < 60 < 35 < 35

Power Source Div. 1, 3 Div. 2, 4 Div. 2, 4 Div. 1, 3

9Two in series valves0Closed barrier outside containment (Piping of IC Quality Group B Design)''Except on IC pipe or tube failure

Page 20: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

With respect to meeting the requirements of US NRC 10 CFR 50, Appendix A, GeneralDesign Criteria 55, the closed loop safety-related IC loop outside the containment is a"passive" substitute for an open "active" valve outside the containment. The combination ofan already closed loop outside the containment plus the two series automatic isolation valvesinside the containment comply with the intent of the isolation guidelines of 10 CFR 50,App.A, Criterion 55 and 56.

Note: For explanation of codes, see legend on Table 6.2-15.

Page 21: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

Table 6.2-29

Containment Isolation Valve Information for the Isolation Condenser System Loop D

Penetration B32-MPEN-000412 B32-MPEN-000819Identification

Valve Number FOOD F002D F003D F004D

Condensate CondensateValve Location Steam Supply Steam Supply Return Return

Applicable Basis GDC 55* GDC 55* GDC 55* GDC 55*

Tier 2 Figure 5.1-3 5.1-3 5.1-3 5.1-3

ESF Yes Yes Yes Yes

Fluid Steam Steam Condensate Condensate

Line Size 350 mm 350 mm 200 mm 200 mm

Type C Leakage Test Yes Yes Yes Yes

Pipe Length from Cont. to COL holder to COL holder to COL holder to COL holder toInboard/Outboard Isolation provide provide provide provideValve

Leakage Through Packing(a) N/A N/A N/A N/A

Leakage Past Seat(b) 13 b6 B6 b6 b6

Location Inboard Inboard Inboard Inboard

Valve Type(c) QBL, GT QBL, GT QBL, GT QBL, GT

Operator(c) NMO/AeeEH NO/Ace NO/Acc NMO,LAeEH

Normal Position Open Open Open Open

Shutdown Position Open Open Open Open

Post-Acc Position Open 14 Open 2 1 Open 21 Open21

Power Fail Position As is As is As is As is

Cont. Iso. Signal(d) I,K I,K I,K I,K

Primary Actuation Automatic Automatic Automatic Automatic

Remote Remote Remote Remotemanual manual manual manual

Closure Time (see) < 60 < 60 < 35 <35

Power Source Div. 1, 3 Div. 2, 4 Div. 2,4 Div. 1, 3

S2Two in series valves13Closed barrier outside containment (Piping of IC Quality Group B Design)14Except on IC pipe or tube failure

Page 22: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AT Rev. 05ESBWR Design Control Document/Tier 2

With respect to meeting the requirements of US NRC 10 CFR 50, Appendix A, General Design Criteria 55, the

closed loop safety-related IC loop outside the containment is a "passive" substitute for an open "active" valve

outside the containment. The combination of an already isolated loop outside the containment plus the two

series automatic isolation valves inside the containment comply with the requirements of the isolation

guidelines of 10 CFR 50, App. A, Criterion 55 and 56.

Note: For explanation of codes, see legend on Table 6.2-15.

Page 23: GE Hitachi Nuclear Energy SI-HITACHI

26A6641AB Rev. 05ESBWR Design Control Document/Tier 1

Table 2.4.1-1

ICS Mechanical Equipment

Equipment Name Equipment ASME Code Seismic Cat. I RCPB Containment Remotely Loss ofOperated

(Description) Identifier Section III Component Isolation MotiveSee Figure Valve. Power

2.4.1-1 Position

Train A Isolation ---

Condenser

IC (A) Heat Exchanger Yes Yes No No N/A N/A

Inline Vessel (A) --- Yes Yes Yes No N/A N/A

IC (A) Steam Supply Line P-I(A) Yes Yes Yes No N/A N/A

IC (A) Steam Supply Line V-I(A) Yes Yes Yes Yes Yes As-Is

Isolation Valve

IC (A) Steam Supply Line V-2(A) Yes Yes Yes Yes Yes As-Is

Isolation Valve

IC (A) Condensate Return P-2(A) Yes Yes Yes No N/A N/A

Line

IC (A) Condensate Return V-3(A) Yes Yes Yes Yes Yes As-Is

Line Isolation Valve

IC (A) Condensate Return V-4(A) Yes Yes Yes Yes Yes As-Is

Line Isolation Valve

IC (A) Condensate Return V-5(A) Yes Yes Yes YNeNo Yes As-Is

Line Valve

Page 24: GE Hitachi Nuclear Energy SI-HITACHI

ESBWR26A6641AB Rev. 05

Table 2.4.1-1

ICS Mechanical Equipment

Design Control Document/Tier I

Equipment Name Equipment ASME Code Seismic Cat. I RCPB Containment Remotely Loss of

(Description) Identifier Section III Component Isolation Operated MotiveSee Figure Valve. Power

2.4.1-1 Position

IC (A) Condensate Return V-6(A) Yes Yes Yes YesNo Yes Open

Line Bypass Valve

Upper IC (A) Header Vent Yes Yes No No N/A N/A

Line

Upper IC (A) Header Vent V-7(A) Yes Yes No Yes Yes Closed

Line Valve

Upper IC (A) Header Vent V-8(A) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (A) Header Vent Yes Yes No No N/A N/A

Line

Lower IC (A) Header Vent V-9(A) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (A) Header Vent V-0O(A) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (A) Header Vent V- I (A) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (A) Header Vent V-12(A) Yes Yes No Yes Yes Closed

Line Valve

Train B Isolation --- --- --- --- ---

Condenser

Page 25: GE Hitachi Nuclear Energy SI-HITACHI

26A6641AB Rev. 05ESBWR Design Control Document/Tier 1

Table 2.4.1-1

ICS Mechanical Equipment

Equipment Name Equipment ASME Code Seismic Cat. I RCPB Containment Remotely Loss ofOperated

(Description) Identifier Section III Component Isolation Motive

See Figure Valve. Power

2.4.1-1 Position

IC (B) Heat Exchanger --- Yes Yes No No N/A N/A

Inline Vessel (B) --- Yes Yes Yes No N/A N/A

IC (B) Steam Supply Line P-1(B) Yes Yes Yes No N/A N/A

IC (B) Steam Supply Line V-I(B) Yes Yes Yes Yes Yes As-Is

Isolation Valve

IC (B) Steam Supply Line V-2(B) Yes Yes Yes Yes Yes As-Is

Isolation Valve

IC (B) Condensate Return P-2(B) Yes Yes Yes No N/A N/A

Line

IC (B) Condensate Return V-3(B) Yes Yes Yes Yes Yes As-Is

Line Isolation Valve

IC (B) Condensate Return V-4(B) Yes Yes Yes Yes Yes As-Is

Line Isolation Valve

IC (B) Condensate Return V-5(B) Yes Yes Yes YesNo Yes As-Is

Line Valve

Page 26: GE Hitachi Nuclear Energy SI-HITACHI

ESBWR26A6641AB Rev. 05

Table 2.4.1-1

ICS Mechanical Equipment

Design Control Document/Tier 1

Equipment Name Equipment ASME Code Seismic Cat. I RCPB Containment Remotely Loss of

(Description) Identifier Section III Component Isolation perated MotiveSee Figure Valve. Power

2.4.1-1 Position

IC (B) Condensate Return V-6(B) Yes Yes Yes YesNo Yes OpenLine Bypass Valve

Upper IC (B) Header Vent --- Yes Yes No No N/A N/A

Line

Upper IC (B) Header Vent V-7(B) Yes Yes No Yes Yes Closed

Line Valve

Upper IC (B) Header Vent V-8(B) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (B) Header Vent --- Yes Yes No No N/A N/A

Line

Lower IC (B) Header Vent V-9(B) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (B) Header Vent V-0O(B) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (B) Header Vent V- I (B) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (B) Header Vent V-12(B) Yes Yes No Yes Yes Closed

Line Valve

Page 27: GE Hitachi Nuclear Energy SI-HITACHI

ESBWR26A6641AB Rev. 05

Table 2.4.1-1

ICS Mechanical Equipment

Design Control Document/Tier 1

Equipment Name Equipment ASME Code Seismic Cat. I RCPB Containment Remotely Loss of

(Description) Identifier Section III Component Isolation Operated MotiveSee Figure Valve. Power

2.4.1-1 Position

Train C Isolation ---.....---..........

Condenser

IC (C) Heat Exchanger --- Yes Yes No No N/A N/A

Inline Vessel (C) Yes Yes Yes No N/A N/A

IC (C) Steam Supply Line P-I(C) Yes Yes Yes No N/A N/A

IC (C) Steam Supply Line V-I(C) Yes Yes Yes Yes Yes As-Is

Isolation Valve

IC (C) Steam Supply Line V-2(C) Yes Yes Yes Yes Yes As-Is

Isolation Valve

IC (C) Condensate Return P-2(C) Yes Yes Yes No N/A N/A

Line

IC (C) Condensate Return V-3(C) Yes Yes Yes Yes Yes As-Is

Line Isolation Valve

IC (C) Condensate Return V-4(C) Yes Yes Yes Yes Yes As-Is

Line Isolation Valve

IC (C) Condensate Return V-5(C) Yes Yes Yes YesNo Yes As-Is

Line Valve

Page 28: GE Hitachi Nuclear Energy SI-HITACHI

ESBWR26A6641AB Rev. 05

Table 2.4.1-1

ICS Mechanical Equipment

Design Control Document/Tier 1

Equipment Name Equipment ASME Code Seismic Cat. I RCPB Containment Remotely Loss of

(Description) Identifier Section III Component Isolation Operated MotiveSee Figure Valve. Power

2.4.1-1 Position

IC (C) Condensate Return V-6(C) Yes Yes Yes Ye-sNo Yes Open

Line Bypass Valve

Upper IC (C) Header Vent Yes Yes No No N/A N/A

Line

Upper IC (C) Header Vent V-7(C) Yes Yes No Yes Yes Closed

Line Valve

Upper IC (C) Header Vent V-8(C) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (C) Header Vent Yes Yes No No N/A N/A

Line

Lower IC (C) Header Vent V-9(C) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (C) Header Vent V-0O(C) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (C) Header Vent V- II (C) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (C) Header Vent V-12(C) Yes Yes No Yes Yes Closed

Line Valve

Page 29: GE Hitachi Nuclear Energy SI-HITACHI

26A6641AB Rev. 05ESBWR Design Control Document/Tier 1

Table 2.4.1-1

ICS Mechanical Equipment

Equipment Name Equipment ASME Code Seismic Cat. I RCPB Containment Remotely Loss of

(Description) Identifier Section III Component Isolation Operated MotiveSee Figure Valve. Power

2.4.1-1 Position

T rain D Isolation ---.........---......

Condenser

IC (D) Heat Exchanger --- Yes Yes No No N/A N/A

Inline Vessel (D) --- Yes Yes Yes No N/A N/A

IC (D) Steam Supply Line P-I(D) Yes Yes Yes No N/A N/A

IC (D) Steam Supply Line V-I(D) Yes Yes Yes Yes Yes As-Is

Isolation Valve

IC (D) Steam Supply Line V-2(D) Yes Yes Yes Yes Yes As-Is

Isolation Valve

IC (D) Condensate Return P-2(D) Yes Yes Yes No N/A N/A

Line

IC (D) Condensate Return V-3(D) Yes Yes Yes Yes Yes As-Is

Line Isolation Valve

IC (D) Condensate Return V-4(D) Yes Yes Yes Yes Yes As-Is

Line Isolation Valve

IC (D) Condensate Return V-5(D) Yes Yes Yes YesNo Yes As-Is

Line Valve

Page 30: GE Hitachi Nuclear Energy SI-HITACHI

ESBWR26A6641AB Rev. 05

Table 2.4.1-1

ICS Mechanical Equipment

Design Control Document/Tier I

Equipment Name Equipment ASME Code Seismic Cat. I RCPB Containment Remotely Loss of

(Description) Identifier Section III Component Isolation perated MotiveSee Figure Valve. Power

2.4.1-1 Position

IC (D) Condensate Return V-6(D) Yes Yes Yes Ye§,No Yes Open

Line Bypass Valve

Upper IC (D) Header Vent --- Yes Yes No No N/A N/A

Line

Upper IC (D) Header Vent V-7(D) Yes Yes No Yes Yes Closed

Line Valve

Upper IC (D) Header Vent V-8(D) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (D) Header Vent --- Yes Yes No No N/A N/A

Line

Lower IC (D) Header Vent V-9(D) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (D) Header Vent V-10(D) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (D) Header Vent V-i1 (D) Yes Yes No Yes Yes Closed

Line Valve

Lower IC (D) Header Vent V-12(D) Yes Yes No Yes Yes Closed

Line Valve

Note: N/A = Not Applicable

Page 31: GE Hitachi Nuclear Energy SI-HITACHI

26A6641AB Rev. 05ESBWR

f'!7-7-- --.-. -. ---- 7 - - 7 7SIn SOLATION CONDENSER .1 I | ["

I !i BIA AIB i .;• : i i

-I IB ~ K 1

Design Control Document/Tier I

I AIMOSPHERICVENT

LEGEND:

NNS - NON-NUCLEAR SAFETY-RELATEDA.,B,C DUALITY GROUPA. B.C

I SEISMIC CATEGORY INCS NON-SEISMIC CATEGORY (NS)

NESEL TRAIN A SHW

I. . .

Figure 2.4.1-1. Isolation Condenser System Schematic

Page 32: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AK Rev. 05ESBWR Design Control Document/Tier 2

Table 3.9-8

In-Service Testing

Valve Act Code Code Valve Norm Safety Fail C TestType (b) Class Cat. Func. Pos Pos. Safe I Test Para Freq.

No. Qty Description (g) (i) (a) (c) (d) Pos V (C) (0

F031 4 Inboard MSIV air supply CK SA 3 C A C O/C N/A R 5YRline check valve (gl)

F033 4 Outboard MSIV air supply CK SA 3 C A C C N/A SC ROline check valve (gI) SO RO

F028 8 Rupture Disk RD SA 3 D A C O/C N/A R 5 YR

B32 Isolation Condenser System Valves

FOO1 4 Steam supply line isolation GT NMA I A A 0 O/C Al Y L App Jvalve QBL EH P 2 YR

SC 3 mo

SO 3 mo

F002 4 Steam supply line isolation GT NMO 1 A A 0 O/C Al Y L App Jvalve QBL P 2 YR

SC 3 mo

SO 3 mo

F003 4 Condensate return line GT NMO I A A 0 O/C Al Y L App Jisolation valve QBL P 2 YR

SC 3 mo

SO 3 mo

Page 33: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AK Rev. 05ESBWR Design Control Document/Tier 2

Table 3.9-8

In-Service Testing

Valve Act Code Code Valve Norm Safety Fail C TestType (b) Class Cat. Func. Pos Pos. Safe I Test Para Freq.

No. Qty Description (g) (i) (a) (c) (d) Pos V (C) (f)

F004 4 Condensate return line GT N40 1 A A 0 O/C Al Y L App Jisolation valve QBL EH P 2 YR

SC 3 mo

SO 3 mo

F005 4 Condensate return valve GT NMG 1 B A C 0 Al P 2 yrsQBL EH SO 3 mo

F006 4 Condensate return bypass QBF NO I B A C 0 0 P 2 yrsvalve GB SO 3 mo

FO 3 no

F007 4 Condenser upper header QBL so 2 A A C C C L App Jvent valve (g5) GB P 2 YR

SC 3 moFC 3 mo

F008 4 Condenser upper header QBL SO 2 A A C C C Y L App Jvent valve (g5) GB P 2 YR

SC 3 moFC 3 mo

F009 4 Condenser lower header QBL so 2 A A C C C Y L App Jvent valve (g5) GB P 2 YR

SC 3 moFC 3 mo

Page 34: GE Hitachi Nuclear Energy SI-HITACHI

26A6642AK Rev. 05ESBWR Design Control Document/Tier 2

M Manually operated

MO Motor operated

SA Self-actuated

SO Solenoid operated

SQ Squib. This valve is a one-time-use valve designed as a single machined forging with a breakaway outlet cap. The valve isopen by a pyrotechnic actuator that drives a shear plunger against the edge of the cap.

VB Vacuum Breaker. Valves that provide pressure relief when a set pressure value is exceeded or when a set differentialpressure is exceeded across the valve.

EH Electro-hydraulic operated

c) A, B, C or D - Valve category per ASME OM Code -Subsection ISTC-1300.

d) Valve Function:

A or P - Active or passive per ASME OM Code - Paragraph ISTC-1300.

e) Valve test parameters per ASME OM Code - Subsection ISTC and Appendix I:

L Seat leakage rate (Paragraph ISTC-3600 and DCD Tier 2 Subsection 6.2.6.3

OMNI1SC Full cycle exercise and stroke closed design basis verification tests in accordance with ASME Code Case OMIN-1

OMNISO Closure exercise and design basis verification tests in accordance with ASME Code Case OMN-1

P Valve position verification (Paragraph ISTC-3700)

R Safety and relief test including visual examination, set pressure and seat tightness testing in accordance Paragraph ISTC-3000, -5230, -5240, Table ISTC-3500-1, Note (2), and Appendix I). Category A and B requirements for safety and reliefvalves of ISTC-3500 and ISTC-3700 are excluded per ISTC-1200.

SO Open stroke tests for Category A and B valves (Paragraph ISTC-3521) and Category C valves (Paragraph ISTC-3522)

SC Closure stroke tests for Category A and B valves (Paragraph ISTC-3521) and Category C valves (Paragraph ISTC-3522)

FO Fail open tests for Category A and B valves (Paragraph ISTC-3560)

FC Fail closed tests for Category A and B valves (Paragraph ISTC-3560)

X Explosively actuated valve tests (Paragraph ISTC-5260)