ML20069K358

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Forwards Listed Documents Requested During 940407 Conference Call Re Callaway GL 89-10 Closure Document
ML20069K358
Person / Time
Site: Callaway Ameren icon.png
Issue date: 04/08/1994
From: Reidmeyer M
UNION ELECTRIC CO.
To: Thomas Scarbrough
NRC
References
GL-89-10, NUDOCS 9406160059
Download: ML20069K358 (137)
v • d • e


Text

{{#Wiki_filter:- Ca!!away Piant Past Ofbce B3 C20 Tattor. Missoun E5?51 i IINION April 8,1994 Ers_cruic m U.S. Nuclear Regulatory Commission Mr. Thomas Scarbrough Mail Stop 7E23 OWFN Washington, DC 20555-0001 Enclosed are the following documents requested during the April 7,1994 conference i call regarding Callaway's GL 89-10 closure document. 1) RFR-87461 - Verify the Thmst Requirements for MOV's Using Grouping. ) Reference Question No. 8 2) Graph titled " Measured Coefficients of Friction for Rising Steam Valves" Reference Ouestion No. 5.3 We are also gathering further infnrmation to support discussions regarding questions numbers 3,7 and 12. Please contact me ifyou need additional information. ) ,ffah J_, Mark Reidmeyer QA Engineer 314-676-4306 MAR /tmw Enclosures cc: NRCI 94002 S. H. Reed, UENE MOV Engineer 314-676-8540 D. E. Shafer, UE Licensing ,s 9 ),

  • \\

'e '$ U l 9406160059 940400'~ l DR ADOCK O I

i REPORT: NERP8171 UNIOff ELECTRIC COMPANY DATE: 01/21/96 PAGE : 1 REQUESTS FOR RESOLUTION SYSTEM TIME: 15:47 i RFR TRAVELER SHEET i RFR NUMBER: 8746 I l RPR

SUMMARY

VERIFY THE THRUST REQ'T FOR MOV'S USING GROUPING f

LIR: Y DRAWING CHANGES REQUIRED: N DIR: N TEXT CHANGES REQUIRED: N NSE: N ATTACHMENT PAGES ATTACILMENT PAGES DETERMINATION OF THRUST VALUES 14 ATTACHMENT 1 2 ATTACHMENT 2 2 ATTACHMENT 3 2 4 ATTACHMENT 5 11 ATTACHMENT 4 ATTACHMENT 6 3 ATTACHMENT 7 13 ATTACHMENT 8 74 ATTACILMENT 9 4 DATE: /-1/.M FROM: ti%ss TO': Sr// HEM l'n-N SHA NOTES: . Ai O sdA M uA (ttAA dL' { - fd-0$ Y f /

4 .~.,-...-.:. s____ w u a _1 u._f_.a eE. 4.s irni a ,um+, ,s ,s REPORV: NERP81G1 U310N ELECTRIC COMPANY DAVE: 04/06/94 PAGE : 1 REQUESTS FOR RESOLUTION S? STEM TICE: 10:05 RFR PRINT RFRW: 8746 REV: 1 FILE CODE: E170.0102 i I STATUS PRIORITY RFR WUMBER REV STATUS DATE PRI DATE CATE GORY SYSTEMS 8746 I 90 19940124 10 19931213 MV AL BB BG EN LF EJ BN EG EM EP l KA KC i ALARA: N NPDES: N PER$0NNEL SAFETY CONCERN: N BUILDINGS: PLAN' PGMS: MV COMPONENTS : ALHV0034 ALHV0035 ALHV0036 BBHV0013 BsHV0014 BBHV0015 BBHv0016 BBHV8000A BBHv8000B BBHV8037A BBHV8037B BBHVB351A BBHVB3518 BBHv8351C BBHV8351D BBPV8702A BBPVB7028 EJHvB701A EJHv8701B BGHV8100 BGHV8112 BCHV8109 BGLCV0112B BGLCV0112C BNHV0003 BNHV0004 BWHVB812A BNHVB8128 EGHV0011 EGHV0012 EGHV0013 EGHV0014 ECHv0062 EGHV0132 EJHVB811A EJHVB811B EMHVB807A EMHVB807B ENHV0001 ENHV0006 ENHV0007 ENHv0012 ENHV0015 ENHV0016 EPNVB80BA KEYWORDS : SETPOINTS REFERENCES : RFR 010324A RFR 0053531 CORR ULNRC 1755 RFR 008746C RFR 008746G CALC 22 117 SUPPLEMENTS: 0 0 0 P SUPPLEMENTED BY: SUPERSEDES: 9878 A 9878 8 0 SUPERSEDED BY: RFR

SUMMARY

VERIFY THE THRUST REQ'T FOR MOV'S USING GROUPING FULL DESC:

THE MOV'S REFERENCED ARE MOV'S THAT HAVE HAD THRUST REQUIREMENTS TO ENSURE OPERABILITY UNDER DESIGN BASIS CONDITIONS DETERMINED USING INFORMATION FROM SIMILAR VALVES, THAT HAVE BEEN DP TESTED. THE THRUST REQUIREMENTS FOR THE MOV'S THAT RAVE NOT BEEN DP TESTED MAY NEED To BE REVISED AS THE THRUST REQUIREMENTS FOR THE VALVES THAT HAVE BEEN DP TESTED HAVE RECENTLY BEEN RECALCULATED USING CLOSr CALIBRATION TECHN! DUES.

  • R3370087461*

'008746 I*

m- __ ~.. h REPCOT: NERP8161 UNI C ELECTRIC COMPANY DATE: 04/06/94 PAGE : 2 REQUESTS FC3 REroLUTIC3 S7 STEM VIME: 10:05 RFR PRINT RFR#: 8746 REV: 1 FILE CODE E170.0102 PROPOSED RES: DETERMINE REVISED THRUST REQUIREMENTS FOR THOSE MOV'S THAT HAVE BEEN SET UP USING INFORMATION FROM OTHER MOV'S THAT HAVE BEEN DP TESTED, ALSO, DETERMINE 1F THERE ARE OTHER MOV'S THAT SHOULD HAVE THRUST REQUIRMENTS DETERMINED USING THIS METHOD VERSUS THE MOVATS DP DATA BASE. CLOSURE DESC: The scope of this rfr has been expanded from what was first requested in this rfr. Instead of only evaluating those mov's whose thrust requirements were previously determined from the grouping of other mov's dp tested at callaway the thrust requirements for all mov's not dp tested to the criteria of edp-zz-01114 were re-evatauted. Some of these mov's previously had thrust requirements based on the movets dp data base, calculations or grouping of mov's dp tested at celtaway. It is intended that this rfr will supercede all of these other evaluations and provide the final thrust requirements that will be used for generic letter 89-10. The dp thrust values previously provided by the movets dp data base (calc zz-117) will be volded (CATS 41501 will track this action). The revised thrust values from this RFR are suunarized on Attachment 4. Note that some of these thrust requirements are conenercial values. In addition, the present minimun avaltable thrust from the most recent MOVATS test was conpared with the new thrust requirements being developed in this RFR and also RFR 8746G. This was also done for rev G but was not docunented. For traceability this review is being included with this RFR. No operability concerns have been identified with the present setup of any safety related MOV with an active safety function. COMMENTS: also covered in this rfr are the following mov's enhv8924 ephvB8086,c,d kahv0030 kchv0253 Lffv0095 and tfhv0105&106 efpdv0019 and 20

          • APPROVALS / SIGNATURES SECTION *****

ORIGINATOR: WINK ROGER C ORIG DATE: 19931210 ORIG. DEPT: NESM ORIG SUPERVISOR: HEINLE!N DAVID E APPROV DATE: 19931213 ORIG DEPT HEAD: MCGRAW JOHN A APPROV DATE: 19931213 DES. SUPV. ENG: MAXWELL DANIEL J RESP SUPV. ENG: HEINLEIN DAVID E DEPT: NESM RESP INDIVIDUAL DISP: WINC ROGER C FORECAST DATE: 19940107 QUALIFIED REVIEWER: REED STEVEN H QR DATE: 19940122 SUPV ENG REVIEW: HEINLE!N DAVID E REVIEW DATE: 19940124 PLANT MGR MINOR MOD: APPROVAL DATE: 0 ORC MEETING NBR: ORC ACCEPTABLE:

f REPORV: NERP8161 UNION ELECTRIC COMPAN7 DAVE: 04/06/94 PAGE : 3 REDUESTS FOR RESOLUVION STSTEM TIME: 10:05 j RFR PRlWT RFR#: 8746 REV: I FILE CODE: E170.0102 ? I i i k i

          • ATTACHMENTS SECT 10N *****

i l NUCLEAR SAFETY EVALUATION: N LICENSING IMPACT REVIEW: Y f DESIGN IMPACT REPORT: N f ATTACHMEWT PAGES ATTACHMENT PAGES ATTACHMENT PAGES [ DETERMINATION OF THRUST VALUES 14 ATTACHMENT 1 2 ATTACHMENT 2 2 f ATTACHMENT 3 2 ATTACHMEN1 4 4 ATTACHMENT 5 11 ATTACHMENT 6 3 ATTACHMENT 7 13 ATTACHMENT 8 T4 i ATTACHMENT 9 4 0 0 i CLA*$ VALID UPDATE NOT./ DRAW / DOC NUMBER 1 DOCCNTL RESP RECEIPT UPDATED RESPONSIBLE INDIVIDUAL s

        • END OF REPORT ***

i i [ i f 1 i I e s i r l 1 I i l

~ i l LICENSING IMPACT REVIEW i /El P -7'M.'2-I This review is appticable to 4 OF IN ANSWERING THE FOLLOWNG QUESTIONS, REFER TO ATT (1) I i APA ZZ-00140. 1_0CFR 50 59 APPLIC_ABillTY (2) d roceed No Formal Safety Evaluation Required.(Refer to Attac O (2.1) l to Section 3) Outside Safety Evaluation (Attach CA41340 and proceed to Section 3) O (2.2) SAFETY EVALUATION SCREENING (2.3) A proposed change to the facility es oescribed in tne r s AR7 f No 1 Yes (23.1) A change to p'ocedures as described in the FSAR7 Yes No g.,,_ (23.2) A test or expenmert not cescrited in the FSAR7 i f No Yes (2.3.3) A change to the Techncat specercatens? No _f, i l ti n per APA-ZZ 00140. If the Yes (2.3.4) If any question in this section is answered "Yes", com l i ed Safety Question does l l not exist. l i rdance with NOTE Changes to the FSAR or Technical Specincations require add j APA ZZ-00108. i EQUIPMENT QUAltFICATION IMPACT REVIEW (3) Does this modification / change involve: An eetivtry whch involves any safety-retsted structure, s ,_/_ No componerd7 Yes (3.1) If no, then mark questions 3.2 through 3.8 *N/A and proceed to q instahauon of a new or moderesten to en easting system, sub equipmeri or component invoMng the assuance of a _,,,,,.,_ No I N/A Yes and/or the assyvnet or new equipmwd tag numters? (3.2) i if yes, then mark question 3.3 *N/A* and proceed to question 3.4, j An acthey whch wW modrfy a change any system. eq B whch must functon in a harsh post accederd onwonmen No _:[,,,, MA Yes (3.3) HELB Category A er B en FSAR TetWe 3.11(B)3). If no, then mark questions 3.4 through 3.6 *N/A* and proceed t i 1 f CA41339 Page 1 of 8 08-26-93 APA ZZ-00140 -

M8 P7W-r This feview is apphCable to For equipment or component changes to tems identifed as being requwed to (3.4) Yes No _ NA funcbon m a harsh post occadent environment (i e., LOCA. MSLB. or HELB Category A or B en F S AR T abee 31t(B)-3). e change m organc (soft) pads from thune spec 6 fed for the esosting equipment or comparent (e g,0-rings. Paciong. poskets, actrve or pressure boundary rubber /plaste parts, ensulaton etc )7 Re40caten of esostng equipment or instauston of new equipment such that (3.5) Yes No N/A submergence efter en occadent es an asue (compare Intended locaten agam FSAR Ta:.ne 3 64J7 For equipment or component changes, e change in performance (3.6) Yes No _ N/A charactenstes that could enpoet safety functons (e g, changes in instrument occuracy}7 For equipment or component changes. e signifcant change in see, mass, ,[_ NA,, onentaten, mountmg or center of gravPy from that of the ersteg configuration (3.7) Yes No (e g, a vow mass change of more than 20% or 20 lbs, per the guidance of EPRI-NP 5639J7 (3.8) Yes Ne ,,2 NA _ F or equipment or component changes, a change to intemat parts tnat may empact seisme Oualifcaten? A change such that the contamment spray system Could cause the pH of the (3.9) Yes No _/ delwered spray to be outside the range of 4 0 to i t 07 An activity whch wWl cause any safety-related system. equipment or component to be moved from its currently mstahed locaten to another room 7 (3.10) Yes No,/, The posaitety of enwonmentat changes to rooms or press containng (3.11) Yes No 4 safety-related structures, systems, equipment or components (i e, changes in radiaton level, or source terms, temperature profies. pressure profues, humidsty profdes, fbod levels or relocaten of a high energy (me)7 An actwity whch will modify or change any system, equipment or component (3.12) Yes No d listed as LOCA, MsLB, or HELB Category C or D in FSAR Table 31 t(B) 3 such that Seisme Qualifcaten may be impacted? ) i Does tne modifcaton, change, or tevew involve a possible Seisme M (3,13) Yes No [_ queston or affect Seisme Category 1 Stress Prob 6 ems? 2933 (3.14) Yes No f The possibility of oddmg an unqualifed coating (paint) to the Reactor Building or on tems capable of bioclung the containment sump? W any of guestens 3.2 through 312 ore morsed "Yes*,seen the environmoveel and/or seems eushra eehan sheti to Such voorcation must be performed by the (Q44etenets Support proup or Doensmg end documormed m secten ; 40022 cooramened edih Design Control pnar to afledad equipenent bemg tetoseed to termos. f Requests ear Romoluti.m (RFRs) that deel with metenal eeulveiency and effect Ceenpory A and 5 equipm enclusen erno the EQ (des. E the Else are impecsed, en EO Change Holme the# me pomerated 6AW APA-ZZ40390. 40B22 W questen 313 m marked 'Yes" addreas the noses /guessene based M Anschment 4. Para 313. Appropnot j l Evaluation, der. sic)outti be ponereted by the Evalue1m0 Engmest to en Bones N Questen 313 is merhed HO", e Eenme M gusehen does not east due to the nature of the meddleshon, ohenge, or feview. N Oussion 3.14 is morhed "YES*,the C6vlWee N hesse Donapn Coveral group should be conteded tot menantence on r CA41339 Page 2 of 8 08-26 93 APA ZZ-00140

r i 1 i /F8 Pv41-l This review is applicable to l 4497 (4) ENVIRONMENTAL EVALUATION i e ~ This rnodification/ change involves: t / An mcreau m thenna! power abow the currenUy bcensed levet? (4.1) Yn No (4.2) Yn No / An bereau m nome lowl? (4.3) Yes No f A phyacal change to one grounds or plant layout 7 I / An advwas impact on area whdkfe and/or vegetaten? l (4.4) Yn No / A change m the rate quanuty, conuntreten, or composRen, or temperature of ho effluents or any NPDES permated outfall? j (4.5) Yes No / A change m the raie. quanuty, concentration or compositen of gueous efnuents?l (4.6) Yes No / A change in particulate errnssons rs'e, concentraton, or compositen? (4.7) Yes No v i / Any ncavaten on UE property outsee of the owner controhed Area ence or any 42916 (4.8) Yes No excavaten disturtung five seres or more on UE property? A passible change to the facility's potental for the discharge of oil mto or upon the [ 42427 (4 9) Yes No r.angabie waters of the U.S 7 / A s gnireant incrase m any aderu enwonmental trnpact prevously evaluated m l (4.10) Yes No NUREG 0813 (FES OL)? _ A maner which has Dgt been prevousY evaluated M NURE G 0813 (FES OL) which (4.11) Yes No may have a sgnificant adverse onwonmental empact? If the answer to any of the above questens es *Ves", a Fna! Enwonmental Evaluaten must be performed b Depa'tment if all of the questens in this secten are marked "No", en unreviewed onwonmental que l Ennonmental Evaluaten s ret required l 10 CFR 50 54 APPLICAB'LITY DETERMINATION t (5) I This modification / change involves: ii (5.1) Yn No / A change to the Radeiogest Emergency Response P6an (RERP7) I (5.2) If yes, forward to the Supervisor Emergency Preparedness to answer the fahowing questen: is RERP effectiveness reduced? DYn D No l (Provide basis for the response h Secten 8 of trys form and sgn below ) f f I i Supervisor, Emergency Preparedness i / A e.ne.inm. re.y.io.is.cway= c e.ie.neyrun? (5.3) v N. (5.4) e v.s==e w v. s .s cwayto== ro.ha.=neei an i j is Security effecttveneas reduced? O Yes D No i, (Provioe bass for the response m Sedson 8 of the form and sign below ) / / 4 Superinten@nt Secunty CA41339 i Page 3 of 8 08-26 93 APA-ZZ-00140 j i ~ '

1 b 88 PWtr This feview is applicable to l ! A cha,ge to the operating Quainy Assurance uanuai(ooAuj mcudeg tne (5.5) Yes No Suppemental Q A Prog ams? if yes.torwn d to the Supennsma Engmeer. Qualty Assurance for competon of a Qualry Assurance e f (5.6) D Tes D No is Qualty Assurance reduced? (Provide bass for ths response m Section 8 of this form and magn benow ) / / Supervising Engineef, Quahty Assurance (6) CERTIFICATIONS (6.1) FIRE PROTECTION REVIEW (6.1.1) Yes No / The mod;fcaton/changevevew may mvolve a change to one or more aspects of the approved Fre Protecten Prog *am as oefined en the checklists of EDP-ZZ4044. Fae Protecton Revews sf yes. cocument areas of concem and resoluton in Secten 8 of the LtR or on a Desgn input Report ! Engineer perform a cross 4sciplinary reven of the LIR or DIR per EDP-ZZet044 (6.1.2) Yes No / This modirication/ change / review mvolves an additon of combustible or flammable rnateraf 6 If yes. evatuate the need for a *CombusteleTiammabie Matenal Additen" form LAW EDP ZZ44044 (6.1.3) Yes NR / CA-e1855 from EDp,ZZ-04044 a'tached to LIR and copy sent to Supervising Engneer - CrvitTre ProtectanOrsgn Bases. ? 621 (6.2) ALARA REVIEW (complete pm sechon. EITHER Sect.6 2198 6.2.2) i l (6.2.1) 4Aodifcaten - Spefc(appicabie for CMPs. RMPs EMPs and Minor Modifcatens) Will ths enod.fcaten require work within the Radolog cat Controlled Area (RCA)? Yes No Will the modifcaten require work on a system containing or potentatty containmg Yes No redcactive matenaf? Will thm snodifcaten involve work on a system whch connects to or interfaces with Yes No a system or component stonng.transfernng. or handkng redonctive matenaf? l Will the modifcaten or associated anplementaten or operaten mvolve modifcaton, Yes No remova! or metallaten of sheadsng? b Wie the mod:fcaten invorve rodeactrve waste genersten? Yes No f If the answer to any of the questens above is *yes' en ALARA design rewww is required per Nuclear Engmeenng ZZ-00100. If ZZ403 00 regurements cannot be met, an ALARA revww must be performed by Radoiogca! Engmeenns i f I Documentaten detailing the results of this revww is incewded in Seebon 8 of the LIR. O At answers to the above questens are *No* and i is cor%ed that the proposed change does not increase poten O exposures beyond the exposures that already eiust. (L.:.2) GENERIC 6 1 bereby cedify that the proposed change does not increase potenbal rad.ston exposures beyo that already erst CA-#1339 Page 4 of 8 08-26-93 APA-ZZ-00140 l

) b i / f /,P 7+'d, r This review is applicable to The change required f#ther evaluaton by a quahfed AL.AR A revewer per Nuclear Enginj D 003@. Documentation of this revew s incJuded m Secten 6 of the LIR. (6.3) ODCM/PCP REVIEW The modifum' change /revww rnay impact the Process Control Program (6.3.1) Yn No (PCP) as onmied in APAJ241011. l l if yn, fonward to the Supenntendent. Chemastry & Redwante to answer the fehownng two (6.3.1.1) with Aomsnrstrative Techncal Specifcaton 613. i 15 the overafl conformance of the soldfed waste product to elosing Crtent for Sohd wastes reduced 7 i DYn D No i 2814 Does this modtfcatervchangetevew requae a change to the PCP7 D Yes D No i (Pronoe bas:s for this response m Secton 8 of this form and sign telow) t I / Superintendent, Chemistry and Radwaste TNs rnodifcatethange/ renew may rnpact the Off-site Dose Catulaton (6.3.2) Yes No ManuaI(ODCM) as aetailed m APA-ZZ41003 if yes, forwara to the supenntendent. Heath Physics to answer the follovnng two questen j (6.3.2.1) Adminstratrve Techncat Specircataon 614. is the accuracy of effluent re' ase calculatons.oose calculatons or setpoints determmatons reduced? e D Yes D No 2815 Does tns modifcatontchange *even require a change to the ODCut DYn D No (Provide bass for the response in Secten 8 of the form and sagn tietow) / I Supefintendent, Health Physics CA41339 Page 5 of 8 08 26-93 4 APA-ZZ-00140 l a

~ t /F# P74_r This review is apphcable to (6A) HUf/ AN F ACTOR EVALUATION This Modification / Change involves: A change to the Main Control Board (RLOO1 throug'i RLC28) or Auxshary Shutdown Panel (64.1) Yes No (RP118)? / A change to the Plant Annuncator Window locaton, engrenng etc.? (6.4.2) Yn No / A change to the Control Roorn temperature, air velocay, bphting, erntpent sound levet, etc. (6.4.3) Yes No e / A change to the Auxikary Shutocwn Panel Room kg%ng? (6.4.4) Yn No if the answer to any of the ateve es "YES*, prepare a trief desenpton of the modtecatervchange and forward tothe if all of the stove are *NO*, a Human F actor Renew is not requred. However,if controls,instrumentaten, etc change to ot[ Engineer e Human F actor Recew shouki be requested. d/d i I Human Factors Design Review Engineer (65) STATION BLACKOUT (SBO) EVALUATION This Modification / Change involves: l (6.5.1) Yes No i/ Pnacing additonal electncal load on the Staten Battenes Adding sources of heat en the Control Room (3601) or Equipment Catunet Area (3605) (6.5.2) Yes No / A change in the source of supplied power for any Containment isolaten Vefve or as posRon (6.5.3) Yes No ) indicators / A change en the source of supplied power for any safety-related or Staten Bisckout (6.5.4) Yu No instrumentaten or controls (6.5.5) vn No /. A change that will encrone the rate of Reactor Coolant inventory loss,,1 (6.5.6) Yes No /_ A reducten in the required Condensate Storage Tank volume. / A reducten en the volume of backup nitrogen for the Auxlha y Feedwater control or Steam (6.5.7) Yes No Generator Atmosphenc Relief valves. The additon of heat generating sources, that will be present after a loss of AC power,to any o (6.5.8) Yes No / the following rooms 1506 Main FosdweierSteam Tunnel 1202 Access Area B & Chilner Surge Tenn Area 1509 Main Teodwatersiasm Tunnet 1304 Auriha y Fooeweter Pepe Chase 1512 Control Room NC & Feraten Units Room A 1305 Aumhary Foodwater Pipe Chase 3302 Engmeered Estety Features $watchgear Room No. 2 1322 Pipeg Penetraten Room B 34De Swnchtmard Room No 4 1323 Pipeng Penetteten Room A 1327 Austhary Foodweier Pump Vabe Companment Nr* 't 3405 Sattery Room No 4 1330 Ausdiary Fomdwater Pump Valve Companment No 4 3407 Benery Room No 1. Turtune Dnven Auxika y Femihusser Pump Room 3408 Sweichtmord Room No.1 i r 1331 3410 Swelchtmord Room No 2 1408 Camdor No 2 3411 Senery Room No. 2 1409 E6metncat ?enetrehan Room B 3413 Senery Room No 3 1411 GAsin F esownterSteam Tunnel 1412 Main Feed.veierSieam Tunnel 3414 Swachtmord Room No. 3 1501 Control Room NC & Feraten Unita Room 8 4201 Condoneer Pd Condensate Starage Tank Valve House if the answer to any of the ateve is YES* propere a tinef desenpton of the modifcaton' change and forward to the S Blackout Renew Engineer. If all of the ateve are *NO*,then no Staten Backout Review as requred. af i 1 Station Blackout Review Engineer CA41339 Page 6 of 8. 08-26-93 l APA ZZ-00140

i /#/ #7vz r l This review is applicable to PROBA98!.ISTIC RISK ASSESSVENT (PRM REVIEW (6 6) i This modification / change involves' / A potent.atiy FRA signifcant change to a p6 ant system (6.6.1) Yes No (6.6.2) Yes No _Z_ A change to plant Techncat Specifcatons - f / A change to amorpency opwating proceoures (6.6.3) Yes No If the answer to any of the above is *Yes*, prepare a PRA Evaluation Request (PRAER 22 04004, Performance of PRA Evaluations). and forward to the Superv: sing Engineer, S Design if all of the above are *No", a probabikstic nsk assessment is not fequired. i i si k e PRA Engineer JUSTIFICATION FOR NO UNREVIEWED SAFETY OUESTION (7) Bnefiy state why this rnoorfcation oces nc4 require a Format safety Evaluation, use puede t I titre sheets if necessa*y) Y / // l} M A frf d4~s W d 7/ m w n,.,>, 4 W / L i / Aul Al vb,$ l Amd5$u w l M f-2 7-o sis l f s.JL.L 1s/ a~o. A-,u A L \\ Y f L1 Y vs

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i l i

  1. E# f 7M 7 This review is apphcable to l

(8) COf/t/EtHS Lst any specet condnons or comments pesining to these evaluatons a d certsreatens l l l ) (8) APPROVALS /-//-9[ Date Responsible Engine

  1. A, m.

f-- Od Date / - 2 7 - 9 '/ Qualified Reviewer a i f CA41339 Page 8 of 8 08-26-93 APA-ZZ 00140 i

S RFR 87461 RFR R7461 DFTFR%11N ATION OF TIIRtiST val (fES 1 INTRODl'CTION Generic Letter 89-10 requires that utilitics differential pressure (DP) test safety related MOVs when practical in order to verify that these components will be capable of performing their intended safety function. RFR 10324 A has been dispositioned and presides the reasoning why it is impractical to DP test selected safety related MOVs at Callaway. It has been the Callaway Plants philosophy to DP test all 3 safety related MOVs when practical, howcVer, because of situations where an MOV cannot be adequately DP tested alternate methods are needed to determine how the thrust requirements for these MOVs can be established in order to satisfy GL 89-10 requirements. The purpose of this RFR is to desenbc for each safety related rising stem valve MOV that has not been DP tested to the criteria described in EDP-ZZ-01114 Motor Operated Vah c Predictive Performance Prograrn, how the thrust requirements are being established in order to satisfy Generic Letter 89-10 requirements. Note that RFR 10324 A addressed both safety related rising stem and butterfly valve MOVs. This RFR is only addressing safet3 related rising stem MOVs as all safety related butterfly MOVs have aircady been evaluated 2, Several attachments are provided with this RFR as summarized below: : Provides a comparison of actual DP test results vs. calculated thrust values. When DP test results arc referred to they originate from this attachment. : Determines the calculated thrust values for valves discussed in this RFR that have not been DP tested. : Provides information regarding the Rate of Loading Factors used in this RFR. l : Provides a summary of the final thrust values for values being evaluated in this ! : Provides seat ring dimensions for Westinghouse supplied MOVs. : Prosides DP test information for ENHV0006 and 12 from Wolf Creek, Attachmetnt 7: Pro ides PRA information for MOVs discussed in this RFR t : Provides the latest information from the EPRI MOV Predictive Performance Program. : Operability verification for the revised thrust requirements prosided by RFR 87461 and G. PRIMARY METHOD OF DETERMINING DP REOUIREMENTS FOR VALVES NOT DP TESTED For those valves that cannot be DP tested the preferred method for determining thrust requirements has been to group similar MOVs that have been DP tested at Callaway and either using that data directly or demonstrating that the thrust requirements can be conservatively predicted using calculations. 3 Note that RFR 10324 A stated that EFHV23,39,40,41,42 could not be DP tested to the criteria of EDP-ZZ-01114. These vahrs have been DP tested greater than 50% of the design DP per RFR 8746H. In addition, RFR 10324 A did not refer to LFFV0095 and LFHV00105,106. These vahes were DP tested but not to the criteria of EDP-ZZ-01114. EFPDV0019 and 20 thrust values are also determined in this RFR even through they are routinely DP tested near the design DP of 134 psid. 2RFR 8746H RFR87461. DOC 01/21/94 1

RFR 87461 ,, Mr d tions should be met. First the valves being b ing d" me manufacturce and type. Secondly, the vahes e Before this method is considered reliable several con i g4,, ,l li d If 4, 4,,,_ f i h t d below before the test results can be directly app e fh used for comparison purposes must be o t e sa h ated_ ison arc above the design DP of the va m ;.,, t. used for comparison must meet the enter a s e il i l the test DP for vahes being used for compar dditionally, the similar valvc(s) should be the same no l the thrust values are reduced proportionate y. fi d the secondary method is employed. valves to determine thrust requirements. A siic or larger. If these conditions are not satis e d if design DP is > 260 psid Test DP must be 80% of design DP for valve not D d if design DP is < 260 psid QUIREMENTS FOR VALVES NOT D SECONDARY METHOD OF DETERMINING DP RE nts for MOV's not DP tested is use of a The secondary method used to determine thrust requ remeis the m i l modified standard industry equationi Listed be ow and globe valves. P VF) OPEN THRUST REQUIREMENTS = ROL x (D AxD x DPx VF) + sax LP) dd CLOSED THRUST REQUIREMENT = ROL x ((DAx (cs*g. b iS' % += 2 d ROL= Rate of Loading ; set dependent on actuator size DA = Mean Scat Arca sq. inches. 11 to 2.2 for globevalves where: DP = Differential Pressure psidVF = Valve Factor = 4 to 1 5 and.4 for parallel disc / slide gate valves SA = Stem Arca sq. inches LP = Line Pressure h ent 2 for ALHV0034: For exampic, refer to the information provided on Attac m ROL = 1.15 D A = 44.92 sq. in DP = 135 psid in closed direction VF =.5 SA = 1.22718 sq in b me: Using the infonnation above the closing thrp requirements eco i 718

  • 135)) = 3677 lbs CLOSED THRUST = (1.15) * ((44.92 *135 *.5) + (1.2 f

f r Motor Operated Valves in Nuclear Power P li 3 Refer to EPRI NP4660-D, Application Guide ne o If b the results of EPRI Predictive Performance Pro eqn 513 4 Refer to Attachment 3 i the individual section of this RFR. 50ther valve factors may be used if supponed yother v RFR87461. DOC 2 01/21/94

I i RFR 87461 Note that the open thrust equation is the same as the closing thrust equation with the exception of the S AxLP term. This term, commonly referred to as the piston effect w ould actually be negatist in the i open direction thus reducing the calculated thrust requirements further. This term is set equal to zero conservatism. Also note that neither term includes a value for stem packing loads. This term is included durmg field testing where the packing loads are measured rather than being provided here based on generic guidchnes. In summary, the discussion above was intended to demonstrate the methodology being used at Callaway to satisfy GL 89-10 requirements with regards to estabhshing thrust requirements. Each of the 54 rising stem MOVs at Callaway that have not been DP tested to the criteria of EDP-ZZ-01114 and the basis for the thrust requirements to allow closc-out of GL 89-10 is provided in this RFR. Note that some thrust requirements are being changed from that previously established in the Callaway Equipment List (CEL) to provide added conservatism while some MOVs have had thrust requirements relaxed because unrealistic thrust requirements that were overly conservative. Finally, it will be noted that the weighting cach MOV has on the Callaway Plant PRA is included on Attachment 7. No MOV's that are of high priority with respect to the Independent Plant Evaluation (IPE) have had there thrust requirements determined using the methods described in this RFR. Thus, any rising stem MOV that is considered to have high prionty with respect to the IPE has been DP tested to the enteria of EDP-ZZ-01114. Al IIV0034,35,36: CST TO AFP SUCTION ISOLATION VALVES These MOVs were panially DP tested during the IE. Bulletin 85-03 program. However, the test DP (14 psid) was inadequate to satisfy the criteria of EDP-ZZ-01114 for extrapolation purposes. The present closing thrust rcquirements for ALHV0034,35,36 originated from RFR 8746D based on comparison of the thrust requirements from EGHV0058,59,60,71,126,127,130 and 131. Hourver,in reviewing the valve design for these valves it became apparent that some of these uhes should not be considered suitable for comparison as similar vahts. ALHV0034,35,36 are Anchor Darling ficx wedge gate fFWG) valves. EGHV0058,59,60,127,130 and 131 are also Anchor Darling valves but are of the paralici disc gate (PDG) design. The difference in the two designs are that the FWG vahe discs are wedged downward into the sloped seating surface of the valve body whereas the PDG vahts are thrus outward by a wedge assembly. The flex wedge design will have a higher valve factor assuming an equa disc fnction cocilicient because of the sloped scating surface. This still leaves EGHV0071 and 126 which are of the same design as ALHV0034,35,36 but of different sizes as described below. VALVE ID MA.NUFACTURER TYPE SIZE ALHV0034 ANCHOR DARLING FWG 8" ALHV0034 ANCHOR DARLING FWG 8" A111V0036 ANCHORDARLING FWG 10" EGHV0071 ANCHOR D ARLING FWG 12" EGHV0126 ANCHOR DARLING FWG 12" For ALHV0034,35,36 it is desired, since the vahes sizes are different, to demonstrate that the thrust requirements for EGHV0071 and 126 can be approximated using calculations and a vahr fac .5 mhen cx>mpared with the actual DP test results. Once this has been shown the thrust requirements fo AllIV0034,35,36 will be determined using calculations and a.5 vahr factor. Attachment 1 prmides the results of the DP test measurements for EGHV0071 and 126 and the calculations using the equations described in the introduction section. The information from Attachment 1 is repeated here for reference. RFR87461. DOC 01/21/94 3

RFR 87461 VAINEID cal.C Cl OSED THRUST MEASURED Ct.OSED TIIRUST EGHV0071 5054 LBS 5267 LBS EGHV0126 4951 LBS 4220 LBS As can be seen the calculational method would have prosided a good approxinution of the closing thrust requirements for EGHV0071 and 126. Note that the thrust values hsted abcwe inherently include conservatism with respect to measured thrust due to the methods in which DP testing is performed at Callaway, i.e. include spring pack appr. rent spring pack preload. ALHV0034,35 and 36 are installed in a system with basically the same fluid medium as EGHV0071 and 126, i.e. sub cooled liquid with a normal temperature less than 100 degrees Fahrenheit. 6 The fluid velocity through EGHV0071 and 126 during the DP testing (-3300 GPM or 11.13 IVsec ) s much greater than the worst case velocity for ALHV0034,35,36 (575 GPM or 3.7 ft/sec for ALHV0034,35 7 and 1145 GPM or 4.7 fVsec through ALHV0036 ). Based on the discussion above the closing thrust requirements for ALHV0034,35,36 can be established using calculational methods. The revised closing thrust requirements for ALHV0034,35,36 are provided below. Note that the opening thrust requirements for ALHV0034,35.36 as prosided in RFR 8746D remain unchanged. ALilV0034,35 CLOSING TilRUST REQUIREMENTS = 3677 LBS 4993 LBS ALilV0036 CLOSING TIIRUST REQUIREMENT = RCP THERM AL B ARRIER RETURN FLOW ISOI,ATION VALVES BBilV0013,14,15,16 Thesc MOVs have been DP tested but did not satisfy the criteria for extrapolation presided in EDP-ZZ-01114 in the closed direction. These arc MOVs that have no sinular valves tested to a high enough pressure to compare DP test data with at Callaway. In referring to the EPRI Performance Prediction Program a 2.5" Velan FWG has been tested under blowdown conditions at 530 degrecs F and 2660 psid. Under these conditions the disc friction coefficient is recorded as.328. Assuming a 5 degree wedge angle this corresponds to a vahe factor of.340. The disc friction cocflicient is comtrted to valve 8 factor using the following equation. VALVE FACTOR = p SIN @ COS @ APPARENT FRICTION COEFFICIENT WilERE p = WEDGE ANGEL (ASSUMED 5 DEGREES) = The design basis conditions for BBHV0013,14,15,16, i.e. isolate under a thermal barrier break, are similar to the test conditions for the 2.5" Velan FWG valve. BBHV0013,14,15 and 16 are 3 inch Velan FWG vahrs. Since the design of these valves are the same and or.ly the size is slightly different (2.5* vs. 3") the disc friction coefficient information provided above is considered valid for determining the thrust requirements for BBHV0013,14,15 and 16. For added conservatism a vahe factor of.4 will bc used in place of the.34 vaht factor determined abost. l Refer to Special Test Report for ETP-EG-STUO2. 6 7 Refer to FSAR Chapter 10.4 Refer to EPRI MOV Program Review Meeting Minutes 12/1/93 included in Attachment 8. 8 RFR87461. DOC 01/21/94 4

RFR 87461 Using the calculational method described presiously with a.4 vaive factor a closing thrust requirement of 8482 lbs closing thrust is obtained9. The opening thrust requirements provided by RFR 14359A should continue to be used as they are based on in situ DP testing within the criteria of EDP-ZZ-01114.. t CLOSING TilRUST REQUIREMENT FOR BBIIV0013,14,15,16: 8482 LBS BBHV8000 afb PORV BLOCK VAINES The present opening and closing thrust requirements for BBHV8000A/B originate from RFR 53531 and are based on a comparison with other Westinghouse flex wedge gate vahts that hast been DP tested at Callaway. The design DP for these valves is 2485 psid open and 2335 psid closed. The test DP's 10to ostrcome the for the valves used for comparison in RFR 53531 and their resised thrust measurements test DP is repeated below. VALVEID SIZE TEST DP MEASURED MEASURED OPEN TilRUST CLOSED TilRUST BGHV8105 3" 2572 PSID 2490 LBS 10373 LBS BGHV8106 3" 2572 PSID 4540 LBS 12127 LBS EMHV8801A 4" 2677 PSID 4458 LBS 4221 LBS ENDIV8801B 4" 2677 PSID 6062 LBS 2815 LBS EMHV8803A 4" 2727 PSID 10586 LBS 4632 LBS EMHV8803B 4" 2702 PSID 3760 LBS 1567 LBS EhDIV8821 A 4" 1595 PSID 4299 LBS 3934 LBS EMHV8821B 4" 1540 PSID 4249 LBS 2709 LBS EMHV8835 4" 1595 PSID 3650 LBS N/A BGHV8105 and BGHV8106 are the same size and 13pe valve, have the largest measured closing thrust requirements and were DP tested at a pressure in excess of the design DP for BBHV8000A/B. Using the :;alculational method a closing thrust of 11630 lbs is obtained for comparison with the test DP thrust requirements on BGHV8105/8106. The calculations are comparable with the test results. However, before using the DP test results from BGHV8105/8106 to predict bounding thrust requirements for BBHV8000A/B the differences between the DP test of BGHV8110&8111 and design conditions for BBHV8000A&B should be addressed. BGHV8105 & 8106 were tested under pumped flow, cold water conditions under relatively low flowrates (<120 GPM or less than 7.2 fl/sec) compared with what BBHV8000A/B would be expected to sec. Under a design basis accident BBHV8000A/B would be expected to isolate under 2 phase blowdown conditions. In referring to the EPRI MOV Predictive Performance Program a Westinghouse 3" FWG vaht is being tested under high DP conditions at a nominal velocity of 15 ft/sec. Under these conditions an opening apparent friction coefficient of.313 is recorded. For the 7 degree wedge angle for this model valve this corresponds to a vaht factor of.328 (refer to the discussion for BBHV0013,14,15 & 16 on how to calculate valve factor). In reviewing the EPRI study it is found that the opening apparent friction coefficients tend to bound or closely approximate the closing apparent friction coefficients in the high pressure cold / hot water test loop data. Thus, for non blowdown conditions it appears that a valve factor of below.5 could be justified. However, since these vahrs have not been DP tested under blowdown conditions the use of a.6 valve factor is recommended for BBHV8000A/B. Using the a valve factor of.6 the revised closing thrust becomes 11355 lbs. 9 Refer to Attachment 2 10 Refer to RFR's 8746F&G RFR87461. DOC 01/21/94 5

RFR 87461 t W8000A/B become in the open dtrcction using a.6 vah c factor the thrust requirements fori ht ue/ thrust It should also be noted that these are limit closed MOVs that will develo 9244lbs. e di i necessary to overcome DP conditions up to locked rotor c i I 11355 LBS BBHV8000A/B CLOSED THRUST REQUIREMENT = 9244 LBS OPEN THRUST REQUIREMENT l = PRESSURIZER REI IEF TANK ISOLATION VALVES BBHVH037A/B d cribedin These valves have had their thrust requirements determined using ca RTR 9878B. The thrust requirements using this method were determined to li htly different than that used in l i closed for a design DP of 104 psid. The method used in RFR 9878B s s g l 4' vahes of this this RFR disposition.BBHV8037A/B are 4 inch Westinghouse FWG valves. The design DP tested under more severe conditions that BBlW8037A/B wouA/B se excess of the design DP for BBHV8037 A/B (refer to BBHV8000 d (EMlW8803 A) and compares largest measured closing thrust from the 4" vahrs that ident that the calculational ii i dscry method provides conservative results. Based on this discussion the thrust conservatively using calculations. For consistency the thrust requirements aree h method desenbed in this RFR. For additional conservatism the t ru using a valve factor of 1.0. l 1337 LBS BBHV8037A/B CLOSING THRUST REQUIREMENTS 1190 LBS OPENING THRUST REQUIREMENTS i RCP SEAL INJECTION 1501 ATION VALVES f BBHVN351 A.B.C.D 2582 and 2824 MOVs BGlW8110 and 8111 are identical MOV's that ha d ere tested under higher l psid respectively. BGHV8110 and Bill are the same s 10 and 8111 are the CCP minflow line isolation valves that have flowtates limited to 60'GP 8 GPM cach)to supply the BlW8351 A,B,C and D normally have a combined flow rate of-32 GPM (or h shavebeen RCP seals.These rhlves are 2" Velan globe vahts with flow under the i itis desired to have determined to not have an active safety function but for commercial cons l8 i i g the DP data for l e requirements established to overcome a DP of 2E13 psid,in rev ew n h t st DP was less ? BGHV8110 and BGHV8111 it is discovered that the amo l their thru than the apparent prcload of the spring packs. Thus, the amount oSince BGIN8111 w l to have been less than the apparent preload of the spring packs. rent preload from B j d - above the commercial DP for BBlW8351 A.B C.D the cll BCD T 7039 LBS - BBHY8351 A.B.C.D OPEN AND CLOSING THRUST RE i f [ b ased on the disposition of RFR 5353G and SOS 90-1584 it w [ ilDP. l active safety function to open or close. RFR 5353X provides a commerc a B l RFR87461. DOC 01/21/94 6 l i 9

i RFR 87461 I RHR PUMP SUCTION ISOLATION VALVES FROM RCS BBPV8702A.B EJilVN701 A.B

1. OOPS 1 & 4 There are no other valves of the same size at Callaway that have been adequately DP t!

BBPV8701 A/B & EJHV8702A/B are 12" Westinghouse FWG vahrs. Additionally, therc is limited information available in the EPRI Performance Prediction Program for this size comparison. valve. What is provided in the EPRI program is an apparent friction coefficicm for the 3" We FWG valve discussed earlier in the section for BBHV8000A/B. The valvl Because of the limited information with regard to this size of vahr it is recommended that the factor continue to be used Using calculations and a.5 vahr factor the thrust requirements for vahrs become: OPENING THRUST REQUIREMENTS 39761 LBS BBPV8702A/B EJHV8701A/B CLOSING THRUST REQUIREMENTS 28065 LBS RCP SE AL W ATER RETURN ISOLATION VALVES BGIIVH100 & 8112 i A review of valves DP tested at Callaway indicates that BGHV8110 & 8111 are identical l that have been DP tested. These valves are 2" Velan globe vahrs with flow under the scat. i testing for BGHV8110/811I was at significantly higher DP's and flowrates (~60 GPM than the design DP and nominal flowrate for BGHV8100/8112 (155 psid and <32 GPM). Re previous discussion for BBHV8351 A.B.C.D. BGHV8100/8112 will experienec lowe BBHV8351's since a portion of RCP seal injection goes into the RCS. Both BGHV8110 and 8111 had thrust requirements to overcome the test DP less than sprinl pack preload so a determination of the actual thrust requireme l l respectively.It is known that SGHV8111 was tested at a DP significantly higher than the design DP! BGHV8100/8112 and it is known that the thrust requirement for BGHV8111 was less than; apparent spring pack preload from BGHV8111. Therefore, the thrust requirements t must be less than the apparent spring pack preload for BGHV8111. For extreme consenatis i requirements for BGHV8110/811I will be set equal to the apparent spring pack pre l (7039 lbs). i - 7039 LBS OPEN & CLOSING THRUST REQUIREMENT = BGHV8100 & 8112 NORM AL CHARGING PUMP MINIFLOW ISOLATION VALVE BGHV8109 Based on the closing This valve is identical to those discussed above for BGHV8110 & 8112. design DP for BGHV8109 (2818 psid) being near the test DP for BGHV8111 (2842 psid data for BGHV811I will be used as the closing thrust requirements for BGHV8109. As stated previously the closing thrust requirements to overmme the test DP for BGHV8 less than spring pack preload so a determination of the actual thrust requirements is unknow spring pack preload for BGHV811I is 7039 lbs. It is known that the thrust required i BGHV811I is below this value, in the open direction it is known that this vahr requires no assistance from the motor oper open. This vahr has been known to open by itself with line pressure as the operato t2 conservatism the opening thrust requirements will be established based on alculations. CLOSING THRUST REQUIREMENTS 7039 LBS BGHV8109 12 refer to RFR 7263A RFR87461. DOC 01/21/94 7 t i

FPRk3'94 08[02Ari U.E. CALLAWAY PLANT P.2 RER 87461 OPENING THRUST REQUIREMENTS 32s LBS i BCLCV0111Rf CHARGING FUMPB $UCTION ISOLATION VALVES FROM VCT Thcoc MOVs were included in the esporise to NRC LE. Buustin 85 03. Because these valves l could not be adequately DP tested as discussed in RFR 10324 A and ULNRC 1755 the thrust requirements for these valves were detcrmaned using valves of the same design but different sizes. In preparing for and testing MOVs in accordanos with GL 89 10 additional Westinghouse FWG valves of the saroc type and size have been DP tamed at sigmficantly higher DP's and Bowrstes than the design DP of 100 psid fbr BGLCV0112B/C. Refer to the table below. VALVEID SIZE TEST DP MEASURED MEASURED OPEN THRUST CIDSED TERUST EMHyssotA 4" 2677 PSID 4458 LBS 4221 LBS EMHvstolB 4* 2677 PSID 6062 LBS 2815 LBS EMHVB821A 4' 1595 PSID 4299 LBS 39341.88 EMHV88218 4' 1540 PSID 4249 LBS 2709 LBS EMHV5835 4' 1595 PSID 3650 LBS N/A If one calculated the thrust requirements for BGLCVolliB/C a thrust roquaremsat of 1286 lbs ciceed and 1145 lbs open would be obtained using valve lheter of 1.0. Theec valves were prowwusly set up for 3110 lbs open and 1965 ros closed. Sinos thans MOVs are capable of providing s'Tn*adly higher thrust and for added conservatism it is recoaunended that the thrust values for BGLCV01128/C be est up to the largest open and closed thrust measurement listed in the table above. BGLCVo112B/C CLOSING TERUST REQUIRE!ENT: 4221 LBS i OPENING TERUST REQUIREMENT 6062 LBS l t I ENHV900M RWST TO CTMT f. FRAY PUMP MOLATION VALVEE i These valves pececcaly have thrum requartments asamhHeberi using ^*lantadast' In accordanos with RPR 9878A. The method used in RFR 987BA is alightly diSerent then that used in this RFIL For I consassency the thrust requirements are being :=r=le=1=* art in this RFR. As shown on Attachment 2 the re-calculated values become 3356 lbs closed and 3301 lbs open using a valve factor of 1.0 to overcome the design DP of 32 paid. In referring to the DP tests perfonned at Callaway the only valves comparabis are EGHV0071 and 126. The only signinomat diSerence between thans valves types are that BNHV0003/4 are stainless i while EGlV0011/126 are carbon sesel valves. Limed below are the meseured thrust requremenis ftom EGHVO07t/126. The DP tem for EGHV0071 was at 94 paid and the test for EGHV0126 at 92 psid. + yAgg,3 MEAEURED OFKN TERUST MEASURED CIASEB THRUST EGHV0071 4885 LBS 5367 LBS EGHVD126 1982 LBS 4220 LBS As can be noen with the data above, if the thrust valuas for EGHV0071 is deresed to the design DP lbr BNHVD00344 lower values than that calculated above would be cotained. For added conservatian the thrust requirements for BNHV000344 will be bened on a valve tector of 1.0 BNEV000344 OPENING TERUST REQUIREMENT 3301IJB f CIASING TERUST REQUIREMENT 33S6 LBS RPR8746LDOC 01/21/94 8

4 t RFR 87461 t l { RWST TO RHR PUMP SUCTION ISOLATION VAINES BNHVHN12 A.B There are no other valves of the same size at Callaway that have been adequately DP tested for i i These are 14" Westinghouse FWG vahrs. Additionally, there is limited information comparison. available in the EPRI Performance Prediction Program for this size and t3pc of valve. What is prosided in l i the EPRI program is an apparent friction cocificient for the 3" Westinghouse FWG vahr discussed in the I section for BBHV8000A/B. The valve factor for this 3" valve is.328. Because of the limited inform with regard to this size of valve and the thrust margin available it is recommended that a 1.0 vah e factor be used. Using calculations the thrust requirements for these vahrs become: BNHVN812A&B OPENING THRUST REQUIREMENTS 4482 LBS l CLOSING THRUST REQUIREMENTS 4607 LBS j EFPDV0019. 20 ESW SELF CLEANING STRAINER DRAIN DP CONTROL VAIXE These valves are routinely operated under DP conditions during ESW pump runs. However, the { MOVATS test equipment has not been installed on these vahrs so measured tluust requirements to ostrcome DP conditions is unknown. EFHV0097 and 98 are identical valves which are also routinely DP [ l tested dunng ESW pump operation and have been diagnostically tested under DP conditions. The DP l data for EFHV0097 and 98 however, is not being used for comparison purposes because the thrust requirements can be more conservatively determined using calculations. The DP data for EFHV0097 was less than spring pack preload and the requircd thrust analysis for EFHV0098 is based on a very { conservative spring pack displacement value not attributable to DP eficct13. In addition. EFPDV0019 and l 20 have been determined to not have an active safety function to close per RFR 5353S so closing thrust requirements are not critical and can be determined conservathcly using analytical methods. Referring to ' the thrust requirements for EFPDV0019 and 20 are calculated using a vahr factor of 1.0 as follows: + EFPDV0019 & 20 OPENING THRUST REQUIREMENTS 834 LBS f CLOSING THRUST REQUIREMENTS 1023 LBS l i ECHV0011.12.13.14 ESW TO CCW EMERGENCY M AKEUP ISOLATION VALVES j i These vahrs are Yarway 1.5 inch globe valves with flow under the seat. The only safety fimetion l for these vahrs is to open18. The purpose of these valves is to open as an emergency makeup water supply for the CCW system. Since the safety function for these valves is to open and flow is under the seat the opening thrust requirements for these vahrs will be minimal and can be conservatively j calculated. Referring to Attachment 2 an opening thrust of 462 lbs and a closing thrust of 560 lbs is ~ obtained using a vahr factor of 2.2. The operators for these vahrs are equipped with heasy spring packs are capable of providing well in excess of these thrust values. For additional conservatism an open and 'i closed thrust requirement of 1500 lbs will be specified. EGHV00011,12,13,14; OPEN & CLOSED THRUST REQUIREMENT = 1500 LBS: l ECHV0062 RCP THERM AL B ARRIER RETURN CCW SYSTEM ISOLATION VALVE { / 13 Refer to RFR 8746G l IdReference RFR 5353S i RFR87461. DOC 01/21/94 9 -~

l i RFR 87461 l l i This MOV has an active safety function to close against 2335 psid and a commercial function to l open against 112 psid. The thrust requirements to open are determined below in the discussion for i EGIIV0132. The thrust requirements to close against 2335 psid were prcsiously calculated in RFR 9878A l using slightly dtfferent methods. For consistency the thrust requirements for EGHV0062 hast been re-calculated to bc 12984 lbs using a vahr factor of.6. This vaht factor is considered conservatist for this style of valve. This is a Velan parallel slide gate vahr that is position closed. This type ofvalve is i designed to operate with lower thrust requirements than their FWG counterparts. In resiewing the EPRI Performance Program no valves were available for comparison. There have been similar vahts DP testod at Callaway, i.e. EGHV0061 and 133. However, they were tested at too low a DP to be considered for determining the thrust requirements for EGHV0062. f ECHV0062 OPENING THRUST REQUIREMENT 1220 LBS CLOSING THRUST REQUIREMENT 12984 LBS l CCW RETURN FROM RCP THERM AL BARRIER EGHV0062 BYPASS EGHV0132 ISOLATION VALVE i The DP that these valves may be expected to operate against is 112 psid for commercial i considerations. Previously these valves had their thrust requirements determined using calculational u [ methods from RFR 9878A. For consistency these thrust requirements are being re-calculated in this RFR. Valves EGHV0061 and 133 are identical MOVs that have been DP tested to 94 and 90.5 psid respectively. Referring to Attachment I the thrust requirements to overcome these test conditions are as l follows: i VALVE ID TEST DP CLOSING THRUST OPENING THRUST EGlWOO61 94 PSID 812 LBS 829 LBS l EGHV0133 90.5 PSID 1609 LBS 983 LBS Using calculations the thmst requirements for EGHV0133 are 379 lbs closed and 247 lbs open using a DP of 112 psid. Thus, it is apparent that it would be most conservative to use the thrust j 1 requirements for EGHV0133 extrapolated to 112 psid to determine the thrust requirements for EGHV0132 (and EGHV0062 in the open direction). Using this method the following thrust values are obtained: OPEN THRUST VALUE = (983 LBS)(112/90.5) = 1216.5 LBS SAY 1220 LBS CLOSED THRUST VALUE = (1609 LBS)(ll2/90.5) = 1991 LBS SAY 2000 LBS 1220 LBS ECHV0132 OPEN THRUST REQUIREMENT = 2000 LBS CLOSED THRUST REQUIREMENT = OReference RFR 5353X RFR87461. DOC 3 01/21/94 l 10

r RFR 87461 EJIIVERI1 A,B RHR PUMP SUCTION ISOLATION VALVES FROM EMERGENCY SUMPS There are no other valves of the same size at Callaway that have been adequately DP tested for These are 14" Westinghouse FWG valves. Additionally, there is limited information comparison. available in the EPRI Performance Prediction Program for this size and type of valve. What is prmided in the EPRI program is an apparent friction coefficient for the 3" Westinghouse FWG valve discussed earlier in the section for BBHV8000A/B. The valve factor for this 3" vaht is.328. Because of the limited information with regard to this size of valve and the thrust margin available it is recommended that a 1.0 valve factor be used. Using calculations the thrust requirements for these vahrs become: EJHV8811 A/B OPEN THRUST REQUIREMENT 7199 LBS CLOSING THRUST REQUIREMENT 7399 LBS EMIIVNRn7A,B Because of how the system is aligned when these vahr are manipulated there is no DP across these valves uhen they are required to be operated. These valves presently have their thrust t6 requirements established to overcome the stem rejection load (930 lbs per RFR 9878A). Howeser, for commercial considerations these valves should be set up to mercome a DP of 252 psid per RFR 5353X. Valves EMHV8923 A/B are identical vahrs which have been DP tested against 178 and 180 psid respectivel). From RFR 8746G the thrust required to mtrcome these DP's are as follows: VALVE ID THRUST TO OPEN THRUST TO CLOSE EMHV8923A 1573 LBS 1929 LBS EMHV8923B 2148 LBS 3186 LBS l Since these are identical valves that have been DP tested it is recommended that for comme reasons the thrust requirements for EMHV8807A/B be detennined by extrapolating the thmst requirements from EhWV8923B to the commercial DP of 252 psid. Using this method the thrust requirements for EMHV8807A/B are as follows: (2148 lbs) * (252/180) = 3007.2 lbs SAY 3110 lbs open i (3186 lbs) * (252/180) = 4660.4 lbs SAY 4665 lbs closed Based on the above the commercial thrust requirements for EMHV8807A/B should be established as follows. These commercial requirements bound all safety related thrust requirements. EMHV8807A/B CLOSED THRUST REQUIREMENT 4665 LBS OPEN THRUST REQUIREMENT 3110 LBS EMHVR924 This MOV has no active safety function and is used solely as a maintenance isolation vahe. During normal power operation this vah e is maintained open with a locking desice installed and with electrical power isolated at the breaker Additionally, this MOV has input into the ESF status panel nhich would alert operators should it become mispositioned. Based on the above discussion this MOV has been removed from the GL 89-10 program and no thrust requirements are being prosidod sia this RFR. 36 Reference RFR 5353X RFR87461. DOC 01/21/94 11

RFR 87461 ENHVn001// CONTAINMENT SPRAY PUMP SUCTION ISOLATION FROM EMERGENCY SUMPS These vahts presently have thrust requirements established using calculations in accordance with PER 9878A. For consistency the thrust requirements have been recalculated en Attachment 2. This resulted in predicted thrust requirements of 2878 lbs closed and 2786 lbs open. In referring to the DP tests performed at Callaway the only valves comparable are EGHV0071 and 126. The only significant difference between these models are that ENHV0001/7 are stainless while EGHV0071/126 are carbon steel valves. These are all 12" Anchor Darling FWG models. Listed below are the measured thrust requirements from EGHV0071/126. The DP test for EGHV0071 was at 94 psid and the test for EGHV0126 at 92 psid. The design DP for ENHV000ln is 54 psid. VALVE ID M EASURED OPEN TIIRUST MEASURED CLOSED TilRUST EGHV0071 4885 LDS 5267 LBS EGHV0126 1982 LBS 4220 LBS If the DP test thrust measurements for EGHV0071 are de-rated to the design DP of ENHV000ln slightly more conservative numbers vs. calculated numbers are obtained for EhEV000!n. Since ENHV000ln are stainless valves it is believed that the valve factor for these valves is lower and requires less thrust than EGHV0071. Based on the discussion above the thrust requirement:; for ENIIV0001&7 are being conservatively established as follows: OPEN THRUST REQUIREMENT = (4885 LBS)(54/94) = 2806 say 3000 lbs CLOSE THRUST REQUIREMENT (5267 LBS)($4/94) = 3026 say 3100 lbs 3000 LBS ENIIV0001 & 7 OPEN THRUST REQUIREMENT = 3100 LBS l CLOSED THRUST REQUIREMENT = ENHV0006,12 CONTAINMENT SPRAY PUMP DISCHARGE 150LATION VALVES These valves are 10" Anchor Darling stainless steel FWG valves There hast been no other valves at Callaway that have been adequately DP tested that can be considered similar. Howestr, these valves have been DP tested at Wolf Creek. The data sheets from the DP test at Wolf Creek have been provided as Attachment 6. The DP test at Wolf Creek was under maximum system flow and DP conditions obtainable (232 psid). Under these conditions the thrust required to open against these test conditions (including VOTES equipment accuracy ) are documented as 3027 lbs for ENHV0006 and 4848 lbs for EhHV0012. No closing thrust requirements were provided since this vahe has no safety function in the closed direction. Note that these thrust numbers are direct stem thrust measurements during the DP test. Wolf Creek then calculated the disc / seat coefficient of friction for these valves to bc.17 and.28 for ENHV0006 and 12 respectively. Using the method described in the discussion for BBHV0013,14,15 & 16 this corresponds to vaht factors of.173 and.288 for a 5 degree disc wedge angic. These coefficients of friction validated the.35 value that was assumed at Wolf Creek prior to performing this D? test. Thus, they successfully demonstrated that the.35 friction coefIicient was conservathe for these l vahes at Wolf Creek. Because of the differences in the MOV programs at Wolf Creek and Callaway it is not recommended that DP test thrust measurements be applied directly at Callaway. Instead it is recommended that a conservative vaht factor based on the Wolf Creek testing and rate of loading factor be assumed to determine the thrust requirements. Since the Wolf Creek testing validated a coefficient of RFR8746LDOC 01/21/94 12

f RFR 87461 friction of.35 it is recommended that a.4 valve factor be used with a rate ofloading factor of 1.20. Using these numbers the thrust requirements are as follows: 8970 LBS ENilV0006 & 12 OPEN THRUST REQUIREMENT = 9487 LBS CLOSED THRUST REQUIREMENT = CONTAINMENT SPRAY ADDITIVE TANK TO CONTAINMENT SPRAY ENIIV0015,16 PUMP SUCTION The present thrust requirements for ENHV0015 and 16 originate from RFR 8746C and is based on the thrust requirements of similar valves. The design DP for these valves is 18 psid. RFR 8746C conservatively determines the thrust requirements for these vahts to be as follows; VALVE ID CLOSING THRUST OPENING THRUST REQUIREMENT REQUIREMENT EhW V0015 4234 LBS 2801 LBS ENHV0016 1938 LBS 1557 LBS These vahrs are being removed from the plant with the implementation of modification MP 92-1053. This modification is climinating the containment spray additive tank and thus the need for these vahes. This modification is scheduled for implementauon spring 1995. Based on the conservatism of the present thrust requirements, the low design DP, and the fact that these valves are scheduled for removal from the plant no further action is required for these valves. The thrust requirements presently imposed should continue to be used until these MOV's are eliminated. EPlfv880R4.B.C,D These vahrs are listed as having no active safety function to open with an aethe safety function to close but at zero difTerential pressure. Based on the above it is apparent that the thrust requirements 17 for these vahts can be adequately determined using conservathe engineering analysis. Using calculational methods and a.5 valve factor the tluust requirements become 26223 lbs open and 30500 lbs closed for a DP of 726 psid. Note that these thrust requirements are for commercial considerations only. l As the thrust rating of the operators on these valves is 140,000 lbs it is esident that these thrust requirements can be easily satisfied. For safety considerations these vahts must be able to mtrcome piston effect associated with a line pressure of 726 psid. This value is calculated below: PISTON EFFECT CALCULATION FOR EPHV8808A,B,C,D (line pressure)(stem arca)(rate ofloading factor) l Piston effect = (726 psid)(4.9087 lbs)(1.20) = 4277 lbs SAY 4300 ibs j = [ Based on the above discussion EPHV8808A.B.C.D hast commercial and safety thrust requirements as prmided below. EPHV8808A B,C & D COMMERCIAL OPENING THRUST REQUIREMENT 26223 LBS t COMMERCIAL CLOSING THRUST REQUIREMENT 30500 LBS SAFETY OPEN & CLOSED THRUST REQUIREMENT 4300 LBS 37 Reference RFR 5353X RFR*7461. DOC 01/21/94 13

i RFR 87461 - i KAIlvon3a The purpose of this MOV is to provide additional redundancy to the hydrogen recombiners in the event makeup air is necded to purge hydrogen from containment following an accident. This valve was installed in accordance with Reg. Guide 1.7. This valve is not considered to hast an active safety function.38 No other valves of this type have been DP tested at Callaway. Since this vahe has no acthe safety function its thrust requirements can be conservatively determined using calculations. Using this methodology a closing thrust of 276 lbs and an opening thrust of 173 lbs is provided for a design DP of 149 psid assuming a valve factor of 1.0. KAHV0030 OPENING TilRUST REQUIREMENT = 347 LBS CLOSING THRUST REQUIREMENT = 450 LBS KCIIV0253 The valve is a 4 inch VELAN paralici slide gate valve with a design DP of 189 psid open and closed. Two other valves of this size and model (EGHV0061/133) were DP tested 94 and 90.5 psid respectively. Ilowever, these test DP's are not within 50% of the design DP of KCHV0253 and thus are not being considered. KCHV0253 is a 4" Velan parallcl slide gate valve that t3pically requires less thrust than the FWG counterparts. No vahr of this t3pc is being tested in the EPRI Performance Prediction Program. For conservatism the thrust requirements for this vaht will be calculated using a valve factor of 1.0. KCHV0253 CLOSED THRUST REQUIREMENT = 1507 LBS OPEN THRUST REQUIREMENT = 1291 LBS LFFV0095.LFHV0105&106 CONTAINMENT NORMAL SUMP AND AUXILIARY BUILDING SUMP DISCH ARGE ISOLATION VALVES i All three of these MOV's were DP tested. However, for LFFV0095 in the closed direction and LFHV0105&106 in both directions they were not tested at a high enough DP to satisfy the criteria of ^ EDP-Z2-01114. Because of the thrust margin available with these vahes the thrust requiremr.nts arc most easily determined by assuming a vahr factor of 1.0 and calculating the thrust requirements. Using f this method the thrust requirements become: + 1766 LBS LFFV0095 CLOSING THRUST REQUlkEMENT = 295 LBS OPENING THRUST REQUIREMENT = 548 LBS LFHV0105/106 CLOSING THRUST REQUIREMENT = OPENING THRUST REQUIREMENT = 532 LBS i t Reference RFR 10320A. j RFR87461. DOC 01/21/94 14 i I

1/21/94 ATTACHMENT 1 TO RFR 87461 COMPARISON OF CALCULATED VS MEASURED THRUST VALUES FOR MOVS DP TESTED AT CALLAWAY RAlk WE A3i.m t.U WEA3VMtu Ik34 IEbf OF VALVE STEW ptiec TM#UST THR1JST De CP VALVE WALVE CALCULATFD CALCULATED CLO9ED OPEN CLOSED OPEN MFG 4 TYPE WODEL SEE TYPE SEE DIA STEM rit A DISC LOADING FACTOR D . fMMURY CLO9ED. THRUST OPEtt fnete ti fnote 11 tocte 11 fnete 11 foote M fnote 31 fue 33 fnets h fnete 2) Ino<e 21 incte 21 AP.EA teens at AREA f note St incte 81 PRELCAD SUB 00 l 0 62s 0 3n6 2 we 314 1 ts 1t 379 MAscer GtOet m207xt-" ~ ~ - ' ( sus OO7~6sM-"Traorb8 At HVooD5 8993 63'4 32*9 2430 1804 1%4 [ MMON GLOBEj 9a 207x1 4 4 -l'i4 i is si e9,- i mi~" 0 0 30s two i te $ $6~- 1T-450 %eie7 64M ens eM2 2s3s is99 is9a~- 4,0,s25, O m,s MASON htOs 94207xi 4 Sus 00 MOON _t,,mO,i ,,s +, F 2,sr ,ts24 % Moo 9 7cas - saia 70 s aosf ie24 2 2 ,,4 E mm, 4 S,s 00 1tF e 5 s6-ic woii ms us4 me M22 ,u r tr i m,4 , w, .4 92 W GArE Esy s Ss 00 6 5 ,' lii~~ 05 Es207-s 8 SMS 00 f is-'122f ts ws 44 92 11s %, mci. 34, 3e 99 ws 14 44 Ao@~W GATE si-gam mu a ,6 u s.. - orw,.,,, s,. - n,- % Mai5 3e t as $ t 39 3053 ia

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94 94 VELAN POG B120144E02 4 Sus 000-~it2Fldfi94 tiiiDil 92 t iB~~ 04 ~ 6 '- O tdiW0060 si21 4e40 9ss2 5394 -~ 64 94 -'~Aeg bet otsc 7 s207 1 12 SMs i iM~~" 6 5940 2W~3 I4 1 i$ -'~ ~6 5-~ iil-~ 7d*ivt6?F 5054 4844' 5347 4aa$ 94 94 Ao FW GATE e6207-i~ ~ 12 SM6 00 f ifIlis449 lienb~89 71 11F ~~ 65~~~ irs- ~ f iF~l is 1i 1233 -~ 7dW/00fi iso zio n 1233 to3 103 'D ARW AY OLOBE sstsSSA105M 2 SM8 000-'--'D is f-6 689"4 I 96 2 ~~l 91~~~i 16~71 149f~ 'tGvivb6fi 340 230 NnA 149f 103 103 VARWAY OLOBE ssnS sat 0AM 2 SM8 '~ OOO- ~6 637-'T689Y h W i p2 tir-71 22s4 - TE5sfV0674 350 240 M 2369 103 103 YARWAY CLOBE ss4&SA10sM 2 Sus OOO 6 biF6Bs9,4Qwi 6 s80'd lit 2s 16f "7 is~~T i-24ss- " Con /0075 340 2so wA 24es ' $03 so3 VARWAf OLOPE ssis&SA10sM 2 SW6 OOO 6 93 I 'iGMi6iks eiet 474s 4:20 tih2 92 92 Ao rW GATE Es207-3 12 Sue 00 137F7 4a499 te es-t so f t 1 i6'~~ Os %s TCRv5iff sist 5067 as39 3444 99 99 Ao del oisc E6207.1 12 SM9 00 li26' 7 07394 H 9Y's tit 97~ ~i t6~~~64 t*5~ 'TdMi6iio 4794 453t disa 2iss as sa Ao Det Disc ts237-2 12 Sws 00 7 6M 1 67394 ti ms lii ti" -~~i is~~6 4 230 ~tchiWilt 5332 5655 sit t si t 94' 9s Ao DOL DISK ES20f 21 12 SW9 00 t s25 2 67394 6t Ft*$ tif) ' 71s~ 04 391 'f6Jv6133 ffs fit i469 983 pf 99 VELAN PDG 8100144B-02 4 Sus--000-7 i2F'6 94402 2?h ~ 5 94 195~~04 309 tifCwit0 49s ses sc9 eie 208 20T-~WEif-~W GA E' ~ iGussFun 3 Sus OoO 7 tis-'6 994a2 2 42 ie 7M t t3-6F 134 - ' tRv6 sit bei sis 8tf 567 261 2c1 MSr rW GArt >GMASFNB 3 SM8 000 7i}5~6 994c2 24w ~55I~ TIS ~ 7 66 336~ F - F-~~ 6~ tjWitt68 16064 89s t O 906f t 189 189 WEST IFW GATE 10000Gus4FEB 10 $8 1 2s 4 90874 see2w ' 74 53 1 26 O 'tAiss64A 3677 2444 73$4 2f33 161 12s wf Sf7 FW GArE' ~ Coon 0Gus4rt e e se 00 tC i221si siaw 33 W'~ l i5~~B 5 ef I FW GATE OP000GW64F EB 8 SS 00 1 25 12ifis aww ~i3 25 tis 65' 34 I WEST"jviGAr mSf r i60urarNCo SsD-7 2s+ 4 90s74 e mo s0 26 t 2o Os 299ai-TmvssMa-3is9 2923 4670 3522 153 153 3 25 1504fi 3 "to 60 20 ~ l.3 0 $~~12006-tjtisfaa658 i riso esas 294a3 asb0 iai is4 ~ tJNvnseos 7646 sii7 264se t1i37 189 1e9 WEST FW GATE 10GW78FNC to S80~ 3- ~ 5-190sfi 80 20 1 20 ~6 I 17170~ TuJvs96ia siit3 14309 422 44M 2s77'-~ ~ is77" WE Sf-040uoGM48FNA 4 500 00 ~~125'72ffi$ge ?tio 2 ' tJWvsseo 7$40 6427 sfi4 tei63 189 999 WEST. FW GATE 10GM7BFNC to SBD 1 3 4400 9 29 115~'-' 6 6-~ 543 Tw+sedib 16ti3 14109 2615 60s2 26tI istf WEIT ~FW GATE ~~04000Gw9AFN8 4 SRo~----OO

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2sF-FW'GME S tB]~ 65 sst WEST FW GATE 04000GM88FNB 3 SBD 00 1CT22fts s 440o 9 29 1 95 6 6----" 64i - ~5is 2767 2009 ess s48 WESf 7Fw dAiE' 64000GM4sfNfi 3 SBD~ ~d 1 25 t 22718 3 44no 9 29 ~ fu4v580}A 4648 3sf7 57sf i357--688 E88-- 'ludvs6034 16424 te75 +632 10486 272f-ifiF'WESf g FW GATE ' 0470GY88FN8 4 580 ~O -7 }5~i 22f14' 4 44op L i }9~ ~I~ 23I 0 t is 1 3 OO ' twwvamo3s _ iem T3440 eAf Wo ito? '-~i ?Of ~ WF si.hk GATE" 040moumarNe a sBo 00 12s 12;?is[ iem T 9 29 t is T7s- $99-- (MNvesoit 4445 Notes:

1. From RFR 8746G
2. From CEL ATT1.XLS
3. From valve drawings.
4. Anchor Darling values from RFR 5353, Westinghouse values from attachment 5. Rest from valve drawings 1 of 2 l
5. From Attachment 3.

l

6. Refer to RFR text.

1/21/94 ATTACHMENT 1 TO RFR 87461 COMPARISON OF CALCULATED VS MEASURED THRUST VALUES FOR MOV'S DP TESTED AT CALLAWAY wait mtA u ss utA m tu usi usi OF VALVE STEM Ofsc WALVE CALCULATED C_^tO?_ATED CLOSED OPEN CLOSED OPEN MFGR TYPE MODEL SIZE TYPE SET. tzA STEM ptA CISC LOADING FACTOR Tt* RUST THRUST DP DP VALVE as mRusTetosro. THRusioPEN en.+. ti rnee. ti enor. tr rno,. t> inee. ri en e.si enee. si rnoi. si enot. 2i te. rt ince. ri AREA emete st ARE.A i ncta ti feet. s t PRELcAD g e734 11 1 125 O tedr72 a t go 2 76 11s j ~l Ti3-6 9aof~i r46-ite tir~~~~ 0 F EWwVB614A i F 199 5293 67S. 80*>s 1995 151s VELAN GLOF9E t to-TW 78F N t' 15 Sw8 -~UO os es9r-t owv= 44 ' ani' 24tr se# f200 1s20 is2o vuAm GLOse -io-tw7em Li s sus OO Sso OO i 3 -~u21*s 3-9 29~1 is-- ~6 5~ 4%~~~ 1 25 9 22tt8 3 *ine 9 6i~~~1 1s twwJuiiA stis7 asie 3e34 4299 iser 1595 WEST rW GATE D4000Gwe7mB I 4 S8 00 ~~i 2s~7 22116 ^ hs' S ei t 15 44f -'- 1 t wwves2it ' $0fW e420 2709 4249 1540 1540 WESY 7W GATE i)4000r#57F HB [4 $8 00 ~~ Peso-sus [ Oo os WeSrj rw GAtr ' IWm/8973A 1 3239 2957 1975 1929 17s 17s WEsig rW GarE~' or00tGw32F BB 6 Sv9 00 1 25~i 22718 + =1a as se T is 06 - 620-o40aoGusame 4 tiemas 40so 6524 e asso 159F isos e is' 1 22758 epio 1 49 713~ 6 5' ~~ 4$4~ osociGus2r se s WESig FW GATE GLOBE 82-14097A 4 SW9 000 f f 2s 0 99402 4 4eio 9 76 t is i 11 971 7 44 3 f 86 180 180 5 7 tS'"] 6I EuHvs9236 32f2 2930 1 15 420 FcHV0312 4A 2367 f MA 9929 1075 1075 'GIMPEL-FW Gaff E6f1E5 6 SMs 00 9 1954 S nes 1 69 05 hF ( 36f Is3 64i 6 6 Ao 000 1 0 78s4 $ nte liiv0093~ 59 si i M^SMe ao tw GA E F611&10 6 MH " ~tts-- os sii L Hvotos tir via [ $43 $409 6 i e swe noo, e o rs=4 e tia= i Ao'd w GATE e s sis,o 6 f F i.ruvoios iff Tid i sit 1242 ~8 T a Notes:

1. From RFR 8746G
2. From CEL ATT1.XLS
3. From valve drawings.
4. Anchor Darling values from RFR 5353, Westinghouse values from attachment 5 Rest from valve drawings.

2 of 2

5. From Attachment 3.
6. Refer to RFR text.

ATTACHMENT 2 TO RFR 87461 CALCULATED THRUST VALUES FOR VALVES EVALUATED IN RFR 87461 DESION CALCULATED CALCULATED DP DESION DP THRUST CLOSED THRUST OPEN WAO RATE OF valve VALVE OPEN CLOSED Wf0 ERROR AND ERROR AND STEM LOADING FACTOR STE'M DISC MFOR (note TYPE MODEL SIZE TYPE SIZE STEM DtA in1C DI A VALVE O fneta 11 innan 11 STEM LOAD LOAD fnete 21 fnete $1 AREA AREA 11 ! fnete 41 fecte 41 fnete 41 Ineta 11 fneta 11 feem 11 unk h 8 SMB 00 1 25 ? 47% j ALHV0034 25 135 3n?7 646 1 15 0 50 1 22718 44 92 [ AfD FW GATE E6207 5 ALHV0035 25 135 3877 646 1 15 0 50 1 22718 44 92 j AfD FW G ATE F6207 5 ~10 SMB~~00 1 25-? %29~ 8 SMB ALHV0036 253*N 135 4991 889 1 15 0 50 1 22718 61 86 A/D FW GA f E E6207 4 O 1 25 a#90 '6BHV0013 14UN 7335 8482 3eI 1 15 0 40 0 90402 5 41 VELAN FW GATE Bio-3054P-02 3 SMB 00 1125 2 6210 6BHV00ie Mf{2335 8482 W __} q __ 0 40 _ 0 99402 _ $ 41_,,_VELAN_.FW GATE, _ B43054P42 3 SMB 00 1 125 2 6210 3 SMB 00 1 125 24210 ~ 5BHV0056 145 2335 6482 Mi I 15~~ d 40-'0 994c2 5 41~vELAN~ FW GA1E~B10 3054P42~~3 SMB OO 1 125 2 6250 SBHv0015 145 2335 8482 381 1 15 0 40 1is ~ 6 ~' 99402'~5 41 VELAN FW GATE ~~B10-3054P'02-i SB 00~ 1 125 ~ ~ ~ 480000 2485~~2335 11355 9244 ~1 16~~b 60~~O 99402 ~ $ 59~"WE ST~'FW G AT E-3 GM88F NB~~5 58 cc 1 i25^l6W 2 62o0 ' 'bOJV8tTfDA 2485 BB 2335 ti355 9244 d O9402 s'39-WE ST~~FW GATE 3GM68F NB BBHV8037A 104 104 1337 1190 1 15 1 00 1 22718 9 95 WEST Fw GATE 040000GM 82F 4 50 00 125 ~~ l %of BBHV00370 104 104 1337 1190 1 15 1 (X) 1 22718 9 95 WEST FW C ATE 0*J000GM 82F 4 SB 00 1 25 5 % 00 BBHV8351 A 2813 2813 13383 9m25 115 1 10 0 994C2 2 76 VELAN GLORE 2TM78FNA 2 SMB OO 1 125 15"O BBHv8351B 26*3 2813 13383 9825 115 1 10 0 99402 2 76 VELAN GLOBE 2TM78FNA 2 SMB 00 1 125 1I190 BBHV8351C 2813 2813 13383 9825 1 15

  • 10 0 99402 2 76 VELAN GLOPE 2TV 78FNA 2

SMB 00 1 125 1590 ~~ 4 ~6 f~ WEST FW G A T5~72002GU685ET ~ OO 1 125 1890 2 SMB 'DB5N8702A~~2913 2R13 13363 9825 1 15 1 10 090402 2 76 VEL AN GLOBE 2TM78FNA ~ 12 SUB ' 2 3 10 ioso BBHV8351D ~ 380 dei 28085 19701 1 20 Old ~iOB858 8 BBPV87C2B 3R0 464 28085 19781 1 20 0 50 7 06858 Be e f~ WEST FW GATE 12002GM885EH 12 SMB 2 3 7010w 'bGiiV85dO'~94 2818 13386 328 1 15 1 id-'699402'7 ~6--VELAN GLOBE ~^P2 6303-N2 2 SMB OO 1 125 1890 BGHV8100 1$5 155 738 541 1 15 1 10 0 99402 2 76 's66Mii2 155 155 736-541 1 i5 i~ tO 9940f7 76 ' ~vFLA E GLOBE P2 6305N2-2 SMB OO 1125~ i#No 7 VELAN GLOBE P2 6303 N2 ~ 's io-2 SMB O 1 125 t BGLCV01128 100 100 1288 1145 1 15 1 00 1 22718 9 95 WEST SW GATE 040000GM82F B 4 SB OO 1 25 1 400 BGLCV0112C 1CO 100 1286 1145 1 15 1 00 1 22718 9 95 WEST SW GATE 04000GM82FBB 4 SB 00 1 25 3 %o0 BNHV0003 32 32 3356 3301 1 15 1 00 1 48489 89 71 AfD FW GATE E6118-3 12 SMB 00 1375~~iolas ~547VC0 4 32 32 3ise 330i i 15 1 00 1 48489 80 71 A/D FW GATE E6118 3 12 SMB 00 1 375 to Ht7 '5fs W8852B 33 33 4607 ~4482 1 20 1 00 3 14159 11319 WE3T FW GATE 14GM74F EC 14 SB 1 2

  1. 2 0010 4482 1 20 1 00 3 14159 113 19 WEST FW GA TE 14GM74r EC 14 SB 1

2

  1. 2 0010 FINHV8812A 33 33 4607 EFFOV0019 134 134 1023 834 1 15 1 00 1227t8 7 41 VELAN SW GATE B40054402d___ _ 3 SUB 0

1 25 2 6210 EF PDV0020 1 34 134 1023 834 1 15 1 00 1 22718 5 41 VELAN SW GATE B10-00540 3 4 SMB 1 1 25 262w EGHV0011 123 123 5eo 462 1 15 2 20 0 68956 1 48 YARWAY GLOBE 55158 15 SMB 000 0 937 L3MO YARWAf~ GLOBE' 55158 15 SMB 000 0 937 1 1'10 EGHV0012 122 122 555 458 1 15 2 26 ' I)68958' i'48~ EGEvD053 123 123 500 462 1 15 2 20 0 68958 1 48 YARWAY GLOBE $5156 15 SMB 000 0 937 3390~ EGNV0014 122 122 555 are 1 15 2 20 0 68956 1 48 YARWAY GLOBE 55156 15 SMB' 000 0 93f~~ i 3 MO ~$~GEv005i 112 2335 12684 48f f 22 0 00 0 90402 5 94 VFLAN PDG B12 0144B42 4 SMB O 1 125 2 Moo-EGHv0132 112 112 434 306 135 0 46 -" 99462'7 51 VELIN POI' B1N144P' 4 SMB 00 11C 2h00 ~ d 67 WES lW GATE 12002GM88SEM 12 SMB 2 3 --~' ~Fo icif 'E5V8f6i A 3tiO 464 200b5 19761 1 20 0 30 7 00858 8 EJHV8701B 380 484 2eoe5 19791 1 20 0 50 'I ~08858 '~h6 6f~~WESi~' iW'G ATE '~ 12GM68SEF 12 SMB 2 3' io ie90~ ~~EJHV58fik 53 53 7399 7t99 1 20 1 00 3 14159 11319 WEST FW GATE 14000CM84rEH 14 SB 1 2 12 0050 TMVeniiB 53 53 7399 ff99 1 20 1 00 3 14159 11319 WEST FW GAth 14000GM44FEH 14 SB 1 2 (2 0090 'liWR d86fA 252 252 4542 4186 1 15 0 50 1 22718 28 89 WEST FW GATE On0001GM92F B 6 SMB 00 1 25 60MO EMHV8807B 252 252 4542 dise 1 15 0 50 1 22718 28 89 WEST FW G ATE Ce0001GM92F B 6 SMB 00 1 25 6 0e90 ENHV0001 54 54 2978 2786 115 0 50 1 48489 89 71 A!D FW GATE E6118 4 12 SMB 00 1 375 10 6R79 ENHV0006 244 244 9487 8970 1 20 0 40 1 76715 76 59 A/D FW GATE Esiisi 10 SMB 00 15 e n'90 ENHV0007 54 54 2678 2786 1 15 O SO 1 48489 89 71 AfD FW G ATE E6118 4 12 SMB 00 1 375 10 6s'1 1 78715 76 59 A/D FW GATE E61181 10 SMB 00 15~ 9no E NHV0015 18 18 ~9487 8970 1 20 0 40-~0W6' 7 39 AID FW GATE E 8118 2 3 W9 00 ~0 75 ' " ) ormo ENHV0012 244 244 88' 77 1 i5 0 30 ENHV0018 18 16 86 77 1 15 0 $0 0 44179 7 39 A/D FW G ATE 4 Ee118 2 3 SMB 00 0 75 locao EPHV880lA 726 726 30500 26223 1 20 0 50 4 90874 00 20 WEST FW G AT E lO(X10GM88F NH~ 10 SBU 3 25^ ~ h50 n i _ sfiso to SRO 3 25 4 90874 fl020 WEST _FW GATE _10n00GV885 NH _EPHv88008 726 728 30500 26223 1 20 0 50 ~ ' 4 90Rf 4I 60 20 t WE ST rW GATE 10n00CMW N64 10 S80 3 25 a mo F PNVMnRC 726 726 30W 26273 1 20 0 50 Notes:

1. Some design DP's are for commercial reasons. CEL has design basis DP's.
2. From Att 3 ATT2.XLS
3. A/D valves seat dia from 5353 analysis, West. valves from Att 5. Rest from drawings.

1/21/94

4. From drawings 1 of 2
5. Refer to RFR text.

ATTACHMENT 2 TO RFR 87461 CALCULATED THRUST VALUES FOR VALVES EVALUATED IN RFR 87461 DEseu cALCutATED cAtCutArEo DP DESCRDP THRUST CLOSED THRUST OPEN WC RATE OF VALVE VALVE OPEN CLOSED WC ERROR AND ERROR AND STEM LOADING FACTOR S TEM DSC MFOR (rete TYPE MODEL SIZE TYPE SCE STEM DA Disc Ds A ! fnete 42 fm 4? fnete 41 fec*e 11 Ineta 11 feete 11 r e li VAtvE O fnets 11 tr. ate 11 stem toad LOAD twe 21 feen St A*IA AREA tI WEST FW G ATE 100nt0Vw w To SSD 1 3 1 2s j sNw E PHv880eD 726 726 30"00 20223 1 20 t 0 50 4 00074 80 20 -WARNER M CAiE((, 15 SM94.OOO][6 6?s))I A)( iso tas eso 547 i ss' -'t oc _o so132 _ 2 02 g_i g sus _t._ow_1 i s2s ~_ dim 30 2s 69 ; vttAu_4 Poo se,s a s os _ _"CHv0252__ tes see m7 1291 sit __, m __ o w.c2 E6116 s 8 $MB i 00 4 3 ins t AfD] FW GATE 4 Essis ta e sus 7 000 4, t _C _;if 0 78se travows so se 178e 29s 1 15 T OD-yesC2s se_Aio_fn GATEj 4 i s_ ses s32 i fs. im_ 1 a 4 tica LFHV0108

  • g 19 548 532 1 15 1 00 O M-ia M9 AO T rW G A rE Feta *O e

SUB d 000 379tos Notes:

1. Some design DP's are for commercial reasons. CEL has design basis DP's.
2. From Att 3 ATT2.XLS
3. A/D valves seat dia from 5353 analysis, West. vafves from Att 5. Rest from drawings.

1/21/94 l

4. From drawings 2 of 2
5. Refer to RFR text.

t

t ATTACHMENT 3 RATE OF LOADING FACTORS USED IN RFR 87461 The following rate of loading factors are used in RFR 87461. These rate of loading factors are based on information contained in MOVATS Engineering Report 5.0 Rev 6 page 20 of 20 attached.. ACTUATOR SIZE ROL FACTOR SMB-000 1.15 SMB-00 1.15 SBD4)0 SB4X) SMB4) 1.22 SMB-1 1.20 SBD-1 SB-1 SMB-2 SB-2 SMB-3 SBD-3 k 1 of 2 ATT3. DOC 01/21/94

[ D4d ATT.3 PS y A ER-5.0, Rev. 6 Page 20 of 20 TABLE 3 Load Rate Testing Sununary Belleville Spring Testing LOAD PATE Actuator Overall Force (#/Sec) Disp (in/Sec) % Difference' Actuator Ratio Max Min Max Min .0L 0.16" 0.28" (18j 14 14 SMB-1 27.2:1 250,000 22,000 1.3 0.13 SMB-1 88.4: 1 82,000 9,000 0.5 0.04 12 11 11 SMB-1 72.42:1 99,000 10,000 0.52 0.09 17 14 14 SB-0 39.11:1 500,000 75,000 5.5 0.8 18 15 10 M SB 0 95.2:1 220,000 26,000 2.7 0.4 25 26 18 ?b' SMB 0 69.59:1 110,000 15,000 1.1 0.2 22 21 21 SMB-00 72.0:1 48.000 4,500 0.83 0.07 14 12 12 SMB-00 23.0:1 130,000 12,000 2.30 0.21 13-13 10 SMB 00 72.0:1 45,000 5,000 0.8 0.1 -5 5 5 SMB 00 41.0:1 88,000 9,000 1.6 0.17 -5 -6 -7 SMB 00 23.0:1 108,000 15,000 4 0.7 8 5 -11 SMB 00 72.0:1 35,000 5,000 1,8 0.3 4 2 -5 SMB-000 33.5:1 13,500 4,000 1.6 0.5 10 7 5 SMB-000 36.0:1 _15,000 4,000 1.7 0.5 9 11 11 SMB-000 75.0:1 6,700 1,700 0.75 0.2 13 10 9

  • Percent difference between force at fast-load rate and force at slow-load rate at a given spring pack displacement.

i.e., At.08" of spring pack displacement:

  • ]

se 15 Thrust at maximum load rate - 15,000 lbs Thrust at minimum load rate - 12,300 lbs

7. difference - 15.000-12.300 x 100 - 18 Sen6-o b

dA 15,000 ,AO BEST AVAILABLE COPY ITI MOVATS Irs,erersted r

1/21/94 ATTACHMENT 4

SUMMARY

OF THE THRUST VALUES DETERMINED IN RFR 87461 CIESED TIIRt'ST OPEN TIIRI'ST PRA SIETif0D USED FOR DETERMINING TIIRt'47 NOTES V 41 AT ip REOU1RESIENT RFOUIREMENT SIGNIF1UAMT IEOt*fRESfENT SI\\lILAR VAIATS DP TESTED VALIDATED CALLTATIONS VS OPEN T11 RUST RFQtilREMI.NT BAST D DP TEST R ESt1TS TilEN 1lSi D CAlfU ALT 10NS IUR Al llV0014 ON DP TESTING AIJIV0034 3677 t'NCilANGE D I.OW SIMIIAR VALVES DP TFSTED. VALIDATTD CALtl.ATIONS VS OPEN T11 RUST REQt1REMENT H \\Si D DP TTST REstl.TS TIIEN ITID CAICUALTIONS IOR A!JtV0035:ON DP TESTING A_LIIV0033 3677 INCIIANGFD IDW SIMILAR VAIATS DP TESTED VAIIDATT D CAttTATIONS VS OPEN TIIRUST REQUIREMENT ILSSFD DP TEST RESULTS T11FN USED CAlfUALTIONS IUR AIJIV00% ON DP TTSTING AI.IIV0016 4993 tWCilANGEDg IDW l' SED CAlft'lAT10N WITil A.4 VAIAT F ACTOR IIASED ON OPEN TIIRL'ST REQt1REMENT D ASID BDifV0013 3422 UNCllANGED NONE FPRI PTRFORMANCE PRIDICTION PR1XiRAM RISUI.TS ON DP TESTING USED CALC 11AT10N WIT 11 A.4 VA1.VE FACTOR BASED ON OPEN T11 RUST RFAJt1REMENT DASI.D ON DP TESTTNG HRIIV0014 8482 t*NCilANGED NONE FPRI PERIORMANCE PREDICTION PROGRAM RESUI.TS OPEN TilRUST RFQUIREMENT BASED USFD CAICLTATION %TT11 A.4 VAIAT FACTOR BASED ON ON DP TESTING 11DlIV001$ 3482 13CIIANGED NONE i PRI PI RI ORM ANCE PREDICTION PROGR AM RESL1.TS 13i D CAIC11AT10N 4TFil A.4 VAIAT F ACTOR 11ASED ON OPEN TITRt'ST REQUIREMENT DASFD j ON DP TESTING Bf1IIV0016 2482 UNCHANGF.D NONE EPRI PERIORM ANCE PREDICTION PROGRAM RESUt.TS COMPARFD DP DATA WIT 11 SIMILAR V AI ATS. USED CAI CULATIONS WITil A6 VALAT FACTOR TO DETT RMINE BBilV2000A 11355 9244 MIDIUM FIN AL TitRt'ST NUMBFRS COMPARf D DP DATA WITil SIMl! AR VALVES USFD CAIft'LATiONS %TFil A6 V ALVE F ACTOR TO DETT RMINE DDifVR000D I1353 9244 IDW FIN AL TitRt'ST Nt*Mi1F RS COMPARED SIMilAR VAIATS T11AT WERE DP TESTFD USED cal.CULATIONS WIT 11 A 1.0 VAIAT FACTOR TO DET1:RMINE 11DilVR037A 1337 1190 NONE FINALTIIRUST NE%fBFRS BT cal'SE OF MARGIN AVAf1AllLE. COMPARE D SIMITAR VAIATS 11 TAT WERE DP TTSTED USED CAI CUIATIONS WIT 11 A I O VAIA*E FACTOR TO DETERMINE TIN Al,T11Rt3T NUMB 1 RS 111 cal %E OF M ARGIN AVAllAllli. DBliVR037B 1337 l190 NONE OPEN ANDCIDSEDT11 RUST t* SED TilRt'ST REQUIREMENTS I ROM AN IDEV. ilCAL VAIAT RF.Qt'IREMENTS PROVIDI D ARF TOR mMMF RCI Af.CONCFRNS IIRIIVS15i A 7019 } 7019 NONE TFSTT D UNDi R I ARGF R DP AND FI OWR ATF ATT4.XLS 1

1/21/94 ATTACHMENT 4 $UMMARY OF THE THRUST VALUES DETERMINED IN RFR 8746l CLOSED TIIRUST OPEN TIIRUST Plu SIETilOD I* SED FOR DET FRMINISG TilRUST NOTES VAIAT.ID REOUIRE%IENT RFElREMF.NT SIGNII1CANUE REOt IRE %1ENT 'OPI.N ANDCIDSEDT11Rt'sT I USEDT11 RUST REQUIREMENTS FROM AN IDENT1CAI, VALVE REQUIREMENTS PROVIDI D ARE FOR T COMMI RCIAL CONCF RNS BillIV8351B 7019 70.9 NONE TESTFD t'NDF R IARGF R DP AND FIOWRA_F~ 1 OPEN ANDCIDSFDTilRL3T 13FD T11 RUST REQL1REMENTT FROM AN IDENTICAL VAIXE REQUIREMENTS PROVIDED ARE FOR BBilV8351C 7019 7039 NONE TESTID UNDER LARGER DP AND FIDWRATE. M)MMF RCIAL CONCERNS 'OPEN ANDCIDSEDT11Rt*ST USFD T11Rt3T RFQU1REMENTS TROM AN IDENTICAL VALVE REQL1REMENTS PROVIDED AR COMMERCIALCONCERNS BilliVE351D 7039 7019 NONE TESTED UNDER LAROFR DP AND FIDWRATE. 00PV8702A 22065 1976l IDW l' SED CALCULATIONS WITil A.5 VAIXE FACTOR Bi1PV8702B 2#065 19761 IDW USI D CA1Ct'IATIONS WITil A.5 VAIXE FACTOR llASED ON TilRUST RFQl1RE MENTS OF IDENTICAL V ALVE DGIIV8100 7039 7039 NONE TESTFD ATlilGilFR DP AND11DWRATE ClDSED TIIRUST B ASI D ON REQUIREMENTS OF IDENTIC AL VALVETESTED AT llIG1tER DP AND FIDWRATE. OPEN DGilV8109 7039 328 NONE TIIRUST IIASED _ N C AlfS. O I)ASED ON T11 RUST REQUIREMENTS OF IDENTICAL VALVE l1GifV8112 7039 7039 NONE TESTED AT li1GliER DP AND F1DWRATE 11ASFD ON T11Rt3T REQE1REMENTS OF IDENTICAL VALVE IKilCVOII2B 4221 6062 IDW TESTED AT lilG11FR DP AND FIDWRATE HASED ON T1 TRUST REQt1REMENTS OF IDENTICAL VAIAT HGirvol12C 4221 6062 IDW TESITD AT Il1GilFR DP AND FTDWRATE COMPARI'D 111 RUST REQUIREMENT OF SIMil AR VALVES TIIEN DETERMINED RFQUIREMENTS tlASED ON CAICS AND DNilV0003 3356 3101 1OW A VAIXE FACTOR OF 10 FOR CONSERVATISM COMPARED TliRUST REQUIREMENT OF SIMil AR VALVES IllEN DE1 ERMINED REQIREMENTS IIASFD ON calfs AND BNIIV0004 3356 3101 IDW A VALVE FACTOR OF 10 FOR CONSERVATISM IINilV8812A 4607 44R2 IDW CAI CUIATIONS Willt A VALNE F ACTOR OF 1.0 DNilV8812P 4607 44R2 IDW CAI Ct1ATIONS %TT11 A VAIXE FACTOR OF l.0 CIDMETIIRUST REQt'IREMENTS ARE FOR COMMERCIAL CONCERNS CAI CU1ATIONS %TTil A VAINE FACTOR OF I O EFPDV0019 1023 934 C1DSE111 RUST REQUIREMENTS ARE FOR COMMTRCI AL CONCI RNS CAI CtTATIONS WITil A VAIXF FACTOR OF 10 EFPDV0020 1023 834 111 RUST REQUIREMENTS HOUND CALCt1 ATIONS USING A ClDSETilRUST REQUIREMENTS ARE FOR COMMFRCI Al.CONCE RNS FGIIV00ll 1500 !?no NONE VAI AT FACTOR OF 2 2-ATT4.XLS 2 ..c ---w,. .c c --w-- . - ~ -

i I 1/21/94 i ATTACHMENT 4

SUMMARY

OF THE THRUST VALUES DETERMINED IN RFR 87461 1 l CLOSEuT11Rt:ST OPEN TIIRUST PR.4 METIIOD i' SED FOR DETERMINING Til3UNT [ NOTES VAINEID REOt'IREMENT ' RFol1RF3fr.NT SIGNIFICANCE _REOt' IRE % LENT TilR15T REQUIREMENTS DOtND CAlft1ATONS USTNG A lCIDSE TilRUSl REQUIREMFNTS ARE FOR COMMERCIALCONCERNS 3 FGilV0012 1500 1500 NONE VALVE FACIOR OF 2 2. 111Rt'ST REQUIREMENTS dol'ND CAlft1AllONS USING A CIDSE T11 RUST REQt12EMENTS ARE IUR COMMERCIALCONCI_RNS EGIIV0013 1500 1500 NONE VALST. FACTUR tw 2 2. 111 RUST REQUIREMENTS DOUND CALCL'tATIONS USING A CIDSE *11 RUST REQUIREkt5 %T3 ARE FOR COMMi RCIAL CONCF RNS EGilV0014 1500 I?OC NONE VAtNE FACTOR OF 2.2. CALCULATIONS WIT 11 A VAINE FACTOR OF 6 CIDSED AND SIMIIAR VALVES Til AT %TRE DP 1 ESTTD IN Tile OPEN OPEN TilRUST REQUIREMENTS arf'. f OR COMMERCI AL CONCERNS EGIIV0062 129R4 1220 NONE OfRECTION TI1 RUST Rf4t'IREMENTS ARE FOR 6 WMMERCIAL CONCERNS. VALVEllAS NO ACUVE S AFETY IVNCTION. EGllV0132 2000 1220 NONE SIMilAR VALVES TIIAT WERE DP TI3TED EJilV8701A 22065 19761 IDW USED CAlftTAllONS WITil A.5 VALVE FACTOR FJilV8701D 28065 19761 LDW l' SED CAlft1 ATIONS WITil A 5 VALVE FACTOR EIIIVRs!I A 7399 7199 MEDIUM CAlfUtATIONS WITil A VALVE FACTOR OF 10 FJflVsslIB 7399 7199 MEDIUM CALCULATIONS WITil A VAINE FACTOR O_F 10 111 RUST REQL1REMENTS FOR CUMMERCIALCONCERNS. SAFETY v RElATED DP 15 0 PSID. NUMI1ERS f llASED ON 252 PSID. EMilV8507A 4665 3110 IEW SIM11AR VALSTS TilAT WERE DP TES1TD 111 RUST REQt'IREMENTS FOR COMMERCIALCONCERNS. SAFETY RELATED DP IS 0 PSID. Nt %If1ERS HASED ON 252 PSID EMilVER07B 4665 3110 IDW SIMILAR VALVES TilAT WERE DP TESTED LN11V0001 3100 3000 IDW SIMilAR VAINES Til AT WERE DP TES1TD t' SED CAlfUIATION WIT 11 A.5 VALVE FACFOR. VAINE CIDSEDTilRUST REQl1REMENTS ARE FACTOR CONSISTENT WIT 11 EPRI PREDICTIVE PROGRAM FOR COMMERCI ALCONCERNS. NO ACl1VE C1DSE 113CTION. ENIIV0006 9487 R970 IOW REST,1TS ENilV0007 3100 3000 IDW SIMilAR VALVES T11AT WERE DP TESTFD l' SED CAlft1ATION %TT11 A.5 VALVE FACTOR. VAINE CtDSED TilRUST RFQUIREMENTS ARE FACTOR CONSISTLNT WITil EPRI PREDICTIVE PROGRAM FOR COMMERCIALCONCERNS. NO ACTIVE CLOSE IUNCTION. j ENilV0012 9487 R970 IDW RESL1TS SIMilAR val ATS DP TESTED t%DFR_DOUNDINO CONDITIONS VAINES BEING ELIMINATEDIN 19 ENilV0015 NO ClIANGE NOCIIANGE NONE L SIMil.AR VAIATS DP TI'STFDl'NDER 110t'NDING CONDITIONS VALVES BFING FIJMIN ATFD IN 199 EN11V0016 NO Cll ANGE NO Cil ANGE NONE ATT4.XLS I 3 h-t--sv. -, e e m*i--e ,-r.,re- <w-na-wwe----ee. e-s.ee---..r.-- ,~.,-.--m.r---,...e-e e ...w re .-~...-w t .e. m ,+-..,e-.t. ...=-..,=.--. w...v-- + - -.- -. - -.. -,.. - - -,.----......--..-mr.w.,

i e 1/21/94 ATTACHMENT 4

SUMMARY

OF THE THRUST VALUES DETERMINED IN RFR 87461 l CIMED TilRIJST OPEN TilRCST PRA METilOD USF.D FOR DETERMINISC TilR1'ST i NOTES VALVEID REOl'IREMENT RFOt1REMEST SIGNIFICANCE RF.Ol'IREMENT CONIMERCIAL TilRIiST VAllTS PROVIDED DRST WITil SAFETY 111RtJST VA11TS (4100 LIIS) PROVIDF D a 30500 26223 EPilVER09A 4300 4300. NONE CAICt1ATIONS % Tnt A 5 VALVE FACTOR NEXT. COMMERCI AL T11Rt'ST VA11TS IRASED ON DP OF 726 PSID VALVEIIAS 30500 26223 EPliV88038 4300 4300 NONE CA1ClTA110NS WITH A.5 VAL \\T FACTOR SAFETY RELATED DP OF 0 PSID. L COMMERCIALT11RtfST VAllTS BASED ON DP OF 726 PSID. VALVE II AS i 30500 26223 EPIIVRSORC 4300 4300 NONE CALCt1ATIONS WITil A.5 VALVE FACTOR SAFETY REIATED DP OF 0 PS!D. COMMERCIALTIIRl]ST VAll'ES BASED ON DP OF 726 PStD. VALVE II AS l 30500 26223 l ErtlV3308D 4300 4300 NONE CALCL'IATIONS uTTil A.5 VALVE FACTOR SAF ETY RELATEO DP OF O PSID. KAIIV0030 450 347 NONE CAI Ct'lATIONS Will! A VALVE F ACTOR OF 10 VALVEINSTALLEDIN AN AIRSYSTEM I KCllV0253 1507 1291 NONE CAI C1'I A110NS WIT 11 A V AINE F ACTOR OF 10 CALCl*lAT10NS W1Til A VALVE F ACTOR OF 1.1 VALVE.S DP TES1TD l'NDER IOW DI"5 f LFTV0095 1766 295 CALCt1ATIONS %TTil A VALVE FACTOR OF l.2 VAINES DPIT.STED t'NT)ER IDW Dl"S If!IVU105 548 ' $32 C AI Ctil AllONS WIT 11 A VAINE F ACTOR OF 13 VAI.YES DP TESITD l'NDFR I OW DPS IIIIV0106 542 - $12 7 i i L i t i ATT4.XLS t 4 ~ f

3 ) i I ATTACllM ENT $ TO RFR 87461 Tile ATTACilED DRAWINGS WERE OBTAINED FROM THE WESTINGHOUSE STRESS REPORTS IN Tile QA VAULT OF THE CALLAWAY NUCLEAR PLANT. j i' TilESE DRAWINGS SIIOW Tile MEAN SEAT AREA OF WESTINGHOUSE j FLEX WEDGE GATE VALVES. i i i i i i v E t r i i lofil 01/21/94 i i

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ATTACilMENT 7 RISK IMPORTANCE CATEGORI7ATION OF MOV'S TIIAT CANNOT BE DP TESTED FOR RFR 87461 I of13 01/21/94 I

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hir. J. A. McGraw. IPE Impact of Non-DP Tested hf0Vs Ref.: UOTE 93-221 This letter responds to the referenced letter, which requested that a review be performed to assess the impact on the IPE due to the inability to AP test selected MOVs. In order to perform a meaningful review, a draft NUMARC document, " Guidelines for Optimizing Safety Benefits in Assuring the Performance of Motor Operated Valves," was used as guidance. This document is provided as Attachment 1. The procedure described in Attachment 1 involves categorization of MOVs into one of three importance groups (high, medium or low). Testing recommendations are then made for each importance category. MOVs are placed into an importance category based on their PRA numerical importance. MOVs that were not included in the PRA must be placed into an imponance category using deterministic methods and/or engineering judgment. Attachment 2 is a flow chart that delineates the NUMARC guidance for application to Callaway MOVs. Using the process represented by the flow chart, MOVs that were included in the Callaway at-power PRA were assigned to an importance category. The review / categorization process is documented in the table provided as Attachment 3. Note on Attachment 3 that only those valves that were modeled in the PRA were assigned to an importance category. Those valves that are not in the PRA v ill have to be assessed by Engineering / Operations for assignment to an importance category. f If there are any quesdons, please contact Keith Connelly et 42868. i 2r A. C. Passwater KGC/kea Attachments A77 m mx A tg L3

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ATTACllMENT 8 EPRI MOV PREDICTIVE PERFORMANCE PROGRAM DATA USED IN Tile DISPOSITION OF RFR 87461 1 of 74 01/21/94

f/W f7VM { i l EPRI MOV Performance Prediction Program REVIEW MEETING Dallas Asrport Hyatt Regency Hotel AGENDA December L 1993 OPEN SESSION (Open to all domestic utilities and to all participating international utilities) 1:00 pm Introduction / Meeting Objectives.. ../. Hosfer (EPRI) 1:15 Technical Advisory Group Perspective.. ..M. Eidson (SNC) i 1:30 NUMARC Perspective.. ..C. Callaway (NUMARC) 1:45 EPRI Program Overview / Status.. .f. Hosfer (EPRI) 2:00 Review of Flow Loop Test Program Results.. . l. Hoster/W. Kennedy (EPRI) 3:00 Break 3:15 Assessment of Potential Implications for Installed MOV's., . N. Estep (Duke Power Co.) 4:00 Question / Answer Period.. .. All 4:45 EPRI MOV Program Follow-on Activities... ../. Allen (TVA) 5:00 Adjourn A TT 8 Agr 79

.- ~. _ - - - _ i l i I EPRI MOV Perfor: nance Prediction Program REVIEW MEETING r Dallas Airport Hyatt Regency Hotel l AGENDA December 2.1993 f CLOSED SESSION (Open only to utilities participating in the EPRI MOV Program) i 8:00 am Introduction 8:15 Review of Key Program Findings / Issues.. ./. Hosfer (EPRI) 8:45 Methodology Overview..... .P. Damerell (MPR) [ P 9:15 Globe Valve Modeling Approach / Status.. ..P. Damerell (MPR) - l 10:00 BREAK i t 10:15 Gate Valve Modeling Approach / Status......... .P. Damerell (MPR) 12:00 LUNCH l 1:00 Butterfly Valve Modeling Approach / Status.........M. S. Kalsi(KEI) i 2:00-Method for Assessment of Rate-of-Loading Effects.P. Damerell(MPR)' f 3:00 BREAK 3:15 Question / Answer Period........ . All 4:00 Adjourn y 'T

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b, n /</ UNITED STATES ,c4 b h # NUCLEAR REGULATOR 1 copetiss!ON OFFICE OF MJCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 Novener 30, 1993 hRC INFORMATION NOTICE 93-88: STATUS OF MOTOR-OPERATED VALVE PERF0fMANCE PREDICTION PROGRAN SY THE ELECTRIC POWER RESEARCH INSTITUTE i Addrettets i All holders of operating licenses or construction permits for nuclear pcwer ) reactors. I Purcese The U.S. Nuclear Regulatory Cosmission (NRC) is issuing this information notice (IN) to alert addressess to preliminary results of meter-operated valve (MOV) tests conducted by the Electric Power Research Institute (EPRI). It is expected that recipients will review the infersation for applicability to their facilities and consider actions as appropriate, to avoid slailar problems. However,suggestionscontainedinthisinformationActicedonot constitute NRC requirements; therefore, no specific action or written responsa is required. Backereund - ~ ~ ~ i Related i theNRCissuedGenericLetter($L)89-10,'Safetylearpower on June 28, 1989, Motor-operated Valve Testing and surveillance,' to request that nuc plant licensees and construction po mit holders Verify the design-basis capability of their safety-related MOVs, in SL 89-10, the NRC staff requested that licensees and pemit helders test each ICV within the scope of the generic letter under design-basis differential pressure and flow conditions, where practicable. The recommeeded schedule in GL 89-10 would have licensees i and permit holders verify MOV design-basis capability by June 28,1994, or three refueling outages after December 28,1989 (whichever is later). j in response to concerns regarding M perfomance, EPRI and its utility advisors established a research progres to develog a esthodology to predict the performance of Ms under design-basis conditions.. lEMARC coordinates the interaction between EPRI, its atti ty Technical Advisory Group (TAs?e,d and NRC staff related to the EPRI program. The EPRI progras includes detall analyses and testing of MOVr at test facilities and nuclear power plants. The EPRI MOV Perfomance Predictice Nethodology is intended to allow licensees to demonstrate the design-basis capahtlity of M0Vs based on analytical l predictions combined with diagnostic tests conducted under static conditions. In August and October 1993. EPRI presented the status and preliminary results i from its Flow Loop Testing Program to the NRC staff. The flow loop results in ^ .44 d BEST AVAILABLE COPY 4,.,..w J fe u

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. :1-4. n a 41 w-i l ~ IN 93-44 Movember 30, 1993 i Page 2 of 6 i the EPR! presentation have not received full quality assurance verification. but the prelisinary information may be helpful to licensees as they implement i their MOV programs. In a letter on September 16, 1993, NUMARC provided responses from EPRI to NRC i staff questions on the EPRI MOV Performance Prediction Program. Among the t informatien proviced in the enclosure to the letter, EPRI stated that its j prcgram is expected to cover about 90 percent of gate valves (about half with its computer code and half with empirically-based data), essentially all globe valves, and about 95 percent of butterfly valves. The globe and gate valves j are covered primarily by the computer code. EPRI also stated its method for determination of cperator output torque capability under degraded voltage conditions is to apply standard methods as documented in EPRI NP-6460-0 l (March 1990), " Application Guide for Motor-0perated Valves in Nuclesr Power Plants.' l Descrietion of circumstances l In conducting its MCV Performance Prediction Program. EPRI tested 18 gate, i 4 9 cte, and 2 butterfly valves under a total of 62 test condittens. These 1 i tests were perfonned at Wyle Laboratories and Siemens test facilities. EPRI plans to cbtain test data for an additional 35 valves being tested in nuclear power plants. In addition. EPRI completed testing at Kalsi Engineering of i 10 butterfly valve designs to assess flow and upstroom piping configuration l effects. The results sumartzed below are based on the Wyle/Stemens NOV tests. 1. Gate Valves EPRI stated that all gate valves tested were initially pretenditioned by l conducting a large number (50-1000) of short (no flow) strokes in cold water under differential pressure loading. Initial ' sliding friction coefficients,' prior to preconditioning, gewr:11y ranged fres 0.8 to 0.4 IPA! indicated that, after preconditioning,e' apparent friction coefficients' ranged fres 0.3 to 0.6 for all but four va v s tested under cold water pumped-flow conditions. The ' apparent friction coefficients

  • for the rossining four valves ranged from i

0.66 to 1.93. EPRI results demonstrated ' apparent friction coefficients' 0.35 to 0.8 ranging from 0.34 to 0.41 for het water pumped-flow conditions lowdown for het water blowdown conditions, and 0.25 to 0.44 for stees b I conditions. EPR!'s ' apparent friction coefficients' reflect all v41ve internal phenomena and are not necessarily indicative of a ' sliding friction coefficient.' The major difference between the ' apparent friction coefficient

  • used by EPRI and the ' valve factor' used historically by valve vendors in sizing motor operators is the censideration of the valve disc angle l

in cetermining the EPRI

  • apparent friction coefficient.'

Most valve vendors have used a ' valve factor' of 0.3 for flexible wedge gate valves and 0.2 for parallel disc gate valves in sizing motor operators. j Therefore, the EPRI test results indicate that the thrust required to operate BEST gyAtLABLE M 16.a /S} M

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hovember 30, 1993 Page 3 of 6 gate valves could be significantly greater than the thrust predicted by the valve vendors. The EPRI blowdown test results are generally consistent with those obtained in the limited testing program conducted by the Idaho National Engineering Laboratory (INEL) for the NRC Office of Nuclear Regulatory Research in 1989. EPRI reported that the valve sliding friction coefficient tends to decrease with increasing differential pressure ~which lends support for linear extrapolation of reduced differential pressure results when there is a low potential for valve damage (for example, under nominal flow velocity pumped-flowconditions). EPRI reported that several gate valves were damaged duri.ng het water and steas i blowdown testing. These included a 6-inch Anchor-Darling valve (disk and seat damage); a 6-inch Crane valve (guide damage); a 10-inch Velan valve (guide dasage); a 6-inch Walworth valve (guide damage); and a 10-inch Edward valve (diskandseatdamage). Two of the damaged valves exhibited " apparent friction ceefficients' exceedir.g 0.6. Two gate valves were damaged under cold water pumped flow conditions. These included a Velan 6-inch valve (plastic bending of body guides at high flow velocity greater t.6.t3 30 feet per second) and an 18-inch Ancher-Carlin9) valve (valve disk ferced through setting area resulting in leakage above disa. 3 EPRI test results revealed that it is generally not'possible to determine accurately the point of flow isolation prior to disk vedging based on the thrust diagnostic trace alone. EPRI stated that it had not observed differences in thrust requirements for valve operation between valves installed in horizontal pipes with the stes either vertical or horizontal. This finding differs from soms operating t experiences in nuclear power plants. 2. Globe Valves EPRI stated that, for incongressible flow conditions, globe valve thrusts are consistent with industry ca.c.11ational-sethod predictions only if the i appropriate area is chosen for differential pmssure application. The appropriate area (dist asan seat area versus disk guide area) Gppears to be unique to valve design. It was determined that use of disk mean seat area rather than disk guide area can result in significant underestimation of required thrust for some globe valve designs. Specifically, one globe valve tested under cold water pusped-flow conditions required approximately twice as i auch thrust to close using disk mean seat area and a valve factor of 1.0. A two-inch Rockwell/ Edward globe valve, tested under hot water blowdown conditions, exhibited thrutt requirements exceeding predictlens based on disk guide area ey approxisately 35 percent. This valve sustained damage to the portion of the body bore that guides the disk. BEM gggtABLE COPY p,-,,-

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%N8 ; y, Nevesber 3o, 1993 Page 4 of 6 l Current industry practice for detenining the required thrust for globe valves varies by manufacturer. Many sanufacturers assume disk mean seat area multiplied by a valve factor in the 1.0 to 1.1 range. Others use disk guide area in making thrust predictions. Therefore, the EPRI naults indicate that actual thrust requirements may exceed those predicted using current industry practice for some globe valve designs. 3. Butterfly Valves EPRI stated that the Wyle flow loop testing revealed torque Mquirements to operate Pratt butterfly valves welch were bounded by the most current torque predictions of the manufacturer. However butterfly valves at seas nuclear power plants lfor example, Catawba and Pale Verde) have demonstrated torque recuirements that exceed vendor predictions. EPRI is u.frently evaluating data from testing ccnducted at Kalsi Engineering to assess butterfly valve torcut requirements for a wide range of butterfly valve designs. 4. Data Inter =retatien aad Attessmeet In July 1993. EPRI sent a Quarterly Status Report to all utt11ttes participating in the EPRI M0V Performance Prediction Progras. This report sumarized preliminary flow loop test Msults. After the completion of Wyle/Siemens quality assurance checks EPRI plans to update t gis infensation in its next Quarterly status report scheduled for late 19g3. Detailed test reports documenting these results are scheduled for delivery to participating utilities between October and December 1993. EPRI stat 66 that, in interpreting the EPRI flow loop test results, utilities need to understand the assuretiens and equations that were used by EPRI in presentin For era: ele, the EPRI calculated ' apparent friction coefficient" g the data.for gate valves is based on the equation provided in EPRI Report NP-6560-41, ' App 1< eation Guide for Motor-operated Valves in Nuclear Power Plants.' This equation is solved for ' apparent friction coefficient' using (1) the saximum asasured sten thrust unich occurs prior to the initiation of wedging (for valve closing) er the maximum thrust which occurs after cracking (for valve opening); (t, full l (valve closed) tested diffsrettial pressuret (3) mean seat area; (4) valve disk angle; (5) full (valve closed) upstrees tested pressure for stem rejection thrust; and (6) measured values of packing loed. EPRI stated that valve design and test conditions, saintenance history, and operating esperience may be important in assessing the applicability of EPRI test results to plant MOVs. 4 EPR! uses the greatest thrust requirement to overcome differential pressure and fice to deterstne its ' apparent friction coefficient.' EPRI assuans the highest differential pressure observed during the test reganiless of the stem position where the greatest eifferential pressure /flev mquired thrust occurs. This results in a lower calculated friction coefficient than would be determined if the actual differential pressure at the point of greatest thrust was used in determining the friction coefficient, g A\\fA\\L M f h-p4'l V73W

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November 30, 1993 Page 5 of 6 EPRI clans to submit sections of a topical report for NRC review as they are cospletec between November 1993 and April 1994. EPRI intends to submit supporting reports in advance of the final topical report to allow the staff to raise Questions with EPRI early in the review process. EPRI stated that its final methodology is scheduled for delivery to utilities in Acril 1994 as a tool that may be used to confim many aspects of MY calculations and setup. Further, the EPRI flow loop test results provide licensees with information which might be helpful in supplementing other 'best available" data in establishing MOV switch settings. Discussion Since EPRI initiated its MOV Performance Prediction Program, the NRC staff has conducted public meetings with WRC and EPRI to discuss the goals of the EPRI program, the development of the program activities to accesplish those goals, the tests conducted in support of the program and the results of those tests. and the cogletion schedule for the program. The staff has provided cuestions and comments to NLMARC and EPRI on the EPRI ICV progres as a result of these meetings. For example, in a public meeting en October 6-7,1993,the staff eeshasized the need for EPRI to ensure that licensees clearly understand the application of the EPRI test data and methodology. Also at this meeting, contents of this notice were discussed and the comments from EPRI have been considered. The staff expressed concern about the valves damaged during the EPRI testing and the apparent lack of action by some valve manufacturers in response to the valve damage. The staff also discussed the need for EPR! to ensure that adecuate peer review of the EPRI methodology is conducted. Although some issues remain to be resolved, the EPRI testing progres should provide a significant amount of MOV test data that can assist nuclear power plant licensens in demonstrating the design-basis capability of MVs that cannot be tested under dynaste conditions as installed. The preliminary test infomation provided in this notice is provided for licensee consideration in implementing prograss in response to Gl. 89-10. The staff plans to conduct additional public meetings with NLMutt and EPRI to discuss the status of the EFR1 M0Y program. The staff will consider the need for additional generic ccartunications to nuclear power plant licensees and construction permit holders as additional information is obtained free the (PRI NOV program. Related cenarle C % nications NRC Information Notice 90-40, 'Results of NRC-5ponsored Testing of a Motor-operated Yalves.' g gMLP3bE 397i

.. -s..a " r ' '"~- ' :. 34

,,4 IN $3-84 November 30. 1993 Page 6 of 6 This information notice requires no specific action or written response. If you have any questions abcut the information in this notice, please contact the eerson listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project sanager.

m:. _2 Brian K. Grimes, Director Division of Operating Reactor Support Office of Nucleer Reactor Regulation Technical contact: Thomas G. Scarbrough, NRR (301) 504-2794

Attachment:

List cf RecPntly Issued NAC Inforination Notices BEST AVAILABLE COPY h.2114 S ig H

r l l l - EPRl/NPD ,} l EPRI MOV Program Review Meeting d} Flow Loop Test Results a2 Data Tables DFW Airport Hyatt December 1-2,1993 i Engineering & Operations # 185VG'JFH clk 1 t /93 10 h

u PUMI'ED FLOW TEST LOOL

  • ilUNTSVILLE COLD WATElt RESULTS SUMM ARY OF G ATE V ALVE TEST HIGH DP PERFORMANCE Comments LOW DP PERFORMANCE M

isol. Close Psid O n 0 135 0140 DP isol. TEMP Close 275 0.168 V Psid O n W 0.141 W Note A

  • F 0 287 0620 Ft/Sec 90 1

0 643 MFG / Size AMll M 1[1 h_l Valve No. 15 A D/6 I 1 KM 15 _M_M '__. ,B.WI6 __0_ 278 _ 7 _M_M _0.304 / _g, _1 g____._ _ _M 15 _17. 0 375 Alovco/4 0.4 0 431 _53 260 _74 0.2 k 15 _ _ _ _. _ _ _. _ _Pacific /4 _____._;_46 03 04 90 AMB __ _0 564 _MgM 0 387 Note B 15 Velan/6 1 _60 23 30 1 2 _._.;_ d[dd 0.390 Velarv6 23 i AMB l 50 d d[d Velan/6 23 15 Wal/6 i High apparent p under study, no damageCantelevered guides best COMMENTS 4y Note A 4 Note B I M\\ i i 64T BLlWSE#' M 4~ m ..-:_.,_.m.,,.....,- _.. _.. -. _ _...,.. ~.

IlUNTSVILLE INTEltM EDI ATE l'RESSUllE l'UMI'ED 1 LOW SIM ULATION TEST LOOL' SUMM ARY OF GATE VALVE TEST RESULTS LOW DP PERFORMANCE HIGH DP PERFORMANCE V TEMP DP Apparent Disc p DP Apparent Disc p Valve No. MFG / Size Ft/Sec F Psid Open Close Isol. Psid Open Close isot-Comments 4 A D/10 15 AMB 250 0 451 0 385 0 371 630 0 389 0.361 0 347 j 4 A-D/10 15 AMB 250 0 460 0.401 0.397 650 0.379 0 370 0 365 Note A i 4 A-D/10 15 AMB 250 0.455 0.417 0.392 640 0.413 0 407 0.389 Note B 4 A-D/10 15 AMB 250 0 448 0 406 0 384 630 0.411 0.403 0 380 Note C 10 B W/12 15 AMB 250 0 685 0 663 0560 630 0 627 0.570 0.497 Note D 17 Pacific /10 15 AMB 100 0.594 0 546 0.483 270 0.513 0.489 0.447 [ k 25 Velan/10 15 AMB 260 0.540 0.594 0.499 750 0.493 0.529 0 447 Note F 31 Wal/12 15 AMB 100 0.752 0497 0.426 265 0.701 0.478 0.405 Note G k 43 Edward /10 15 AMB 650 0.486 0.700 0.584 1800 0 E.18 0 495 0363 Note H I I e Q y ff / ~/l* Y COMMENTS Note A Stem Horizontal Note B Et>ow from side Note C Elbow from top Note D Wear on interior surface of one body guide - no seat damage Noto E Heavily scratched at 4:30 and 7:30 positions on disc and seat -- leaked 1 ml/ min Note F No torque arm Note G llegh openity p*s associated with disc / body interference on o[mning Note il Valve llow isolated but failed to wedge on max dp closure due to nx> tor stall 63T UL/WSK/jp

NOitCO filGil l'ItESSUltE COLD /IlOT WATEll TEST LOOL' SUMM ARY OF G ATE VALVE TEST RESULTS LOW DP PERFORMANCE HIGH DP PERFORMANCE V Temp DP Apparent Disc p DP Apparent Disc p Valve No. MFG / Size Ft/Sec 'F Psid Open Close Isol. Psid Open Close isol. Comments 1 A D/3 15 AMB 200 0 464 0 504 0 320 780 0 440 0 432 0 361 3 A-D/6 15 AMB 660 0 526 0 615 0 535 1830 0 475 0 515 0 463 3 A-D/6 15 450" 630 0 418 0 423 0 410 1300 0 382 0 416 0 399 3 A D/6 50 AMB 660 0 585 0 569 0 489 1900 0 539 0.561 0 435 3 A D/6 B/D 530* 1210 0 453 0 430 Note A 3 A-D/6 B/D 530* 1290 0 420 0 402 Note B 7 B-W/3 15 AMB 630 0 458 0637 0537 2600 0 521 0 564 0 480 7 B-W/3 50 AMB 670 0 514 0 715 0.514 2630 0 513 0553 0 430 9 B-W/6 15 AMB 650 0.665 0.710 0 480 1800 0 610 0 642 0.423 Note C N 9 B-W/6 B/D 530* 1250 0 393 0 366 13 Velan/2.5 15 AMB 1300 0 646 0 484 0.260 2650 0.593 0 460 0 282 13 Velan/2.5 50 AMB 1360 0 635 0 496-0.284 2660 0.580 0.452 0 287 13 Velan/2.5 B/D 530* 2660 0.328 0 279 COMMENTS Note A Some body and disc seat damage, flow hmited by loop piping Note B Some disc seat damage Note C Wear on downstream side of body guides g i 65TBLiWSK lp =se w s-s-+e# . - * -5r-w- w a-www-e ~, - .---e+- r m w.-

NOllCO IIIGli l'IRESSURE col _D/IlOT WATEll TEST 1.001' SUMM Al(Y OF GATE VALVE TEST ItESULTS LOW DP PERFORMANCE HIGH DP PERFORMANCE V Temp DP Apparent Disc p DP Apparent Disc p Valve No. MFG! Size Ft/Sec 'F Psid Open Close Isol. Psid Open Close isol. Comments 14 Crane!6 15 AMB 650 0 442 0 419 0 295 1930 0 379 0 415 0 344 14 Crane /6 50 AMB 650 0 507 0 378 0 337 1900 0 436 0 429 0 347 14 Crane /6 B/D 530* 1280 0 788 0 762 Note D 16 A D/3 15 AMB 500 0 672 0 620 0 526 1870 0 487 0 451 0 436 21 Rock /Ed/2-1/2 15 AMB 470 0 320 1 930 0 928 1810 0 375 24 Velan/f 15 AMB 480 0 530 0 567 0 324 1910 0 531 0 501 0 365 i X 24 Velav6 15 AMB 460 0 585 0 596 0 451 1930 0 539 0 486 0 385 Note E y N A k 24 Velarv6 15 450* 670 0 527 0 343 0.300 1180 0 487* O324 0 280 24 Velan/6 50 AMB 640 0 602 0 567 0 353 1800 0 536 0.498 0 367 24 VelarV6 15 AMB 940 0 640 0 592 0.383 1720 0 621 0 552 0 401 Note F 24 VelarV6 B/D 530* 1270 0 468 0 417 30 Walworth/6 15 AMB 650 0 359 0287 0 207 1890 0.422 0 399 0 331 30 WalworttV6 B/D 530* 1320 0.531 0 497 Note G 34 West /3 15 AMB 750 0 475 0 319 0 315 2650 0 313 41 A D/6/PD 15 AMB 480 0.762 0.950 0 469 1900 0 545 0 548 0 444 41 A-D/6/PD B/D 530 1270 0 348 0 331 COMMENTS Note F Torque arm disconnected

  • Downstream seat Temperature lower Note D Damage to guide rails Note G Gouging damage to guide rails than 450;(probably 200 300 Frange)

Note E Stem honzontal 65TBL/WSKtjp

SIEMENS/KWU lilGli PRESSURE COLD WATEll AND STEAM TEST LOOL' SUMM ARY OF GATE VALVE TEST RESULTS LOW DP PERFORMANCE HIGH DP PERFORMANCE V DP Apparent Disc p DP Apparent Disc p Valve No. MFG / Size FI/Sec Temp Psid Open Close Isol. Psid Open Close Isol. Comments 5 A / D /10 15 AMB 460 0.576 0.465 0.408 1350 0 442 0.394 0.376 6 A/D/18 15 AMB 167 0.226 0.327 0.194 333 0.295 0.18 Note A 24 Velan/6 200 Sat. Steam 1200 24 Velan/6 B/D Sat. Steam 600 1200 7 26 Velan/10 B/D Sat. Steam 1200 0.718 0.56 Note B 41 A/D/6/PD B/D Sat. Steam 1200 0.333 0.591 0.347 i l \\ l M 43 Edwards /10 B/D Sat. Steam, 1200 0.344 0.41 0.33 Note C N COMMENTS Note A Disc driven below normal wedge location; flow leakage above disc: disc permanently " pinched" Note B No damage to disc and seat, severe damage to bod / guide rails Note C Some stellite edge damage to disc and seat

  • Still under evaluation i

661121 WSK -lp 5

SUMM ARY OF GLOllE VALVE FLOW LOOP TEST RESULTS Valve Valve Max AP V Factor Factor Valve No. MFG / Size Psid Ft/Sec Temp (Seat Based) (Guide Based) Comments 44 B-W/6 1800 15 AMB 1925 0 978 44 B-W/6 1800 50 AMB 1998 0 976 48 Edward /2 2500 15 AMB 1246 0 905 48 Edward /2 2500 50 AMB 1417 0 922 48 Edward /2 2500 B/D 530 HW 2 146 1 480 Note A ( ( 49 Velan/2-1/2 2500 15 AMB 1.039 0 514 kk 50 A-D/10 740 15 AMB 1.062 0 719 Note B T I 50 A-D/10 740 15 AMB 1 065 0 738 Note C q k COMMENTS Note A Valve dxl not close, valve factor abnormally high Note B Fbw over disc Note C Flow under disc 6 7Tbl/WSK 11:

Key in Situ Test Results, Gate Valves Maximum Apparent Maximum Apparent Stem Thrust et Disk Friction Coef. Stem Friction Coef. Torque Switch Talp Valve Manufacturer, Differential Flow Fluid Number Size and Type Pressure Velocity Temperature Open Close Open Close Static Dynamic Borg Wamer 17 Wsec g 16M psM Ambient 0.305 O.135 0.105 24,605 lbs 20,376 lbs 4-inch FWG (water) (0.555) "9 8 sw 3 300 psid 86 7 0.332 0.373 0.161 0.113 36,622 lbs 34,114 lbs 16-inch FWG (water) 5 D m g W arn w 12 Wsw 1 4 300 psid 86 T ' O.371 0.355 0.166 0.134 35,039 lbs 35,281 lbs 16-inch FWG (water) N 0.174 An hmSa% N 11 340 psid ~ 8" 110 7 0.210 (0.328) 65,827 lbs 52,948 lbs 16-inch FWG (water) ^"Ch" 8 6.4 Wsec 39,990 lbs 34,994 lbs 12 350 psid 105 7 0.208 0.238 16-inch FWG (water) Velan 0 Wsw 17 900 psid 535 7 0.394 O.167 0.122 9,810 lbs 10,020 lbs 4-inch FWG (steam) (0.512)

  • "9 sc 18 965 psid 540 7 0.196 0.353 13.410 lbs p

Sa These valves showed brief thrust increases lust before wedging. The first value of apparent disk friction coetticient is just prior to the increase. The second value in parenthesis is at initial wedging. Data indicato a possible zero shift during opening stroke which would increase apparent disk triction coctricient to about 0.30. + M

u I i l l l EPRI MOV Performance Prediction Program TAG Perspective EPRI MOV Performance oecember 1-2,1993 Prediction Program t 1. TAG Overview II. Recent TAG Activities I Technical Advisory Group Perspective lit. TAG Perspective A. Positive Notes Industry Update Meeting B. TAG Concerns C. Program Objectives D. Program Results/ Impact December 1-2,1993 IV. Summary y amh-*Emontsuci 3 N: Pd EPRI MOV PPP Technical Advisory Group and EPRI MOV PPP Technical Advisory Group Subcommittee Structure i.e e.eom ee i e 5-I Q 18. Em isov Portormene. Prediction Program (PPP) Tectmical Advisory Group (TAG) provides technical goldence to the EPHI Sierf in the pEenning oo tene a na heen ne. and implementation of the progreert Techassee, sube m Q The primary i AG foeve le on program geefe, elgnificent technicallewoe. ochedoeng and budget octhhtes, t e the T AG acte l'ho e steering comndelee. The T AG preendes manhoring and oeereight of technical I'" huee h rehbg and oppredng www end EM Nect M ,,g

=

W g"O' j re -re.nd.ione. 5------ ., o <e o the doished,,og,.miechnieel =p.cte are -

d and roeie.e4 by the evbcomnditees, which include en empended morreperehty frorn the C.eep g

g g teoV PPP vewardnet wthttles. The subcomndelsee toport back to the T AG. sere.enea fas res I piew a I n o The TAG to-nee the ov PPP rn. erd e,.t vi.e. 3 e--e is-a een Q The TAG reporte to the EPHI Operettone & Reebdenence Technology l l l Subcomnettee end the EPRI Engineering & Opereptone isen F orto. Q The T AG beerf acee wnh outeW orgentrattene euch me MSSS Ownee's 6*""***'*> Groupe MutA ARC and NRC. [' [- .~

e a 1993 EPRI MOV PPP TAG Members EPRi MOV PPP TAG Subcommittees I i "8* NAME COMPANY g,,,,,,,,,,,,,, ,,,g tems tweea somewea sewe==

  • John Alten Tennessee Valley Authority Deee4 Ese p.C'*6 mea Ode Penee Denver Atwood Southern Nuclear sio yo d,

gPse asoonJosG a stranars amers Bill Br ck TU Electric I'," o Clive Cellowey NUMARC , g g Bden Curry Phttedelphie Electric sieames to tiociete C;,_e., r,r;.'n*,oe,,,,e,,, .ch.o Eidson Cho..n Souihom Nucie., e Noel EstopeVice Chairman Duke Power chuet tgach sewhem cempen, sewe.e bed '8"a"% C* C****" Chris Hensen Yankee Atomic Sten bed Unten Eweede Sam Henry Tennessee Valley Authority ma scheemen.C+Chasee a ciewmad Iwetde "e" We" ' P*' N!ch Konstantinou Commonwealth Edison r r esunsaac Fred Mertson New York Power Authority can ceae.e, Che's 't=a==% Chetaaea Tsance Atom

  • Bob McPhoerson Southern Californie Edison

<Pa non Sc.,er n Cieweiend siect,ic = ee,,e_,e

  • Robert Woohl PCSE eden seawea somea td+esa

[_

  • Uenon to Operations & Maintenance Subcommittee.

j D h l 5 \\ i Recent TAG Activities 1993 Recent TAG Activities 1993 (Cont'd) e, _ e-o... e.ne.me - o . n e.-evas ,.e.e,e de.ng. e-e.,,oe,s .eeme e mee.e.g Jea 12 i AG Subeemme** meWingo July 15 E PM ts0W PPP vydem meettig with pegeom pealeIpmes Joa 1314 i AG esproceed teaceene esse teeing proyees, ee9ueeted sew ** Jtdy 30 f Pf4140 lenee to emery managemese regweets eeneaued piese to meesw 3 esov s e-1 AG end 9.teemmenee Iapsuppen. e Jea te E rse1&G eopea m ose tech s. tee==m*e Ave 8 '**L***8***- e "'e"9 F 6s T AC tenw to pentriperes esqueme esov in en. tem eme avees 1aC meestag Fet il f P85 esOV PPP opeme metag weh peegram pwHelpente; e.g to to T AOfPfe/9stesanC meetang eNh teRC se Uryte 1ete to reelee 90% popwemien to be inetuded la progesen, flew loop eeewns and laopect sehes Ane ?4 T AG Infeemed as noe reee eso, tem seguence deseHene sad la ee'* Sept e EPfu eenee m mftC foresey eseyende se totC eenevaa toes date teesse; eppreced 3 oction phms go,t 27 Pe iPfe1 AG eepen to 04GA tech 9deoenmatee end Eto f een Force Apr 72 TACA ;. - --_Noteo gnanwesegweee moottag eeh DIRC oct S T AGTPfWe8Lef AIIC meeHg evee ACftS 9% 9 EPW eneme preendee omoseement of tese datelessee sa oct 6 7 i AGitPfE18U18&ftC/Veen ^^ A-- ", weh teRC 8"e'h***8*er N octit37 T AG meeHas tesy 19 3e EPse1 AG moon se Eso Teek feeee end DAC. g g,p,,, g, gg,,,,,,,,,,,,,,,qq Junee 9 AC tone se eseewho eeenacte seaposee SEDY Ir. ene toes aleta M 12 iPf5 es0W PPP gh mq wMh IndWey end pgm peMicppm June 19 EPfeT AG eyeomose en ed8ttense New toop teattag June to Topless flopee Schromennsee meenne /i _ /..

t December 1993 Positive Notes December 1993 TAG Concems I l Flow Loop Subcommittee O Additional flow loop testinD O Preliminary scopelopplicability of code methods identitled. O Plant In sHu inung O Gate volve snelytical model development. O Data enelysis O Globe & butterfly valve model development /vetidation. Modeling 8 Separate Et/ccis Subcommittee O Scope expanded by developing new non-code methods. O "OV ''''' *d'"9' o Butterfly valve parametric test program. 00'"**"***'*'*h*""*** O Velve design effect test facility. O Gate volve designs with T-bend perpendiculer to flow O Overterly progress report for program participants' o Globe volve performance under blowndown conditions O Volve manufacturers support improving. o Gete velve carbon steel guide friction changes with temperature O Recent program reports

  • quellty improving.

TopicalReporf Subcommitfee O EPRI MOV PPP Project Staff performance. O Project schedule end budget f O TAG end Subcommittee work load /8 O Reviewfapproval of topical report by HRC / h 4 i 4 Q EPRUTAG Agreement For Additional Program Objectives s-Flow Loop Testing (June 15,1993; Amended September 27,1993) I oeevio,.no esed. en..wd*e, sw,,.dic=, se=,r oi.ied uov,wtoren.nc.. mice, eeew. -rss,.,us.iion end e,e essone. e O Priority #1: 2500 pel cold water and hot water parametric and 2500 pel 90 testing Ornemic In eliu essens le not required. of one or two globe volves. ~ O Priority #2: 2500 pel steem testing of 21/2* gate volve et 200 FPS and 80 condillons, and cold weler testing of 10* volve et 50 FPS . G.te and giobe vetvo towet toeding etwete are secessed (cold water test is complete). O Priority #3: Cold water,15 FPS, testing (porttel stroke) . User +tendiy. of a 18* gele volve et DPs up to 500 pold. g,,,,,,,, operator internese deisbese O Priority 84: Cold water,15 FPS, testing (pertlet stroke) 3 o,,eio, uoyg,ner es iniormenon detsbeoe. of a 12* gate volve et DPs up to 1800 psid. O Priority 85: Cold water 15 FPS testing of volve 819. 5 Detennene woes for future reneweh. jps

Distribution Of ~16,000 Safety-Related Af0Vs Program Objectives - The Report Card i I - 20% Globe - 50% Gate Valves Valves a.e e i e e a c a,a,a,e M,s.a.s l a a.a s. e a a x - 20% Butterfly Valves l \\ c e-o. -~.e i .r.._.._.e.a.. > * * * * = = = - 10% N or ~ ff: Valve Types f-4 ..... h..i? ""!'" .~ tg i 1N i EPRI MOV Program Results/ impact - Good News & Q \\ ~80% Population Covered By EPRI MOV PPP Dad News ~~ \\ I -15% ~85% Non-Computer Computer

i. mode en have deveioped daiened goes voive p,ediction er.thodoiogy.

- Scope n.y t iimned due to inevetidene fm-ioop ie.i dein Model Model 4 and certeln gate wafve design leasurve. t;; - creeste voive vendor ogvenione m not e mdent end give non< ceervosivereeuno. - Some vetve manutecturer designe ander manuf acturing processes toevet in volves that.M have non-predictoble -90% P*d**"*'- Computer . uniii.e e,ithoui.ogree.tve uGV Programe eney have many Model move.iih oo.iorgo. a.eich netting. .nd.retred monocoperevoce, - Sono volves may have to be reworked, replaced, ond'or i here enotoeoperators teeired - Art gate volve designe, stree, macufecturero, e4 non-eteinte are not covered. E.. /L

EPRI MOV Program Results!!mpact - Good News & EPRI MOV Program Results!!mpact - Good News & Bad News (Cont'd) Bad News (Cont'd) I l 2 Modetere have refined globe vehre prediction methodology.

3. Modeleve have developed detened butteroy vetve prodletion

. Scopo does not include blowdown. enethodology. . Volve spenutecturere end stuny engeneere using classic - Velve manutecturere selng older-generstion equaWone vender equeWane and votre 'nomener* demonosone meY and uitory engineere colng closeacol equatione spey

1. _ _,,-,t ttweet requiremente under-predtet torque.

^^ - Some erleung switch eetenge may be InsufMclent or the . some estetin0 ewitch settinge may be ineutticient or motoroperefore may be underetred, the motor-operatore may be understred. 6 - AN globe volve designe, stres.menufacturere are not . All butterWy serve doetgne, stree, and manufacturere In ecope. are not in scope. 4. NRC hee egreed to rev6ew EPfll MOV PPP topical report and iceu. st a Y / / / ! N %'h, Summary Summary (Cont'd) I O Must complete Investigation! resolution of key O Model validation procese en&or NRC review may MOV phenomene. necesettete edditional testing. . ReWWng O NRC tentatively egrees to use generic funding for . Gate valve T. head influences EPRI MOV PPP topical report review. - Stellite behowlor in cold water - Globe volve blowdown performance Q Ouelity of recent program reports is much improved. - Carbon stset beherfor in worm water g O Must comp ete additionel testing. model development and validetion. l -FIO*lo0P O Good progress with gate volve modet development -In situ and validation. O Continued utalty support for T AG end Subcommittees O Scope of oppilcebility exceeds objective. O plants without aggressive MOV Progroms may be in trouble. O Must odhere to very tight schedule to ensure ppp g g g, April 1994 comptetecn. O Program funding is mergInst. g j f\\ / l'E

e EPRl/NPD Assessment of Potentialimplications

ig for Installed MOV's 34 EPRI MOV Program Review Meeting yA DFW Airport Hyatt December 1,1993 l

N. Estep l Engineering & Operations

EPRI-Dallas Update Meeting N Introduction information Available for Evaluation e - EPRI Weekly Status Reports - EPRI Special Update Reports D - EPRIindustry Meeting Presentations - NRC Information Notices Issues: q Q - Gate valve apparent disk-seat friction coefficient and anomalous behavior - Globe valve apparent valve factors and anomalous behavior - Butterfly valve hydrodynamic torque coefficients - Stem-stem nut friction coefficient - generic issue and not considered in this evaluation - Rate-of-Loading - generic issue and not considered in this evaluation Duke Power Company ~.

EPRI-Dallas Update Meeting Approacli step 1: - EPRI weekly status reports, special update notices, and industry presentation results were reviewed to identify valves with performance that: a. Would not have been bounded by Duke 'tg thrust / torque predictions, and/or \\ b. Sustained damage during testing 5 Duke Power Company

EPRI-Dallas Update Meeting Approach Considerations for Step 1: 1. In presenting the apparent disk to seat sliding friction h coefficient ( ) results for gate valves, EPRI used the 't NMAC Guide [1] equations for differential pressure h" load, FDP: h Closing (Equation 5-3a) For(Ibs) = ( )( AP)( A,,,__ mo (cos0 -sin 0) n Opening (Equation 5-3b) 1 For(lbs) = (p)( AP)( A ~., _ mo (cos0 + sin 0) Duke Power Company 3 O

EPRI-Dallas Update Meeting Approach Duke uses the following equation to predict the open and close FDP term [2]: For(Ibs) = (VF)( AP)( A..:. x.a) Therefore, to convert the EPRI apparent seat friction V coefficient values to the valve factor (VF) term used in the Duke equations, the following relationships are used: k n Closing: q M VFa., = (cos0 - sin 0) Opening: U V F,.., = (cos0+psin0) i ) Duke Power Company 4

EPRI-Dallas Update Meeting Approach VF and are identical when the disk half-wedge angle (0) is l l 0-degrees (for example, Anchor-Darling double disk gate valves). bd lx For a 5-degree half wedge angle and a of 0.5: k VFc = 0.525 VFo = 0'.481 For a 5-degree half wedge angle and a VF of 0.5: Close = 0.477 Open = 0.520 Duke Power Company 5 e --e- + y -e -u-- w e w i _,w- +s-

EPRI-Dallas Update Meeting Valve Factor vs Friction Coefficient (for 5-degree half wedge angle) 1.2 i 1.1 ~ = 1 m I' 0.9 U 0.8 8 0.7 6 u-0.6 VFgc = h 0.5 t; f 0.4 0 O V F,o ( 0.3 O ) 0.2 0 r ? 0.1 o i 0 0 0.1 0.2 0.3 0.4 0.5 0.60.7 0.8 0.9 1 Friction Coefficient Duke Power Company 6

e EPRI-Dallas Update Meeting Approach Consideration 2: 1 - The EPRI values for seat friction coefficient under cold water test conditions represent " preconditioned" values. Therefore, the EPRI friction coefficient results may represent worst case conditions for cold water test conditions. For elevated temperature water (above 200 'b3 degrees F) and steam testing, it was observed that seat g 31 preconditioning had little effect on the apparent seat yi friction coefficient results. Consideration 3: - For globe valves, the valve factor (VF) is essentially a correction term to account for the difference between the assumed and actual area upon which the DP is acting. Duke typically uses a VF for globe valves of 1.1. Therefore, EPRI globe valve test results with a VF greater than 1.1 were noted. Duke Power Company 7

EPRI-Dallas Update Meeting Table 1 - EPRI Test Valves Exceeding Duke Criteria ANSI Class / EPRI Valve No. Type M fg Size Material 3 FW G Anchor Darling 6 900 cs 6 FW G Anchor Darling 18 300 cs 7 FW G Borg-W arner 3 1500 cs 8 FW G Borg-W a rne r 6 150 cs i 9 FW G B org-W a rne r 6 1500 cs { 10 FW G B org-W arne r 12 300 cs 13 FW G New Velan 2.5 1500 ss 14 FW G Crane 6 900 cs k 19 FW G Powell 6 150 cs ( 21 FW G Rockwell 2.5 900 cs 23 FW G Velan 6 150 cs 24 FW G Velan 6 900 cs 25 FW G Velan 10 300 cs 26 FW G Velan 10 900 cs 30 FW G W alworth 6 900 cs 41 PDG Anchor Darling 6 900 cs 43 SWG Edwards 10 900 cs 44 Globe Borg W arner 6 900 cs 48 Globe Rockwell / Edwards 2 1500 ss Duke Power Company 8

EPRI-Dallas Update Meeting Approach step 2: This list was further reviewed to determine if MOVs of similar i design were in service at Oconee, McGuire or Catawba: a. MOV data bases were searched for a match of h manufacturer and valve type. b. MOVs with matching manufacturer and type were further grouped based on size and ANSI pressure class similarity. An EPRI test valve 6-inches in size may include a review of 4,6,8 and 10-inch valves of similar pressure class Pressure classes of 150/300, and 600/900/1500 were grouped together 1 ( l Duke Power Company g

EPRI-Dallas Update Meeting / Approach Step 2, continued: c. Next, MOV design similarity was determined from a review of the EPRI and Duke valve outline drawings. i b Disk shape %4 Stem-disk connection i Guide configuration Valve disk materials (for some valve designs) l Duke Power Company 10 I -e, e --e - - - -,+ a ,, - - +,

EPRI-Dallas Update Meeting Table 2 - EPRI Test Valves Exceeding Duke Criteria and Having Potential Applicability to MOVs in Duke Plants EPRI Valve ANSI Class / No. Type Mfg Size jiaterial '( 7 FWG Borg-W arner 3 1500 cs 8 FWG Borg-W a rne r 6 150 cs 9 FWG Borg-W arner 6 1500 cs 10 FWG Borg-W arner 12 300 cs ( 14 FWG C rane 6 900 cs D 21 FWG Rockwell 2.5 900 cs 26 FWG Velan 10 900 cs 30 FWG Walworth 6 900 cs 41 PDG Anchor Darling 6 900 cs 43 SWG Edwards 10 900 cs 44 Globe Borg Warner 6 900 cs i 48 Globe Rockwell / Edwards 2 1500 ss - Duke Power Company 11 e-%v-y-

t e EPRI-Dallas Update Meeting Approach step 3: Each valve is individually examined to assess 'g applicability to the EPRI test results: a. MOVs that are not safety-related or included in the Generic Letter 89-10 scope were eliminated from consideration. k b. .MOVs that do not have design-basis requirements similar to the EPRI test conditions that produced the unexpected behavior were eliminated from consideration. Pumped vs Blowdown Design-basis stroke direction l i Duke Power Company

EPRI. Dallas Update Meeting Approach l Step 3, continued: Next, Duke in-plant DP and flow test results for MOVs c. similar to EPRI test valves were reviewed to determine le if more favorable results were obtained. For purposes I of this evaluation the Duke in-plant test results and not %t the EPRI test results are considered to be the "best available data" for evaluation purposes. k d. Finally,if an MOV of concern remains the Duke Problem investigation Process (PIP)is entered for l further action. f l Duke Power Company 13 L

EPRI-Dallas Update Meeting 4 Final Results EPRI Valve No. Disposition ~ 7 No corrective actions iik 8 Some corrective actions necessary - PIP generated 9 No corrective actions 10 Some corrective actions necessary - PIP generated 14 No corrective actions Q 21 No corrective actions per letter from manufacturer N .26 No corre~ctive actions 5 30 No corrective actions 41 No corrective actions 43 No corrective actions 44 Some corrective actions necessary - PIP generated 48 No corrective actions i Duke Power Company g

I EPRI-Dallas Update Meeting References 1. NMAC, Application Guide for Motor-Operated Valves in Nuclear Power Plants, NP-6660-D, March 1990. 2. DPS-1205.19-00-0002, Guideline for Performing Motor Operated Valve Reviews and Calculations. h 3. NRC Information Notice 89-61, " Failure of Borg-Warner Gate Valves to Close Against Differential Pressure," August 1989. 2 4 4. EPRI Weekly Status Reports 5. EPRI Special Update Notices 6. EPR: Program Update information 7. NRC Draft Information Notice on EPRI Test-Results 8. Letter, Earl Bake of Edward Valves to William Kennedy of EPRI, January 15,1993. 9. Telecopy Message, Earl Bake of Edward Valves to N. Estep of Duke Power, October 25,1993. Duke Power Company 15 _y--,~r= .y---+-,- ,e- ,y +i,a- = ~ m, e, y.

,---.v w

f r m-

\\ EPRl/NPD l EPRI Mov Performance Prediction Program !wU OVERVIEW & STATUS i k WQ EPRI MOV PROGRAM REVIEW MEETING DFW Airport Hyatt December 1,1993 JOHN F. HOSLER 185VGUHl'cik 11/93 1

EPRl/NPD BACKGROUND NRC Generic Letter 89-10 In Situ Design Basis Testing of MOV's Initiation of EPRI MOV Performance Prediction g u Prograrn 'is Formation of Utility Technical Advisory Group ,i (TAG) s Establishment of NUMARC/ TAG /NRC interface Engineering & Operations 185VG/JFH'cik 11/93 2 ~ a g-a- -w p c -, +

EPRl/NPD PROGRAM OBJECTIVES Provide 'Ulilities with a validated methodology to analytically predict MOV performance Provide a technically defensible alternative to w t. 'S i in Situ design basis testing id' l1 l Engineering & Operations 185VG1Jfil'cik 11/93 3

EPRl/NPD APPROACH Utilize NMAC MOV Application Guide as starting point Develop improved methodology for MOV 6 Performance Prediction to include: %( fluid system modeling valve computer modeling (gate, globe, and butterfly) methods to apply flow loop /in situ MOV test results to plant specific applications (some gate valve designs) motor-operator dynamic response assessment Engineering & Operations 185VG'JFH clk 11/93 4

l i EPRl/NPD l APPROACH l i Perform separate effects evaluations to address areas of known uncertainty rate of loading valve design effects { friction stem lubrication ( \\ Engineering & Operations - 185VGtJFilctk 11/93 S

i EPRl/NPD APPROACH i Develop engineering models and software modules l

x to predict MOV performance 6

gj DP vs stroke position %( required thrust / torque vs stroke position assessment of potential for gate valve interna! y 4 T damage prediction of motor-operator dynamic response Rate-of-loading effects to be addressed by in situ static test -- validation of test method in progress l l 185VG/JFH'clk i!!93 0

~ l EPRl/NPD l APPROACH Refine engineering models based on results of l i Separate Effects Testing Validate predictive methodology by comparison to g } flow loop and in situ test results %y 185VG1JFit'cIk 11/93 7

w p EPRl/NPD [ Summary of All MOV Test Data to be used for Methodology Validation / Assessment No. Valves No. Test Seq. EPRI Wyle/Siemens Flow Loop Testing 34 62 Duke F/L Testing at Utah State 2 8 EPRI Kalsi Poutterfly Valve F/L Testing 10 37 EPRI In-Situ Testing (Fully Enhanced) 28 28 \\gi 74 135 EPRI In-Situ Tests w/o full enhancement 8 8 INEL/NRC Blowdown Test Program 9 12 91 155 - Engineering & Operations 185VG'JrH'cik 11/93 9

SHQWyd b h .? EPRI MOV PERFORMANCE PREDICTION PROGRAM PRODUCTS Product DRAFT FINAL PUBLISH Apphcation Guide for MO\\"s in Nuclear Complete Complete Complete Power Plants (NM AC Product r Review or INEL Gate Valve Test Program Complete Complete Complete in Situ T est Guide

  • Complete Complete Complete N10\\ Margm improvement Guide
  • Complete Complete Complete

\\10V General Inf ormation Database

  • Complete Complete Complete Butterfly Appbcation Guide (W AC Ndum*

Complete Complete Complete Stem Nut Lubricant Test Report Complete Complete Complete Methodology input Specthcation Draf t Complete Complete Complete Huntsville Low Pressure Flow Loop Test

  • Complete Complete Dec. 3,1993 Frunon Test Report Complete Complete Dec. 3,1W3
c. mpuian.sn.u nuid Dvnamu Analysis Report Complete Complete Dec.15.1@3 Globe Valve Model Report
  • Complete Dec. 3,1993 Jan. 31,1994 Huntsville Int. Pressure Flow Loop Test
  • Dec. 3,1993 J an. 7,1994 Feb.7,1994 Norco Flow Loop Test Report
  • Dec.13,1993 Jan.20,1994 Feb.20,1994 Butterfly Valve Model Report
  • D ec. 31,1993 Jan. 31,1994 # N 20,1994 Siemens/KWU Flow Loop Test Report
  • Dec.17,1993 Ja n. 31,1994 Feb.28,1994 Butterfly Valve Subscale Test Report Dec. 3,1993 Jan.15,1994 Mar. 7,1994 System Model Report D cc. 31,1993 ja n. 31,1994 Mar. 20,1994 in Situ Test Report (Phase IF Dec. 31,1993 J an. 31,1994 Mar. 20,1994 1ntegrated Methadology PC Code
  • M a r. 20,1994 Mar. 20,1994 Ma r. 20,1994 Cate Valve Design Effects Report Dec.10,1943 Pktf15.1944 Mb 7,lu44

()perator 1ett Report Feb.1.1444 Mar.1, I444 Apr. 23.1W4 Gate Valve Model Report Feb.15,1994 Mar.15,1994 May 7,1994 PC Code Users Manual

  • Feb.14,1994 Ma r.15,1994 May 7,1994 Operator Effects Methodology Report
  • Feb. 28,1994 Mar. 31,1994 May 20,1994 1n Situ Test Report (Phase 2P Mar.15,1994 Apr.15,1994 June 7,1994 Integrated Methodology Assessment Report Mar. 20,1994 Apr. 20,1994 J une 10,1994 Model implementation Guide
  • M ar. 20,1994 A pr. 20,1994 J une 10,1994 Empirically Based Methods Reports" M ar. 31,1994 Apr. 30,1994 June 20,1994 MOV PPP Topical Report Oct.1993 to May 15,1994 July 7,1994 IDratt Sections to be issued as completed.)

Apr.1994

  • Product 3 w hich can be directiv applied bv Utilities in assessmg MOV performance capability.

\\ote. Bolded products are des eloped under 10CFR50 AppenfpitpqsjptAh S gg lr and are the best ccp.es nabb e. 1 atteptab'e as-is This Document is c0'isidere: A Record per revew m ir for processlag as aj _ date Mf/ perlo:med by A ~ x1

~ EPRl/NPD EPRI MOV Program Product Distribution Two catagories of products Non-Q/A Q/A All non-Q/A products will be distributed to MOV Program g technical contacts automatically as published l u All Q/A products must be procured directly from Power u Computing Corporation in Dallas, Texas via a P.O. which l imposes Appendix B and Part 21 requirements A single blanket P.O. will be sufficient to procure all O/A products Q/A products will be issued as they are published and once P.O. has been received Engineering & Operations 185VG JFH clk 1193 8 i

m_._ m,_ m._ - >1 - 9l 9s Power Computing l Babcock & W5 con a McDermou emparty

  • 930 H Lne Dnve Dadas Texas '5207 I

i214) 655 E822 + November

2. 1993 l

t i TO: EPRI MOV Program Participants - Technical Contacts FROM: John Hosfer. Electnc Power Research Institute l Sarah Scott. Power Computing Company The EPRI MOV Performance Prediction Program will produce a computer program and a number of reports which have been developed under 10CFR50 Appendix B. In l addition, some of the work will be reported in non-QA reports. As a participating member of the MOV program, you are entitled to receive all reports and the sof tware. I The non-QA reports will be sent to you automatically as they are published by EPRI. Additional copies of e'! non-QA reports can be ordered from EPRI's Report Distnbution Center at (510) 934-.121':. f The QA reports and software will be distributed for EPRI by the Electric Power Software Center (EPSC), operated by Power Computing Company (PCC) in Dallas. Texas, in order to receive the QA material, each utility should place a purchase order with PCC (nominal cost $100). The P.O. should request all MOV QA Program Products (shown here as Atchment A) and should specify that the terms of the agreement be in accordance witn the applicable provisions of 10CFR50 Appendix B and 10CFR21. In addition. the P.O. should specify the name of the utility contact to wnom the product should be shipped. r it is recommended that a blanket P.O. be placed with PCC for all products shown in Attachment A. In that case, PCC will distribute the products as soon as they are available. It is suggested that sufficient copies of each report be ordered to support utility engineering and each nuclear site. Utilities should minimize the number of Flow Loop Test Reports ordered, since each of these is comprised of approximately 10 volumes with a total of as many as 600 pages per volume. Purchase Orders should be sent to the attention of Sarah L. Scott at PCC at the address above If you have any questions or need further information, please feel free to contact Ms. Scott at (2141655 8828.

ffi9ft->t-4 Y j TO 7M i Attachment A P 1 EPRI MOV PERFORMANCE PREDICTION PROGRAM QA PRODUCTS 1. MOV Performance Prediction Methodology Computer Code and Supporting Hardcopy Documentation (SW-103242) The PC-based code will predict the force or torque required to open or close a valve at each position in its stroke. The computer code shall consist of five modules. The System Module will calculate the differential pressure across the valves at each stroke position, input to this module will include pipe lengths, fluid properties, pump curves, etc. Three Valve Modules will be required. The Gate Valve Module and the Globe Valve Module shall calculate the required stem thrust at esch stroke position. The Butterffv Valve Module shall calculate the required torque. Input to these. modules includes a differentialpressure calculated i by the System Module as well as valve dimensional parameters, material types, etc. In addition to calculating thrust, the gate valve module l shall determine if the valve is likely to exhibit anomalous performance during its stroke. These four modules shall be integrated under the User interface Module which will handle I/O routines and manage module execution and file maintenance fuentions. j The code will be delivered with a User's Manual (TR-103243) and a l I Model implementation Guide (TR 103244). i i Page 1 of 2

5(9 9+ p%,d Attachment A (continued) EPRI MOV PERFORMANCE PREDICTION PROGRAM QA PRODUCTS 2. Additional reports which are being made available as OA controlled documents include: TR - 103220 In Situ Test Report (Phase 1) TR - 103224 Butterfly Valve Model Report TR - 103225 System Model Report TR-103226 Operator Methodology Report i TR - 103227 Globe Valve Model Report TR - 103229 Gate Valve Model Report TR - 103231 Integrated Methodology Assessment Report TR - 103237 EPRI MOV Performance Prediction Program Topical Report TR-103232 Engineering Analysis Report: Anchor / Darling Double Disk Valve TR - 103233 Engineering Analysis Report: Westinghouse Gate Valves TR - 103234 Engineering Analysis Report: Edward Equwedge Va!ves TR - 103235 Engineering Analysis Report: Aloyco Split-Wedge Valves TR-103236 Engineering Analysis Report: WKM Gate Valves TR - 103190 Cold Water Pumped Flow Loop Test Report TR-103239 Cold Water Intermediate Pressure Flow Loop Test Report TR - 103240 Norco Flow Loop Test Report TR - 103241 Karlstein Flow Lcop Test Report TR-103238 in-Situ Test Report (Phase 2) l l Page 2 of 2 l 1

EPRl/NPD ? Review of Flow Loop Test Program Results e t ) EPRI MOV PROGRAM REVIEW MEETING DFW Airport Hyatt December 1,1993 John F. Hosler/W. Kennedy \\ Engineering & Operations - 185VG'JFH ip 1193 1

EPRl/NPD KEY RESULTS FROM FLOW LOOP TESTING Objectives f} Scope Gate Valve Preconditioning Approach / Philosophy Data analysis Techniques Key results Engineering & Operations - ,es - n n.,,,,,,

EPRl/NPD OBJECTIVES is Obtain test and inspection data (both valve and i operator) for most populous valve designs over a range of size, pressure, AP, and flow conditions to: L

1. Provide data for validation of the MOV Performance Prediction Methodology; and I
2. Quantify the performance of valves typical of those installed in nuclear power plants under a wide range of media, flow, differential pressure and temperature conditions.

Engineering & Operations # \\ 185VG JFH jp 11/93 3 g%.- g-ys+ y..w,,.- -,e-+ 9- --ys.--yav er ,.%2,,-,-- =.i-e. e-, ,,e,,

EPRl/NPD SCOPE FLOW LOOP FACILITIES (Wyle & Siemens) ? Low pressure, cold water pumped flow at Wyle Laboratories, Huntsville, 1. Alabama. 6" valves tested at DPs up to 250 psi. y d 32. Intermediate pressure, cold water blowdown (simulating pumped flow) at Wyle Laboratories, Huntsville, Alabama.12" valves tested up to 500 h i psi,10" valves tested up to 740 psi. High pressure, cold water and hot water pumped flow simulation and 3. hot water and steam blowdown at Wyle Laboratories, Norco, California. i 6" valves tested up to 1800 psi,3" valves tested up to 2500 psi. 4. High pressure, cold water pumped flow simulation and steam blowdown at Siemens/KWU, Karlstein, Germany.10" valves tested up to 1800 psi,18" valves tested up to 500 psi. Engineering & Operations - 185VG'JFH'ip 11/93 4 .. ~ -

EPRl/NPD 4 SCOPE Wyle/Siemens Flow Loop Test Program t( Testing completed on 34 valves (62 test f sequences) at 4 Wyle/Siemens flow loop facilities. 28 flex or solid wedge or parallel disc gate Q valves ranging in size from 2-1/2 to 18 inch and 150 to 1500 lb. class 4 globe valves ranging in size from 2-1/2 to 10 inch and 300 to 1500 lb class 1 2 butterfly valves; 6",150 lb. class Engineering & Operations t85VG-JFH jp 11/93 5 - - ~ ~ - - - - _...

1 A111.1: 1 111)W LOOL' I1.5T M A II(l\\ tJo Valve Manufacturer Sue ANSI limetorque Ambient Ambient 450 F 500 F Sat. Sat. Alternate Type (Inch) Classr Actuator Water Water Water Water Steam Steam Conh. s f Material 15 FPS 50 FPS 15 FPS Olowdown 200 FPS Ulowdowri guration SMB-(Note 6) (Note 5) (Note 1) (Note 2) (Note 2) Testing Type (Note 4) M AX DP M AX DP MAX DP MAX DP M AX DP M AX DP Notes 1 FVA) Anchor Darling 3 300 cs 00 740 (HI) 2_ FVAi Anchor Darleng 6 ISO ss ,000 250 (HP) 3 FVG Antlior Darling 6 900 cs 0 1800 (N) (N)t800 (N) 1200 (N) 1200 D C. F 4_ FVG Ancitor Darleng 10 300 ss 0 740 (HI) 5 FVA1 Anchor Darhng 10 900 cs 2-150 1800 (S) 6 FWG Anchor Darling 18 300 cs 2 500 (S) h { IVAi Berg Warner 3 . 1500 cs 00 2500 (N) [N) 2500 y 8 FVG Borg Warner 6 150 cs Rotork 250 (HP) w 9 FVAi Borg Warner 6 1500 cs 1 1800 (N) (fi) 1200 I 17 FVG Borg Warner t2 300 cs 1 25 500 (HI) 13 FVG New Velan 2 Is2 1500 ss 000 2500 (N) (N) 2500 (N) 2500 14 FVG Crane 6 900 cs 0 1800 (N) (N) 1800 (N) I200 b t5 FVAi Watworth/Aloyco 4 150 ss Rotork 250 (HP) 16 TVAi Anchor Darling 3 900 cs 00 1800 (N) {b E FYAi Pacihe 10 150 cs 000 250 (HP) 18 FVA) Pacific 4 150 cs Rotork 250 (HP) 2TFVG Rockwell 2-112 900 cs 000 5 1800 (N) 23 FMG Velan 6 150 cs 000 250 (HP) (HP) 250 24_ FVG Velan 6 900 cs 0 t800 (N) (N) 1800 (N) 1200 (N) 1200 (S) 1200 (S) 1200 25 FWG Velan to 300 cs 0 500 (HI) 26 FVA1 Velan 10 900 cs 2 1800 (HI) (S) :200 29 FVG Walworth 6 150 cs Rotork 250 (HP) 30 FWG Walworth G 900 cs 0 1800 (N) (N) 1200 31 FVG Walworth 12 150 cs Rotork 250 (HI) G 34 FWG Westinghouse 3 1500 ss 00 2500'750 (N) 41 FOG Anchor /Dar ting 6 900 cs 0 1800 (N) (N) f200 [S) 1200 43 SWG Edwards t0 900 cs 2 1800 (HI) [SL1200 44 Gkbe Borg - Warner 6 900 cs 2 1800 (N) (N) 1800 48 Globe Rockwetl/ Edwards 2 1500 ss 00 2500 (N) (H) 2500 (N) 2500 49 Globe Velan 2-1e2 1500 ss 00 2500 (N) D 50 Globe Anchor Darl.ng 10 300 cs 2 500 (HI) 54 BFly Pratt 1400 Sym 6 I50 cs 000 HOOC I50 [HP) D 55 BFly Pratt 1200 Single O/S 6 150 cs 000 .HOBC 150 (HP) XX FVAi .Powell I4 600 cs 500 (HI) t il - Ws le llunt s ille hmigwl 11.w l niy 1.-t I.w ilits I il W s le Ilunt-ulle Int.1mnh.ite lh-ure Ic-t I a. ibts N W sic N..i... llegh th-iric f est I.m ilits s sicin.m Kh t ' l hgh h.-ine le-41.n ihts 126G.fi il jp

EPRl/NPD SCOPE i i TEST CONFIGURATIONS tk Pump flow - simulates opening or closing against the head of an upstream centrifugal pump with some specified downstream 3 t resistance Accomplished in each facility by holding test valve upstream pressure nearly constant and providing a throttle in series to limit flow Blowdown - valve is opened or closed against a storage vessel of hot water or stream whose pressure remain essentially constant and whose piping has low flow resistance ie5VC JRijp 11'93 7

L EPRl/NPD DATA CHANNELS Stem thrust Spring pack displacement Iy Stem torque Spring pack force Stem' position Switch timing (5) kp Valve upstream pressure Motor speed Valve downstream pressure Motor voltage (3 phases) i Valve differential pressure Motor current (3 phases) Valve bonnet pressure Motor power Valve under disc pressure Motor power factor l Valve downstream total Valve temperature pressure Fluid temperature Engineering & Operations 85VG'JFH'lp 11/93 9 i

y EPRl/NPD GATE VALVE i PRECONDITIONING APPROACH / PHILOSOPHY ? 4 \\ Preconditioning of Flow Loop Gate Valves Objective Precondition (age) test valves prior to test to eliminate stroke effect (reach " plateau" level) Flow. loop parametrics would be unaffected by stroke effect Determine relationship between contact stress and number of strokes required to reach plateau Approach Short stroke (~ 10%) open/close MOV in test loop with DP and very low cold water flow until apparent p reaches " plateau" level DP to be based on max test DP or DP resulting in a contact stress of 20 ksi on seats, whichever is less 2 Engineering & Operations 185VG'JFH 'ip 11793 9

N &Ig W >i-17 pt APPARENT DISC COEFFICIENT OF FRICTION VALVE # 16, PRECONDmONING o.8 i i z O.7 9 y 0.6 m i u-0.5 04 I i g 0.3 E l M 'i l l 0.2 w O m I O 0.1 i I I O O 100 200 300 400 500 SOD 700 800 900 1000 STROKE NUMBER m OPEN A CLOSE ' ggg pigu@tE COM MLMWY

l \\ EPRl/NPD l ) DATA ANALYSIS TECHNIQUES l 't. Data sheets are completed on each test stroke to document the values of key parameters at specific %d D " events" in the stroke. 2? Ed -r N \\\\= Engineering & Operations 1BSVGJFH jp 11'93 11 --m-= v m w

'9 M 7 + g,, a EPRI Gate Valve Test nalysis Data Sheet / Test Date /4 f 2 Test Time / 4 ' 2 2 ?/J Valve # Test # 6/ - / - ### 7' '3 ~// Stroke Direction D -7 C % i7 Test Deectlption /5 hi /00 d Valve Mean Seat Diameter .3.25 in. Data File Efe/F Data Set /7 Motor Current Start Time' Anatyzed by: d%7p 2 'Vi Motor Current Stop Time' Verified by: 6-l /Ly /f *f 3 -i

  1. '#'3 55 avass. i g% s me.

Contactor Dropout Time' W/# lb. mci [#ft sm., we 4,4,, Packing Load at Running 'nr Fa'*A ro r m esw a n 62 B F VenturilSuppty Temp. 83 'F Test Valve inlet Temp. Closed to Open Time Thrust Torque SPDISP h b APP APP (sec) (ib.) (ft-Ib) (In.) Upassess DP Disk Stem Prese(pelg PSID n u ~ A. At cracking

  • l B. Just after cracking l

C. Max after cracking D. Running (No DP) E. Limit SW Trip F. At Flow initiation j Open to Closed Time Thrust Torque SPDISP h b APP APP (esc) (ib.) (ft-lb) (In.) Upseenm DP Disk Stem Prose (peid PSID n u ~ A. Running (No DP) 4.32o - 983 /7 7.46 a.osts 18/.5-

0. 75 B. Mu pnorto inealwoopng 11.156 7877.V J2.T2 A sef.5 747.6 17 r, t

.VJ/6 . t 7.80 ~ C. At initial wedging (f.tVJ -3fJ1.8 yg,yp as&fy 79 5.& 77 z,4y .yg,4z. ,i4 g; D. TS Trip * /4.978 tot 1N '69.-64 o.1730 .t3ct E. Max after wedging i9.526 87Y&.8 74.sp d.ig54. . :i 31. .0914' F. Final 7eM72 -87M 3 44.ta 4185/ G. At flow isolation r7 543 -737t.3 26.3e

o. n zt 114. 4 74,4.2.

3ff3 .1 L 5 t

  • Values to nestest.001 second, al other vabues to nearest.01 second.

BEST AVAILABLE COPY

/$ r-> r -1f 6If j Typical I _a l Trace i c c-fe f%ir T = T - P A + P A, + AP Ag(cos 0 - sin 0) A A s c e

^P

~ ~ ' c j Typical s,g ( Thrust A4 l' Trace T = To + ppa, P A + PAP Ag(cos 0 + p sin 6) Bs B Opening Stroke T = Stem Thrust. Ib. AP = Different pressure, psi P = Upstream pressure. psi p = Disk coefficient of frienon As = Stem area,in.2 0 = Half disk angle Ao = Disk mean seat area,in.2 Stem = (24FS cos o d ces a tan a)/(24FS tan a + d) FS = Torque / thrust, ft. a = Half thread angle d = Stem OD - P/2. in. a = Thread lead angle p = Pitch,in. Stem p = Stem coefficient of friction p 1 pp9 9 1 . N I.,))

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  • N t

'j T A I R 1 5 1 I L 0 8 6 4 2 M 0 0 0 o 0 0 0 0 n 0 Tl 0 0 .0 ,o 0 .O FR O O O o. O 0 5I I ~ ( DP n M 1 6 5a 4 r ) r L A e 5 D 0 Ma 4 3 VE LB c E W S ) c O 1 l g 7 1 ~ 0 ( C 2 O c. O 8 0 ) 7 4 - 9 7 8 5 M 2 7 7 K B E-3 4 T T6 1 3 I 8 5 " S 1 8 MC E 1 E L C 7 l ~ 0 B S E ' C se c e 1 .9 9 1 = 0 (C - E l ) 3 2 8 4 2 3 3 9 0 f ( M 0 ) L B C S ~ ~ 2 ~ 1 O ~ n Ea5. .c g0> ) - - .J c

EPRl/NPD Method Used to Determine Point of Flow Isolation 3 k 't Determine change in stem position from cracking g 1. T't peak to flow initiation from hydropump opening stroke 2. Determine stem position at initial wedging from a flow /DP stroke i 1 3. Subtract change in stem position from (1) above to determine stem position and time of flow isolation Engineering & Operations 185VG'JFH jp 10293

EPRl/NPD Evaluation of Globe Valve Apparent Valve Factor E.m s + E. + f( A....,,..) Al' 's F, (ihs) = N Where: N D Fa= Maximum stem thrust measured at anytime during stroke F,.s, x = Packing friction load (Ibs) - determined from avg of pre / post test static strokes F,. = Piston Effect load (Ibs) - above disk pressure X A stem (valve closed) f = Valve factor (dimensionless) ( A..,, ) = Mean seat or guide area (evaluated for both assumptions) AP = Pressure difference across the valve (psi) (valve closed) Engineering & Operations x 185VG'JFH'jp 11/93 16

EPRl/NPD PRINCIPAL FINDINGS 2 "4 g Butterfly Valves Comparison of measured torque to vendor torque 2' g predictions not generally possible due to unavailability of vendor methods No conclusion relative to adequacy of current methods possible at this time Engineering & Operations 185VGJFH lp 10293

EPRl/NPD PRINCIPAL FINDINGS r Y l Globe Valves \\ Incompressible flow (non-flashing) 4 h Use of mean seat area and a value factor of x y 1.0-1.1 found to match data for some valves but found to be significantly non-conservative for others 8 185VG p 10293

EPRl/NPD V PRINCIPAL FINDINGS 1 ? I lt Globe Valves (Con't) lshS Accurate prediction of globe valve thrust requires use of appropriate area for DP application (disc mean seat or guide area). - Determination of appropriate area for a specific valve design requires evaluation of valve physical design characteristics l l / Engineering & Operations 185VG'JFH'jp 10293 .-m-m ---w e ,v<, -iw+ -s y, u g w. e -a---- c, is m 3 m m- - m

EPRl/NPD PRINCIPAL FINDINGS i 4* Globe Valves Jcon't? Nk g Flashing or compressible flow k Data for single valve tested found to exceed {* g even guide area based predictions 1 1 High thrust requirements attributed to plug side loading due to circumferential pressure variations within valve body 185VG'JFHejp 10293

EPRl/NPD I PRINCIPAL FINDINGS t } Gate Valves Number of strokes to ^hieve a plateau in l g) apparent disc coefficient of friction during cold 1 water preconditioning varied from 100 to 900 (Initial values in 0.1 - 0.4 range) Maximum apparent disc 's during cold water pumped flow testing (after preconditioning) were generally between 0.2 and 0.9, with the exception of one valve l (Industry practice had been to assume a of 0.3) Engineering & Operations 185VG'JFH jp 10293

44 --_E a-- PRINCIPAL FINDINGS tends to decrease with higher AP (Disc slidinghigher seat bearing stress) -- supports k extrapolation of reduced DP data -- particularly for g non-blowdown applications ~h Hot water (450 F,15 FPS) testing after cold water W preconditioning and testing, decreased apparent disc to the range of 0.32 to 0.49 No damage or anomolous performance observed under 15 fps flow conditions except: The disc was pushed through seats allowing leakage above disc on an 18",3 angle gate valve Engineering & Operations l ,es -,,,o,

EPRl/NPD PRINCIPAL FINDINGS Hot water (530 F) blowdown apparent disc 's q g ranged between 0.30 and 0.79 -- some valves D sustained significant guide and/or seat damage 1 U ! Steam blowdown disc 's ranged between 0.33 to $ s 0.72 -- some valves sustained significant guide and/or seat damage 4 j No measurable effect on apparent disc (gate t 8 valves) due to upstream elbow orientation or stem orientation k ?\\ DW i Engineering & Operations x 185VG'JFH jp 10293 -}}

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