ML20034E517

Summary of 930205 Meeting W/Westinghouse in Monroeville,Pa Re Discussions on Design Characteristics of Valves Used in AP600 Design.List of Attendees,Meeting Agenda & Handouts Encl

ML20034E517
Person / Time
Site:	05200003
Issue date:	02/23/1993
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9302260266
Download: ML20034E517 (70)

Text

{{#Wiki_filter:7, C I Sn pro o UNITED STATES g E ' 3,, .g NUCLEAR REGULATORY COMMISSION. 3 'E WASHINGTON, D. C. 20555 [ February 23, 1993 Docket No. 52-003 APPLICANT: Westinghouse Electric Corporation PROJECT: Westinghouse AP600. Design

SUMMARY

OF MEETING TO DISCUSS DESIGN OF VALVES USED IN THE AP600 DESIGN On February 5, 1993, representatives of the U.S. Nuclear Regulatory Commission (NRC) and Westinghouse met in Monroeville, Pennsylvania, to discuss the design characteristics of valves used in the AP600 design. is a list.of attendees. is a copy of the non-proprietary slides presented at the meeting. A copy of the proprietary slides was submitted by letter dated February 5, 1993. The following is a stenmary of the discussions during.the meeting with additional elaboration of concerns identified during the meeting. The NRC opened the meeting stating that the purpose of the meeting is to obtain information necessary to assess the reliability of " critical" valves. used in the AP600 plant design (see Q210.27 and Q210.28 in the staff's letters to Westinghouse dated January 26, 1993 and February 9, 1993). Westinghouse began their presentation with a brief overview of the passive safety systems used in the AP600. Then they discussed the following types of valves: Motor Operated Valves - including: ADS Stage 1-ADS Stage 2/3 Air Operated Valves - including: ADS Stage 4 Core Makeup Tank Isolation PRHR HX Control-Check Valves - including: IRWST Injection Containment Sump Recirculation Core Makeup Tank Discharge Core Makeup Tank Pressurization Squib Valves - including: pH Tank Outlet Isolation For each valve type, Westinghouse described the functional requirements of the valve, provided valve and valve actuator characteristics (as applicable and as - is currently available), and described valve testing that is planned. -Most of the information provided was preliminary (" draft") and proprietary. For each cnnnSS e f 9302260266 930223 m r PDR ADOCK 05200003 b A PDR- \\ 1 E

4 ', s . February 23, 1993 valve type (except the squib valve), Westinghouse provided a draft valve specification, i.e., a " Control Valve Data Sheet." These Control Valve Data Sheets typically had general information about the valve, specification of the hydraulic conditions under which the valve would be required to operate, opening / closing conditions and characteristics, leak tightness requirements, and a list of notes related to the valve's design. While the Control Valve Data Sheets demonstrate that Westinghouse has made a good start at defining the information that will be needed for a complete valve specification, the staff determined that the Control Valve Data Sheets should also contain: Specification of the environmental conditions under which the ' valve, actuator, and/or motor would be required to operate (as appropriate). For example, the Westinghouse design for the ADS valves, the ADS test solenoid valves, and the check valves in various systems will incorporate provisions-for non-intrusive position indication. Westinghouse'should address the qualification requirements for these position indicators. Additional specification of the valve design. For example, Westinghouse stated that they were not sure yet that certain check valve seats would be stellite. Other materials, such as nickel, may be much more susceptible.to galling. The valve seat types need to be determined and identified. Specification of the " anticipated duty cycle" for the valve, actuator, and/or motor (as appropriate). Specification of how the Code test requirements will be met.- (Specific examples are provided below.) Definition of pre-service test plans. A description of how each valve's design differs from conventional valve designs. Westinghouse indicated that they also plan to include test conditions and. electrical information on revised Control Valve Data Sheets. Most of the Control Valve Data Sheets contained a note similar to the follow-ing: The reliability of this valve is important with respect to public A probability of failing to close', when required, of 1 safety., demands has been used in AP600 reliability calculations. in 2000 'The valve position and number of failures per demand varies from valve to valve.

't . February 23, 1993 This note was not listed as a valve design requirement. Rather, it was listed to give the valve manufacturer some indication of the valve reliability expectations under the specified valve operating conditions. Westinghouse indicated that they did not believe that it is feasible to have a valve vendor design to a reliability target. Nevertheless, the staff indicated that, in some cases, the Westinghouse estimates were substantially lower than current experience would indicate and that Westinghouse should develop a basis to support their estimates. Westinghouse stated that the ADS Valves for Stages 1, 2, and 3 will only be tested under reduced DP/ flow conditions on some periodic basis. The testing proposed is essentially a pressurized valve body test where the conditions principally will only simulate actual stem rejection loads. This type of testing is not responsive to the staff's position.in SECY-90-016 that states: "(d)esigns should incorporate provisions to test motor-operated valves'under design basis differential pressure." Westinghouse should reconsider the-proposed testing and make modifications as appropriate. Westinghouse indicated that while the 4th stage ADS valves are not part of their ADS test program in Cassacia, Italy, they will try to get data on these valves, even though they are not yet certain of the specific valve type or vendor. Westinghouse said that they planned to work with ITT/MOVATS to determine how to monitor the ADS Stage 1, 2, and 3 valves during the ADS valve test. program. Westinghouse indicated that they were not planning on doing any ADS. valve testing under adverse environmental conditions. Also, they are not testing the valve's de operator. The de motor on these operators have.a torque output that varies with motor temperature. Motor temperature is a function of both duty cycle and ambient temperature. Supplying an oversized motor for this application may create a problem of excessive torque input because the high ratio gear train planned for these actuators are susceptible to damage from excessive torque. The Stage 4 ADS valves are required to open at a certain pressure (e.g., 1100 psig) and are required to be designed to be incapable of opening.above a certain higher pressure (e.g., 1500 psig). The staff questioned whether the window between these two pressures is too narrow to achieve their design objectives, given the type of valve to be used (i.e., air-operated gate valve)- and current technology. There was also a question whether lubricants used in this air-operated valve could contaminate the solenoid-operated valves used in its air supply and return lines. This concern is discussed in EPRI NP-7414, "EPRI NMAC Solenoid Valve Maintenance and Application Guide," April,1992, on ~ pages 6-18, where it is stated that " petroleum lubricants used in actuators will find their way back to the air pilot SOVs... the use of petroleum-tolerant elastomers may be necessary." Unfortunately, the petroleum-tolerant elastomers do not withstand radiation as well as other elastomers. One option discussed during the meeting was to locate the pilot valves remotely. Another option may be to use a direct lift, "through the wall" magnetic principle type of solenoid valve so that packing and diaphragms are eliminated. These valves are also available with stellite seats if slight leakage can be tolerated. Westinghouse should provide a response regarding how they intend to address these concerns. 1

c , February 23, 1993 The NRC expressed concern that the designs of the AP600 valves may not ade-quately address valve functional and Code test requirements. For example: Westinghouse had not identified that the ADS valves for Stages 1, 2, and 3 have a function to open against full RCS pressure. Westinghouse needs to revise the functional requirements to address opening against ful1 ~ RCS pressure. In the discussions of the in-series Core Makeup Tank (CMT) discharge check valves, Westinghouse identified that these valves are biased-open check valves and that they are both required to close under reverse flow condi-tions. Westinghouse should develop a method to test both of these valves for reverse flow closure. There was discussion regarding the fact that these are tilting disc check valves. When tilting disc check valves are designed for low leakage, i.e., when they have low angle of taper, they are susceptible to jamming shut. Westinghouse stated that low leakage was not a requirement, but the maximum allowable leakage was not yet determined. Westinghouse should address the maximum allowable leakage and the angle of taper; testing for reverse flow closure followed by reopening on forward differential pressure should be provided. In the discussions of the Containment Recirculation check valves, the staff pointed out that the Code would require that this pair of valves be feruard flow tested and that at lear.t one or_ both of the pair of valves be reverse flow closure tested. Westinghouse should address this testing requirement. In the discussions of the IRWST Injection check valves, Westinghouse indicated that these valves could be full flow tested at low differential pressure during refueling. The test differential pressure quoted was substantially higher than the minimum differential pressure opening requirements for the valve and the proposed test may not verify the differential pressure assumptions. Westinghouse should address this concern. The NRC indicated to Westinghouse that it would like to get more detailed Control Valve Data Sheets for each of the " critical" valves specified in the staff's revisnd RAI (see letter dated February 9, 1993). In addition, the staff indicated that it would like Westinghouse to provide the basis for the antic l pated valve reliability stated on each Control Valve Data Sheet and a commitment that the valves will be included in the Inservice Testing and Reliability Assessment Programs to ensure that the anticipated valve reliabil-ities are achieved and maintained. Finally, there was a discussion about the passive core cooling system accumu-lator outlet check valves (PXS V028 A/B and PXS V029 A/B). While these valves were not considered " critical" valves because thcy are conventional valves,

e 4 i e Februa; f 23, 1993 i similar'to those used in the current design Westinghouse plants, they were of concern to the NRC because there has been a history of problems with the. testability of these valves. There was some question as to how these valves would be tested in accordance with the Code to their full open position. According to Westinghouse, these valves will have position indicators-and will-be able to be leak tested individually. The staff noted that the use of a non-intrusive diagnostic system for position indication may present unique challenges due to the potential interference of acoustic signals between the valve pair. This is generic to paired valves located ~in close proximity to each other. An overall system flow test does not provide adequate information on specific valve degradation. Westinghouse will need to develop a qualified system that addresses this concern. In general, the Westinghouse design as it is currently developed has.incorpo-rated provisions for scme degree of valve testing. However,-as identified in some of the specific comments above, there are a number of staff concerns in this regard. Operating experience indicates that provisions for valve testability in current designs is less than optimal. Westinghouse should reconsider this aspect of their. design to ensure that all Code testing requirements will be able.to be met. Westinghouse should also ensure that the system designs will enable the operators to periodically verify the capability of all valve types under conditions as close as possible to the des.ign basis. At the end of the meeting, the NRC indicated that the information presented during the meeting resolved a number of the staff's concerns. However, the staff raised a number of concerns during the meeting-(as identified in this meeting summary) and expected to see documented evidence that these concerns were considered and factored into the design. The staff indicated that it would be developing more detailed questions in the area of reliability and failure rates of these valves. The staff further-indicated that the informa-tion requested in Q210.28 would need to be placed on the docket. The staff agreed to send Westinghouse the following: A revision to Q210.28 (see February 9, 1993 letter), and Selected NRC generic communication (s) related to the use of stainless a steel, including NRC Information Notice No. 88-85, " Broken Retaining Block Studs on Anchor Darling Check Valves"; NRC. Bulletin 89-02, " Stress Corro-sion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded

[: 4. 4 , February 23, 1993-Bolting'in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design;" and the AE0D Special Study on " Pressure Locking and Ther-mal Binding of Gate Valves" (AE0D/S92-07). OdginalS!nn 4y,, Thomas J. Kenyon,', Project Manager ~ Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ enclosures: See next page DISTRIBUTION w/ enclosures: - Docket File - PDST R/F TKenyon PShea PDR BPerch, 8H7 DTerao, 7H15 DISTRIBUTION w/o enclosures: TMurley/FMiraglia DCrutchfield WTravers RBorchardt EJordan, MNBB3701 JNWilson ACRS (11)' TSullivan, 7E23 DFischer, 7E23 JMoore, 15B18 GGrant,.17G21 0FC: LA:PDST:ADAR PM:PDST(ADYR-SC:PNT:ADAR NAME: PShea()t// TKenNn:h RBokhardt 02/9/b 02/k/d3! 02[JJ/93 DATE: OFFICIAL RECORD COPY: DOCUMENT NAME: VALVE. SUM

Docket No. 52-003 Westinghouse Electric Corporation cc: Mr. Nicholas J. Liparulo Nuclear Safety' and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. B. A. McIntyre Advan.ed Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 350 Rockville, Maryland 20852 Mr. Sterling Franks U. S. Department of Energy NE-42 Washington, D.C. 20585 Mr. S. M. Modro EG&G Idaho Inc. Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. Steve Goldberg Budget. Examiner 725 17th Street, N.W. Room 8002 Washington, D.C. 20503 ) e

4 a; VALVE HEETING ATTENDEES FEBRUARY 5, 1993 NAME AFFILIATION John C. Butler Westinghouse Preston A. Vock Westinghouse Mark J. Loeffler Westinghouse Terry Schulz Westinghouse Sue Fanto Westinghouse Don Casada ORNL John Kueck' ORNL Karen McElhaney ORNL Robert Staunton ORNL Ted Sullivan NRC Dave Fischer NRC Tom Kenyon NRC . Enclosure 1 h

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l Westinghouse /NRC Meeting on AP600 Valves' l

U Presentation Material 1i '. h .i .i 1 February 5,1993. Westinghouse Energy Center j . Monroeville, PA - g s 9 .r, h .p i ? I i t l

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ii. i NRC/ WESTINGHOUSE VALVE MEETING ~ ~ ~ FEBRUARY 5,.1993. AGENDA.

1. INTRODUCTION Butler Hasselberg.(NRC)l

2. PASSIVE SYSTEMS OVERVIEW Schulz

3. MOTOR-OPERATED VALVES

-(**) o t

4. AIR-OPERATED VALVES

(**)

5. CHECK VALVES

.(**)l

6. SOUlB VALVES

(*'*)

7. CONCLUSION / DISCUSSION

' all (**) PRESENTATION MATERIAL FOR EACH VALVE TYPE - System Applications. Schulz - Valve Functional Requirements . Schulz j - Valve; Design Information Vock- - Valve Testing Information Fanto. ] - Miscellaneous Questions As required-i i l: i

s ?AP300 SYSTEMS DESIGN Greatly Simplify Systems to improve Safety, i Cost, Construction, Maintenance,.& Operation. i Provide Simple Passive Safety Systems Use natural" driving forces only One-time alignment of active valves No support systems-after actuation j Reduced operator dependency i Provide Non-Safety Systems Reliable active equipment for normal operation I "First line of defense"; redundant active equipment powered by on-site non-safety diesels-Reduced use of passive safety systems' Reduced risk to utility & public lierative Design Development Safety analysis studies I Risk and severe accident analysis studies Plant arrangement and modularization studies T:.3 - 2/2/ 3 0 i 1 i 2 i

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AP600 ^SAFETYlSYSTEMS 4

2 Provide ~ Passive Safety: Systems l Greatly lsimplitied consideringfconstruction,- maintenance, operation, ISI / IST ~ Mitigate design basisLaccidents withoutiuseLof- ^1 NNS systems 1 Meet;NRC safety-goals without NNS sysL(EPRI) 1 Meet EPRI safety goals withiNNS systems

l

~ 2 Safety. Systems. Design Features Only passive processes; no active equipment: j Significant design margins z Redundancy to meet single failure enteria-lj PRA based redundancy / diversity: Greatly reduced need for operator actions. j

. )

Safety Equipment Design Features ' Reliable 1 experience; based. equipment Improved. inservice testing / inspectionL Reg: Guide 1.26 Quality Group A, B, or C j Seismic I design- . Qualified Er tpment Availability vontrolled by Technical Specifications; with shutdown.. requirements Reliability Assurance Program Tier i description and ITAAC TLC - ;/2/93 5g 7:.- --. P.=.

- 4.: + FAP600 PASSIVE SAFETY FEATURES 1 q - 3 Passive Decay Heat Removal Natural circulation HX connected to:RCSL t Passive Safety injection j N2 pressurized accumulators Gravity drain core makeup tanks (RCS-pressure). Gravity drain in-containment refueling water-storage tank (containment. pressure) Automatic = RCS depressurization I Passive Containment-. Cooling Steel containment shell transfers. heat to natural' circulation of air and evaporation of water drained by gravity. Passive HVAC Compressed air for habitability of main control. room Concrete walls for heat sink (MCR and I&C rooms) 1 T:.3 - 2/2/r0 9

~ n.;. -AP600 PASSIVE SAFETY SYSTEMS I _L Pcevst @~ 1 X A IRvST X Ax Nn/ "5 l 1 I o a [ [ RV' ' ~*

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.j i 4 a MOTOR OPERATED VALVES: q 1 -] l Special Applications ADS Stage 1 ADS Stage 2 / 3 j h .l I' f 3 5 I n.s - 2 n / 93 q s

ADS VALVES - STAGE Functional Requirements = Normally isolate Pressurizer from IRWST Limited Manual RCS Depressurization Automatic RCS bepressurization Valve Characteristics _,,e a r L Valve Actuator o Motor-Operator, dc Powered Normally Closed, Fail-As-Is ,c. Slow Opening,u _,sec Open Against Full RCS Pressure Valve Actuation o Low-1 CMT Level Setpoint j Valve Testing ,, e =-2nm 7 )

-o -: l ADS VALVES - STAGES 2 LAND 3; i) } Functional Requirements i Normally isolate Pressurizer from IRWST Automatic RCS Depressurization-Valve Characteristics ~ e,c_ Valve Actuator Motor-Operator,.dc Powered-Normally-Closed, Fa.il-As-Is .c_ Slow Opening,_. _sec Open Against Full RCS Pressure 9 Valve Actuation Low-2 & -3 CMT Level Setpoints 1 Valve Testing o,c: 'I 1 l

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j a CONTROL VALVE DATA SHEET NO:; CT-001: o Plant: System:

== Description:== Tag Number (s). DRAFT [

AP600 RCS ADS Stage 1 V001 A,B,C,D :

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- CONTROL VALVE DATA SHEET NO: TCT-001: .a . Plant: System:

== Description:== - Tag Number (s) -{gg l AP600 RCS. ADS Stage 1 V001 A,B,C D- ~ c, c. : .a 1 f 6 Rev: 5 - Date: 01/31/93 Page 2 of 3 - 1 .. %e c2mm o:44 ro.c w.ra^^vALvacvv4 rz_- e

n . '9 CONTROL VALVE DATA' SHEET NO: CT-001 ~' Plant: System:

== Description:== , Tag Number (s) AP600' RCS - ADS Stage 1 ' V001 A,B,C,D - DRAR L.,- ~ ~ I ~ t Rev: 5 ' Date: 01/31/93 .Page 3 of 3' % o w 3o,;u u. l r*cwmavevtsm a ..ek,

a CONTROL VALVE DATA SHEET NO: CT-002 Plant: System:

== Description:== Tag Number (s) j OR4FT 'AP600 RCS ADS Stage 2 and 3 V002A,B,C,D, V003A,B,C,D 4,c. i 1 J ~ Rev: 5 Date: 01/31/93 Page 1 of 3 ' Pnnd 02h4/93 08.35 04 Fdef6AVALVESd'\\% 4 Ik'

4 CONTROL VALVE DATA SHEET NO: CT-002 Plant: System:

== Description:== Tag Number (s) ORAFT I AP600 RCS ADS Stage 2 and 3 V002A,B,C,D, V003A,B,C,D 4,C. J Rev: 5 Date: 01/31/93 Page 2 of 3 anna emniu,o

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CONTRO'l VALVE DATA SHEET NO: dT-002 W b4N Plant: System:

== Description:== Tag Number (s) i AP600 RCS ADS Stage 2 and 3 V002A,B,C,D, V003A.B,C,D 4,CL l 1 i l Rev: 5 Date: 01/31/93 Page 3 of 3 l Pnm.e amou5m s c w w x evts m a it, i _..__-.____.___..__.....M m

-i.. t .- G, [ &, _- 4 AP600 AUTOMATIC DEPRESSURIZATION SYST8M (ADS) TEST VALVES TAG NO. ADS 41 TAG NO. ADS-02 TAG NOJ ADS-02 4, C_. r-- DESCRIMlON 6 STROKE TIME VENDOR ANCHOR DARLING. ANCHOR DARLING . WESTINGHOUSE - t 9 f-w a ww -- *.*s 4 we -== rue-e e e w=we' t he=ii tier--' e v$-e

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28. Packing Gland Nut 3.

Disc 14. Yoke

29. Spherical Washer 4

Main Flange Gasket 17, Operator Cap Screw

31. Guide 5.

Bonnet 18. Leak-Off Pipe 32. Torque Arm 6. Stem

19. Main Flange Stud 33.

Stem Pin 8. Primary Packing

20. Main Flange Nut

34. Disc Pin Ba. Secondary Packing 21.

Link

35. Lock Pin 9.

Lantern Ring 22. Pin 36. Bearing. Block

10. Yoke-Bonnet Nut 23.

Torque Key

37. Lock Pin

11. Yoke-Bonnet Stud 24.

Torque Arm Set Screw 38. Lock Ring

12. Gland

27. Packing Gland Stud Gate Valve (Exploded View)

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~ y, g BONNET OVERPRESSURIZATION > Potential Causesi - Pressure in the valve bonnet is trapped'when the valve' is closed under pressure and pressure in both upstream and downstream piping is relieved or reduced. ~ - Higher then normal pressure can be trapped in the bonnet when the system experiences. pressure spikes or surges. - Pressure in the bonnet can be increased when the valve is closed full of fluid and then - subjected to a thermal transient. Methods to Reduce Overoressurizadon: - Drill weep hole in the upstream disc - Install external bypass with a check valve to connect the bonnet cavity to the upstream pipe : - Install relief valve in bypass to vent excessive pressure in the bonnet. - Implement administrative controls to relieve pressure by periodically cycling the valve -

References:

NRC Information Notice No.: 92-26' " Pressure Locking of Motor Operated Flexible Wedge Gate Valves" } n

AIR OPERATED VALVES: i I Special Applications 9 ADS Stage 4 Core Makeup Tank Isolation PRHR HX Control ? i i 1 -l

j

.~ I 1 TLO - 2/1/4'4' l23

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A DS VALVES - STAGE 4 Functional Requirements o

Normally. Isolate RCS from Containment Automatic RCS Depressurization Valve Characteristics,, Valve Actuator Air Piston Operator Normally Closed, Fail-As-Is _ a, c_. e J Valve Actuation Low-4 CMT Level Setpoint Valve Testing ,9,c o J- ~ l l t TL3 - 2/3/93 .If

4 AP600 ADS TEST

FEATURES, STAGE 4

~ (AT POWER TEST) ~ W WESTlHGHOUSE - 2/93 i l L-----

e s AP600 ADS TEST

FEATURES, STAGE 4

s-(SHUTDOWN TEST) q,e h k l wrstincaousE - 2/93 w-1 /*-*P+ 4 N' 9PWs' M' e -w e in s T F'N4 T -c A-m-m-Ta %e 4 4 t' e-w e => W h'-'w"4

' CONTROL VALVE DATA SHEET NO: CT-003 ' Plant:, System:-

== Description:== . Tag Number (s) 0N4FI F AP600 RCS ADS Stage 4 ,'. ?a 8,C,D MA 1 t {I I a Rev: 5 Date: 01/31/93-Page 1 of 3 - " cmsnm ru.c m e w u w s L2. .y

CONTROL VALVE DATA SHEET NO: CT-003 I DRAFT Plant: System:

== Description:== Tag Number (s) j APG00 RCS ADS Stage 4 V004A,B,C,D %gC f l k 5 L-Rev: 5. Date: 01/31/93 Page 2 of 3 % e c: w 3es.e e r+cwmevercun * (( .1

y .4 e I' ' CONTROL VALVE DATA SHEET NO:: CT-003 Plant: System:

== Description:== Tag Number (s)L f J AP600 RCS-ADS Stage 4-V004A,B,C,D 4[ r-- 7 ' Rev: 5-Date: 01/31/93- ..Page 3 of.3 - ene evenusu - .mcw mevavtscn*- lA.;- -m. T w

O AP600 4TH STAGE ADS VALVES SOLENOIDS O-n, c_ - i 6 e WESTINGHOUS - 10/91 =. .-x-.1-x--- ---s- -w e.- L. A 2-u w-lW*w U p v e "-*w' s' O ---a------

AP600 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) l TEST VALVES l' l l-TAG NO. ADS-03 TAG NO. ADS-03 l q, c_ l T~~ 7 l-DESCRIPTION l-l MOTOR OPERATOR STROKE TIME VENDOR EDWARDS ATWOOD MORRILL t i 4 g> # .g ~

CVIT ISOLATION VALVES Functional Requirements Normally isolate CMT from RCS Initiate CMT Injection Valve Characteristics - e, c_ a _t Valve Actuator. o Air-Operated Diaphragm Normally Closed' Fall Open Sized for Limited DP Valve Actuation SI, Low Pzr Level, and Low SG Level Valve Testing , q, c_ ~ l T 3 - 2/3/93 32_ e-

CONTROL VALVE DATA SHEET NO: CT-004 Plant: System!

== Description:== Tag Number (s) DN4E7 AP600 PXS CMT Inlet Isolation V002A,8; V003A,B ~ - 4,C Rev: 5 Date: 01/31/93-Page 1 of 3 %

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4-CONTROLVALVE DATA SHEET NO: CT-004 Plant: System:

== Description:== Tag Number (s) -l DRAFT l

AP600 PXS CMT Inlet isolation V002A,B; V003A,B

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x, i r ..i 'i q 8 8 ~i l i ~ Page 2 of 3 ', 1 -.Rev: 5 - Date: 01/31/93 ' J - Pnnwi 0244/93 08 46A5 Ner.e4WALVEftl\\ \\ * ' O3 'I 5Y : .J-j

CONTROL VALVE DATA SHEET NO: CT-005 ? Plant: System:

== Description:== Tag Number (s)' LAP 600 PXS-CMT Outlet Isolation V014A,8; V015A,B. ~ R t-I. j b f 1 1 i s ) L l Rev: 5 Date: 01/31/93 . Page 1 of 3: . rnow c:msos nu mcwmavetsm :. . II ~e O

. l CONTROL VALVE DATA SHEET NO: CT-005 Plant: System:

== Description:== Tag Number (s)- . DRAFT [ i AP600 PXS CMT Outlet isolation -V014A,B; V015A,8 9 ' c_

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L u Rev: 5 Date: 01/31/93 Page 2 of 3 N* '""8 '6:45 ru.cmemvenm 'e..,,

u a PRHR HX CONTROL VALVES j L e Functional Requirements. j Normally Prevent RCS Flow Initiate PRHR HX Flow 1 o Provide Nonsafety Throttling lCapabilitp. _ Valve Characteristics -gg Valve Actuator Air-Operated Diaphragm with Positioner-Normally Closed, Fail Open j Operator Sized for Limited DP Valve Actuation Low SG Level, ADS, andLHigh SG Level 1 Valve Testing- _-_. q, e_ l ~ 1 ; - TL3 - 2 /3/93 .;_..,---+

1 j CONTROL VALVE DATA SHEET NO: CT-006 i 'j N Plant: System:

== Description:== Tag Number (s) j f . AP600 PXS PRHR HX Control V008A,B l 1 I A,c- - ) q 1 i 1 -i .] l 7 l 1 l .f f t: i i q t Rev: 5 Date: 01/31/93 - Page 1 of 3 Pnnted: 02,04 % 08 35:04 Fw:c. 6 AVALVEss n a .. $Y. ..,a_i.

CONTROL VALVE DATA SHEET NO: CT-006 Plant: System:

== Description:== Tag Number (s) N, ~DRAFTJ AP600 PXS PRHR HX Control V008A,B J ~ Sc_ a ~ Rev: 5 Date: 01/31/93 Page 2 of 3

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CHECK VALVES Special Applications IRWST Injection CV Containment Recirculation CV

~ Core Makeup Tank Discharge CV Core Makeup Tank Pressurizer CV- 'E 5 TLO - 2/3/03 y

n; \\; y f IRWST. INJECTION CV l Functional Requirements Normally Prevent RCS. Leakage to IRWST i Open for IRWST Injection After ADS-Valve Characteristics Simple. Swing Check Design No Dampers / Actuators No Body Penetrations _t Valve Testing _,x 1-a l l I j

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i CHECK VALVE DATA SHEET NO: CK-001 - N' j DRAFT N Plant: System:

== Description:== Tag Number (s) AP600 PXS IRWST Injection V122A,B, V123A,B, V124A,B, V125A,8 p 9,C t Rev: 0 Date: 01/31/93 Page 1 of 2 Pnnted OM493 0825 to NerM1JHA4xVALVEff KV 4 Yl' ~= ~. n =

CHECK VALVE DATA SHEET NO: CK-001 1 . Plant: System:

== Description:== Tag Number (s) _~ AP600 PXS IRWST Injection V122A,B, V123A,B, V124A,B, V125A,8 ^ C.. r, l L i l l t 1 l 1 i l i l 1 ) i l A Rev: 0 Date: 01/31/93 Page 2 of 2 Pnnied: OW4N108-45.22 FilsfM1Ji'AtNALVEh'E4 4 - l

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CONTAINMENT RECIRC CV Functional Requirements Prevent Draining of.lRWST to Containment Open for Recirculation from Containment Valve Characteristics = Simple Swing Check Design No Dampers / Actuators No Body Penetrations _ Valve Testing g a i 8 G P W - 2/3/O $Y l a

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[f ' CHECK VALVE DATA SHEET NO:.CK-002 1 U*L c-Planti System:

== Description:== Tag Number (s)- OR4p7 ~AP600 PXS-Containment Recirc V119A,8, V120A,8l M',C.i 1 l .c' 2 ..I r s i J a i -.Rev: 0 - ' Date: 01/31/93 - Page 1 of 2: JPnntas: 01049308.28:10 - ^ FUefW7HAAVALVESCK 4 - 3: ax. U

T-CHECK VALVE DATA SHEET NO: CK-002 i-Plant: System:

== Description:== Tag Number (s) ()g AP600 PXS Containment Recire . V119A,B, \\ 120A,8 ,c Rev: 0 Date: 01/31/93 Page 2 of 2 w o m Sion e n ru.cw.nuvAnan 4 h.

y CMT DISCHARGE CHECK VALVES Functional Requirements 1 Normally Stay Open Close to Prevent Gross Accumulator Backflow Through CMT During Cold Leg Break;or Balance Line Break Valve Characteristics e t Valve Testing. _q,c T 0 - 2/3/4% b' 1

CHECK VALVE DATA SHEET NO: CK-004 Plant: System:

== Description:== Tag Number (s) ~ DRAFT F AP600 PXS CMT Injection V016A,B, V017A,8 { 4,C. 1 w Rev: 0 Date: 01/31/93 Page 1 of 2 %e oneca.::ao ni.c e u v a vtscx u if

h- '. CHECK VALVE DATA SHEET N6fI~Ck-004 ~ Plant: System:

== Description:== Tag Number (s) - L ORAFT 'AP600 PXS- - CMT injection V016A,B, V017A,B. .J W F iiC s t t -i 1 4 n; .' { e [ '1 Revi O'- ' Date: 01/31/93: Page 2 of 2. ^ ~ Pnnud: 0104S3 0828:10 Fdef.%I.MIAtNALVEf4 K4 A

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~ LCMT PZR LINE CV ] Functional Requirements Normally Pass Steam Condensate to CMT: 1 Steam Trap Close to Prevent Gross CMT Backflow to:Pzr 1 During Pzr Pressure Balance Line: Break:or ADS: Valve Characteristics Simple Swing Check Valves No Dampers / Actuators 7 .l No Body Pe.netrations __ q.c_ Valve Testing o 'j s - T:. - 2/3/93 'j l -.m-

to* CHECK VALVE DATA SHEET NO: CK-005 . Plant: System:

== Description:== Tag Number (s) DRAp7 AP600 PXS CMT Pressure Balance V006 A,B; V007A,8 4,C 9 Rev:0 Date: 01/31/93 .Page 1 of 2. Pnnted. CL%H 08.2810 Filerm*NALVEF4 K\\ 4 SI-i a

~ CHECK VALVE DATA SHEET NO: CK-005-Plant: . System:

== Description:== Tag Number (s) .y-DRAFT 'AP600 PXS. CMT Pressure Balance -V006A,B:V007A,8 - R,C. ~ l c 4 Rev: 0 Date: 01/31/93 - Page 2 of 2 - Pnmad: 02A493 04 45.22 Ne c.m*NALVEF4 'E\\ 4'. ^ -Q. I

d AP300 CHECK VALVES o Current PWRs Use Check Valves in Similar Service RCS chemistry Stainless steel with stellite seats Infrequent use, normally closed o Well Designed, Simple Check Valves Are Reliable in Nuclear Power Plant Service Search of NPRDS failure records (1984 to 90) indicate 4500 check valve failures Of these only 87 were failures to open None of the failures was for a check valve with similar conditions to the IRWST valves No indication of boric acid corrosion or self welding was found o Check Valve Testing Performance tests show AP600 IRWST injectior and recirculation check valves perform well Further testing is being discussed to determine if in plant testing could be conducted to determine if corrosion bonding or other sticking failures would-occur at IRWST opening pressures -C3

PW9 C-EC4VA_VE FAl_URE OBS E RVATIOh S ~ ~ ~ ~ ~ o Most check valve failures occurred due to mechanical / wear damage (not applicable to AP600-valve application) o No failures to open due to corrosion observed for stainless steel valves o No failures to-open due to foreign debris in water service for stainless steel valves O 6 GI

Q APa00' CHECK VALVE TEST o Verify hydraulic performance of swing check valve-(provide valve design feasibility information) Opening differential pressure Differential pressure over the expected valve flow rate with prototypic valve arrangement o Develop a qualification plan Contract Penn State University to review existing check valve data-P ~ o Utility participation Have contacted 5 utilities about the possibility of testing existing check valves l 1 (s

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.o BONNET \\_ / \\j y\\ __ / - \\ _._ _ / Q \\ \\ O DISC ARM \\ DISC /:( HARDFACING (SEAT RING 8 DISC) e BODY Swing Check Valve Assembly Figure 4.1 4-2 52

+" 3_ - y : s M 8 O L o O -O. O -O O s ~1.. Body x N

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r 'E N 4.- Main Flange Gasket s N q 5. Bonnet 6 t ti n Pin ~- O 9. Collar Pin' 5

10. Pivot Pin" i

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11. Bearing Block

12. Main Flange Stud::

7 'N,

13. Main Flange Nut-

17. Lock Pin'.

q S O .g I e. [a ^ /. (o P MN = O e /7 Swing Check Valve (Exploded View) Figure 4.2 4 1-. $(;_ I

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SQUlB VALVES F Special Applications pH Tank Outlet isolation I I 'l TL? - 2/3/93 n-.

f. p-l ADJ TANK SQUl3 VALVES Functional Requirements Normally Prevent Leakage of NaOH from pH Tank into Containment Initiate pH Tank Discharge Valve Characteristics -g o _) Valve Actuator o g [ Ram Assembly Shears Inlet Fitting Valve Actuation o High Containment Radiation Valve Testing a I I L TL3 - 2/3/93 60

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