ML20205G022

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Rev 4 to Mechanical Equipment Qualification File 091-01 to Environ Qualification of Mechanical Equipment. W/Four Oversize Encls
ML20205G022
Person / Time
Site: Beaver Valley
Issue date: 03/24/1987
From: Carol Hill
DUQUESNE LIGHT CO.
To:
Shared Package
ML20205F939 List:
References
NUDOCS 8703310354
Download: ML20205G022 (43)
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{{#Wiki_filter:. DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNIT N0. 2 l ) ENVIRONMENTAL QUALIFICATION OF MECHANICAL EQUIPMENT l I j Mechanical Equipment Qualification File No. 091-01 Revision 4 Specification No. 28VS-091 Xomox (Atwood & Morrill) Plug Valves I 4 b.,,h b NY 2-6 -87 M f 4Cl & 3/24f6) l Prepared by Date Checked by Date l c0 0 N OLC Approval D' ate l 1 Impell Job No. 1290-005-1671 P >m m&, PDR v

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+3 t Mechanical Equipment Qualification F1.le No. 091-01 Revision 2 &O i, TA8LE OF CONTENTS kj Title P3 Equipment List 4 Equipment Evaluation i 5 i Mechanical Equipment Environmental Qualification Worksheet \\ 8 j Component Materials Evaluation Worksheet 12 Component Materials Evaluation Wortsheet References 15 1 ) ATTACHMENTS i j Attachment Title i 1 Atwood 4 Morrill Drawing No. 18149-01, Revision 2 (SW File No. 2006.380-091-34C) 2 { Atwood a Morrill Drawing No. 18149-02, Revision 3 (S W File No. 2006.380-091-31D) i i 3 Atwood 4 Morrill Drawing No. 18149-03, Revision 2 (SW File No. 2006.380-091-33C) 4 Atwood & Morrill Drawing No. 18149-04, Revision 2 (SW File No. 2006.380-091-32C) 5 Maintenance Manual for Cat. I Plug Valves (Excerpts) (S W File No. 2506.380-091-001C) 6 Record of Conversation: s Inc.) and K. Moody (Impe11), dated 7-24-84R. Atanasian (Proces i i l l l ~ i !!O i h 1 I Page 3 of 15 ,,.,,.f..~,_-..- .-,----------e- , -. _.. -.... _ -, - - -.. -, - + - -.. - -. - - - - + - -,

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k n Mechanical Equipment Qualification File No. 091-01 Revision 4 O EQUIPENT EVALUATION

1.0 DESCRIPTION

This evaluation pertains to X0M0X (Atwood a Morrill) Plug Valves procured in accordance with Specification No. 28VS-091. The specific identification of each valve, its model number, and location is found in the Equipment List. The materials of construction were deterisined from the appropriate Atwood & Morrill Drawings (Attachments 1 through 4). A listing of subcomponent materials and their tolerance to temperature and radiation are shown on the Component Materials Evaluation Worksheets (CNEW).

2. 0 QUALIFICATION EVALUATION These valves are located in the Auxiliary Building, Safeguards Area, 5

Reactor Containment and Rod Control Area. This equipment is evaluated to the postulated environmental conditions for each of these locations as shown on the Environmental Qualification i Worksheets. 2.1 Temperatum The maximum postulated accident temperatures for the Auxiliary Building and Safeguards Area are 220*F and.120*F, respectively. The limiting non-metallic material for the valves located in these areas for this parameter is X0MOX-7 which is capable of withstanding temperatures of up to 300*F (Reference A). The maximum postulated accident temperatum for the Rod Control Area is 180*F. The limiting non-metallic material for ~the valve located in this area for this parameter is UmWP s (Polyetttylene) which is capable of withstanding temperatures of up to 225*F (Reference A). 4 The maximum postulat,e8 accident temperature for the Reactor 5 Containment is 333 F. The limiting non-metallic material for lt the valves located in this area for this parameter is UlefWP (Ultra High Molecular Weight Polyethylene) which is ca withstanding temperatums of up to 225'F (Reference A)pable of Therefom the valves located in the. Auxiliary Building, Safeguards Area and Rod Control Ama atre considered to be l capable of withstanding the postulated accident temperature condition. The valves located in the Reactor Containment are not considered capable of withstanding the accident temperature condition (See Section 3.0 for justification). l4 Pace 5 of 15

Mechanical Equipment Qualification File No. 091-01 Revision 3 EQUIPPENT EVALUATION (continued)

2. 2 Radiation The postulated 40-year-norinal-plus accident dose for the Safeguards Area is 1 x 106 rads. The limiting non-metallic material for the valves located in this area for this parameter is X0M0X-7 which is capable of withstanding radiation doses of up to 7 x 10' rads (Reference B).

The postulated 40-year-plus accident dose for the Rod Control Area is 5 x 106 rads. The limiting nonweetallic material for the valves located in this area for this parameter is UMWP (Polyethelene) ich is capable of withstanding radiation doses of up to 1 x 1 rads (Reference B) ) The postulated 40-year-plus accident dose for the Auxiliary Building is 1 x 10' rads. The limiting non-metallic material for the valves located in this area for this parameter is X0MOX-7 which is capable of withstanding radiation doses of up to 7 x 100 rads (Reference B). The postulated 40-yeab-plus accident dose for the Reactor. Containment is 2 x 10 rads. The Ifmiting non-metallic O material for the valves located in this area for this parameter is UWWP (Polyethylene) which is capable of withstanding i radiation doses of up to 1 x 10" rads (Reference B). Therefore the valves located in the Safeguards Area and Rod Control Area are considered capable of withstanding the postulated 40-year-plus accident radiation dose. 1 \\ The valves located in the Auxiliary Building and Reactor Containment are not considered capable of withstanding the i postulated 40-year-plus accident radiation dose. (See Section i f 3.0 for justification.)

2. 3 Pressure i

The maximum postulated accident pressure is 45 psig. The design pressure of these valves is either 275 psig or 615 psig (Attachments 1 through 4). Therefore, these valves are considered capable of withstanding the postulated accident pressure condition. t

2. 4 Humidity The maximum postulat5d accident relative humidity is 1005.

These valves are sealed units by design. Page 6 of 15

W i Mechanica1' Equipment Qualification File No. 091-01 Revision 4 O EQUIPENT EVALUATION 1 (continued) Therefore, these valves are considered capable of withstanding the postulated accident humidity condition. 4 2.5 Chemical Spray For the valves located in the Reactor Containment, the composition of the chemical spray is 2,000 ppe Boron; Na0H pH = 8.5 to 10.5. The only materials that would be exposed to i chemical spray are carbon steel and stainless steel, which are not adversely affected by chemical spray of this composition (Impe11 Calculation No. 1290-005-002). 1 t For the valves located in the Auxiliary Building, Safeguards Area and Rod Control Area these areas are outside of containment and would not be subjected to chemical spray. Therefore, the valves located in the Reactor Containment are considered capable of withstanding the chemical spray exposure. {

3.0 CONCLUSION

The valves located in the Safeguards Area and Rod Control Area are capable of per. forming their intended safety function under the postulated environmental conditions to which they could be exposed. The valve located in the Reactor Containment is not capable of performing its intended safety function under the accident conditions to which it could be exposed. postulated This valve contains UIMie components, which are not expected to withstand either the maximum postulated accident temperature or the postulated accident radiation dose. The valves located in the Auxiliary Building are not capable of performing their intended safety function under the postulated accident conditions to which they could be exposed. These valves contain X0M0X-7 components, which are not expected to withstand the postulated accident radiation dose. With respect to temperature, SWEC Engineering Analysis Supplement No. 1, Rev. 1 to MEQ File 091-01, states that a Thermal Transient 9 Analysis calculation has been performed, ensuring that the internal temperature of 2IAC*MOV133 remains below 2200F. O Page 7 of 15

l 1 Mechanical-Equipment Qualification File No. 091-01 Revision 4 EQUIPENT EVALUATION (continued) With respect to radiation exposure SEC Engineering Analysis Supplement No.1. EAS-14 2. Rev. I to EQ File 091-01, indicates y that SEC has performed location specific calculations (SWEC Calc. Nos.12241-UR(8)-071-0,12241-UR(B)-176-2 and 12241-UR(B)-149-0) which show that the actual efvironmental dose for the equipment inside containment is 2 x 10 rads, which is enveloped by the qualification dose. For the valves located in the Auxiliary Building, SWEC analysis shows these valves are qualified because (1) they are not required for a LOCA, (2) they are not required to be internally leak-tight and (3) external leakage (seepage) will be controlled by normal maintenance adjustment or replacement as required. Therefore, based on the above analysis the valves located in the Reactor Containment and Auxiliary Building are capable of performing their intended safety function under the postulated accident radiation conditions. 4.0 1%INTENANCE For the valves located in the Safeguards Area and Rod Control Area, no specific maintenance beyond the manufacturer's requirements is O valves. y to maintain the environmental qualification of these necessar For the valves located in the Reactor Containment and the Auxiliary Building see Conclusion (Section 3.0). O Page 7a of 15 J -,,,..,-,---~ e ,.a-- ,-----,a_,- r-,ne - -, -. ~, ---c ~-,, -, - - - - - ~ - - - -, - -

O O O Dugn .ight Comparqr Pmpand by: bM Det. Y//4 Seave.. lley Power Station. Unit No. 2 i Impe11 Job Ilo. 1290-006-1671 Checked by: Date: ~Y I l, MECHANICAL EQUIPENT ENVIR010 ENTAL QUALIFICATI0ll WoMSIEET ] 10EQ File alo. 091-01 ~ i i l l 1 l l PU5IULAltg ggyn"- - "I I IFIED LNWI el H ~ l I EQUIP 9ENT DESCRIPTIM l I (NiaWENTAL I I l' I l! WTSTAIIDIIE l l lli PMR l VALUE I KFEEEE l VRE l EFEEEE l ITEBIS l I I I I I isr s./r.o. up.: IEisium i f i z l 12sV-891 Iliampeenture 1 220 1 1 1 3o0 l (sectfen 2.1) I unne l !I ll(desemos F) 1 I a g i E90lPIENT TVPE: Vumavage I I I l' r l l-lifeste) l l l Plug Valve lPressuse 1 0.90 1 61 5 ! (Sectfen 2.3) l Ilone ll9 sI411MFACTUKR: ISIDM ligtalama I I I I Z I l j l(Atunod 8 Ilerrill) i1Relattwe i 100 1 1 l 100 1 (section 2.4) I blame 1

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1 leso0EL N0.: llCestateneet I z l l ' 11366 au lis I II/A l 1 II/A l (Section 2.5) l Mene l ' l (ISSI-7 Trial ll pew l lLIstITIE' ENISNBENT lige-Tear Essoal l I ( l I lIRediation Rose i 1 x 106 1 3 l l l l 1 lLOCATIW: Aux. Bldg. Il W :) l l l 2 l l !l 710' 710' ll Total I i 8 x 108 I (sectfen 2.2) I alone 1 lefD 2ME: 14 h llIntegrated -) 1 x 10 1 3 l l (Section 3.0) l l 7 ii llandfatten nose 1 I I I a l l y ,I ll(Ands) l l l l l l 1

References:

1. Appendix A of Equipment Qualification Report, Volume 1, Revision 1, dated September 20, 1986. 2. MEQ File 091-01, 3. For Resolution of Radiation Qualification, see SWEC Engineering Analysis Supplement No. 1, l1 j EAS 1 and 2, Rev. I to MEQ File 091-01. l Page 8 of 15 Revision 4 )

Duquesne i Campasy Prepared by: N Date: N-M Beaver Valley Pouer Statten. Unit No. 2 l Impe11 Jeb No.1298-005-1671 Checked by: Date: 9/M \\ ECMANICAL EQUIPIENT ENVIRGIBENTE QNALIFICATION INWCSIEET ) IEQ File No. Oe'l-01 i I l ll l r IWLAILD EWWE _ _MI l _ _IFLEn EWWE ml _l '

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I I 1 WWING I i 1l PABMETER l VEME I REFERENCE I VEME I AEFEENCE 1 31555 l i 1 1 I I i laru..ir.s. ms.: I usessman 1 l l l r 1 i 12sV-sel lifesperature i 120 1 1 1 300 1 (section 2.)) I gene 1 i I l 'idearoes F) l l I EUIPIENT TYPE: 1 I summimum 311getly l z iPlug Valve Pressere Negative 1 275 (Sectfen 2.3) None 1 (ests) l lIIAIAFACTNER: 398E I i:ssesseum 1 l z 1 l l(Atuesd-flerrf11) lAelative 90 I 'J l 100 1 (Sectfen2.4) l IIene l I Illumidttr (5) lleOEL 110.: llir.estatement l i z l l i 1156-$N (EWEE-7 Trfe) ll 15 pray N/A i 1 N/A I (Sectfan 2.5) None 1 1 1 l lLI"ITING ENIA0 WEN i Mu-Tear somei i l l l l Ileadfatten esse I 1 a 103 L 1 1 I I I l LOCATION: SB 741 Il(Radsl l l 2 1 I 10 Total I l 7x106 I (Sectfen 2.2) l Mene 1 IRAS I M : B-

11 Integrated 1

1 x 106 y i lRadfattenBe'sel 4 L l(tads) l ll l l l 1 l l

References:

1. Appendix A of Equipment Qualification Report, Volume 1, Revision 1, dated September 20, 1986. l 2, MEQ File 091-01. I Page 9 of 15 Revision 4

Duques. At Company Prepared by: k Beaver Valley Power Station) Unf t No. 2 Date lapell Job Ilo. 1290-005-167 Checked by: Date: ( y a v MECHANICAL EQUIP 9ENT ENVIROISIENTAL QUALIFICATION NOIESIEET IEQ File llo. 091-01 i I l EQUIPIENT DESCRIPTION l.1 1 POSTULATED ENVIROIRENT I QUALwlED t.svlRDIBENT l l ElfvlA010EllTAL l I I I i 15TSTAllDIllG l i i i PARNETER l VALUE l REFERENCE l VALUE l REFERENCE l ITDIS I I I I I i l i Isru./r.o. up.: sunnsmun i I i i z i-Tes 1 12sV-091 Il Temperature 1 333 1 1 1 225 I (Section 2.1) , See nef. 2 i 1 1 1(degrees F) l l l (Section 2.1) l i lEQUIFIENT TYPE: 1 : T imme I I z i i IPing Valve llPressere 1 45 l 1 1 275 l (Sectien 2.3) I liene 1 l(psis) l 8048EFACTURER: XSRM[ I i l l(Atmoed-80errf11) llRelative i 100 1 1 1 100 1 (Section 2.4) I tiene I I r r l llitumidity (5) I l IIEDEL N0.: iICieistament muu ppm I l l l p z i 1166-861 (INetr Tria) llSpre l Beren; 81a018 l 1 l Beren; pmIIsoll I (Sectfan 2.5) l Ilene i pN = 8.5 - 10.51 pli = 8.5 - 10.5 LIMITIls ERIVIRDISENT i efear eermal, I i I l Iltadfatten Dese 1 4 x 104 1 3 l l l l l l l LOCATION: Centafament fl(Rads) l l l 2 l l 1 ldTotal l l 1 x108 t l (Section 2.2) I alone I w< l RAD 201E: Outside lL Integratedi el 2 x 108 1 3 l l (Sectlen 3.0) l Crane lle11 . Radiation Dese l l i (Rads) 1 l l l l l l

References:

1. Appendix A of Equipment Qualification Report, Volume 1, Revision 1, dated September 20, 1986. 2. MEQ File 091-01. l 3. For Resolution of Radiation and temperature qualification, see SWEC Engineering Analysis Supplement No. 1, EAS 1, Rev. I to MEQ File 091-01. lv I Page 10 of 15 I Revision 4

Duque i..ght Campasy Beaver Valley Pouer Statten. Unit No. 2 Prepared by: dM Date: i- #~M a-Impe11 Job No.1296 005-1671 I oj j Checked by: AV Date: 9//F## ECMANICE EQUIPENT ENVIRGINENTAL QNALIFICATION NOKSEET 1 E Q F1le lle. 0'91-01 1 l i 1 r isi.ane tavs _ _ei ._ _seits turs _ei l I i l EgilPIENT SESCRIPTION ll EWISMNTAL l I l I L INTSTABIIIG l I 11 PMAIETER I VEK I REFEarucF l VEE l AEFEENCE l ITEIIS l 1 I ll l 1 laru../r.o. us.: plusessmus l I z l -l j 12sV-ost liTemperatere I iso-l 1 1 225 I (section 2.1) I isone i I Illeserees F) l l l ) lEQNIFIENT TYPE: llIIantene I i I Z i lPlegValve l IPressere 0,90 l 1 l 275 l (Sectfen 2.3) l None lI(psfel l i III41AFACTIER: Meult lissanteum l I Z l l l 1 ,(atuseHenrrfill 'Insistive l 100 1 1 l 100 ' (sectten 2.4) i None 1 IIImmfdtty (S) i l IIllML 110.: I r.eetainment 1 l l z l 1166-ON (Igger Tria) ISpray N/A 1 N/A (Sectien 2.5) None l I l l lLIIIITING ENIAINENT ligp-Year mesual l 1 I llRadtatten Dese i 1 x 103 1 i I i ILOCATIM: RS 718 Il(Rads) l i I llTotal 1 ) l 1 x 108 I (Sectfen 2.2) l Nene l 2 l l RAD ZmE: Een Area ll Integrated -l 5 x 106 i i l llRadtattenRose1 l 9 i i ll(Rads) i I l 11 l l l 1 I

References:

1. Appendix A of Equipnient Qualification Report, Volume 1, Revision 1, dated September 20, 1986. j 2. MEQ Fi1e 091-01. l l 1 i i l Page 11 of 15 t I Revision 4

Duqu s i ht Comp Beaver Vall!y Power:S$stion, Unit No. 2 Prepared by: dM Date: -d## Impell Job No. 1290-005-1671 j _j Checked by: Date: f//4V S i COMPONENT MATERIALS EVALUATION WORKSHEET Model No.: EQ File No. 091-01 1366 BW I I I i i i I I COEONENT l MATERIAL l TEW ERATURE (*F) l REFERENCE l RADIATION (RADS) lEFERENCEl l l l I I l { l i I I I l lNon-metallic I l l l l I l i I I l l ISleeve lX0M0X-7 1300 l A 17 x 106 l Diaphragm IX0MOX-7 1300 l A 17 x 106 l 8 l l B I IDelta Ring lX0M0X-7 1300 l A 17 x 106 l 1 1 I I I 8 l l Metallic l l l l l l l l l l 1 l l ) 180dy lASE SA 351 CF8 l(Metallic parts are l N/A l(Metallic parts are l N/A l l Plug l ASE SA-351 CF8M inot considered sensi-l lnot considered sensi-l l lCcver lASE SA 351 CF8 Itive to thennal I ltive to radiation i I lC:ver Scw. LASE SA 193 D6 l degradation) l l degradation) l l lAdjustment Scw. lAISI 304 l l l l l l Metal Diaphragm l ASTM A167 304 l l l l l l Thrust Collar l ASTM A167 304 l l l l l IBracket ISteel l l l l l ICompensator ISteel l l I l l IKey lAlloy Steel l l l l l 1 IH;x Cap Scw. l Steel l l l l lLockwasher ' Steel I l Hex Cap Scw. l Steel l l l l lLockwasher l Steel l l l l l l Nameplate l Stainless steel l l l l l l Nameplate,ASME l Stainless steel l 1 l l l I I I I I I I I I I I I I I l l l l l l l 1 1 I l I i 1. Page 12 of 15 Revision 0

Duquas . ht Compeg l Beav:r Vall!y Power Station, Unit No. 2 Prepared by: dM a -- Date: -//"## Impe11 Job No.1290-005-1671 f Checked by: K Date:

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I COMPONENT MATERIALS EVALUATION WORKSHEET l Model No.: i EQ File No. 091-01 166 SW l i I I I - I w l i COW 0ENT l NATERIAL l TEWERATURE (*F) lREFEREEEl RADIATION (RADS)? g ENCE i l i ~ l i I 1 o l INon-metallic l l l l l l l 1 I I I I I lsleeve IX0M0X-7 1300 l A 17 x 106 l g ) IDiaphrage IX0MOX-7 l300 l A 17 x 106 g g l l Delta Ring lX0M0X-7 l300 l A l7 x 106 I I I I I I I i l 8 l IMeta11tc I I I I l -l l 1 1 I I l l I l8ody LASE SA 216 WC8 l(Metallic parts are l N/A l(Metallic parts are l N/A 1 lP1 g l ASE SA 351 CF8M Inot considered sensi-l lnot considered sensi-l l l lC ver LASE SA 216 E8 ltive to themal tive to radiation l lCiver Scw. LASE SA 193 87 l degradation) degradation) l l Adjustment Scw. lAISI 304 l l l l l IMetal Diaphragm lASTM A167 304 l l l l l j IThrust Collar l ASTM A167 304 l l l l l 18 racket ISteel l I l l l l Compensator ISteel l l l l l l Key l Alloy Steel l l l l l IH;x Cap Scw. l Steel l I I l l lLockwasher l Steel l l l l l l Hex Cap Scw. l Steel l l l l l lLockwasher l Steel l l I l l I INameplate - 1Stafnless steel i l l l l l Nameplate,ASME IStainless steel l l l i l l l i l i i l i l l l l 1 1 l l Page 13 of 15 Revision 0 i k

o o O i 1 Duquasne Light Compary Beaver Valley Power Station, Unit No. 2 Prepared by: h Date: 9-#W j Impe11 Job No.1290-005-1671 Checked by: Date: 9[/h COWOIENT MATERIALS EVALUATION WORKSHEET 4 { Model No.: EQ File No. 091-01 a I I I I I I l l C(WOMENT l MATERIAL l TEWERATURE (*F) lREFERENCEI RADIATION (RADS) KFEENCE I I I I i i I I I l l INon-metallic I l l I .I I 1 I I I I I ISleeve llRNGdP (Ultra High Molecular 1225 l A 11 x 108 1 3 l l Wei ht Polyet%1ene) l l l l l j Diaphragm I (Ultra Hf Molecular 1225 l A 11 x 108 g i I I We ht Polyet 1ene) l I I i IDelta Ring l (Ultra High Molecular 1225 l A 11 x 108 l 8 l l 1 Weight Polyethlene) l l l l l I I I I I l lNetallic I I I I I l i l I I i l l j . Body LASE SA 351 CF8 l(Metallic parts are l N/A l(Metallic parts are l N/A l 3 Plug LASE SA 351 CFSI lnot considered sonst-1 Inst considered sensi-l l l l Cover lASE SA 351 CF8 Itive to thermal l Itive to radiat1on l l l lCever Scw. l ASE SA 193 86 ldegradation) l l degradation) l l j ' Adjustment Scw. IAISI 304 l l l l l Metal Di rags-l ASTM A167 304 l l l l Thrust Co lar l ASTM A167 304 1 I I l 18 racket l Steel l l l l l ICompensator ISteel I l l l l l Key lA11oy Steel l I l l l .I Inex Cap Scw. ISteel i I I I I I ILockwasher ISteel l l l l l l l Hex Cap Scw. l Steel l l l i l lLockwasher iSteel l l I l l Nameplate Stafniess steel I l I l i Nameplate, ASE , Stainless steel l l l l l { l I I I I I I i. i Page 14 of 15 Revision 0 o j

O MechayEquipment Qualification File No. 091-01 Revision 0 1 COMPONENT MATERIALS EVALUATION WORKSHEET REFERENCES A. Maintenance Manual for Cat. I Plug Valves (SW File No. 2506.380-091-001C) (Excerpts), (Attachment 5) 8.. Record of Conversation: R. Atanasian (Process Valves. Inc.) and X. Moody (Impe11), dated 7-24-84 (Attachment 6) T O l l l i I O 1 i l Page 15 of 15 i

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stust a, wtusita tuciNLiniNo cORPOH ATiON SUPPLIER'S DOCUMENT DATA I"CRM BEAVER VALLEY POWER STATION UNIT 2 DUQUESNE LIGHT COMPANY V, REVIEW & RETURN TO SUPPLIER REQUIRED J.O.12241 (EI) g SUPERSEDES S & W FILE NO. (EI) tat 341 (3s Jos FOR INFORMATION ONLY - NO REVIEW REQUIRED flllllllll) } $ l 0[4s} Q k 0 l _0 / RE ENG. DEWJDlV. 3 y fcE#"o*ng,igALg,g,g,g,a:amNuHam M S Ti s M ,, y,,, j,, E [ foygg P/4)R (E1) S & W EQUIP. l.D. CODE (EI) ARE A DESIGNATION DATE TO REVIEWER (E1) REQUIRE RETU N DATE(E1) l l lll ll b // 83 2/ 3 MF R'S DOC. NO. (E1) tuult To 24 CHARACTams a eLANus)13740 2 (iNCLuot ooc.MEV.oM oATE: REVIEW STATUS (R) N A- ~ APPROVED MFR1 NAME (El) fuusT 70 30 CHARACTEMs a SLANMsHS1400 Ae oeni.. NOfMO /[7tvCrM / bb CV i N da APPROVED AS REVISED eN specipicAm>N 3 ate MONTH ' oAv vn 2s-3ci ooc 13:e max oavs

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1 FUNCTIONAL TITLE (Ell tu,i T 137 401 RE LE EE 'SD TE AM (E2) b AINT. M A Aj()%Fod CPIT T r L U 6 V A L(/E S ,c, ,,o,,c,et,,, ,,y,,,,, inii mas,oNeista sNoiNasa eneon To naview $ & W FILE NO. (Ell (C) 't t 1301 i 121 241 (E23 MasPON810LE ENGINEER AFTER REVIEW U O TYPE Coot StoutNCE too. 41 3 12241 009] A3.lg FL83051 CCO/ REVIEWER COMMENTS: nH -i4 m Ara ss s o~ s -yng A nvw Mus+- a C we moppo/. = .. JF st' i r irr j t,la ,t. i4 = me wuuw % y. 1 G (H GQ F L G tdo. 09 8 - l ATrwAment C ll3 ATTACH TO DOCUMENT

l i f I (' BEAVER VALLEY POWER STATION - UNIT NO. 2 1 J.0.No. 12241-0.F.E.No. 10080-c.0.No. 6289 j INSTALLATION, MAINTENANCE, AND OPERATION INSTRUCTION MANUALS FOR PLUG VALVES - ALL SIZES Purchase Order: 2BV41 Applicable to: VPW015-AW-3 VPW015-B-3 2CHS*MOV100A 2CHS*MOV1005 2HCS*MOV110A 2HCS*MOV110B ers t a e ts 2HCS*MOV112A tocattams compourice 2HCS*MOV1125 ~J Ci.Tu,,,, 2IAC*MOV130 3 a a sac'e'= 2IAC*MOV133 O aace<" 2IAC*M0V134 O'"~~"~""'"*"*'"" 2SWM*MOV562 2SWM*MOV563 O m 25WM*MOV564 'Lo. M.' W ' 25WM*MOV565 sesc.no.28 W 'l8 2HCS*MOV120A gf, gjg 3 g 2HCS*MOV1208 pjm V I l I i O... t j B4-12241-1407 ey3 4 i

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Adjustments 1 Tufline valves are designed and built to give long, trouble- ~ free service. Property applied, adjusted and operated, they should require rninimum attention. In most cases, a simple ad ustment, as described below, is all that is necessary, in l such cases, please first read these instructions carefully. If there are any questsons, consult your Tufline valve repre-1.... ^ ~~ sentative. +# O 1. css of seal. All Tuffine valves are factory adjusted for bub- ,-.[,:, 1 )* c. .g. ble tight shutoff at 100 psi air pressure. Normally, no fur. p-ther adjustment is required. If seepage does occur at the W~$"N%,, l plug shank or downstream, tighten the Allen head screws ik.' 'T uniformly % turn at a time. Operate valve and check for ~ . #t leakage before tightening further. 37."j-@3M W 5 Wh 7 A .y l Hard turning. Torque adjustments should not be made be-s tp fore operating a valve for at least 12 hours under service .] N. - @ 9 "'T.~. w,. l =' l Condihons, since the initial breakaway torque normally re. duces with usage and temperature. Otherwise. valve may 3 l become too loose. If still too tight, reduce torque by loosen. z,4y-. j ing Allen head screws uniformly % turn at a time. After op-l erating valve, repeat as necessary, but no more than 2 or 3 times, or else leskage may occur,if valve is on cold service and after adjustment it is still too hard to turn, try heating valve with lamp or similar source of d heat, being careful Valve repairs not to exceed temperature of a00'F, Normalrunning torques Field repair of I'-4* sites may be satisfacterify cc-*c" e" by carefully carrying out the following instruc! sons. ewt again TFE UHMWPE should be weighed against the advantage of returnir ; val es Size FtAbs. st stem Ft. lbs at stem to factory for repair where this is poss.bfe Because of the 3 15 30 speciaHzed equipment available at the factory. suen recam Og. 20 a0 can be performed in many instances more eccac*cahy g g than in the field, even considering transportat.on c*arges 3 M 100 back and forth. Also, factory repaired vaf ves car y *e t'a*0-4 70 NO ard new valve guarantee and, of course, are tested to the same specifications as new valves. DO NOT EXCEED A TDiPEFATURE OF 300 F WITH XOMOX, 7 TRI.% AND -' ] 225CF WITH UFDMP TRLM v i ~ ~ - - - - - ~ ~ - - - - - - - - -. - - -. - - - - - - -

er O O(3 IMPELL cosmRATION August 27, 1984 1290-005-NY-060 Process Valves, Inc. 21-T N. Michigan Avenue Kenilworth, New Jersey 07033 ATTENTION: Mr. Ron Atanesian

SUBJECT:

Verification of Record of Conversation Gentlemen: Thank you for the information you supplied to Impell with respect to X0MOX valves. Impe11 Quality Assurance Procedures require that you receive the enclosed record of our conversation of July 24, 1984. If this is an accurate account of our conversation, no action is O, required. Should there be any errors or misunderstandings in this 1 record, please contact me at (516) 420-3200. If I do not receive a telephone call from you by Septeirber 10, 1984, we will assume that this is an accurate account of our conversation. Very truly yours, N& .N Kenneth D. Moody Principal Engineer Duquesne Light Company BVPS Unit 2 Mechanical Equipment Qualification Program Enclosure KM/jm i tuEf WE A0 Oh-l O /) Tr a c e s u r G 225 BROAD HOLLOW ROAD

  • MELVILLE. NEW YORK 11747'(510)420 3200

\\ t L" I M P E L, M Y p v, Record of Conversation L 1290-005 1641 pg,. Copy: @ Telephone O Meeting O Other Ron Atanesian . K.1%ody ggfM/M[ T;. From: 201-bil-3973 cat.: 7-24-84 Company: Process Valvis, Inc. Phone No.: X0MOX Valves

Subject:

I Summary of Conversation: i i-Ron provided thA following infomation e.cncerning materials in X0MOX Q valves "UHWMP" is " ultra high weight pt ethylene,"which is resistr.nt to i / k' 1 x 10b rads. q 'X0MOX 7" is a non metallic material which is resistant to 7 x.106 rads. He was not able to' provide me with the generic compound name'of the material i as this is proprietary infomation. l 3 KM/jm ) I l 1 l' f

~. . j. I l \\ t lp Y, .[ DUQUESNE LIGHT COMPANY 4 BEAVER VALLEY POWER STATION UNIT NO. 2 1 p i ( - x. i _F.NVIRONMENTAL QUALIFICATION OF MECHANICAL EQUIPMENT ? i Stone & Webster Engineering Corp. f J Engineering Analysis Supplement No. I s, t }, Revision 1 i i to "^ f Mechanical Equipment Qualification File No. 091-01/Rev. 2 j f ~ Specification No. 2BVS-091 X0MOX PLUG VALVES t i b l i B LJ FI k s & >. 2MA u' 4rk l Prepared by / D&te ( Cheeked by f / ate D M 9} SWIC A$ proval Date _$ h Y Y 3/s9/87 DLC Approval Date j !O l 4 I 1 'J 4 I r-.~n -p---,rmm.,-,,-.-e-c_m w-3 -w-en-,.v---+-------r-,,m w.- - -,.., - - - - -, - -. - - -y--w---,--,,.-----,w,--,,. .r --e-,,-- s

SWEC Supplement No. 1 Revision 1 h MEQ File No. 091-01/Rev. 2 i RECORD OF REVISIONS 9 0 Revision Description Date A Draft 9/18/85 0 Original Issue 10/8/85 1 Pages 1,2,4,5, & 6 03/17/85 ] s D t O 1 t i s i s Page 2 of 9 4 E J

O SWEC Supplement No. 1, Revision 0 MEQ File No. 091-01/Rev. 2 TABLE OF CONTENTS Title g Summary 4 Engineering Analysis EAS-1 5 EAS-2 7 ATTACHMENTS At tachment Title 1 Test of Tufline Valves-with Xomox-7 Tria Conducted by the Nuclear Science Center of Texas A&M University for the Xomox Corporation, February 1970 (excerpts) \\ O w +, ,,,r n. --~, m- ,.w, n r -,, -,. -----,w

.~ SWEC Supplement No. 1 Revision i h MEQ File No. 091-01/Rev. 2 ENGINEERING ANALYSIS ENVIRONMENTAL QUALIFICATION OF MECHANICAL EQUIPMENT

SUMMARY

1. SCOPE The following Xomox plug valves are evaluated in this data package: 2IAC*MOV133 2CES*MOV100A and B 2. IMPELL FINDINGS The above valves are located in areas where the postulated 40 year plus accident radiation dose exceeds the equipment qualification dose. Additionally, valve 2IAC*MOV133 is not qualified for the pos tulat'ed accident temperature. 3. 'SWEC CONCLUSIONS Valve 2IAc*MOV133 is qualified for the radiation dose and for the postulated accident temperature. Valves 2CHS*100A and B are qualified because (1) they are not required for a LOCA, (2) they are not required to be internally leak-tight and (3) external leakage (seepage) will be controlled by normal maintenance adjustment or replacement as required. 1 O Page 4 of 9 i 1 =

EAS-1 Revision 1 ^ SWEC Supplement No. 1 MEQ File No. 091-01/Rev. 2 J ENCINEERING ANALYSIS SHEET EQUIPMENT: PLUG VALVE MARK NO.: 2IAC*MOV133 VENDOR / MANUFACTURER: ATWOOD MORRILL MODEL: 166-BW SYSTEM: IAC - INSTRUMENT AIR CONTAINMENT 1. Equipment Function: Instrument air containment isolation valve. 2. Non-Metallic Sub-Components Requiring Engineering Analysis: Valve ultra high molecular, weight polyethylene (UHMWP) trim materials (i.e., sleeve, diaphragm and delta ring). 3. Sub-Component Function: Parts comprise valve body to plug seating surface and shaft seals. 4. IMPELL Findinas: Valve 2IAC*MOV133 is qualified for a temperature of 225'F and a radiation dose of 1 x 108 rads. This valve is located in the Reactor Containment where the accident temperature is 369'F and the postulated 40 year plus accident radiation dose is 2x 108 rads. Therefore, the valve is not qualified. 5. SWEC Evaluation: SWEC has performed location specific calculations (ref.: SWEC Calc. Nos. 12241-UR(B)-071-0, 12241-UR(B)-176-2 and 12241-UR(B)-149-0 which show the actual environmental dose to be 2 x 107 rads. A thermal transient analysis calculation (12241-PH-153-0) has been performed concluding that 2 1/2 inches of calcium silicate insulation will ensure that valve internals g remain below 220*F. E&DCR No. 2PS-4649 has been authorized to add the required 2 1/2 inches of insulation to valve 2IAC*MOV133. Page 5 of 9 0 - -. + - --,..,,._,,.,n.. ,n..y

EAS-1 Revision 1 O SWEC Supplement No. 1 MEQ File No. 091-01/Rev. 2 6. SWEC

Conclusions:

The valve is qualified for the radiation exposure based on the calculated location specific dose being less than the material qualification done. Based upon the addition of insulation the valve is now qualified to its' temperature environment. 7. Maintenance: No special MZQ requirements. O i l l 1 Page 6 of 9 i ~,

O EAS-2 Revision 0 SWEC Supplement No. 1 MEQ File No. 091-01/Rav. 2 ENGINEERING ANALYSIS SHEET 1 EQUIPMENT: PLUG VALVES MARK NOS.: 2CHS*MOV100A and B VENDOR / MANUFACTURER: ATWOOD-MORRILL MODEL: 1366BW SYSTEM: CHS - CHEMICAL & VOLUME CONTROL 1. Equipment Function: These valves are located in the Reactor Coolant letdown lines from the Non-Regenerative Heat Exchanger (2CHS*E22) to (1) the 1 Domineralizers (valve.2CHS*MOV100A) and (2) the Boron Recovery System (valve 2CHS*MOV100B). These valves are provided to divert letdown flow when going to cold shutdown following the loss of of f site power. 2. Non-Metallic Sub-Components Requiring Engineering Analysis Valve Xomox-7 trim materials (i.e., sleeve, diaphragm and delta ring). 3. Sub-Component Function: Parts comprise valve body to plug seating surface and shaft seals. 4. IMPELL Findinas: Valves 2CHS*MOV100A and B are qualified for a radiation dose of 7 x 106 rads. They are located in the Auxiliary Building where the postulated 40 year plus accident radiation dose is 1 x 107 rads. Therefore, the valves are not qualified. O ~ Page 7 of 9 j

i 4 EAS-2 Revision 0 SWEC Supplement No. 1 MEQ File No. 091-01/Rav. 2 5. SWEC Evaluation: Valves 2CES*MOV100A (normally open) and 1005 (normally closed) are required to close and open, respectively, to divert the normal Reactor Coolant Letdown flow out of the Non-Regenerative Heat Exchanger (2CHS*E22) from the Domineralizers to the Boron Recovery System when going to cold shutdown af ter a loss of off-site power anticipated operating occurance. Since both valves are provided for diverting purposes, they are not required to be absolutely leak-tight internally; but, must remain operable for the above occurance. These valves are not required to operate following a LOCA. SWEC has performed location specific radiation calculations (ref.: SWEC Cale Nos.12241-UR(B)-148-2,12241-UR(B)-154-2 and O 12241-UR(B)-377-0) which show the following rad doses for the above valves *: External Internal i Normal 0.1 x 107 rads 0.3 x 107 rads (40 year) (Gamma) (Gamma) 7 1.2 x 10 rads (Beta) 0.4 x 107 Accident rads Not Applicable (401.5 Days) (Gamma)

  • These values are location specific and include internal radiation sources so they differ from the radiation doses previously reported in 2BVM-119 (40 year normal of 1 x 106 rads, 40 year normal plus accident of 1 x 107 rads). is ar. abstract and data sheet from a test conducted for Xoaox Corporation which shows how Tufline plug valves with Xoaox-7 tria material responded, in terms of operating torque and leakage, to various radiation doses up to 8 x 106 rads These results show that the valves remained operable (based on slightly decreasing torques with increasing radiation dose) and showed no leakage.

O Page 8 of 9 1

O EAS-2 Revision 0 SWEC Supplement No. 1 MEQ File No. 091-01/Rav. 2 The test dose of 8 x 106 rads represents 20 years of normal dose; therefore, since the valves were not tested to the leakage point, the qualified dose is at least 20 years. Since the total radiation dose of 1.6 x 107 rads occurs gradually over a 40 year period (4 x 105 rads / year), no rapid changes in material properties are expected as the accumulated dose exceeds the test verified qualification dose. Should internal leakage or external seepage occur, it would be detected and corrected by normal maintenance adjustment or replacement of parts as necessary before the safety function of these valves is impaired. 6. SWEC

Conclusions:

Valves 2CHS*MOV100A and B are qualified based on their (1) O not being required following a LOCA, (2) remaining operable for a loss of offsite power occurance and (3) not being required to be absolutely leak-tight (internal leakage and external seepage being handled by normal maintenance). 7. Maintenance: No special MEQ requirements. t I See IOC dated 3-18-87 l ~ O Page 9 of 9 l l

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b p cdk.em, Eahru lit 70 ABSTRACT Xomox Corporation contracted the Nuclear Science Center of Texas A&M University to provide a reactor irradiation program to study the radiation resistance of flurocarbon seals in stainless steel valves to determine if these valves would be suitable for application in nuclear power plants. The project consisted of experiment design and fabrication, dosimetry calibration, sample irradiation, and performance testing of each valve before and after irradiation. The valves were exposed to a maximum dose rate of 1 x 10' rada per hour of high energy gamma rays in five separate. tests. The final set of three Xomox stainless steel valves survived a total exposure of 8 million rad and exhibited no leaking during any part of the test. l Q MEQ Ea No. cal ol v.J Arr a m av A..I 'l4

1 O TEST V Valve No. 2 0 Mrad 3 Mrad 5 Mrad 7 Mrad 8 Mr.ad (Xomox-7 Materials) 2/12 2/13 2/13 2/13 2/16 Torque open 35 open 31 open 26 open 31 open 27 close 40 close 32 close 30 close 29 close 25 not not not not not leaking leaking leaking leaking leaking ~ Valve No. 3 0 Mrad 3 Mrad 5 Mrad 7 Mrad 8 Mrad 1 (Xomox-7 Materials) 2/12 2/13 2/13 2/13 2/16 open 42 open 33 open'31 open 26 open 28 close 42 close 32 close 30 close 31 close 31 not not not not not i leaking leaking leaking leaking leaking ~ l Valve No. 6 0 Mrad 3 Mrad 5 Mrad 7 Mrad 8 Mrad (Xomox-7 Materials) 2/13 2/13 2/13 2/13 2/16 open 45 open 41 open 40 open 42 open 43 close 40 close 40 close 38 close 44 elese 42 not not not not not leaking leaking leaking leaking leaking I g p v.s O A p

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