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Forwards Documentation Packages for Containment Purge Sys Containment Isolation Valves,Rhr Pumps & Pressurizer Porv,In Response to NRC 830303 Request,Per 840306-08 Onsite Audit of Environ Qualification of Mechanical Equipment
	ML20083M965
Person / Time
Site:	Catawba
Issue date:	04/16/1984
From:	Tucker H; DUKE POWER CO.
To:	Adensam E, Harold Denton; Office of Nuclear Reactor Regulation
References
	NUDOCS 8404180407
	Download: ML20083M965 (109)
	v • d • e

{{#Wiki_filter:( V ) e DUKE Powen GOMPANY 18.O. ISOX 33180 CIIAltLOTTE, N.C. 28242 II AL II. TUCKER Tzternosz vum enrenormt (704) 373~&531 ... m... -. " " April 16,1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414

Dear Mr. Denton:

On March 6-8, 1984 the NRC Staff and their consultants conducted an on-site audit of the environmental qualification of mechanical equipment at Catawba. As a follow-up to this audit and in response to question 9 of Ms. Elinor G. Adensam's letter of March 3,1983, please find attached documentation packages for three types of mechanical equipment. The cover sheet for each package notes the equipment name, manufacturer and model number, as well as accident and qualified environments and the qualification mandated replacement interval for each nonmetallic subcomponent. In addition, documentation references for the replacement interval and qualified. environment are identified, and the pertinent portions of the references are provided. It should be noted that the replacement interval is based on thermal and radiation degradation effects, and is derived from test data, industry experience, and/or manufacturer's recommendations. Inservice degradation is addressed through preventative maintenance and surveillance programs with equipment and component refurbishment and/or replacement based on known susceptibility to aging degradation. Additionally, these programs will be modified to incorporate, as necessary, information from EPRI research, NRC studies, NPRDS infonnation, IE Bulletins, and industry research and testing. Very truly yours, 98 OAdd Hal B. Tucker ROS/php Attachment cc:.(w/oattachment) I A Mr. James P. O'Reilly, Regional Administrator j I U. S. Nuclear Regulatory Commission f g )\\\\ Region II \\- 101 Marietta Street, NW, Suite 2900' Atlanta, Georgia 30303 8404180407 840416 PDR ADOCK 05000413-A PDR

Mr. Harold R. Denton, Director-April 16,1984 Page 2 cc: (w/oattachment) NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq. t Attorney.-at-Law P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 21351 Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 (w/ attachment) Mr. Richard Boborgen EG&G, Idaho 1520 Sawtelle Street P. 0. Box 1625 Idaho Falls, Idaho 83401 ,nw

4 CATAWBA NUCLEAR STATION MECHANICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION PROGRAM 3 ITEM SUBMITTAL A... CONTAINMENT PURGE SYSTEM CONTAl'NMENT ISOLATION VALVES B... RHR PUMPS C... PRESSURIZER POWER OPERATED RELIEF VALVES c, '\\,,l

CATAWBA NUCLEAR STATl0ft 4.: ENVIRONitENTAL QUALIFICATION CF SAFETY-RELATED MECHANICAL EQUIPMENT - 1. EQUIPMENT IDENTIFICATION: Containment Purce Ventilation System ~lVP) Containment Isolation Valves 2. MANUFACTURER: Fisher Control s. Inc. 3. MODEL OR ID NUMBER (S): 24" Type 9220 4 ACCIDENT ENVIRONMENT: PEAK TEMPERATURE: 240 DURATION AT PEAK: Continuous . RAD: 7.5 x 106 EXPOSED TO CONTAltlMENT VESSEL CHEMICAL SPRAY ENVIRONMENT (BORIC ACID & SODIUM HYDROXIDE SOLUTION): Yes 5. QUAllFIED ENVIRONMENT: MAT'l TEMP RAD ACCEPTABLE FOR SPRAY REPLACEMENT INTERVAL REFS. EPT 300 lx107 Yes. ~ N/A 1,2,3 (Parker E740-75) 6. COMt1ENTS: See Attachment 1 7.

REFERENCES:

1. Parker 0-Ring Fluid Compatability Chart 2. Fisher Nuclear, Selection Guide 4NSG4'

3. -Barbarin, R. " Selecting Elastomeric Seals for. Nuclear ~ Service,"

Power Engineering, 5680 (December,-1977) L.-

P O Summary of Environmental Qualification 24" Fisher Containment isolation Valves 1. Valve List (Units 1 & 2): VP1B VP4A VP88 VP11B VP15A VP2A VP68 VP9A VP12A VP16B VP3B VP7A VP10A VP13B 2. Operator Qualification: The valve pneumatic actuator contains several elastomers which are 2.1 not listed on the summary sheet. These elastomers act as piston seals and their failure would not affect the safety function of the valve actuator assembly: i 2.1.1 in the event of an accident, air is vented from the pneumatic cylinder by a class 1E solenoid valve. 2.1.2 The valves are forced to the closed position by the action of a mechanical spring in the actuator. 2.1.3 Failure of the elastomer piston seals would not impede the action described above. &('"N 6 3 Required Operability: LOCA: The safety function of these valves is to isolate Containment 31 Atmosphere in the event of a radiation release inside Containment. The listed accident doses and temperature are for the LOCA. 32 Main Steam Line Break: These valves are not required for the Main Steam Line Break Accident. i 4 f f 4 L' Ce ___m. __m._._.... ..y,,.,,,,__

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$60Es9' March 1980 N Page 3 EUCLEAR SEICTION CUIDE piston Rine and Seal Rint *uterials for Class 600 Desttns ED. ET. tWD. AND TVT ' Cama Radistic'n Nzinum Service part Material Liste (Ead)* Temperature (*T) Design ID and EWD piston Ring Craphite suitable for 800 p' e Radiation Service 1 m 10' 450 seal ring Carbon-filled TTd 8 Optional mCW polyethylene 1 a 10 200 3 i Titon (except for use 1 a 10 400 y Standard seal ring construction for with eteam or hot water). Des 15n ET thru y 6 inches and all backup ring optional ethylene-1 a 10 300 Design Evf propylene I optional nitrile 1 x 10 200 1 x 10' (consult factory for d50 Spring-loaded seal Seal ring TTE with Eastelley C apring higher radiation lir_it) ring constructica e inch Design ET Backup ring 416 stainless steel Suitable for radiation 800 (e, (standard for 8 service

g" and optional for (not used with 7 toch e-1 thru 6 inch or larger port)

Design ET and all Design EVI Retaining ring (not 302 stainless steel suitable for radiation 1100 service used with 7 inch or larger port)

CAUTION - Evaluate the combined maximum radiation and namisr.ma service temperature of the application before specifying a material.

Trim Materials for Class 600 Desires YD and Ys Body /gonnet Maximum pressure Trio y,g,,pg,, g,g, g,,g gg,, Material Drop

Designaties

) Same es working ASE SA-351 Crade CA15 ACI CB-7CU Crede 17-ASTM A582 best-1- pressure la N1 Type 410 statalesa 4 pH stataless steel treated Type 416 ASE USC3 for Class steel with E1075 best-stataless steel treat precedure SA 216 600 Desige TD Crede WCB er YS A5E SA 479 Type 316 ACI CB-3CU Grade 17-A5 1 Sa-679 Type er ASME I stataless steet & pH stataless'eteel 316 staidless SA-217 300 pst 32 with 51075 heat-treet steel Crede WC1 precedure ASE SA 479 Type 316 ASE SA-351 Crede As s SA-479 Type CTBMelectre11:edi 316 stataless ASE 9 stainless steel SA-351 300 pet N3 stataleas steel steel Crede ctg 5 go (*

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ILimited to 300'T with seatubricating fluids such as superheated stene. The resulting IElectrettstes is a proprietary process of applying hard throeive elle, ee the base asterial. surface does set gall, peel, er flake. Trio Materials for Class 900 Desian ty* Bodylheanet fets. Material Designatten primary Valve plus pilot plog Case and Seat Elas A5ME 54 216 ASME $4 479 Type 316L ' ASME $s 166 !acesel' 600 ACI C3-7CU Crede Crade WCB er stainless steel with with sest and gasde hard. 17-4 pH stainless ASME SA-217 N1 seat and guide hard-surf ared with AW5 A5.13 steel with 31075 Grade WC9 surf aced with A5W AS.13 CoCr-A cabattachrome heat-treet procedure CaCr*A totalt*throme ASE SA 479 Type 316L A3ME 53-166 Incesel 600 ASME $3-164 heat- >t. stateless steel with with aus ase seide bari-treated laceaal 718 N-2 seat and guide hard* surf ace 6 with AW5 AS.13 ASE SA 351 f Ceede CTSM surf aced with AWS A5.13 CoCr-A r% lt-eheese t ( CeCr*A tehalt*throme -1

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I 1 Oi Selecting elastomeric seals o. for nuclear service %u I Compression set tests have. proved more reliable than M Rs ker (on f a i im ed tensile tests in the selection of elastomer compounds L6% Wins for use as seals in a nuclear environment By ROBER7 BARBARIN, Parker Hannifin Corp./ Seal Group 4 t in the early 1%0s, the primary test Typical applications for elastomeric tests are frequently omitted as con-used in setecting elastomers for seals in and around nuclear reactors temporary criteria for nuclear seal reactor seals was a tensite test con-include the static seals in pressur-compound selection.

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ducted on unstressed slabs of tt.e ized conduits containing radioactive -tf compounds of%r they had been sub-fluids, and the cynamic seals in Of the three major types of radiation M jected to irradiction. These standard structural hydraulic snubbers. om n[cle ss o, k tests had the unfortunate ability t c ns dere hazard to elastomer seals that art g make compounds look very aopeat-Compre.,slon set ing to the nuclear engineer while Compression set may be defined as completely enclosed in conventional g completely faihng tne primary re-the partent by which a seat fails to metal grooves Alpha and beta rays q

y,,y stopped by thin metal
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quirements of seaf engineers. To-return to its original dimension after barriers. Gamma rays, however* day, a test has been developed compression, expresses as a per-VP which promises M satisfy tfie cent of its deflection. This Inss of ne nd c e ,e demands of bot,h engineers. This is a dimensional memory is due t 1 test to determine the compression changes in the elastomer's arrange-lative chan9es in the compounds -h set of seals which are simultaneous-ment and density of molecutar (see Table 1). ' {i j ly squeezed (as they would be when cross-links. As the change in cross-All elastomers tested to date have g installed) and irradiated (as they linking progresses, the seal will shown excessive compression set at 'i may be when in service) over gradually take on the shape of the 10' rads, yet a number of com- ~ prolonged periods. The new data confining groove and relax the force pounds showed acceptable com-ngt provide criteria by which com-that it exerts on the confining sur* pression set at 10' rads of gamrna unn I pounds may be selec'ed for long faces. C0"' life, normally requiring eplacement radiation dosage. incri only durisig conservat' e'y sched-Since 155 normally occurs before Therefore, no elastomer known to-reae x uled five-year reactor merhauls. tensile property changes, the tensile day should be considered for Tabt .h elas- !b Table 1. Effects of gamma radiation en the principal properties of elastomeric compounds most often considered on 5 p for seats in and around nuclear reactorr. Compression set tests were conducted at room temperature and 25% j; deflection, for the number of days notej, while under radiation from cobak Stnps in air, g d Bass - M,j Generse or Radiation Hardness in Tensile Elongation Mceulus in Tear Compression Set Ten (Co bW Base Polymer Dosage in Pts on Shore Strench in in % @ Psi @ 100% Strength Days CS in % of .N, o Jf - (No ICompound . Rads "A" Scafe Psi @ Break Break Stretch in Ib/in. Deflec-Onginal Polg -i (Pts Change) (% Change) (% Change) (% Change) (% Change) ted Deflection (P4( Q l Sihcone Original 69 807 117 668 63 93 7.6

j (5455 70) 107 72 (+3) 733(-9) 89 (-24) 63(0) 93 31.4 q

108 85 (+16) 93 90.5 Polg Sihcone Or inal 66 1010 149 695 70 93 3.8 (P64 i ?. (S604 70) 10 69 (+3) 1020 (+1) 129 (-13) 833 (+25) ~62 (-11) 93 20.0 JM 108 85 (+19) 939 E7) 31 (-79) 29 (-59) 93 92.4 rJ Ethylene Original 78 1450 213 689 164 93 16.2 Eth-d Jp lll Propylene 10e 78 (0) 1220(-16) 176 (-17) 740 (+7) 148 (-10) 93 46.6 Prog (E515-80) 108 84 (+6) 1030(-29) 79 (-63) 71 (-57) 93 96.2 (E7o f-Ethylene Original 70 2080 233 554 174 93 6.7 ), il Propy'e 107 73 (+3) 2140 (+3) 194 (-17) 808 !,+46) 153 (-0) 93 28.6 Eth! l (E740- ) 108 79 (+9) 1700t-18) 96 (-691 70 (-60) 93 90.5 Pror i ' l Fluorocarbon Orpnal 75 1510 190 634 128 93 14.7 (E6' ~ (V747 75) 10 76 (+ 1) 1580(45) 130 (-32) 1120 677) 87 (-32) 93 66.7 l l I 108 _88 P15) 1180 (-22) 29(-85i 82 (-36) 93 93.3 Eth; ~ i 1 l O Und 66 ' 3560 582 342 306 56 17.1 Pror Polyurethane 10f l j (P642 701 67 (+$1 3570 (0) 491 (-16) 444 (+30) 374 (+22) 56 55.2 (E5c 108 66(0) 1420(-60) 201 (-65) 146 (-52) 56 91.4 Fluoro'- Or Mal 53 1050 180 520 72 128 13.3 Etht ~ 128 67.6 Pro f 4' silicote 10 721+4) ' ' 66G (-36) 97 i-46) (E6c J, (L677 70) 108 ' 84 i+16) 128 97.1 l ~ j , 54 powra run=rramentsea-si se-li .-_m

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f applications where 10' rads dosage ties after exposure to 10' rads. At not be recommended because they will be exceeded between scheduled this cosafe, two silicones, Two all tested out at marginal or ex-l overhauls. Etiiles ' arid'orie~ ethylene propylene cessive compression set. The results Q Table 1 documents several com-comp u Gxh'iFit acceptable _ cont-for polyurethane are particularly p5Wnds frequentjy conside7e~d for pressi n set. A second ethylene revealing; th's tensile, tear and nuclear halsThowing their original pr pylene compound, as well as rnodulus tests were either un-properties ~ arid IN5se same proper-- polyurethane, polyacrylate, fluoro-changed or actually improved by 10' carbon, and fluorosilicone, would rads, but the compression set rose from approximately 17% to over 55%. l Temperatures and fluids Service temperatures and/or fluids ymww,Mr?7/ W#$ "WA d. T*M $*11l .d..d} W f' $$M:OTIAi 5 ~ h ~ o p 7 W F ' N *,* often degrade an elartomer faster f and more severely than gamma f d " 7"i' "'"' '*d ' Y W con-W-D bg S

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, M1.M 'M M' effects of gamma radiatiori without '[] % Compression Set = C X100 fluid or temperature influences, D Table 2 shows the effects of fluids Jc and temperatures frequently en-countered in nuclear reactor en, vironments but without the gamma _Y radiation. It is interesting to note l(CS=10% 3~- that the polyurethane degradation .7 documented in Table 2 was the { CS=30% l w g, _j_lCS=60%lj result of temperature, but that it 'to-(__ -_L, %, j j would doubtless have been at-d tributed to radiation if it had oc-curred in a reactor, sve SEALING FORCE VS COMPRESSION SET The combined effects of radiation, ' CI temperature and fluid are seldom a ) l gure 1. Compression set (the percentage of initial deflection which is __ simple addition of their individual effects, but are synergistic. How-na unrecovered when a seal is released) directly affects the force that a ever, knowledge of all three char- ,e compression seal can maintain on its sealmg lines. This factor, which is acteristics for each compound will increased by radiation. is a prime criterion for the selection of seals for help in the selection of the best reactors. o, compounds for testing. at Tatne 2. Effects cf fli/d immersion in principal reactor fluids on polyurethane and othyfene propylene elastomers considered for seals in and around nuclear reactors. Note severe effects of temperature excursions on properties of polyurethane compounds compared to the properties of most ethylene propylenes. Generic or immersion Test Fluid Hardness m Tensile Elongation Modulus in Volume Compression Base Polymer immersed 3 hrs @ 340F Pts on Shore Strength in in % @ Psi O 100% Change Set in % of "i ' (Compound + 3 hrs @ 320F "A" Scale Psi @ Break Break Stretch in % Original _No ) + 18 hrs @ 250F (Pt s Chance) (% Chanoa) (% Ch3non) (% Chance) Opflectinn $q Polyurethane Origina1 properties 95 7240 470 1590 (P4611) GE SF 96 Silicone (200 c/s) 89 (-6) 4250 (-41) 537 (+14) 1370 (-14) -0.8 119.2 9 GE SF1154 Silicone 89 (-6) 3650 (-50) 550 (+17) 1400 (-12) -0.3 cancelled Water 89 (-6) 4680(-35) 576 (+23) 1180 (-26) +2.3 96.5 Polyurethane Original properties 66 3780 699 350 (P642 70) GE SF 96 Silicone (200 c/s) Deteriorated - 1.7 cancelled GE SF1154 Silicone Deteriorated- -2.2 cancelled Water Deteriorated Ethylene Original properties 73 2390 177 991 ? Prepylene GE SF 96 Silicone (200 c/s) 73 (0) 2800 (+17) 207 (+17) 865 (-13) - 1.5 19.9 (E740-75) GE SF1154 Silicone 70 (-3) 2660 (+11) 198 (+12) 800 (-19). +3 0 17.8 Water 74 (+1) 2600 (+9) 182 (+3) 873 (-12) 0.0 14.4 Ethylene Original propertees 88 2330 146 1230 Propylene G E SF 96 Silicone (200 c/s) 91 (+3) 2330 (0) 146 (0) 1500 (+22) -2.5 44.9 (E652-90)

GE SF1154 Silicone 89 (+1) 2430 (+4) 143 (-2) 1490 (+21)

+0.4 cancelled Water 90 (+2) 2450 (+5) 145 (-1) 1430 (+ 16) - 1.0 42.0 'thyler.e Original properties 61 1450 273 279 { I: viere GE SF 96 Silicone (200 c/s) 61 (0) 1680 (+16) 317 (+16) 296 (+6) - 4.5 29.6 M9 65) GE SF1154 Silicone 60 (- 1) 1520 (+5) 279 (+2) 290 (+4) - 2.1 28.4 f o Water 61(0) 1590 (+10) 298 (+9) 276 (-1) - 0.1 29 8 , Ethylene Original properties 74 1610 239 563

Propylene GE SF 96 Silicone (200 c/s) 72 (-2) 1350 (-16) 209 (-13) 578 (+3)

- 3.4 25.4 m . (E69215) GE SF1154 Silicone 72 (-2) 1620 (+1) 219 (-8) 549 (-2) +0.8 30.5 . Water 73 (-1) 1100 (-32) 171(-28) 545 (-3) +0.2 16 7 ,pr -

(, I f ELASTOMERIC SEALS .; ili S n; L: ,...l. .l A O' I Q,

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LOW SET I HIGH. TENSILE O. SPRING I POLYURETHANE u i 1 } ..1 BODY - - - - ~ - ' - ' - - - - ^,-' B-) h.l' ar l .( m...--...... in Figure 2. Excenent tensite, tear and modufus properties of polyurethene under radiation may be pres orf by a desigti which compensates for poor compression set under radiation. An O-ring with supenor yh( compression set can be used as a spring to energue a polyurethane seat body with superior tensile l gig j. proosmes. switching to the E740 75 ethylene (I l T Base polymers vs verlations terials containing fluorine or propylene for reactor service. p, 11 can be very misleading to escribe chlorine. Even if the fluid is com-5;, either fluid, temperature or radiation patible, and the rad,ation tolerance Work to overhaut periods ty' .? resistant properties to a generic can be acceptad at 10' rads, such Compounds that are recommended (- class of elastomers Variations in specifications as the AEC's FIOT for service as seats in reactor en- '0 compounding within the generic M11-IT may prchibit their use. vironments should have ample re-class can cause wide differences in Polyurethane takes a ramer high maining life at regularly scheduled ci d properties. Early tests of nitriles, for comprassion set in radiation even overhaul intervals to permit routine U 'fI example, discouraged their use in thougie its unstressed physical reptr-.ement without stretching their projected life. Many engineers who reactor environments for many properties hold up well at room tem- - N.f inquire about seals ask for 20 to 40 { )1 years. However, later tests of other pye sa P ef 9 years of service even though shut-II formulations showed that nitrile - their compression set properties or other compression type seals. It down and overhaulis scheduled at$- a were among the best when sub-probably would serve well in an O-or 10-year intervals. er jected to gamma radiation. ring energized lip seaf, however, if Designers working with elastomenc c the O-ring is radiation-resistant (see seals must leam to work to the over-s m.3 Ethylene propylene is a case in Figure 2), or in lip type seals that are haul periods and not to the reactor p M point. The standard Parker E515-80 activated entirely by continuous compound (see Tables 1 and 2) de-life. Even then, it is important to test fluid pressure. elastomers undar the combined de-veloped nearly twice the compres-s d.. ? 4 sion set and lost sigNficantly more While polyurethane compounds are gr a n fades aWpated W tensile and tear strength than E740-not generally recommended for use each application to earn a high con- .Q {t .5; 75-another ethylene propylene in water fluids,it should be pointed ey facW. r{ compound. The E740-75 material out that the rapid' deter! oration of 17 ; has compression set charactenstics the P4611 and P642-70 compounds No blanket recommendation can J y; > . gimi.larjo the sihcones and nitriies repcrted b Table 2 was due pri-logically be made for the one best ap o seal compound for nuclear reacto s tested and also has much better marily to temperature, or non-nuclear applications. While -} resistance.than the latter to water Nitrile compounds

resistance to the E740-75 ethylene propylene e

- ;.f and silicone fluids commonly use_d gamma radiation varies greatly, de-compouno exnioits the best com .4% i i .W in_LtaciQII - pending on the specific formu-Sination of radiation, fluTd and tem-lation. Thus far N674-70 and N741-pTr~ature tolerance ol'all' tKe iiri6lii i ,-. g Silicones are deceptive in that they show excellent compression set 75 are unique in their ability to comencers Yor reactor sea %,.even S ,'/. characteristics under radiation, Nt tolerate 10' rads with lit!!e cor.. pres-Eexcellent compound should be

-- A.

show poor resistance to water and slon set. These two tormulations, evaluated under the combined con- , g-. ,[%. the silicor9 fluids. This severely therefore, may become quite useful ditions for the specific application. limits thr.r usefulness in reactors. In some nucleer applications. Even Tensile tests alone cannot predict these formulations, however, could elastomer's. response to radiation 4 3g Fluort, elastomers (fluorocarbons - not be recernmended for long-term environments. This may not only ) .Y and fluorosilicones) have long been use it the seated fluid were hot air or lead away from the optimum mate-equated by many engineers with o er critical fluid / temperature com-. rial, but may lead to a compound 3 40 1- the best available" primarily that develops excessive compres-8' sien set early in its exposure to gam-g because of their outstanding tem-3 h. perature range. Not only do test Polyacrytales are like polyurethenes END results contradict this optimism, ire thst they have a low toirrance for ma radiation. a with neither recommended for more water, especially at higher tempera-tures, while being quite compatible than 10' reds, but fluoroelastomers with silicone fluids up to 350 F.Their f>. steam. Also, some reactor specifi-compression set properties under.$ $ M %'MD*'#d ' y tend to degrade rapidly in water or .f cations forbid the use of any ma-radiation usually would suggest ti O co-u emco m 1p .o f k n - w w m- :: m = = -- m- - ~ t m--.-- v ---- - - - -- -~

CATAWBA NUCLEAR STATION ENVIRONMEllTAL QUALIFICATION OF SAFETY-RELATED MECHANICAL EQUIPMENT ,~ 1. EQUIPMENT IDENTIFICATION: Residual Heat Removal Pumps IA, 1B 2. MANUFACTURER: Ingersoll Rand through Westinghouse NSSS 3. MODEL OR ID NUMBER (S): 8 x 20 WDF 4. ACCIDENT ENVIRONMENT: PEAK TEMPERATURE: 212 DURATION AT PEAK: 2' hrs. 6 BAD: 1,8 x 10 EXPOSED TO CONTAINMENT VESSEL CHEMICAL SPRAY ENVIRONMENT (BORIC ACID & SODIUM HYDROXIDE SOLUTION): No 5. QUALIFIED ENVIRONMENT: MAT'l TEMP RAD ACCEPTABLE FOR SPRAY REPLACEMENT litTERVAL REFS. EPT 300oF 1.8xid6 N/A N/A 1,2,3 6 COMitENTS : Non-metallics listed are parts of Durametallic Type HPTO Mechanical seal. Pump is close-coupled to Motor. There are no bearings in the pump. Mechanical seal is cooled by a water-to water seal injection cooler to ASME Ill; therefore, seal is not exposed to the external temperature environment. Circulation is by shaf t driven pumping ring. 7.

REFERENCES:

1. Durametallic Corporation Publicati sn SD-1265 1 2. Durametallic Corporation Publication 50-1256 3. EPRI NP-2129 " Radiation Effects on Organic Materials in Nuclear Plants" November 1981, pg. 3-24 9.

a i \\ l r-- \\s)a ~ RESIDUAL HEAT REMOVAL PUMPS Additional Comments 1. Radiation Qualification: Reference 3 provides test results for several formulations of ethylene propylene and ethylene propylene terpolymer. In each case, the formulations exhibited acceptable performance at radiation equipment. ~ 40 year plus one year LOCA dose for this levels in excess of the 1.8 x 106 2. Reference 2 demonstrates the resistance of the EPT o-rings to high tempera-ture use, as the mechanism for seal failure was demonstrated to be wear of the seal faces. The EPT o-rings remained sound throughout the testing. ( / s_- (. i wa m..

( EHR_ Pm s - T24-c.,_ # / w _g hwd O DURAMETALLIC CORPORATION Kalamazoo, Michigan so.ites 1 January 197 DsR 25 DURA SEAL @ RECOMMENDATIONS FOR NUCLEAR POWER PLANTS INTRODUCTION l I in the early 1960's Durametallic recognized the growing importance of nuclear power for generating electricity. The complexity of safety considerations indigenous to this new technology, suggested that mechanical seals would take on new significance in the power industry. In keeping with the reputation for building engineered seals of unsurpassed quality, the decision was made to pursue this new and challenging market. Since that time, Durametaffic has completed a survey of the market potential, concluded a study of the effects of radiation on materials and conducted qualification tests for two major reactor dasigners. Our performance under test conditions simulating those anticipated during normal opera-t!on and emergency reactor cool down has won unqualified approval of the Dura Seal for use in nuclear power plant primary, auxiliary and emergency system pumps. To substantiate this claim, we are proud to report that as of July 1,1978, Durametallic seats have been selected for use in 119 domestic and 22 foreign plants... The fo!!owing brief review of reactor systems and the pumping services encountered in each of the systems willlead to a better understanding of the conditions imposed on mechanical seats for nuclear power plant liquid handling equipment. A description of the Dura Seals used in each service b bduded. REACTOR SYSTEMS In the Boiling Water Reactor (BWR) system, Fig.1, water in the reactor is evaporated to steam 1 I and pasted to the turbines, condensers, feed water heaters and then returned to the reactor by a feed pump. The steam from the reactor is saturated and the pressure is maintained at about 1,000 { PSIG. A recirculation pump recirculates the water in the reactor to keep the metal temperature of the reactor core elements at poper values. General Electric Company is the supplier and licensor of. BWR systems. w ~,e Coprght 1979 Durametene Carpershon a,b. (Pape et9J =. e. 'ftM__~_p.***.e,ye_opg_-+=-__-__r,.*f_y_-*_=__e +.m*- ~-=*-*f<+--= - --++- e + g, = =e- =* e. e, p-a e e *** 4 .,a es as**e- =e e p, w er pa==, *

-,,a .:.a.L d x.,. .:.. :.. x,. ....2 .1 i ..I T b ) s pu% d-bco o y C ~ jF u 2 um. g n-4,,3.,;ag. _r t_ neacroa atacToa racoeuur C,gsatt ar,cja,c,utarc= ~ FIG. I actLING WATER REACTOR ( SWR) SYSTEM in the Prossurleed Water Reactor (PWR) system, Fig. 2, borated cooling water la pumped through the reactor cere to remove heat and transfer it to the steam generators. Steam conditions, saturated at about 1,0C/) PSIG, are similar to those of the BWR, but the primary water must be at a higher temperature than tM steam to make the heat transfer equipment economical and to prevent boiling in the primary loop. Pressures of 2200 PSIG, are maintained by steam pressure in a pressurizer connected to the primary coolant loop. The secondary loop water and steam do not pass through the reactor and, therefore, should not become radioactively contaminated. Babcock & Wilcox Co., Combustion Engineering, Inc., and Westinghouse Electric Corporation Manufacture and F (.) License PWR Systems. d A m u.et. A ,u.., ~ sitau # %200 PSl4 9 GENERaf R R I l dopop ,y M. p' con un n esacutatins rume r } 4 FttowaTER 1 I MEaTEng {' 'H \\ 71t) strau sentaaron co..En,s,yg v reso euer cou AEaCTom Peruany coolant PuuP FIG. I PREssuRlIED WATER REACTOR (PWR) SYSTEM i The Canadian Candu" reactor system, Fig. 3 employs natural uranium as fuel rather than enriched uranium that is used in the BWR and PWR systems. The fuelis set in tubes that form part of the primary coolant system pressure boundary. The tubes are spaced in a large vessel containing I heavy water as a moderator. In this system, heat transfer is from fuel rods to the heavy water coolant j and then to light water in steam generators where boiling occurs. Steam conditions are simiar to the I BWR and PWR systems but the primary coolant is at lower temperatures. h A fourth type of reactor, the gas cooled reactor, uses heGum gas as the primary coolant through j tt e reactor core and steam generators, relying on large compressors to circulate the heEum gas. dy s 2, : 2 ~ v

P I, S.. l L, 5ftau g,,,J L, -*= CEN(nat0R N 2 ~ ~ I N E, M G,*',~s'c"H t_5

M GEN.

G i tl G - k l C64C TeNG PUuP J L., =%, )) 1:c-:-: 2-:

, 9 i

g C U aTEns f r ^ 1 IN-[P55-M FEEDWattR staCTon / MCATER otagnaron CONDENSATE ouwP rgga T ANit pgup FIG. s ME AVV WATER *CANDu" RE ACTOR SYSTEM Contelnment Vessel The containment vesselis a pressure resistant concrete or metal structure completely surround-ing the reactor, stea?n generators and coolant or recirculation pumps. Its purpose is to prevent escape of radioactivity if pressure boundaries of vessels or piping should fail. The high cost of con-tainment vessels make their size a factor, compelling designers to position equipment carefully and include only what is absolutely necessary. Inaccessibility of the containment vesselinterior during operation is another reason for locating equipment outside whenever possible and emphasizing the reliability of what must go inside. Radioactivity hazards directly influence equipment design. Materials can deteriorate under ex-C)f posure to radioactivity during the 40. year life assumed for most plants. Elastomers and gasket J materials used in mechanical seals are of ten affected and must be carefully selected, in some cases, no suitable material willlast for 40 years, thereby requiring provisions for regular replacement. Prlmery Coolant / Recirculation Pumps These large pumps circulate the cooling water through the reactor. They are the largest pumps in the plant and are normally vertical to conserve space in the containment vessel. The sealing of these pumps has required considerable development and, in general, the pump manufacturers make their own seats. Although Durametattic has not supplied mechanical seals for this service, Durametallic performed a design overview undc. contract with one of the major primary coolant pump manufacturers. Feed Pumps The steam generator feed pump in a PWR and the reactor feed pump in a BWR perform the same function as a boiler feed pump in a fossil. fuel plant; they return the condensate from the feed water heaters to the reactor or steam generators. However, rather than using conventional multistage bar-ret type boiler feed pu:rps, the feed pumps for nuclear plants are single stage pumps with double suction impe!!ers and twin volute or diffuser type casings. The operating speeds for these p' umps are as high as 6,200 RPM and the stuffing boxes are subject to 300 PSIG pressure and 374* F. temperature. Most feed pumps installed to date ublize controlled leakage throttle bushings for stuff-ing box sealing which require a constant flow of gland sealing water. Durametallic is currently working in conjunction with a major manufacturer of these pumps in the development of a suitable high speed high pressure mechanical seal desi2n for,this service. y Feed pumpE, in Candu reactor systems are fitted with mechanical seals because of the expense of heavy water that would be needed to flush controlled leakage bushings. Cartridge Type HPTO Dura Seals, per Fig. 4, have been supplied for this service. Fies. t. a. a a are euerewed som Power.*% door Fue Hanene Eeement." May 19T4 /o ~ a.q . m o. , -,w m..L -- __m .a .m._~.. m, ]

~ ,. r .' w I 'f Xv / N_g, V x1 O O i x 1 i l/ 'W lllQ a /, / /^ fn! O fm { FIG. 4 CARTRIDGE TYPE 'HPTo' DuR A sE AL. CANDu REACTOR FEED PUWP Control Rod Drive Pumps lEWR) in the BWR system, a hydraulic system is used to drive the control rods in the reactor requiring a pump to circulate the hydraulic medium. A multistage horizontal pump is used for this service with a design pressure of 2,000 PSIG. Cartridge Type PTO Dura Seals. per Fig 5. are used. Stuffing box pressures do not exceed 300 PSIG and temperatures do not exceed 1400F. \\ N Y& U. / medb: j> k ' ins \\ \\'%- , II MM x x^ 5 h I ) FIG. s CARTRlDGE TYPE 'PTo' DUR A SE AL. CONTROL R00 DRIVE PUMP SAFETY RELATED PUMPS A key to understanding pumps in a nuclear plant is the Safety Classification as ind cated in Sec-tion lit of the ASME Boiler and Pressure Vessel Code. Primary coolant pumps are in Class 1 and are subject to the strictest requirements in design, manufacture and quality assurance. The plant designers' evaluation of the relation of a pump to the plant's safety determines the safety class of the pump. There are numerous safety related pumps in the nuclear power plar,t system, most of which l fall within Class 2 with others in the lower Class 3. Charging Pumpo IPWR) In the PWR system, a bypass flow from the primary coolar.! loop is passed through heat ex. (, W s f.~, changers and domineralizers which treat and clean the water. A high pressure multistage barTel type charging pump, capable of overcoming full prirnary loop pressure, takes the treated water from a v '-~ volume control tank and delivers it to the primary coolant loop, the pressurizer or to the primary coolant pump seats. The charging pumps are also used to fill the pnmary coolant system at startup. In acme installations the charging pump is part of the Safety !niection systems and performs dual rotos. k W " ** . a., mn com. n es .--y.~*. -w--.-~-.3-~~ j e.

q-- ~ . :.. s...

w. a _.,-

A o These charging pumps operate at speeds as high as 4.850 RPM with the stuffing boxes subjected br to pressures up to 1,500 PSIG. Type HPTO Dura Seals as shown in Fig. 6 have been supplied for V this service. A smaller boric ac.d t,harge pump. usually a reciprocating pump, is used to maintain the boric acid concentration in the primary coolant loop. These reciprocating pumps are fitted with spring-lo$ided rod packing. Durameta!!ic furnishes the spring assembly. j i e. // y / ~ ,M _m l L ,h H jil* N N S N I a ( d t x x,/r / / s e s I'n ty i N fri l f FIG. 6 CARTRIDGE TYPE *H PTo" DuR A SEAL w/ CIRCULATING RING & FLOATING THROTTLE BUSHING. CH ARGli4G PUMP 'A Clenn.up Recirculation Pumps (EWM) In the BWR system, the feed pump performs the function of a charge pump. However, water clean up is necessary and is also done by a bypass flow from the primary coolant loop. Clean-up ,, y recirculation pumps are used to inject the cleaned demineralized water back into the primary system. In plants using high pressure demineralizers, the pump are only required to produce heads necessary to overcome system losses. These pumps are single stage, overhung impeller designs with the stuffing boxes subjected to 1050 PSIG suction pressure and utilize Type HPTO Dura Seals as shown in Fig. 7. A Dura circulating ring and an external water cooled heat exchanger is used to control the stuffing box temperature. ~ i / / "%N i A / \\ F4 2z qx g h ) Y x u ) FIG. 7 TYPE

H P To* DUR A S E AL W/ CIRCULATING RING.

f.LE AN - UP RECIRCUL ATION PUMP .i-f .,em ..m

.. ~...... - l-e, Reeldual Neat Removal Pumpa Both BWR and PWR plants have residual, heat removal systems which remove heat from the reactor core during shutdown and refueling. Both vertical and horizontal single stage pump designs (,) are used operating at 1800 or 3600 RPM. Although design pressures are below 500 PSIG, Type HPTO Dura S tals with circulating ring. as shown in Fig. 8 are used to withstand the high hydrostatic test pressure imposed on the pump. A floating throttle bushing is incorporated in the gland ring to control leakage in the event of a seal failure. This auxiliary device is available with any of the seal designs shown. r si r il .i L 1 l 5 s v i p T s E\\ T% NN \\\\ \\ \\ X u FIG.8 TYPE *HPTo* DUR A sE AL W/ CIR CUL ATIN G RING S FLOATING THROTTLE SusHING. REstDuAL HEAT REMOVAL PUMP Emergency Core Spray Pumps (SWR), Safety injection Pumps (PWR) and Standby Cooling Pumps (Candu) Emergency systems, activated in the event of a loss of coolant accident, pump water to the (,, reactor core to prevent fuel rod cladding damage. In the BWR system, emergency core spray pumps ~- perform this function while safety injection pumps perform similar tasks in the PWR system. High pressure core spray and safety injection pumps must be able to overcome the pressure in the reactor. Vertical and horizontal multistage pumps operating at 1800 or 3600 RPM are used. Although high discharge pressures are required suction pressures are low, below 100 PSIG, taking suction from the suppression pool or storage tanks. Here again, although stuffing box pressures are low, Type HPTO Dure Seals per Fig. 9 are used to withstand high hydrostatic test pressures. ~ 1l l II F I \\ [ t 1 4 i i m l l b. Tff g/ RETAsNINS PLATE p I sufMiN g {\\ \\ \\ \\ \\ \\ VY a s s u SNAFT 4 f gggggy ( gggggy ISOUNTl804 ROTARY UNIT -SEAL RINS FIS, 9 TY P E *HPTO' DUR A sE AL W/ FLoAtluo THROTTLE Susnins. p, w% O 3 - GFeee e et at ..7......... L__,, ._e*-.

(rk G d Reactor Core Isolation Pumps (SWM) and Contelnment Spray Pumps (pWR) A major accident would result in isolation of the reactor core from the plant condenser and from h] the feedwater flow. Should such isolation occur, the reactor would continue to generate steam. Reactor cc e isolation pumps in the BWR and containtrent sp*ay pumps in the PWR deliver water to the reactor head and cores from the suppression poos, storage tank or heat exchanger. Reactor core isolation pumps are horizontal multistage barrel type pumps operating at turbine speeds of about 4500 RPM delivering pressures up to 1500 PSIG. Section pressures and cor. responding stuffing box pressures are low, below 100 PSIG, requiring Type PTO Dura Seals, covered by Fig. 9. Containment spray pumps are single stage vertical pumps operating at 1800 RPM. Design pressures are 550 PSIG and Type PTO Dura Seals are used as above. Other Safety Related Pumps All of the safety related pumps covered above are generally Class 2 pumps. There are other safety related pumps falling in the Class 3 category; such as fuel pool cooling, flash tank, reactor, drain, etc., pumps which are single stage, overhung impeller, horizontal pump designs. Speeds are low,1800 and 3600 RPM, pressures are low,150 PSIG, and Type PTO Dura Seals per Fig. 9 are used. Radioactive Weste System Each nuclear power plant must have a rad waste system to remove and concentrate gas and li-quid wastes throughout the plant. The rad waste system contains any number of holding tanks, flash tanks and an ion exchange system. Several pumps are used in the system, most of which are single stage overhung impeller horizontal ANSI B 73.1 pump designs. Both single Type RO per Fig.10 and g 4 double Types RO per Fig.11 or CRO unbalanced Dura Seals are used for these low pressure ser-vices. I SEAutis Uculo pdLET y H S h x ., 2 5WM / \\ l FIG.10 INSIDE RO FIG.11 DOUBLE RO ARRANGEMENT MATERIALS 09r CONSTRUCTION Codes and standards set requirements for the design, manu%cture, installation and operation of nuclear equipment. Section ill of the ASME Boiler and Pressure Vessel Code govems the pressure boundaries of code stamped fluid handling equipment. Mechanical seats are specifically excluded from the requirements of the ASME Code. However, the mechanical seal gland ring is considered a j pressure boundary in most cases and is, therefore, covered by the Code. The gland ring, then, must be designed and manufactured in accordance with.he Code, be of an approved material, anc' be j covered by appropriate quality assurance. l The primary concem for radiation resistant materials in mechanical seals for nuclear services is the secondary seal elastomers. Table I covers the radiation and temperature limits of common secondary seal elastomers. Requirements for these elastomers other than radiation resistance are covered by Nuclear Regulatory Commission RDT Standard M11 17. Non-metallic Seal Materials." ~ ~9 .......m..-......_.,.....-..- + t .c....

J > -A h.

C, TABLEI RADIATION AND TEMPERATURE LIMITS OF SECONDARY SEAL MATERIALS y

~ RADIATION TEMP. RADIATION TEMP. MATERIAL

UMITs, UMITs.*

MATERIAL

UMITs, UMITs

RADS
F RADS
F Necerone 4 xi o' 90 Vrton 1s t o*

35o ) EPT 2x10' 350 Bune "N" 1st oa 225 Secone 1 1o' 225 Duraflon (PTFE) 5xio* 35o t EPR t u t o' 35o Glass Feed Durafton 5:1o* 45o

Temperature Imts shown are that for borc acus solutions.

Mecommended Afsferials for Dura Seals (See Fig. 9 for Nomenclature) Rotary Unit: Major Metal Parts: 316 Stainless Steel per ASTM A 276 or A 479 Springs, Pins, Set Screws: 20 Stainless Steel similar to ASTM B-473 ~ ~ Seal Ring: Tung Car 62 6 (6% Nickel Binder) Shatt Packing and Insert Mounting: EPT insert and Throttle Bushing: #5 Carbon Graphite Gland Ring and/or Retaining Plate: 316 Stainless Steel per ASME SA-479 (Bar), ASME SA-240 (Plate) or ASME SA 182 (Forging) NOTE: Customer must specify acceptable material and required non-destructive testing. Durametallic stocks ASME SA-479 (Bar). QUALITY ASSURANCE Suppliers of nuclear equipment must provide adequate documentation that the components are (- j;. suitable for their intended use and are designed and manufactured in accordance with applicable Codes and Standards. Quahfication testing under actual or simulated conditions are often times necessary in order to provide documentation that the components are suitable for intended use. Durametallic performed an extensive test program, the results of which are available upon request, as SD 1256 " Qualification Testing of Dura Seals for Nuclear Power Plant Services." Suppliers of nuclear components are also required to have an acceptable in house Quality Assurance Program. Such a program has been in effect at Durametallic Corp., Kalamazoo, Michigan ?, since 1965 and at Durametallic of Canada Ltd., St. Thomas, Ontario since 1976. Numerous quality assurance audits by OEM and user customers have been made resulting in complete approval. Copies of Durametallic Quality Control Manual are available upon request. Y (~'w. v;c i ~ s .s p. 7.. -

mv.. p (2_ R he. he h 7_. 3 -. s l ~ (Q_Y8J -Td 6l S LT KEL DURANETALLIC CORPORATION ato4 rectory street natamuoo.Hercgen 49003.U.S. A. TEST REPORT ON THE QUALIFICATION TESTING OF DURA SEALS FOR NUCLEAR POWER PLANT SERVICES The contents of this report ha.2 been compiled for the sole use of Durametallic customers, direct or indirect, who are engaged in providing services or equipment to users of nuclear reactors. Durametallic Corporation reserves the right to determine and make distribution of this report in part or in its entirety. .. Contents of this report may not be reproduced without the written consent of Durametallic Corporation. Q(3..) 1978 by Durametallic Corporation. All rights reserved. SD-1256 PrintedIn6SA 010974

~ i TABLE OF CONTENTS n PAGE INTRODUCTION i SECTION I: The Testing of Dura Seals in 2.5*, Borated Water I-1 Conclusions I-2 Test Seal 1-3 Test Equipment and Fluid I-3 Test Conditions I-4 Results I-4 Table I-1: -Sumary of Test Results I-9 i Table I-2: Number of Changes to Various Conditions for Multiple Cycle Tests 12 and 13 I-10 Figure I-1:.T,vpe "PT0" Test Seal with Bypass Flush I-11 Figure I-2: Type "HPT0" Test Seal with Bypass Flush I-11 i Figure I-3: Schematic of Test Setup I-12 Figure I-4: Steady State Condition Test Results I-13 Figure I-5: Moderate Cycling Condition Test Results I-14 ] Figure I-6: Multiple Cycling Condition Test Results I-15 SECTION II: The Testing of Dura Seals in 5*. Borated Water 11-1 Conclusions II-2 i Test Seal II-3 i Test Equipment and Fluid II-3 lI Test Conditions II-4 Results 11-4 Table II-1: Summary of Test Results II-10 i Table II-2: Number of Changes to Various Conditions for Multiple Cycle Test No. 12 II-11 4 Figure II-1: Type "PT0" Test Seal with Bypass Flush 11-12' j Figure II-2: Modified Type "HPT0" Test Seal with Bypass Flush 11-12 ~ Figure IF 3: Steady State Condition Test Results. II-13 i Figure II-4: Moderate Cycling Condition Test Results 11-14 l Figure II-5: Multiple Cycling Condition Test Results 11-15 i Figure II-6: Cycling Test Results Sil-Car 1 vs No. 5 Carbon II-16 SECTION III: The Testing of Dura Seals in 12% Borated Water III-1 Conclusions III-2 Test Seal III-3 Test Equipment and Fluid w ^III-3 Test Conditions III-4 Results III-4 Table III-1: Sumary of Test Results III-6 i Figure III-1: Type "R0" Test Seal Arranghment "A" III-7 Figure III-2: - Type "R0" Test Seal Arrangement "B" III-7 Figure III-3: Test Equipment III-8 .I k .. A *. ~;*. ~ **~ ** * .. L. $:~ I x ..u,--.-,-.-.-:r.--.----~::..- r-

TABLE OF CONTENTS Continued PAGE SECTION IV: The Testing of Type "HPT0" High Pressure Dura Seals for Boiling Water Reactor (BWR) " Cleanup Recirculation" ) Pump Service IV-1 Conclusions IV-2 Test Seal IV-3 Test Equipment and Fluid IV-3 Test Conditions IV-3 J Results IV-4 Table IV-1: Dynamic Test Results at 1000 PSIG and Room Temperature IV-7 Figure IV-1: Type "HPT0" Dura Seal with Rigid Insert Mounting Design IV-8 Figure IV-2: Type "HPT0" Dura Seal with Flexibly Mounted Insert Design IV-9 Figure IV-3: Schematic of Test Setup IV-10 Figure IV-4: Pressure Cycle Test Results IV-11 Figure IV-5: Temperature Cycle Test Results IV-12 i, 'l (h 68 ,.w a +- 1 I s e f f 1 4 ev l- - M-*="-~~~~"*"*****'*******"*******"

?. ~ :. ?.=... ......:... :. w..,. _..,. O Page i DURAMETALUC CORPORATidN mo4 rutory sunt M.I.ww.*hva escor.u.s. A. INTRODUCTION In the early 1960's Durametallic recognized the growing importance of nuclear power for generating electricity. The complexity of safety considera-tions indigenous to this new technology, suggested that mechanical seals would take on new significance in the power industry. In keeping with our reputation for building engineered seals of unsurpassed quality, the decision was made to pursue this new and challenging market. Since that time, Durametallic has completed a survey of the market potential, concluded a study on the effects of radiation on materials, and con-ducted qualification tests for two major reactor system designs. Our performance under test conditions simulating those anticipated during normal and emergency reactor cool-down has won unqualified approval of Dura Seals for use in nuclear power plant primary, auxiliary and emergency system pumps. To substantiate this claim, we are proud to announce that as of July 1,1978. Dura Seals have been selected for use in 119 domestic and 22 foreign plants. The purpose of this report is to convey the results of our nuclear test-ing program to the systems designer, pump manufacturer, or engineering contractor, who will find the information useful for projecting what can be expected from the Dura Seal when it is subjected to various environments. The report includes testing ennducted on 2.5% and 5% borated water which would be typically found in Pressurized Water Reactor (PWR) services such as Residual Heat Removal pumps. Containment Spray pumps Low Pressure and High Pressure Safety Injection pumps, etc. Borated water was chosen since this fluid imposes more severe conditions on seals than the ultra pure water used in Boiling

2 . +. :... .u.....,.. ',Page 11 n V-terReactor(BWR)or"Candu"HeavyWaterReactorsystems. These' tests were conducted without cooling at the request of reactor designers who wanted to svaluate the performance of uncooled seals for emergency core cooling system pumps. We are told that these systems would only be activated at elevated temperatures, should a break occur in the primary circuit resulting in the loss of reactor coolant. Although many nuclear designers currently inc'crarate provisions for cooling such emergency safeguard equipment, the seal must perform its function without cooling in the event of a simultaneous component cooling system failure. In addition, it has been suggested that some designers may actually prefer reduced seal life to the high cost of installing auxiliary cooling when there is assurante that uncooled seals will function satisfactorily through-cut the duration of the emergency reactor cool-down period. It has been further suggested that total system reliability is also enhanced if cooling components f ' susceptible to malfunction can be eliminated without adversly affecting the safety and efficiency of the system. One is not to conclude, however, that Durametallic r:comends the elimination of auxiliary cooling for hot water seals. To cool or not to cool is a decision left to the system's designer after reviewing the results of our tests. The report also includes two other test series; one on 12% borated water which is found in Charging pump services for Pres:;urized Water Reactors, and the other on high pressure Cleanup Recirculation, pump service found in Boiling Water Reactor systems. We trust that those readers involved in the " nuclear comunity" will find the contents of this report of both interest and value. Ak R. E. Battilana, Manager of Engineering [6

D. ) fQtTTEGN_=1NGCM DURAMETALLIC CORPORATION rio4 rectory sue.i u.. soc.M;chtgen 4sool.U.S. A. SECT 10N I THE TESTIllG OF DURA SEALS IN 2.5f; BORATED WATER FOR NUCLEAR POWER PLANT SERVICES Ref: Durametallic Corporation l Research Report No. 1209-A October 20, 1976 j t

Page I-I ^ THE TESTING OF DURA SEALS O. IN 2.5; BORATED WATER This report suninarizes the tescing accomplished by Durametallic Corporation on Dura Seals for use in Nuclear Power Plant pumps handling 2.5% borated water. The sumarized data, shown in Table I-1, represents over 4,100 hours of testing, simulating the most severe and adverse conditions that such seals might be subjected to during plant emergency conditions. All the tests that were conducted assume no external cooling was available. Only bypass flush-ing was used to cool and lubricate the seal faces even under the severe conditions of high temperature with little pressure above the corresponding vapor pressure. All tests were completely successful with no failures encountered during the entire test program. This series of tests is an update of the test program conducted by Durametallic Corporation in 1969. The 1969 report is still valid in that the basic conditions under which the seals are to operate have not changed appreciably since 1969. However, seal technology has progressed and present seal designs and materials may perfom better and withstand more severe conditions with less wear.. This latest series of tests show the projected wear life for each of the adverse conditions tested, including the condition of 150'F product temperature and 250. PSIG seal chamber pressure which was not in the 1969 test program. Of special significance are the moderate cycle and rapid cycle tests which severely test the ability of the seal to adapt to rapid changes in temperature and pressure and to detemine whether or not boric acid will immobilize or " hang-up" the seal. 6 b ~ 8T 888 SD 984PW# N w ea e e 6.. 46 m 9 p#' : * 't pe se,p ey er see a3 meepaWe WWSS

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~ Page 1-2 CONCLUSIONS 1. Type PTO Dura Seals in the design and materials of construction tested perfonned totally satisfactory in ~ distilled water containing 2.5% by weight boric acid under all conditions tested. 2. External cooling is not required. 3. Bypass flushing of the pump product from the discharge to the seal faces provides adequate cooling and lubrication. 4. The projected wear life of the seal faces when operated at various steady, stable conditions on a continuous basis were: CONDITIONS Projected Wear Life Product Temp., 'F Pressure Hours 150 V.P. + 6 ft. head 79,000 150 250 PSIG 40,400 300 V.P. + 6 ft. nead 3,800 350 450 PSIG 4,770 5. Wear increases when the conditions are cycled from one to another. However,' even after several product temperature and pressure cycles, seal wear was minimal and the seals could be returned to a normal condition and operate O. satisfactorily. Q 6. Seal leakage is essentially nil when the seals operate at any single condition on a continuous basis. 7. Seal leakage of a minor nature often occurs when changing from one condition to another. 8. Immobilization or seal " hang-up" from boric acid crystallization on the atmospheric side of the seal could not be made to occur from any combination of cycle changes and/or periodic minor leakage. The boric acid crystals appear to be dissolved and washed away from the seal area by any minor leakage that occured. e y U. J k _ _ ___.. m _.,.

N~- ...._..._.__.__.m.._._. ...w... Pag 2 I-3 TEST SEAL O. The seals tested were n' 2" shaf t size rctating at 3550 RPM and are shown schematically in Figs.1-2 and I-2. Figure I-1 is a PTO Dura Seal de' sign which was used for most of the testing. Figure I-2 is a modified PTO design having the insert supported against the gland in a manr.er similar to our HPTO high pressure Dura Seal series. The purpose of testing both designs was to indicate that either design performs equally ~well and could be substituted if the need should arise. The secondary seals were EPT terpolymer "0" rings in all instances. This compound is approved for use in the radiation enviroament anticipated for nuclear power plants where such seals are to be used. Other secondary seal materials; such as, Durafite, were not tested because an "0" ring is considered the most reliable and least expensive for this service. At the time of our first report (1969), no elastomer'was considered satisfactory, hence the choice of Durafite was mandatory. No secondary bushing seal was used with the test seals. In our prior testing it was found that such secondary seals,did not adversely effect operation or hangup characteristics of the seals. It is even possible that secondary seals may reduce any tendency to hangup the seal by retaining liquid leakage longer and, thereby, tending to wash away Sny boric acid crystal buildup more readily. Since a design without the secondary seal may present the more severe condition for the seal, it was decided not to include it in the test arrangement. The rotary seal rica es of solid Tung-Car f 2-6 (nickel binder) and the insert of No. 5 carbon. The c:npression unit was of 316 stainless steel and springt O pins and set screws #20 stainless steel. The insert rubbing faca design used for the final testing had a balance of 31" and face width of.175". The insert rubbing face nose length was standard at.125" for both the PTO des gn and HPTO design inserts. There was no anti-i rotation pin used for either insert. ^ TEST EQUIPMENT AND FLUID The test arrangement consisted of a heavy duty centrifugal pump circulat-ing product to a 15 gallon accumulator tank. The top of the tank was approximate ~ 6 feet above the seal chamber so that at the vapor pressure condition the seal actually had vapor pressure plus 6 feet of head. Figure I-3 is a schematic of the best arrangement used. Temperature of the aroduct was monitored by a dial thermometer in the l discharge line and a thermoccaple in the seal chamber as a double check. t Pressure was maintained by an external air operated pressurizing pump 1 l monitored by a calibrated pressure gage in the system. Environmental control to the seal chamber consisted of a bypass flush from the discharge. A full 1/2" stainless steel tubing bypass line was used. The throat bushing had a.0075". radial clearance. The oypass volume was approxi-f mately 1-1/2 GPM for all tests. The product fluid was listilled water with 2.5'i by weight boric acid (4.375 PPM Boron). i. [

w Page I-4 I TEST CONDITIONS 7he specific conditions tested sir. gly and in combination were: Product Temperature Condition "F

C Seal Chamber Pressure 1

150 66 V.P. + 6 ft. static head 2 150 66 250 PSIG 3 300 148 V.P. + 6 ft. static head 4 350 176 450 PSIG It is believed that these conditions in various combinations represent the best and worst that might occur to a mechanical seal in a pump used for residual heat removal, containment spray injection, etc. The tests were broken down into three categories, as follows: 1. Tests at a steady state condition (one condition only). These tests established the wear rate to be expected for each condition of temperature and pressure outlined above. 2. Tests with moderate cycling from condition 3 to 4 and then to 1, which represents a breakdown situation. f 3. Tests with multiple cycling of the conditions. These tests i I were designed to try to foul the seal with boric acid crystals ( and cause a seal failure due to hangup of some type and are not representative of any set of conditions that might occur, to our knowledge. It is firmly believed that the seal design presented can withstand any condition or combination of conditions that might occur and recover to operate normally. The entire test series was carried out with the objective of finding a way to fail the seal within the constraints of the conditions that could be encountered. As will be shown, the seal performed extremely well and recovered from adverse conditions many times over. RESULTS The results of testing are sumarized in Table I-1 and shown graphically in Figures I-4, I-5, and I-6. STEADY STATE CONDITION TESTS Tests 1 through 8 of Table I-1 and Figure I-4 show the results of the steady state testing. The results of these tests reveal the expected life for the seals for a variety of potential operating conditions. Tests 1 and 2 are a condition anticipated as a normal operating condition of 150'F and vapor pressure which rray occur for long periods of time. It can be Jy seen that at this condition the' seal faces have a projected life of 79,000 hours G ',or more than nine years. In the two tests of 238 hours duration each, used to determine the wear life, there was no measurable wear on the Tung-Car face. k

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Pag 2 I-5 s Tests 3 and 4 reveal tne wear of the seal if the temperature was 150*F and the pressure in toe rarge of 250 PSIG. This condition ~riay occur for long O periods in some systems. Tne wer of the carbon at this condition was nominal and resulted in a projected seal life of 40,00 hours or nearly five years. Inspection of the seal faces indicated no pitting or chipping on the carbon face and a narrow groove (.010" .020" wide) on the Tung-Car seal ring face, adjacent to the 0.d. of the contact area of the carbon wear face. This groove was 0.7 mils and 0.55 mils deep respectively and a matching ridge was observed on the carbon nose 0 D. The exact cause of this grooving is not under-stood but it has been observed when sealing hot water and when sealing high pres-sure using carbon against Tung-Car. This phenomenon was observed in all tests of the series except tests 1 and 2 above where it was not evident. In the very severe test cycles of tests 13 and 14, these grooves were still of nominal depth and width. It is believed that this grooving proceeds to a point and is self-limiting and, therefore, has very little effect on the total projected wear life of the seal. Tests 5 and 6 conducted at 300*F and vapor pressure represent the most severe conditions for wear since the liquid film between the deal faces turns to a vapor and the faces are essentially running in a vapor. The wear per hour shown on Figure I-a was.03274 mils per hour for a projected seal life of 3,800 hours. There was no liquid leakage during these tests; however, there were white crystals of boric acid around the area of the pump and base near the seal. These crystals are the evidence of vapor leakage. It is estimated that 5 - 10 grams of crystals were in the area which would trar. slate into 200 to 400 cc of liquid leakage for p* Ine test duration of about 72 hou's. O Inspection of the carbon wear faces following these tests revealed some face pitting and a few small chips out of the I.D. edge. The damage was not extensive and the seal would have returned to normal operation without difficulty. Inspection of the Tung-Car face revealed a narrow groove about 0.6 mils deep at the 0.D. contact area of the carbon face. This groove and corresponding ridge in the carbon were about the same as that observed in Tests 3 and 4. It was evident that the seal would perform satisfactorily under this adverse condition and that it may have a reasonably long life (3800 hours projected) even when operated at this condition continuously. Tests 7 and 8 conducted at 350*F and 450 PSIG represent another severe condition, principally due to the high temperature. Again a condition of emergency rather than norm is portrayed. Tne wear per hour averaged.0262 mils per hour which translates into a seal life of 4770 hours duration. Throughout these tests l there was no liquid leakage except small amounts of boric acid crystals. i Inspection of the carbon revealed face pitting and minor chips on both I.D. and 0.D. The damage was not extensive and the seal ' appeared that it would return to rormal conditions without difficulty. The Tung-Car seal ring revealed little effect except the small groove i i adjacent to the 0.0. of the carbon wear face similar to that noted in tests 3 and g 4. A measurement of depth was not taken. 9 k T e,-u,_ men-. --e.-.*y*q.3.; .-. z~ 3 =_

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~ Page I-6 00EDATE CYCLING TESTS ' ! and Figure I-5 show the effects of 'a Tests 9, 10,.inc !6 9 ~ :- - ~~~ moderate cycle from one cenD :0, wether. These tests attempt to illustrate that the seal design will Utri.r. en $r an emergency operating condition such mdition changes to 350'F and 450 PSIG and as 300*F and vapor pressure m: then returns to more normal ce n. 5 of 150'F and vapor pressure. The 150'F and 250 PSIG condition was not useo cecuse it is not as severe as that to 150'F and vapor pressure. Figure I-5 snows the exact cycle and time at each condition for the tests. The total wear on the carben is also shown and the total measurable leakage at each condition is noted. It can be seen that both wear and leakage were relatively constant from test to test. Mos of tne leakage occurred over a short period of time, usually following or during a change from one condition to another. There was a considerable buildup cf tcric acid crystals around the gland and shaft where leakage is expelled but tne sesi wa s apparently not " hung-up" or harpered since it recovered to leak-free opera-icn in each instance. Again the leakage was often in the form of crystals rather than liquid and the amount is approximate and probably low since crystals of;en fi;ateo into the air and were lost. The notation of " nil" for leakage deacted va: "e mount of boric acid crystals was very small and not readily collectable. Tne wear was genenl*. r.:--

or each test.

Tnis would indicate that changing conditions increHn. --

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The carbon insier r..e: ::: eared satisfactory af ter each test with only r.iror pitting and chipp k,:.s 'ct r e tne severe conditions encountered. The Tung-Car seai ri%s raeealed the groove at the 0.D. of the contact area with the carbon. The groove was 1.2 mils deep and after test 10 it was 1.8 mils deep. Test 11 was not measured. The grooves remained at about.020" wide. The groove was somewhat deeper but otherwise the same as observed before. In all instances the sea!s performed well and at no time indicated iminent failure. On several occasions at high temperature the seal spit and popped periodically over several hours during changes from one condition to another while the seal re-adjusted to tne new concition. This may have been a reaction during the wear-in period of the faces to a new condition and would account for the minor chipping and pitting on the carbon face. It should be noted that the'same carbon was used for tests 9 and 10 which was the PTO design'and for test 11 the HPTO design was used. No difference in general operation was noted. MULTIPLE CYCLING TESTS Tests 12 and 13 of Table -1 and Figure I-6 show the results from multiple cycling tests. These tests were conducted principally for the purpose of illustrat- . ing the ruggedness and recoverf abi'ity of the seal design proposed and to further b jetermine whether or not boric acic..olutions in this percentage range could . immobilize or hang-up the seal. I . Y '" s tor / imposed on the seal. Two separate Figure I-6 snous, % tests we,re conducted ustrg i re e r. im ert of the FPTO design for each. Table 1-2 y

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} m. , n .s...: Paga I-7 ~ f shows the nur.ber of changes and conditions as well as total hours of operation in each condition for the entire test. It can be seen that Test 12 endured 20 cycles for a total continuous time of 608 hours. After the 20th cycle the seal was leaking at 6 cc per minute but slowing when the test was terminated. Examination of the seal revealed that the carbon face was severely pitted and several large chips had occurred on the 0.D. and I.D. diameters. The cause of the leakage was believed due to face damage rather than seal insnobilization. It is ) would seal off 4 believed the seal would have gradually worn in so that the faces i after a period of time. The Tung-Car face had a groove about 2 mils deep adjacent to the 0.D. of the carbonsrubbing face. Although the groove was a little deeper here than in prior tests, it was of the same general width (.020"). It is felt j the extreme cycling would represent the very worst conditions for grooving that It is believed that about a 2-3 mil deep groove is about might be encountered. j the worst that will be encountered and that this phenomena would not seriously effect t i seal life when returned to a normal condition. { 1 Test 13 was a receat of Test 12 with a new carbon and re-lapped Tung-Car l 3eal ring. After 27 cycles and 905 hours, the test was terminated even though the seal was operating leak-free and satisfactorily. The test proceeded similar to i test 12 in that minor leakage occurred at several times during the test, always 2 related to a changing condition. In all cases the leakage stopped or became nil j after a few hours operation. 1 tJpon tear-down, the carbon appeared similar to that in test 12 but not as badly pitted. The Tung-Car seal ring had a groove 2.2 mils deep. The wear on the carbon seal faces was extensive at 22.7 mils and 50 mils respectively but in consideration of the extensive cycling and conditions the faces-j held up well and the wear was moderate. I e WEAR RATE A'lD PROJECTED SEAL LIFE The projected. seal life.for the seal was determined based on the wear i that occurred to the carbon graphite stationary element. - The wear nose on the carbon is.125" long and its useful life is considered expended when this is worn j i away. It can be seen, however, that the seal would continue to function once the wear nose is expended since the rotary unit would then begin to wear into the main [ body of the carbon.. The rate of wear would accelerate when the body was reached ] due to the wider contact area and greater heat generation. Therefore, the seal i-is considered worn out once the wear nose is expended. 1 The wear on the Tung-Car, seal ring face is many times less than for the carbon and is generally disregarded for normal conditions. In the case of high j temperature operation, such as 300*F and vapor pressure and 350'F. and 450 PSIG. .the tungsten carbide elementdoes wear but again in proportion to the highly accelerated wear of the carbon it is ~still a small matter and not considered in the proje'cted life of the seal'as shown in this report. A projected seal life is not shown for the modrrate c)cle and rapid. J-cycle conditions. It is believed that the combination of extreme conditions for j such'iong periods of time would not occur but 'once and. therefore, a projected ~ life would r.ot be a realistic fatter. ..~-u.,r.-.-. m, -,w*,.....,-,,y-. w-+ +,~--~.-,~..--+.-r,--n-- r. -.w .., ~ - '

4 ~ Page I-8 y l LEAKAGE AND IMMOBILI2ATI0ft One of the major concerr.s witn seals for this service is leakage and the i 4 possibility of immobilizing or hanging up the seal. Leakage in particular was quite modest and infrequent throughout this testing. As noted before, it seemed i to occur only during a change from one condition to another and even then it did not occur with each change of the same type; it was not predictable as to which change might produce moderate leakage. It could only be speculated, but it is believed that when boric acid crystals build up from vapor leakage, the seal ring I tends to be held up by deposits'en the sleeve adjacent to the seal faces. This restriction of the forward movement of the seal ring begins to reduce the closing force on the faces which eye.ntually causes some liquid leakage through the faces. 4 The liquid leakage soon washes away the boric acid, which is readily dissolved, j and frees the seal ring, thereby stopping leakage. I Innobilization, which is sometimes referred to as hang-up, is related to a deposited buildup usually emanating'from between the seal rubbing faces. In j this case it may be occurring but, if so, it is also self-destructing by virtue of the leakage. Upon careful inspection of the seal area after each test, it was noticed that the area adjacent to the seal on the sleeve and in front of the "0" ring shaft l packing was clear and free of any boric acid. The area near the outlet to the gland was usually covered with boric acid crystals. The crystal buildup was readily washed away with cool tap water requiring little or no mechanical scrubbing for removal. The ease with which the boric acid crystals were washed away supports our premise that boric acid will not immobilize the seal in any permanent fashion. It was believed that these tests demonstrated that the seal design will take extensive abuse and continue to seal and that boric acid crystals do not readily innobilize the seal. The number of cycles to extreme conditions and the intermittent liquid leakage during some cycles provided ample opportunity to destroy j the seal faces causing extensive leakage or innobilization of the shaft packing or j the movable seal ring. The seal withstood all this abuse many times over and ~1t I was concluded that the seal will withstand the severe conditions and changes and it should not be innobilized by boric acid crystals under any combination of conditions that might be encountered when sealing 2.5% borated water. In our 1969 Report it i was speculated that liquid leakage dissolves and washes away boric acid crystals i and these tests seemed to further strenthen this hypothesis. l l c l P. ),m. - n-- .-, m .-n.u ~~- r- : -- .-- m ---- :q---'i ;. ~sq :r* r.~.~~r~:":,:*:. ~. : ^

p p 4 1 '~ .g, - TABLE I-I

SUMMARY

OF TEST RESULTS: 2.57. 00 RATED WATER TOTAL TOTAL AVERAGE PRODUCT CONDITIONS NUMBER OF TEST CARBON PROJECTED TEST TEW. PRESS. CONDITION CHANGES TIME WEAR SEAL LIFE NO. 'F PSIG TEMP. PRESS. HOURS LEAKAGE - MILS HOURS STEADY _ STATE CONDITION TESTS 1 150 V.P. 0 0 238 Nil 0.45 .79600 l 2 150 V.P. 0 0 238 Nil 0.30 3 150 250 0 0 351 Nil 1.05 40400 4 150 250 0 0 305 Nil 1.00 6 5 300 V.P. 0 0 72 Nil 2.25 3800 6 300 V.P. 0 0 70 Nil 2.40 7 350 450 0 0 53 Nil 1.10 4770 t 8 350 450 0 0 92 Nil 2.70 MODERATE CYCLE CONDITION TESTS 9 150/350 V.P./450 5 .5 324 Nil 17.0 10 2 2 348 Fig. I-5 11.0 11 3 3 519 Nil 14.2 MULTIPLE CYCLE CONDITION TESTS t* 12 150/350 V.P./450 20 20 608 Fig. I-6 22.7 13 27 27 905 50.7 l' o a,. Y a w

1 s - 3 1 Fage I-10 i 3 i-8 4 TABtE I-2 l NUMBER OF CHANGES TO VARIOUS CONDITIOf;S 50R KILTIFLE~ CYCLE TESTS 12 AND 13 r i l i NO. OF TOTAL HOURS AT TEST NO. TEST CONDITIO1 TMS CONDITION 12 150*F & V.P. 8 383 l 12 300*F & V.P.. 7 119 12 350*F & 450 PSIG S 106' Total 20 608 hrs. I 13 150'F & V.P. 8 465 i 13 300*F 1 V.P. 11 264 s l 13 350?F&450PSIG 8 176' i 's s. J Total 27 905 hrs. s.. S (,. 'N 3 x, s y i 4 1 .k ii ~'j \\ s l s s s \\ k 5 s \\ .!\\, \\ 6e i i i

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.= - - -- so e Pa g6' l-11 FLUSH FROM DISCH ARGE Y f]/ r / f /> N f / dlIWU @ QM L CARBON T UNG C AR 62 GRAPHITE E P T "O" RINGS 7 TYPE 'PTO' TEST SEAL WITH BYPASS FLUSH _a FLUSH FROM DISCH ARGE v r / R Jh-, s_

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O o.M ~ l ~I i PRODUCT TEST TIME, HOURS TEST CONDITIONS N O. TEMR PRESS. 'F R S.I.G. 200 400 600 800 1000 LEAK AGE C C G-0,.,] o 8.,O 350 450 ] ] O c ,g 12 300 V.R I ) ) Q ] ] O s a i 0 C-"] ] C""] .0 C 3 ] ISO V. P. i I SS a 350 450 0 E]n ] I 'O ] ] U s L s a i i i, 13 300 V. R ] ] ] O ] O] OO] O s n e, a, [3 i 15 0 . V. P. O O C O ~-] D' i FIG. I-6 MULTIPLE CYCLING C O N DITION TEST R E SULT S i ) I 3 l b o m (D I Y 0;

h cam-4 DURAMETALLIC CORPORATION 2104 rectory street Katemenee.Mahigen 49001.U.S. A. SECTION II 'l THE TESTING OF DURA SEALS IN 5, BORATED WATER FOR NUCLEAR POWER PLANT SERVICES O Ref: Durametallic Corporation I Research Report No. 1209-B i January 16, 1978 w& Research Report No. 1209-C May 9, 1978 l l ~ . ~ - -.

l TESTING OF DURA SEALS IN 5. BORATED WATER 5 This report summarizes the testing accomplished by Durar - Corporation on Dura Seals f6r use in Nuclear Power Plant pumps har-borated water. The summarized data shown in Table 11-1 represent-hours of testing, simulating the most severe and adverse conditir,r - Al seals might be subjected,to during plant emergency conditions. that were conducted assume no external cooling was available. Or i ing was used to cool and lubricate the seal faces, even under tha of high temperature with little pressure above the corresponding All tests were completely successful with no failures encountere' G entire test program. This series of tests parallel the test series conduc:e- .m,f ws er reported in Section I of this report. In addition, a new Carbide, was tested as orevious test work indicated its potent' e pressure nuclear applications because of its superior abrasion - high modulus of elasticity. e "Y s%q $. J I j; d' 4 ~ ~ "' ~. s 'l E a _ (' .n-...-,....-.,.-..-._-.-,.,

. :. ~ 'L.*,*.1-K.. F ...T c- ..~...>~.x.- 1 s e 11-2 C0.CLUSIONS_ Type PTO Dura Seals in the design and materials of construction tested 1. performed totally satisfactory in sof tened water containing 5'. by weight boric acid under all conditions' tested. 2. External cooling is not required. 3. Bypass flushing of the pump product from the discharge to the faces provides adequate cooling and lubrication. 4. The projected wear life of the seal faces when operated at various steady state conditions on a continuous basis were: Condition Projected Wear Life, Product Temp., 'F Pressure Hours 91,000 150 V.P. + 6 ft. head 72,300 150 250 PSIG 300 V.P. + 6 ft. head 4,130 350 450 PSIG 6,490 5. Wear increases when the conditions are cycled from one to another.

However, even af ter several product temperature and pressure cycles, seal leakage. as p) minimal and the seals could be returned to a normal condition and operate (C satisfactorily.

6. Seal leakage is essentially nil when the seals operate at any single conoition on a contir.uous basis. 7. Seal leakage of a minor nature occurs when changing from one condition to another. 8. Silicon Carbide performs equally as well as Tungsten Carbide when mated against No. 5 carbon. As compared to Tungsten Carbide, under similar operating conditions, there is less wear with Silicon Carbide when mated against No. 5 caronn. 9. Immobilization or seal " hang-up" from boric acid crystals on the atmospheric side of the seal could not be made to occur from any combination of cycle i changes and/or periodic minor leakage. The boric acid crystals appear to '.4 dissolved and washed away from the seal area by any minor leakage that occurs. t

m ... -........ :w =. ~ z -...:. .s.. ~.. :.. u :.... Page II-3 1 TEST SEAL ~ The seal tested was a 2" shaft size rotating at 3550 RPM and is snown schematically in Figures 11-1 and Il-2. Figure 11-1 is a PTO Dura Seal design whicn was used for most of the testing. Figure 11-2 is a modified PTO design having the insert supported.against the gland 'in a manner similar to our HPTO high pressure Dura Seal series. The purpose of testing both designs was to indicate that either design performs equally well and could be substituted if the need should arise. An auxiliary gland, incorporating Durafite auxiliary shaf t packing was used on tests 2, 3, 4, 9, and 10 as shown in Figure II-2_which is the modified HPTO seal design. It was felt that the greatest potential for hang-up would occur when using the modified HPTO arrangement since they tend to leak more than the PTO arrangement, probably due to insert face distortions that are transmitted from the gland when bolts are tightened or when temperature and pressure changes Test I was a test of the modified HPTO design without the auxiliary gland. occur. There was no evidence of, seal hang-up with either arrangement. No auxiliary sealing device was used with the PTO design of test seals (tests 5, 6, 7, 8, and 12). In our prior testing it was found that such auxiliary devices did not adversely effect operation or lead to hang-up of the seal. It is even possible that cuxiliary devices may reduce any tendency to hang-up the seal by retaining liquid leakage longer and, thereby, tending to wash away any boric acir. rystal buildup more readily. Since a design without the auxiliary device (], g' ' ray reesent the more severe condition for the seal, it was chosen not to include it in s ;; e of the tests. The rotary seal ring was of solid Tung-Car 62-6 (nickel binder) for tests 1 tnrcugh 12 and Sil-Car 1 for tests 13 through 15. The insert was of No. 5 carbon. The compression unit was of 316 stainless steel.and springs, pins, and set screws were =20 stainless. -~ The insert rubbing face design used had a balance of 31% and face width of.175". The insert rubbing face nose length was standard at.125" for both the PTO design and HPTO design inserts. There was no anti-rotation pin drive used for eitrer insert. TEST EQUIPMENT AND FLUID The test arrangement consisted of a heavy duty centrifugal pump circulat-ing product to a 15 gallon accumulator tank. The top of the tank was approximately 6 feet above the seal chamber so that at.the vapor pressure condition the seal actually had vapor pressure plus 6 feet of static head. Figure _I-3 in Section I is a schematic of the test arrangement used. l J Temperature of the product was monitored by a dial the.mometer in the dis-harg'e line and a thermocouple in the seal. chamber as a double check. Pressure was maintained by an external air _ operated pressurizing pump 4 6.; monitored by a calibrated pressure gage in the system. 1 Y O:

Page 11-4 O V Envirc'~ acid e r Ma t'er c N.isted of a bypass flush from the disch3rge

N'.

eel tu:.ing bypass line was used The ' ~; '4arie.e ins hypass volume was approximately ~ throat bushing nai i I to 2 GP:1 for all teits. The product 'iuid u v h.fiened water with 5.- by weight boric acid (8742 PPM Boron). . tis,T CONDITIONS, The specific conditions tested singly and in combination were: Pro 1:ct Terperature Condition

F

'C Seal Chamber Pressure 1 30 E6 VP + 6 ft. static head .70 94 250 PSIG 2 3 143 VP + 6 ft. static head 4 .N 176 450 PSIG lt is believed to- .-we conditions in various combinations represent the best and worst tnat ricr*. .r.c .o a 'e-hanical seal in a pump used for residual heat rer. oval. contai -9' - t ra. Safety iniection, etc. Tne.est wre bro'un... .nt. c ee cateaories. as follows: .a. s 2 e ecnoition 'one condition only). 1. Tee s e. t The m s t - + : e ! i neet toe wea-rite to be expected for each C.:ndi' v. ' tenperature and pressure outlined above. 2. Tests with recerate cycling from condition 3 to 4 and then to 1, wnich rep esent a breakdown situation 3. A test with r.ultiple cycling of the conditions. This test was designed to tev to foul the seal with boric acid crystals and cause ? nil failure due to nang-up of some type and is not reprewntative of any set of conditions that might occur, to our krc.. ledge. It is firmly believed that the teal design presented can withstand any condition or combination of conditions tn'3t might occur and recover to operate normally. The number 2 and 3 test series were carried out with the objective of finding a way to fail the seal within the cni.straints of the conditions that could be encountered. As will be shoun, the seal performed extremely well and recovered from adverse conditions many times over. i l F.E.S_U..L.T.S 1 j The.results of tes'.inq *ee surnarized in Table 11-1 and shown graphically m{ in Figures II-3,11-4, !!-;, and :!-6. j. ( i v i STEADY STATE CONDIT!G'. ~ES Tests 1 fr.~r~oWn - - li-1..d Fi.:ure Il-i show the results of the l steady' state testin.1 '..'i'.. t....e tests: reveal the expected life for the (, seals f'or a.variet/ of notest: : .N-ra t ino c.mrti t iant ! a K. ,m-.w wrp.-m iN1 m= M %~~7?~,.'-,~ -% '- % % ' ~ TG5 ? 'E ~T ^

3 ....L.=~. .c.. i Page 11-5 O V Tests 1 and 2 are a condition anticipated as a normal operating condition i of 150'F ana vapor pressure which r:ay occur for long pericos of time. It'can be seen that at tnis condition the seal faces have a projected life of 91,000 hours or i more than ten years. In the two tests of over 300 hours duration each used to determine tne wear life, there was no measurable liquid leakage on one test and an { average of 3 cc/ hour on the'other. The leakage was associated with night operation when the arbient temperature dropped. Both tests used the modified HPTO insert design which is more prone to warpage from gland tightening and temperature and pressure variations. Tests 3 and 4 reveal the wear of the seal if the temperature was 200*F and the pressure in the range of 250 PSIG. This condition may occur for long periods in some systems. The wear on the carbon at this condition was nominal and resultea in a projected seal life of 72,300 hours or nearly six years. Inspection of the seal faces indicated no pitting or chipping on the carbon face and a narrow groove (.010" .020" wide) on the Tung-Car face adjacent to the contact area of the carbon at the 0.D. of the wear nose. This groove was 0.6 mils and 0.2 mils deep respectively and a matching ridge was observed on the carbon nose 0.D. The exact cause of this grooving is not understood but it has been observed when sealing hot water and when sealing high pressure using carbon against Tung-Car. This phenomena was observed )n all tests of the series. In the very severe test cycles of test 12, the groove was still of nominal depth and width. It is believed that this grooving proceeds to a point and is self-limiting n) and, therefore, has very little effect on the total projected aear life of the ( < seal. For example, tests of a hot water seal af ter 21,000 hours of operation in 300*F water resulted in the Tung-Car groove still only 0 0017" deep. Tests 5 and 6 conducted at 300*F and vapor pressure represent the most severe conditions for wear since the liqvid film between the seal faces turns to a vapor and the faces are essentially running in a vapor. The wear per hour shown on Figure 11-3 was 0.03 mils per hour for a projected seal life of 4,130 hours. There was no liquid leakage during these tests; however, there were white crystals of boric acid around the area of the pump and base near the seal. These crystals are the evidence of vapor leakage. There were very few crystals evident in the area so that leakage was very small during this test. Inspection of the carbon wear faces following these tests revealed some face pitting and a few small chips out of the I.D. edge. The damage was not extensive and the seal would have returned to normal operation without difficulty. l Inspection of the Tung-Car face revealed a narrow groove about 0.4 mils l deep at the 0.D. contact area of the carbon face. This groove and corresponding ridge in the carbon were about the same as that observed in Tests 3 and 4. It was evident that the seal would perform satisfactorily under this adverse condition and that it may have a reasonably long life even when operated at this condition continuously. Tests 7 and 8 conducted at 350*F and 450 PSIG represent another severe 3 condition, principally due to the high temperature. Again, a condition of emergency rather than norm is portrayed. The wear per hour averaged 0.019 mils per hour which translates into a seal life of 6,490 hours duration. Throughout these tests there was no liquid leakage except smoll amourts of boric acid crystals. i

m, e s Page 11-6 O inspection of tne carbon wear faces revealed face pitting and minor chips j i on both I.D. and 0.D. The damage was not extensive and the seal appeared that it would return to normal operation without difficulty. The Tung-Car face revealed little effect except the small groove adjacent to the 0.0. of the carbon wear face similar to that noted in Tests 3 and 4. The grooves were 0.3 mils and 0.1 mils deep respectively. MODERATE CYCLIN'G TESTS Tests 9,107 and 11 of Table 11-1 and Figure II-4 show the effects of a moderate cycle from one condition to another. These tests attempt to illustrate - that the seal design will perform when in an emergency operating condition such as 300*F and vapor pressure and the condition changes to 350*F and 450 PSIG and then returns to nore normal condition of 150*F and vapor pressure. Figure II-4 shows the exact cycle and time at each condition for the tests. The total wear on the carbon is also shown and the total measurable lEJkage at each condition is noted. The wear and leakage varied over a wide range.in these tests. The high leakage of test 9 was due, we believe, to a poor job of tightening the gland in the original set up. Once set up, the gland was not re-adjusted to minimize leakage. This illustrates a condition that can occur when using an HPTO insert desien. Test 10 used the same type of insert but the gland was adjusted more carefully to minimize leakage. Such adjustment is not difficult but does require some experience. Test 11 used the PTO flexibly mounted design insert and O revealed a modest leakage. As in prior testing, much of the leakage occurred during periods of change from one condition of temperature to another. ~ Also, the leakage at the elevated temperatures was in the form of boric acid crystals which were collected and weighed to estimate the amount of liquid leakage. A notation of nil leakage meant that there were.not enough crystals to collect although some crystals were present and some floated away in the air. There were no problems with hang-up of the seal as evidenced by the fact that the seal recovered and operated leak-free after the many upsets. The wear variation is not readily explainable except that wide variations in wear often occur. In consideration of the large number of temperature and pressure changes, the wear is considered satisfactory. The overall average waar life of the three tests was 6584 hours or about 9 months. i The carbon insert faces appeared satisfactory after each test with only minor pitting and chipping to indicate the severe conditions encountered. The Tung-Car faces revealed the groove at the'0.D..of the contact area with the carbon. The groove was less than 1 mil deep in all three tests and almost 0.020" wide. The Tung-Car seal ring faces appeared very similar to those when 2.5% borated water was' tested as reported in Section I. The major difference in seal face appearance was.that the grooves in the Tung-Car ~ faces were not as deep when using 5'; borated water. i n In all instances the seals performed well and at no time indicated. (w[iperiodically over several hours during changes from one condition to another while .inninent failure. On several occasions at high temperature the seal spit and popped ( the seal re-adjusted to the new condition. There may have been a reaction during the_ wear-in period of the_ faces to a new condition and would account for the minor chipping and pitting on-the carbon face. _ ? M _% _ g 9 8 46 8t*87'#F 6 4 h @@ e*%* N 98W%**'" P-- 48" M W9 %.P89"* %**=n Np W* _O'W***** **DW"{- 'NW_4 '*iu*94u4-*4* W(*N e wd *nP'Ar'. w e g*74

^^ ~. t w :.:. :c " u. - 1 .2 a= - u n - - - I Page II-7 O A different carbon insert was used for each of the three moderate cycla tests. Tests 9 and 10 used the HPTO design insert and test 11 the PTO design in e MULTIPLE CYCLING TESTS Test 12 of Table 11-1 and Figure 11-5 shows the results from a multiple cycling test. This test was conducted principally for the purpose of illustratim the ruggedness and recovery ability of the seal design proposed and to further determine whether or not boric acid solutions in this percentage range could ininobilize or hang-up the seal. Figure II-5 shows the cycling history imposed on the seal. One test was conducted using a new carbon insert of the PTO design. Table II-2 shows the number of changes and conditions as well as total hours of operation in each condition fo" the entire test. It can be seen that test 12 endured 25 cycles for a total continuous ti" of 655 hours. After the 25th cycle, the seal recovered to operate leak-free at 150*F and vapor pressure. Examination of the seal revealed that the carbon face was only moderate i pitted and that moderate chipping had occurred on the 0.D. The Tung-Car face had a groove about 0.8 mils deep by 0.020" wide adjacent to the 0.D. of the carbon rubbing face. It is felt the extreme cycling would represent the very worst condition for grooving that might be encountered. It is believed that about a 2 ! O " mil deep groove is the worst that will be encountered and that this phenomenon would not seriously effect seal life when returned to a normal condition. The results of tests 13,14, and 15 are shown graphically in Figure II '- These results are comparable to the multiple cycling tests of Figure 11-5. The tests on the Sil-Car 1 were not of as long duration but consisted of more time of operation at the V.P. and 300*F condition, which is quite severe from a wear and face damage standpoint. Considering this factor, the carbon wear running against Sil-Car 1 is considerably less than with Tung-Car 62-6. The Tung-Car vs No. 5 carbon in test 12 wore the carbon 28.4 mils whereas test 13 with Sil-Car 1 vs No. t carbon wore the carbon only 13.2 mils. It was concluded that Sil-Car 1 causes less wear on the carbon counter-face than that which would occur if Tung-Car were used. Another factor noted with Tung-Car was that the Tung-Car face was groovett in the area adjacent to the 0.D. of the carbon rubbing face. With Tung-Car in tes' 12 the groove was.0008" deep x.020" wide. In the case of Sil-Car in test 13, the same groove appeared but it was only.0002" deep and about.020" wide. It appears that both materials are grooved but Sil-Car 1 grooves only about 25% as deep as when Tung-Car was used. It was concluded that both Tung-Car and Sil-Car 1 are grooved by No. 5 carbon when operating in 5% borated water but that Sil-Car 11s more resistant to this grooving phenomenon. l WEAR RATE AND PROJECTED SEAL LIFE The projected seal life for the seal was determined based on.the wear that occurred to the carbon graphite stationary element. The wear nose on the t carbon is 125 mils (.125") long and its useful life is considered expended when this is worn away. It can be seen, however, that the seal would continue to m mm =- .a -m.. , ~ ,e .3 m-w-d +..

~ s Page 11-8 l functiononcethewearnoseisexpendedsincetherotaryunitwouidthenbegin j to wear.into the main body of the carbon. The rate of wear would accelerate -when the body was reached due to the wider contact area and greater heat generation. Therefore, the seal is considered worn out once the wear nose is expended. The wear on the tungsten carbide rotary face is many times less than for the carbon and is generally disregarded for normal conditions. In the case of high temperature operation, such as 300*F and vapor pressure and 350*F and 450 PSIG, the tungsten carbide element does wear but again in proportion to the highly accelerated wear of the carbon it is still a small amount and not considered in the projected life of the seal as shown in this report. The wear is generally in the form of a narrow groove, less than 2 mils deep x 10-30 mils wide, at the 0.D. of the wear nose track. A projected seal life is not shown for the moderate cycle and multiple cycle conditions. It is believed that the combination of extreme conditions for such long periods of time would not occur but once and, therefore, a projected life would not be a realistic factor. LEAKAGE AND IMMOBILIZATION One of the major concerns with seals for this service is leakage and the possibility of immobilizing or hanging up the seal. Leakage in particular was quite modest and infrequent throughout this testing. As noted before, it seemed to occur only during a change from one condition to another and even then it did not occur with each change of the same type; it was not predictable as to which change might produce moderate leakage. It could only be speculated, but it is believed that when boric acid crystals build up from vapor leakage, the seal ring tends to be held up by deposits on the sleeve adjacent to the seal faces. This restriction of the forward movement of the seal ring begins to reduce the closing force on the faces which eventually causes some liquid leakage through the faces. The liquid leakage soon washes away the boric acid, which is readily dissolved, and frees the seal ring, thereby stopping leakage. Immobilization, which is sometimes referred to as hang-up, is related to solids emanating from seal face leakage, accumulating on the shaft at the atmospheric side of the shaf t packing. In this case it may be occurring but, if so, it is also self-destructing by virtue of the leakage. Upon careful inspection of the seal area after each test, it was noticed that the area adjacent to the seal on the sleeve and in front of the "0" ring shaft packing was clear and free of any boric acid. The area near the outlet to the gland was usually covered with boric acid crystals. The crystal buildup was ~ readily washed away with cool tap water requiring little or no mechanical scrubbing I for removal. The ease with which the boric.:id crystals were washed away supports the premise that boric acid will not immobilize the seal in any permanent fashion. It was' believed that multiple cycle testing demonstrated that the seal design will take extensive abuse and continue to seal and that boric acid crystals do not readily imobilize the seal. The number of cycles to extreme conditions ard the intermittent liquid leaktge during some cycles provided ample opportunity C4 o destroy the seal faces causing extensive leakage or immobilization o t

k. scal ring. The seal withstood all this abuse many times over and it was concluded i

that the seal will withstand the severe conditions and changes and it should not be imobilized by boric acid crystals under any combination of conditions that k _,*"**j**#?""" "[ ~~,~ e

- w
w

.. ( h l ?' l : Y"

Page II-9 1 might be encountered when sealing 5% borated water. In our 1969 report.it was speculated that liquid leakage dissolves and washes away boric acid crystals and these tests seemed to further strengthen this hypothesis. It was evident that as long as the seal leakage is dissolvable in water, the seal should not become imobilized and leak from. upset conditions similar to those tested herein. e (.' l i 4 6 Gl u -1 e .a - _ - s u - - - :- -- - = -. -:: :.-- :. 4:-- -- :z.,.,;;: -. - _ -..r...., ~_.._ _ _,.. _... _. _., _ _ -.. - - _.

l Q O o.! t[ .T..A.B.1. L... 1 1.1 } .SU.M. MARY OF. T.E.ST.RE. SUI.TS: 5 '. I:0.R.AT.E.D. WAT.L.R TutAL TOTAL AVERAGE u lj P_R000CT CONDIT_10_NS NUMBER OF IL SI CARBON PROJECTED j 1 TEST ' TEMP. PRESS. CONDITION CHANGES TIME LEAKAGE WEAR SEAL Life NO. "F PSIG 'T EMP. PR'E S S. HOURS CC/IIR. MILS HOURS C ~ ~~ ] 1 STEADY STATE CONDITION TESTS T ] i! 1 150 V.P. 0 0 303 Nil 0.60 91,000 'l

l 2

150 V.P. 0 0 333 3 0.35 d 3 200 250 0 0 329 1 0.70 72,300 4 200 250 0 0 309 4 0.45 5 300 V.P. 0 0 161 Nil 10.0 4,130 l 6 300 V.P. 0 0 135 Nil 2.7 4 ll 7 350 450 0 0 95 Nil 2.4 6.490 8 350 450 0 0 90 Nil 1.4 uj 4 MODERATE CYCLE CONDITION TESTS .:l ~ 9' 150/350 V.P./450 10 10 571 26 11.6 9 9 450' Nil 4.8 0 10 11 11 824 1.5 15.1 11 h'1 MULTIPLE CYCLE CONDITION TESTS ]l, 12 150/350 V.P./450 25 25 655 Fig. 11-5 28.4 i l'jg;. MULTIPLE CYCLE CONDITION TESTS: SILICON CARBIDE VS NO. 5 CARBON ii 13 150/350 V.P./450 13 13 486 Nil 13.2 o 3 3 191 Nil 5.8 14 12 12 313 Fig. 11-6 4.4 15 il I it

Page 11-11 s TABLE 11-2 N_ UMBER OF CHANGES TO VARIOUS " CONDITIONS FOR MULTIPLE C NO. OF TOTAL HOURS AT TEST NO. TEST CONDITION TIMES CONDITION 12 150*F & V.P. 9 459 12 300*F & V.P. 6 114 12 350*F & 450 PSIG 10 82 Total 25 655 { , em 1 l l *Y M944* WM g gey o%=.wz._p p g 7,g

Fagt 11-12 r FLUSH FROM / DISCH ARGE N,) l / N /- -/,, !lR@JQM L ~ CARBON T UNG CAR 62 GRAPHITE E P T "O" RINGS ~ ~ , FIG H-1 TYPE *PTO' TEST SE AL WITH BY PASS FLUSH FLUSH FROM DISCH ARGE v / f / ~~ f-_,/, /-au* c'*"o ?JIREE P1n $ Mdd N CARBON TUNG C AR 62 GRAPHITE bDURAFITE E P T "0" R IN GS PACKING ~ FIG. E-2 MODIFIED TYPE "HPTO" TEST SEAL WITH BYPASS FLUSH G i p., a ENY M mw e e IM m' IA%+*e + < = * - -

' ' * ~ * * ' '

l li ! ! il fh' .t l8

% =.

D E 0 0 0 0 T S 0 0 3 9 4, C L E R 0, 3, 1 E A FU 6 2 4 J E O I i O S L 7 H 9 S N T 5 O R S 0 0 5 L I 4 0 7 4 4 3 U B A L 6 7 R E 0 2 2 S l A WM O O O O 1 E C R T S E T I i N O 0 I 0 i I T S 3 I R D U N O O H C 0 E 0 E 2 M T A I T T i S T S I Y E D T 0, A I 0 I E 1 T S 3 II S R P. 0 0 S S G. P 0 0 N E I. R 5 5 5 5 G V. V. 2 2 V. V. 4 4 O R S I P R F I T I D P. 0 0 0 0 0 0 0 0 N MF 5 5 0 0 0 0 5 5 O E' 2 2 3 3 3 3 1 1 C T T S O 2 3 4 5 6 7 8 l E N T 1l1lll ll l

i O O O.. r -n t i l 2 "E L PRODUCT TOTAL h I ,H TOTAL YEST CONDITIONS CARBON LEAKAGE WEAR N O. TEMR PRESS. ,j

F R S.I.G.

100 300 500 700 MILS CC 350 450 ] ] ] 11,130 ll, 9 300 V.R 3, J O ]

11. 6 2 20 u

i0 -] 3,675 150 V. P. l i 350 450 3 0 3 'll 10 300 V.R D l0 0 4.8 Nll 3 150 V. R C i I i 4- , I, 350 450 0 J O 80 s

j, 11 300 V. P.

D D ] 1 15.1 1240 'l 150

v. e a

aa i f 4 e j FI G. II-4 MODER ATE CYCLING CONDITION TEST R E SU LTS 4 l l !.

A r " PRODUCT TEST TIME HOURS TEST CONDITIONS N O. T E M P. PRESS.

F P. S.I.G.

10 0 200 300 400 500 600 t I t a e 9 e a 3 g i e g LE AKAGE - C C 8 8 SS o 350 450 l Q C ] l l 3 3 'O ] i. i s, i i, o ,0 8 12 300 v.R "D D D C o o e .7 f O [] Q Ot 0 i 150 V P. t i t i p i FIG. II 5 MULTIP LE CYCLING CONDITION TEST RESULT h i,t i h8 4 1 s? 2 ~ 's ? 8 G t.'

% "Yg l N L O R S A 2 8 4 B A L 4 T 3 5 R E I O A W M 1 T C N O B R 0 A 0-C 5 'fi 5 tI O ' N 0 0 S 4 V I i S R R A n U 3 C O 0 H 0i 'O -L ) I 3 O S f E S M f' T I L T U 0 S T 0 I E S 2 3 R E f "f= T T i' S i E T 0, i 0 G 1 i1I N I L

&

CY "i= C 6 SG 0 0 R P. 0 P. R S S l. R P. I T N ES 5 V. 4 4 5 V. I 5 V. V. V C O R R 4 V I P U T D I G OD P 0 0 0 0 0 0 0 0 O I F R N M 5 0 5 5 0 5 5 0 S P O F 3 3 3 3 E* 3 3 I 1 1 C T T S O 3 4 5 1 1 E 1 N T 1 l 1 ll1; i'l L b

G s]-7?k-n_.== -( M. _ W [- O DURAMETALLIC CORPORATION 2tod rectory $treet Kalamaroo.Hichigen 490ol.U.S. A. SECTION III THE TESTING OF DURA SEALS IN 12% BORATED WATER FOR NUCLEAR POWER PLANT SERVICES ~ I l i l Ref: Durametallic Corporation Research Report No. 1200-B ~ June 4, 1975 Oe'g.' J l l l 3, %A

W ! D O"

s Page 111-1 ~ V TESTING OF DURA SEALS IN 125 BORATED WATER This report summarizes the testing accomplished by Durametallic Corporation on Dura Seals for use in Nuclear Power Plant pumps handling up to 12% borated water. The summarized data, shown in Table III-1 represents over 3,250 hours of testing. The purpose'of Test Series A was to determine the seal life of a Type R0 Unbalanced Dura Seal in a dead-ended stuffing box operating in 12% by weight boric acid. Three combinations of seal face materials were operated on long term tests to determine the projected seal life of each. The purpose of Test Series B was to define the operating linits of a Type RO Unbalanced Dura Seal in a dead-ended stuffing box operating in boric acid. It was intended to perform a short series of tests to quickly confirm that this seal design would' operate satisfactorily in boric acid concentrations up to 12% by weight and determine the maximum allowable boric acid concentration for each set of face materials. All the tests that were conducted assume that no external flushing or cooling was available. m Os W <., -n, - - w. m. - m - m.- m --- -- - ---.-- : m _ -. _, .__;--~~-----~~~,-<

s Page III-2 i CONCLUSIONS _ Type RO Dura Seals using Tungsten Carbide vs No. 5 Carbon seal faces operating in a dead-ended stuffing box performs satisfactorily in a boric acid solution 1. up to and including 5% by weight boric acid. Type R0 Dura Seals using Tungsten Carbide vs Tungsten Carbide seal faces operating in a dead-ended stuffing box performs satisfactorily in a boric acid 2. solution up to and including 12% by weight boric acid. The External cooling is not required up to product temperatures of 180*F. 3. wear rate increases rapidly at temperatures above 180*F. 4. Seal leakage is essentially nil. Wear rates weremoderate and overall seal performance was' very good indicating 5. that these seals would provide good seal performance and long seal life. Bronze vs Tungsten Carbide is not satisfactory for sealing 12% by weight 6. ooric acid. O \\ J . -..-..- g. -- - 3.. ;-.-- - 3 ;. - -~ ~ ;- - ~ = -

Page III-3 TEST SEALS The seals used in Test Series A were 1-3/4" Tupe R0 Unbalanced. Dura Seals orerating at 3500 and 1750 RPM. The rotating seal ring material for all tests was Tung-Car 62-6(nickel binder)..The stationary insert was a clamp style insert, shown schematically in Figure III-1. Three insert materials were tested; No. 5 carbon, Tung-Car 62-6 and Bronze. Each insert had a standard rubbing face nose length of.125". The compression unit was of 316 stainless steel with 720 stainless springs, pins, and set screws. The "0" ring shaft packing was EPT. The seals for Test Series B were 2" Type R0 Unbalanced Dura Seals operating at 3500 RPM and are shown schematically in Figure III-2. The rotating seal ring material for all tests was Tung-Car 62-6 (nickel binder). The stationary insert materials tested.were No. 5 Carbon and Tung-Car 62-6. The compression unit was of 316 stainless steel with #20 stainless springs, pins and set screws. All "0" ring secondary seals were EPT. The insert rubbing face nose length was standard at.125" and no anti-rotation pin drive was used. A fixed bushing with a radial clearance between the shaft 0.D. and the bushing I.D. was installed on the pump product side of the seal to reduce self-flushing and to provide a dead-ended seal chamber. TEST EQUIPMENT AND FLUID The seals in Test Series A were tested in a single stage, end suction norizontal process pump. The pump speed was 3500 and 1750 RPM. The pump recircu-4 lated the fluid through a 12 gallon tank via a 3/4" discharge line and 1-1/2" 3 suction line. The stuffing box temperature and pressure was measured through taps to the stuffing box. The product fluid was demineralized water containing 12% by weight' (20,981 ppm Boron) boric acid. No cooling or bypass flushing was used. 4 The test arrangement for Test Series B consisted of a simulated stuffing i box attached to a mounting plate as shown in Figure III-3. The shaft was supported by a bearing housing. Pressure was maintained by external air pressurizing the top of an accumulator tank holding the product fluid and monitored by a calibrated pressure 1 l 9 age. J Temperature was controlled by the use of a Dura thermocooler (evaporation o type heat exchanger) with :irculation induced by a circulating ring attached to I l the shaft. Temperature was monitored by dial thermometers. Temperature control of the boric' acid solution was the major problem encountered. The test facility was modifiad many times so that this parameter could be reasonably controlled. Even so, without automatic temperature controls, constant temperatures could not be maintained. It was attempted to keep the product temperature between 155'F ~and 180*F. 1 The product fluid was softened water containing 5% by weight (8,742 ppm Boron)-6% by weight (10,490 ppm Boron) and 12% by weight (20,981 ppm Boron) boric acid. ~

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Page III-4 TEST CONDITIONS Test 3eries A was conducted at pressures varying from 10-F1 FSIG on the stuffing box. Tests were run for a nominal of 30 days with frequent stops and starts to simulate on-off conditions. Stops were occasionally prolont: ' to pemit the boric acid to settle out in order to determine if start-up problems would occur. Test Series B was conducted at pressures varying from 20-50 PSIG. Pressure normally has an effect on the wear rate but at these low pressures the difference in Pear rate was not sifnificant. This is indicated by comparing Test Series 4 - 6. l Tests 4 and 5 were run at 50 PSIG and Test 6 at 20 PSIG, all other conditions being identical. The wear results on this set of tests is very consistent, in spite of the differences in pressure., RESUI.TS The results of testing are sunraarized in Table III-1. I The carbon insert of Series A Test No. I operating at 3500 RPit wore rather rapidly and resulted in 19.7 mils wear in 28 days of operation. - Assuming the seal wear nose to be worn out after.100" wear on the carbon, the projected life of this seal would be only 142 days. The seal performed well otherwise and did not leak noticeably or show signs of clogging or wear of other parts. The seme carbon insert was tried at 1750 RPM, Test No. 2, and performed well. As expected, the wear at the lower RPM was less and a projected life of 322 days was indicated. Performance othemise was quite satisfactory. ) A solid Tung-Car 62-6 insert replaced the carbon in Test No. 3 and per-formance was excellent. The wear af ter 33 days of testing was hardly measurable on the tungsten carbide faces. The life expectancy was, therefore, extremely long suggesting that perhaps some other pump components may wear out-before the seal. There was no indication of wear or damage to any other parts of the seal upon completion of the test. ~ Since tungsten carbide is an expensive material, Test No. 4 was tried ) using a bronze stationary insert. The bronze wore heavily and sufficient leakage occurred to warrant termination of the test after only three days time. Tests 1 - 6 of Test Series B were conducted using Tung-Car 62-6 and No. 5 Carbon as face materials. No modifications were made to the standard type RO seal 1 design. Tests 1 - 3 were conducted in a 5% boric acid solution.' Moderate wear was experienced and overall seal perfomance was very good.- Tests 4 - 6 were con-i l ducted in 6% boric acid. The wear rates in these, tests were high, indicating short seal life. Tests 1 - 6 indicate that No. 5 Carbon against Tungsten Carbide performs well in boric acid solutions up to and including 5%. Test 7 was run in 6% boric acid using a Tung-Car 62-6 insert and seal-ring. No wear was measured for this test. The same face materials were then used for Tests 8, 9, and 10 sealing 12% boric acid. Again no wear was measured for these I tests. These tests ran very satisfactorily and indicate that this face material G combination would provide good seal performance and long seal life in boric acid solutions up to and including 12L ._.;.._7._.... g..._-....,.,~.a..-m..,...,..

.m. b ~, s s N g-s s ~ t Page III-5 t i + 1 During Tests H and 12, prpduct temperatures ran higher than desired. ine average product and, box tenperaturee dd[ing' these tests was 200*F. Wear rates caring these two tests wPe very high, indicatir.3 flashing across the s'eal faces !%is problem was not experience,d dt slig5tly lower temperatures General test resultsindicatethattemperaturesupto'180(Fcanbetoleratedwithoutseriously 'l effecting the seal life. v -,s s s. During all tests, leakage wss Til. 3, x s s i k 's g 3 4 -I %k s. g4 s, s \\ g . 4 A, k i ti l 1- ,. t E. 1, i t I ' k 1 \\ i ~' + \\ w 1 .. - ~\\ 5 s .( g m,v. s, wT e } =9, = 44 N N g Is s x-l l i 1 j m i 4 + g_.' s .s g W i L I gN,. g h-L -,. s 4 g i* '.i N g \\ s s k \\ ) ~~ \\ s -Y N- ' i N s i s, s-y.-m , kg h ' y k.,., - 5 1 = s 3 th, .. g. s s 4 i g~ l j j %g , *= g* g m .t, +t - i \\ m4 T i. kh

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SUMMARY

OF TEST RESULTS 1 g 1 i AVERAGE TOTAL l AVERAGE PROJECTE0 PRODUCT CONDITIONS TEST i TEST TES. I BORIC TEMP. PRESS. SPEED TIME SEAL FACE MATERIALS-CARBON WEAR SEAL LIFE SERIES NO. ACID

F PSIG RPM HOURS P,0TAtlHG STATIONARY MILS / DAY HOURS Il A

1 12 160 10 3500 672 Tung-Car No.5 Carbon .70 3,408 62-6 .31 7.728

5 Ji

-2 12 140 15 > 1750 720 3 12 172 20 3500 792 Tung-Car 62-6 0.003 24,000 + ij 4 12 167 15 3500 72* Bronze f k o Test stopped after 72 hours of operature due to excessive leakage of 80 drops per minute and increasing., I B 1 5 145 20 3500 96 Tung-Car No.5 Carbon .18 13.333 4! 62-6 Jlr 2 5 160 20 96 .18 13,333 4 3 5 170 20 48 .20 12,000 '4 4 6 180 50 72 .80 3,000 ji 5 6 180 50 192 .60 4,000 1 6 6 155 20 24 .80 3,000 7 6 145 20 148 Tung-Car 0 24,000 + ]'3 62-6 'i! 8 12 150 40 24 0 24,000 + .!j 9 12 180 40 72 0 24,000 + 10 12 160 35 72 0 24,000 + ji 11 6 200 20 144 .56 4,285

i 12 12 200 45 8

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O 9 ~ Page 111-8 AIR PRESSURE PRESSURE GAGE / PRES SURE RELIEF VALVE ,J w' v AC CU MUL ATOR TANK MOTOR A BE ARING ) HOUSING k,,\\gt (g,+>. j eLA O g a SIMUL ATE D ST UFFING BOX k 7 TEueERATURE GAGES g g MND ~ > N %AM THERMOC00LER/ PRODUCT OUTLET FROM 80X g F I G. III-3 TEST EQUIP MENT D,*: h g eq y,-.,.. n. s - c. ~... - ~~,-~ ~.~ -~ -. . r-n.~- y - - ~. -- -. v ~ ~.- n -: * t r.. ::'= *=::&. * *: ~ " "...

s ) a c ww m a) DURAMETALLIC CORPORATION 2io4 r.ewy street we=um.Michig.n 4 soot.u.s. A. 5ECTI0N IV l THE TESTItG OF TYPE HPTO HIGH PRESSURE DURA SEALS FOR BOILING WATER REACTOR (BWR) " CLEANUP RECIRCULATION" PUMP SERVICE O' l I Ref: Durametallic Corporation Service Report No. SR-78-228 i May 1, 1978 h.' s u_ :mnxe x_e__e_.:_ _o_ _ _- -_-~_m m -~~ - ~-*-

.....; a a......- i. Page IV-1 THE TESTING 0F TYPE PPTO HIGH PRESSURE DURA SEALS FOR BOTLING WATER REACTOR (BWR) " CLEANUP RECIRCULATION" PUMP SERVICE This report summarizes the testing accomplished by Durametallic Corporation on Type HPTO High Pressure Dura Seals for use in " Cleanup Recirculation" pumps used in the Boiling Water Reactor nuclear power plant system. The sumarized data, shown in Table IV-1 and Figures IV-1 and IV-2 represent several weeks of testing with the final design subjected to both pressure and temperature cycles. The acceptance criteria used was a maximum allowable seal leakage rate of 360 cc/24 hours in the cold condition for the first 48 hours and 180 cc/24 hours at the design temperature or beyond 48 hours of seal running time.

~ ~ Page IV-2 CONCLUSIONS Type HPTO Dura Seals'with a flexibl'y mounted insert design performed satis-1 factorily under all conditions tested. Type HPTO Dura Seals with a rigid insert mounting design leaked excessively 2. l as a result of gland deflection caused by gland nut tightening procedures. 3. A seal balance of 37% should be used for maximum seal life under the con-ditions tested. Seal balance will vary depending upon operating conditions and should be selected for each individual case. 4. Seal leakage for the first 48 hours of operation may average up to 15 cc/ hour (360 cc/ day) for the conditions tested. 5. After a 48 hour run-in period, seal leakage should not exceed 7.5 cc/ hour (180 cc/ day) for the conditions tested. 6. Seal leakage rates will vary depending upon seal design and operating conditions. Estimated leakage rates can be calculated for each individual case. V 'O 6 e. l I ~ ' ~ * ~.

Page IV-3 TEST SEAL The seals tested were 2-1/8" Type HPTO Dura Seals rotating at 3600 RPM and are shown schematically,in Figures IV-1 and IV-2. Figure IV-1 shows a rigidly mounted insert design wherein the stationary insert backs up to the gland ring shoulder when subjected to high seal cavity pressures. Figure IV-2 depicts a flexibly mounted stationary insert design wherein the insert is completely isolated from the gland ring. The rotary seal ring and insert were of solid Tung-Car 62-6 (nickel binder). The compressio,n unit and gland ring were of 316 stainless steel. Pins and set screws were of d20 stainless steel and the springs were of XM-19 stainless steel. The secondary sealing "0" rings, hold rings and back-up rings were EPT terpolymer. A 316 stainless steel circulating ring was used to circulate the seal cavity fluid through a heat exchanger to maintain seal cavity temperature. The insert rubbing face designs used had balances of 32% and 375 with standard.062" nose lengths. There were no anti-rotation pins used on any inserts. TEST EQUIPMENT AND FLUID Tne test arrangement consisted of a commercial high pressure centrifugal p) pump circulating product to a 15 gallon accumulator tank as shown in Figure IV-3. V' Temperature of the product was monitored by temperature Sages located near the suction nozzle and discharge nozzle. The temperature values taken were an average of the two temperature gages. Pressure was maintained by an external air operated pressurizing pump monitored by a pressure gage location near the suction nozzle. The product fluid was softened water. Environmental control to the seal cavity consisted of a circulating ring mounted on the shaft forward of the seal which circulated the seal cavity fluid through a water cooled heat exchanger. The process fluid outlet from the heat exchanger was returned to the seal cavity through a drilled passage in the seal cavity housing leading directly to the seal faces. TEST CONDITIONS l Fluid: Softened Water Temperature: 535'F maximum Operating Pressure: 1040 PSIG Hydrostatic Pressure: 1725 PSIG Speed: 3600 RPM A) (S TEST PROCEDURE 1. Vent all air when filling the system with water. i b ~ ~ ~ --. ~.. mm. .,s .g..., y.- - - -. -.. -. _..., -.,.. ~.... -..

Page IV-4 Hydrostatically apply pressure of -1725 PSIG and hold fcr 30 minutes. 2. Measure the ar.ount of leakage for the 30 minute perioi. 3. Apply pressure of 200 PSIG and start '.he pump. Measure leakage for 10 minutes. Repeat 3 above for the following pressures (pSIG) in the following 4. order: 400, 600, 800, 1000, 800, 600, 400, 200, 400, 600, 800, 1000. 5. Maintain pressure at 1000 PSIG and increase temperature to 535'F. i Maintain pressure and temperature for one hour and measure leakage for this one hour period. 6. Close pump suction and discharge valves to isolate the pump from the system. Allow the pump to cool 30*F lower than the system temperature. 7. Reopen the pump' suction and discharge valves. 8. Decrease the systen ter.perature to 160*F or less and measure leakage collected in 10 minutes. 9. Repeat 5, 6, 7 and 8 three times for a total of four startups and i shutdowns. O RESULTS The results of testing are summarized in Table.IV-1 and shown graphi-cally in Figures IV-4 and IV-5. Test No. I was run with the rigid insert mounting design as shown in-Figure IV-1. The insert balance was 37% and a spiral wound metal gland ring This first set of tests quickly revealed that seal leakage was gasket was used. inconsistent from one test to the next with leakage rates ranging from 2 to 500 It was found that seal leakage was dependent upon the gland nut cc/ hour. tightening procedure, torque ' values and whether_ the gland ring spiral wound ^ gasket was new or used. It was also found that seal-leakage could be changed significantly by loosening or tightening-the gland nuts while the pump was operat-l i ing. l Test No. 2 was run under the same conditions outlined above with the ' insert balance reduced to 32%. Results similar.to those above were observed with the initial leakage rates at 1000 PSIG pressure ranging from 40 to 120 cc/ hour. I l Test No. 3 was conducted with an EPT elastomer "0" ring gland gasket _in place of the spiral wound metal gasket, requiring only ~15 ft-lbs of torque to-i seal at the gasket. Although the initial leakage rates were reduced to 24 to: 30 cc/ hour,' leakage remained unpredictable. As a result of these three series of tests, the insert design was revised-to a flexibly mounted insert wherein the insert is completely isolated from the gland ring as shown in Figure IV-2. This change provides an insert design which would be uneffected by gland ring distortion.' Tests 4_ and 5 were: M.s. _w~-,._m ~ ~. 6.. m ___..m.,,,,.

+ page IV-5 conducted to evaluate seal perforr:ance with tne flexibly mounted insert and seal balances of 324 and 371. Test No. 4 was coeducted with a 37; seal balance. Dynamically at 1000 PSIG, these seals leaked 2-20 cc/ hour at startup. After a run-in period of 48 hours, leakage dropped to near zero. Test No. 5 was conducted to determine if the initial leikage rete and run-in time could be reduced without sacrificing seal life. The seal balance for these tests was lowered to 325 to increase the unit loading on the seal faces. -Initial seal leakage ranged from 6-12 cc/ hour. After a run-in period of 48 hours, seal leakage was near zero. Examination of the seal faces also revealed some slight neat checking not seen in Test No. 4. It was concluded from test series 4 and 5 that flexibly mounting the insert reduced the leakage rate to 2-20 cc/ hour initially and to near zero after a run-in period of 48 hours. It was also concluded that even though a lower balance would slightly reduce initial leakage, it was not significant. Examination of the seal parts from test series 4 and 5 showed that initial leakage was being caused by convexing of the seal faces. Even though this causes more initial Seal leakage, tne dduitional fluid between the faces during run-in reduces the aeoant of wear and damage sometirees associated witn seal run-in. This is, tnerefore, considered beneficial to overall good seal life. Ot! Once satisfactory seal performance was established, a test procedure for seal acceptance was erittenas outlined. The pump was hydrostatically tested for 1/2 hour at 1725 PSIG. Seal leakage.vas measured at 13 cc/nour. The pressure cycle testing consisted of cycling the pump from 200 PSIG to 1000 PSIG, back to 200 PSIG and finally up to 1000 PSIG again. This was done in 200 PSIG increments with each pressure increment being held for 10 minutes. When the pump was first started at 200 PSIG, a leakage rate of 12 cc/ hour was observed. After this, the leakage settled down, ranging from 0 - 6 cc/ hour as shown in Figures IV-4. The temperature cycle tests consisted of heating the pump to 535'F, holding that temperature for one hour, performing a 30'F minimum temperature shock on the pump, then cooling to below 160*F. At this point the leakage was measured. This cycle was run four times at a pressure of '1000 PSIG. During the first two cycles the pump remained running during the cool-down portion of the cycle. During the last two cycles, the pump was shut off during cool-down and the leakage was measured with the pump off. The temperature cycles and results are shown in Figure IV-5. j . The leakage rate at the end of cycles 1 and 2 was 6 cc/ hour. The leakage i rate at the end of cjcle 3 was 3 cc/ hour,.while no leakage was measured at 'the g:.- end of the fourth cycle. At the end of cycle four, the pump was started and run ten minutes to see if the seal would begin. leaking dyrimically; nocleakage was observed. q g 9.+, ~3.y.. .. --.p...-. -,- n.- - --.e--~~..?.~.----v.-.-?-*p.~.-ma-.-~~~.-----~;.-.. ~,

'.T T.m::...'. ~ a.:... ^ Page IV-6 The acceptance criteria for this test series was based on'the seal leak 197 rates. Under 48 hours running time or when the pump was in a cold condition, a leakage rate of 360 cc/ day (15 cc/ hour) was allowed. After 48 hours running time or when the pump was hot, the leakage could not exceed 180 cc/ day (7.5 cc/ hour). At no time during the " acceptance test series were these leakage rates exceeded. me 4.

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q, TABLE l_V-1 DYNAMIC TEST RESULTS AT 1000 PS!_G AND ROOM TEMPERATURE TEST INSERT GLAND GLAND NUT INSERT NO. OF LEAKAGE NO. DESIGN GASKET TORQUE, FT-LBS. BALANCE,% TESTS RATE, CC/HR. 1 Rigid Spiral Wound 40 - 175 37 12' 2 - 500 2 Rigid Spiral Wound 200 32 5 40 - 120 3 Rigid "0" Ring 15 37 2 24 - 30 ',i 4 Flexible Spiral Wound 200 37 1 16 c 5 Flexible Spiral Wound 200 32 3 2 - 12

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b d SE AL FLUSH FROM HEAT OUTLE TO HE AT EXCHANGER EXCHANGER 160 TO 180*F =

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GLAND RING il 9 3, I / / y 2 HOLDING RINGS L-t 8 \\ 180' APART TO KEEP 0 RCULATING RING i \\s / INSERT IN PLACE t I \\ RING ASS'Y. r-f \\ l / 7~ i NG CAR 62-6 g SEAL RING ( TUNG-CAR 62-6 h [ f;' f INSERT I ji EPT INSERT N; ( MOUNTING g EPT SHAFT EPT BACKUP ( PACKING RING 11 ( i Q 'f , \\\\ } A\\ J /1! s' 5+4iW"481W ' _ !j g 8lb 7'/A h s ,/ / '~ o R A, N L, t mx x x x x v h mx u si FIG. E -l TYPE "HPTCf DURA SEAL WITH .i RIGID INSERT MOUNTING DESIGN

Q O-SE AL FLUSH FROM HEAT OUTLET TO HE AT EXCHANGER EXCHANGER 160 TO 180*F <s, GLAND RING / # ~ / I I a s e g / 2-HOLDING RINGS /' 8 \\ 180* APART 10 KEEP IRCULATING RING \\ jj!,/ I 't p/ INSERT IN PL ACE ' \\' { r-x s. ,.r/, QU RI N G ASS

Y j

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==.h,'-T.~E.._..M-,3 Vi / / 4, t - r ?.L._... ,/ j,x y i 1 __j _ _ .o Ax rung.CAh G2 6 l r e o .N f -- l _8l SEAL Fi! N #2 i! N. '-j b, l. TUNG - CAR 62-6 a- ) 5 i y I N S ER T_. _. J. 1 EPT INSERT j ( MOUNTING q EPT DACK UP, EPT SHAFT g /- l } PACKING s\\ RING j { --o ./ f. \\. .], \\\\,%_y~.3 ~J4.17 W e T #31 F 1, 'f.,,h y/ f l f f N l ',/ / - A 1 N AN x ;,V b , l /,// k Y Y ORAIN / g i px x s jI m F I G. I3T - 2 3 TY PE "H PTO" DUR A SE AL W ITH FLEXIBLY MOUNTED INSERT DESIGN

1m. c l i !l ? 2 d t .i b o THERMOSTAT TEMP CONTROL .[ =t r 1 fl ELECTRIC POWER a L ~' SUPPLY N 1 -,~ HEAT EXCH ANGER DISCHARGE LINE O 1 (- 'y 15 GAL. WATER h i I COOLING WATER TANK INSUL AT ED ( ) 'j I 1 'I f ) P T SUGTION LINE g._.1.], .. '.(( f m. -[y... b-t e= ] ~~~h \\"\\ I i j 4 8 2/ INCH SE AL SIZE DURAMETALLIC CORPORATION 4 8 j A KALAMAZOO MICH. 3600 n eu. PRESSURIZING UNIT AIR POWERED r, PUMP TO MAINTAIN PRESSURE DESIRED untc SCALE N_O N E DH A*N D. AV ARD - M AME UP FIG. E-3 WA1ER SUPPLY Dwo. No. SCHEMATIC OF TEST S' TUP

F ,C ~. D' l l l FIGURE IE - 4 a 1 PRESSURE CYCLE TEST RESULTS 1 T,.,..., P.. I 1. i ..II , i.,, i ei. 'l., e .t.- SEAL C AVITY .i. .ll l ll.li .'8 'j.. 81* i,I g, TEMPERATE = 60* F ,l' ..ti i.i i .i 1000 iii. i., l .l. PRESSURE t. ~

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.n N 3 - 24. b ar c4 ) Ethylene-Propylene / threshold-1 x 106 rads / compression set ~ Although some experimental formulatiens showed poor radiation resistance, a number of commercial materials appear to be comparable to crosslinked polyethylene. As with other polyolefins, radiation resistance will depend on the effectiveness of antioxidant systems (especially at elevated temperatures). Reference 28 reports dose rate effects with greater degradation at low dose rates when the total dose exceeded about 2 x 107 rads for one ethylene-propylene cable insulation. Reference 8 details effects of radiation on cable insulation and jacket materials, including EPDM-based and EPM-based insulations (both mineral filled). No changes in oxidation resistance were found following total dose up to 108 rads (dose rate was 5 x 105 rads / hour). Elongation of the EPDM insulation was not significantly changed after 5 x 106 rads, but was reduced to 48% of the initial value after 5 x 107 rads and 37% after 1 x IOS rads. The EPM insulation retained 31% of its unirradiated value after 5 x 106 rads, 41% after 5 x 107 rads, and 26% following 1 x 108 rads. Reference 39 also reports very good radiation resistance of EP rubt,er (EPDM base) and that cables using special chloroprene jackets and EP insulation passed IEEE-383 tests. EPDM retained 79% and EPM retained 90% of the original tensile strength after 108 l O' rads. Changes in pemanent electrical properties were relatively unimportant. Reference 35 reports similar results for ethylene propylene cable insulations, but i reports that a fire-retardant additive appeared to cause instability of electrical properties in an EPDM-based material at exposures above 107 rads. Reference 55 reports minor reductions in mechanical properties of EP-F234 after 5 x 104 rads, but less than 25% decrease in those properties at 106 rads. A 50% decrease in elongation was noted after 2 x 107 rads and in tensile strength after 2 x 108 i rads. The 5 x 104 rad value is not cited above, since it is not generally applicable and does not represent significant change to the material. Barbarin6 recomended an EP compound (Parker-Hannifin E740-75) as exhibiting the ~ best known combination of radiation, fluid, and temperature tolerance. He warned that variations in compounding can cause wide difference in properties. One EP compound showed 28.6% increase in compression set after 107 rads and would be acceptable as a dynamic seal, while one (Parker-Hannifin E515-80) exhibited 46.6% ' increase in that property under the same test conditions. He recommended that no j dynamic, seals be used after radiation doses greater than 107 rads due to excessive compression set. Reference 61 indicates a 107 rad " allowable" dose for EP as for polyethylenes. 3-24 m- = - - -- ,__m

e m CATAWBA NUCLEAR STATION ENVIR0flMEllTAL QUALIFICATION OF SAFETY-RELATED MECHANICAL EQUIPMENT OL ~ 1. EQUIPMEtlT IDE!!TIFICATION: Pressurizer Power Operated Relief Valves 2. MANUFACTURER: Control Cor conents International 3 H0 DEL OR 10 NUMBER (S): C2GO-X2-X38W-X4BV-41AH43 Taas: 1-2NC328. 34A-36B 4. ACCIDEllT EllVIRONMENT: PEAK TEMPERATURE: 330 F DURAT10*1 AT PEAK: 10 -1,iges 0 0 RAD: 1.1 x 10 EXPOSED TO CONTAltlMENT VESSEL CHEMICAL SPRAY EllVIRONME!1T (BORIC ACID & SODIUM HYDROXIDE SOLUTION): Yes ~5. QUALIFIED ENVIRONMEtlT: O-imT'l TEMP RAD ACCEPTABLE FOR SPRAY REPLACEMENT INTERVAL REFS. See Comments and Reference 1 N/A 1 6 COMMENTS: Integrlty of non-metallic materials not required for-equipment .to perform Its current-safety functlon. 7.

REFERENCES:

1. Acc iden t. Envl ronmen ta l Ar.11 ys i s Repor t :. ' Coverinq 15003 Class 1 - (CHM-1205.10-0171) Nuclear Pressurizer Power Operated. Relief Valves n ~

m m,_...-= (2e le cene e d/ P c3 R V Pre ss.O e:e.a,- DATE ' ( ST ATUSI INIT. I Div REH nH A J AP ORD C me. K MGO r AA f v7 e is ,,yyg"$oys 1 5 1981 MAR m:=Wi2 pCO. arj QA CONDITION 1 DUKE POWER .A.mONM CHigF EN j ACCIDENT ENVIRONMENTAL ANALYSIS REPORT Sy: FOR DUKE POWER COMPANY, CATAWBA NUCLEAR STATION UNITS 1 and 2 MILL POWER SUPPLY COMPANY ORDER NUMBER A-63027 DUKE POWER SPECIFICATION NUMBER CNS-1205.10-1 and ADDENDUM #9 CONTROL COMPONENTS INTERNATIONAL WORK ORDER NUMBER 18789-1 ~ ~~ COVERING 1500f CLASS I NUCLEAR PRESSURIZER POWER OPERATED RELIEF VALVES DRAWI G NUMBER 921101010 6D DATE 2-M-8/ PREPARED BY: 1 Z. / V /f/ DATE REVIEWED BY: F APPROVED BY:_ h,e 'DATE L/9///- I c O CNM 1205 10-0171 ~ AM b ..~.. .._ _ _.~ __.-._ ____._, - ~ _.. _ _ _. -.. _.. _ _. _ _ _

y n TABLE OF CONTENTS

-)

PAGE NUMBER I. ABSTRACT....................... 1 II. BACKGRDUND AND INTRODUCTION.............. 2 III. VALVE AND ACUTATOR MATERIAL SPECIFICATION....... 3 IV. ANALYSIS A. ANALYSIS OF RADIATION IMPACT ON NON-METALLIC COMPONENT 4-5 B. EFFECT OF DEGRADATION OF MATERIAL ON ACTUATOR FAILURE MODE..................... 5 C. EFFECT OF SAFE SHUTDOWN EARTHQUAKE ON ACTUATOR FAILURE MODE..................... 5 V. CONCLUSION...................... 6 VI. REFERENCES.................,.... 7 f O. 1 DOCUMENT l, CONT 7,3 DATE MAR 51981 DUKE POWER COMPANT DE51CH ENGINEERING i L

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. \\ A8Ent The analysis valve-actuatorcontained in this I e / condition given in IEEE 3 assembly will fail closreport is t /w r.1 *-f of the degradation at of non-metallic 82-72. Table 1. Table durin exposure of the studied separatelyand effect of safe shutd mat were own The will fail close when b v'It is earthquake radiation effect concluded on the and provided proper temperature eing subjected the valve-actuatoractua that exhaust at the bottom to the / the actuator is maiaccident of . -f A* <; condition, ? ntained. ... ] .)j1- ~ M.x/J a A ~. Coy MEtty -~~t~/ w [&py_y " A. d.;ll' A A?Afl? Msn' w~ JM4 2 a 4 4 '.L ,c u T

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~, O II. BACKGROUND AND INTRODUCTION paragraph 8.1.16, states thal +M p*atsurizer Duke Specification CNS-1205.10-1, power operated relief valves and operators shall be designed t p O while being subjected to the accident environmental conditions given in IEEE , u%. 8 382-72. Table 1. Table 2, and Figure 1 concurrent with a safe shutdown earth-y The analysis contained in this report to [Ir lthedesignis quake (SSE). based on information obtained from other manufacturers and tests performed at Control Components International. It is not the intention of this report to prove the structural integrity of the valve-actuator assembly under the given accident environmental conditions. q E DOCUMiENT CONT'OL DATE MAR 51981 DUKE POWER COMPANY DESIGN ENGtHEERING j gn

205

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D III. VALVE AND ACUTATOR MATERIAL SPECIFICATION _ = The actuator consists of a 4130 steel cylinder, carbon steel springs 300 series stainless steel end caps, piston and stem, four ethylene propylene o-rings, two Halar piston seals, and Halar rod seal. (SeeFigure2and BillofMaterial.) The valve body, the bonnet, and the seat ring are made of ASTM A182 GR316. The disk stack is made of 410 stainless and the plug is ASME SA637 GR688-2 material. (For specific material of each component, please refer to Figure 1, and Bill of Material.) The stem packing material is GTN-70, and the gaskets are made of SS 347 and asbestos, low chloride. O 9 e6m C N M '120 5

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2 .z...... c. C H 120 5 10-0171 iv. # m vSIs ANALYSIS OF RADI ATION At4D TEMPERATURE IMPAC A. Metallic components, grafoil packings, and asbestos flexitallic gaskets / in the valve and actuator assembly are considered basicly immune to l{ / rr'adiationexpo7ure'.'iThecomponentsthatmayundergodeteriorationwhen I xpoieTtothe$adiationdosageandtemperaturegiveninIEEE382-72, ~~ O,[, Table 1. Table 2 and Figure 1, are the o-rings and seals within the actuator. As mentioned in the previous section, there are four ethylene propylene o-rings, two Halar piston seals, and one Halar rod seal inside the The following is a brief report extracted from vendor's actuator. literature on radiation and temperature impact on these materials: l i. - Ethylene Propylene ,'b5 ' ' ',. ~.5 , -i .;.b M* are conducted in a nuclear environment with a radiation Compression y 8 ith various grades of ethylene propylene (see Table dosage of 10 RAD The o-rings used in the actuator are the standard 7 Q 1 of Appendix). The results shows a slight increase in hardness 23 grade which is E515-80. N But there is a significant Zo E Em and some decrease in the tensile strength. g g decrease in the elongation in percent at break and tear strength. {0 The 3 to E. 5 U f o-g' compression set test shows a 96.2% compression set of the original 1 g N yj deflection after 93 days under 25% deflection. g I L J Halar "The radiation-sensitized grade Halar 502 resin was developed to permit efficient cross-linking at low dosages, typically 10 megarads, compared ( with as much as 30 megarads for the unsensitized grades. In addition to cross-linking more efficiently, radiation-sensitized Halar resin has f improved radiation resistance, i.e., it has better retention of properti ,i onexposuretohighdosages'(100-1,000 megaradsofradiation)."*

Quote from " Radiation Cross-Linking of Halar Fluoropolymer" by Allied Chemical.

See Appendix II, /ds[39

- - = DOCUMEN".~ ' CONTROL De :-- MAR 5 1981 O DUKE POWER COM41'Y DESIGN ENG; NET.9ING j A. Halar ontinued In Table I of Appendix II the material is subjected to a maximum of 4 As shown, 25 megarads of electron-bean irradiation at 73F and 392F. the strength of the material decreases significantly as the test temper-Table II shows the effect on the material when exposed ature increases. l to Cobalt-60 irradiation at the same dosage and temperature. The same results are seen. 1 EFFECT OF DEGRADATION OF MATERIAL ON ACTUATOR FAILURE MOD B. As seen in the analysis, both the ethylene propylene o-rings and Halar i seals and o-rings will undergo certain amounts of degradation when exposed l to the radiation dosage and temperature requirements given in IEEE 382-l 72, Table 1. Table 2, and Figure 1. Due to the compression set of the 4 f f.,,f .gls., tney are no longer able to maintain the sealing ability. /**~', Nevertheless, upon air failure, the valve and its operator will be driven to fail close by the spring preload force in the actuator despite the ( failure of seals, provided proper exhaust of the bottom of the actuator ~ is maintained. ~ Note: The exha ting devices are not within the CCI scope of supply. EFFECT OF SAFE SHUTDOWN EARTHQUAKE ON ACTUATOR FAILURE MOD C. i d test with applied side load was performed on a pres- . et*I. An actuator spee surizer power operated relief valve in June 1980. During the test, a \\ ~1 side load of 3,000 pounds is a,, plied to the bottom end cap of the stainless d 't,D': . 4. i The valve opened in 2.0 seconds, closed in:1.1 seconds, 'J.~ ,., steel actuator. I This and failed close in 1.8 seconds (see AppendixIII, paragraph 2.3). e test demonstrates the ability of the valve to fail close under the simulated. .a. : 3 :* r' C A.vp t./f seismic condition.f '; c,. e d '4 NE A-(f[g,"'" ' 7)y N "0NM 1205 10-0171 ~, s1/3? .. -... ~

f u. V. CONCLUSION The pressurizer power operated relief valves and operators will fail close while bieng subjected to the accident environmental conditions given in IEEE 382-72, Table 1, Table 2, and Figure I concurrent with a safe shutdown earthquake. y ?$* g 3e Y N I q? lQ CNM 1205 lI' 0.7 1 1 i 1 l 7 l l w

4e 19/A1

VI. REFERENCES 1. Duke Specificati)n CNS-1205.10-1 Addendum #9. 2. IEEE 382-72. 3. Parker Seals General Bulletin #23, March 1978. Radiation Cross-Linking of Halar Fluoropolymer" by Allied Chemical, 4. Specialty Chemical Division, 1975. Combined Seismic Analysis for Duke McGuire and Catawba, Revision F. 5. by B. Petrick, September 1980. s \\ g eae CEA1205.}0-0171 l l f ffffSN _ = = =,.._._,_=_

.~ e. APPENDIX I 'I DOCUMENT ^* Selecting elastomeric seals MAR 5198f ) for nuclear servic.e DUKE POWER m au.Ny DE5iCN ErfGI sc Compression set tests have proved more reliable than i tensile tests in the selection of elastomef compounds i for use as seals in a nuclear environment 05 10-017 3 o s By ROBERT BARBARIN, Parker Hannifin Corp 1 Seal Grnup In the early 1960s, the primary test Typical applications for elastomeric tests are frequently omitted as con-used in selecting elastomers for seats in and around nuclear reactors temporary cnteria for nuclear seal reactor seats was a tensile test con-include the static seals in pressur-compound selection. - ducted on unstressed stabs of the ized conduits containing radioactrye Of the three major types of radiation compounds after they had been sub-fluids, and the dynamic teafs in hom nuclear hssion, only gamma jected to irradiation. These standard structural hydraulic snubbers. rays are norrnally considered a tests had the unfortunate ability to hazard to elastomer seats that are rnake compounds look very appeal-Compression set completely enclosed in conventional in9 to the nuclear engineer while Compression set may be defined as metal grooves. Alpha and beta rays completely failing the primary re-the percent by which a seat fails to are effectively stopped by thin metal quirements of seat engineers. To-return to its original dimension after barriers. Gamma rays, however, day, a test has been developed compression, expressed as a per-easily penetrate the typical elasto-which promises to satisfy the cent of its deflection. This foss of meric seal glands and cause cumu-demands of both engineers. This is a dimensional memory is due to lative Changes in the compounds test to determine the compression Changes in the elastomer's arrange-(see TaWe 1). 8 set of seals which are simultaneous-ment and density of molecular cross links. As the change in cross-All elastomers tested to date have installed) and irradiated (as they linking progresses, the seal will shown excessive compression set at l~ ly squeezed (as they would be when rnay be when in service) over gradually take on the shape of the 1 08 rads, yet a number of com-( prolo,nged periods. The new data confining groove and relax the force pounds showed acceptable com-l - D, provide criteria by which com-that it exerts on the confining sur-pression set at 10' rads of glimma pounds may be selected for long faces. radiation dosage. life, normaRy requiring replacement only during conservatively sched. Since this normally occurs before Therefore, no elastomer known to-uled five-year reactor everhauls. tensile property changes, the tensile day should be considered for Table 1. Effects of gamma radiation on the principsf properties of ernstomeric compounds most often considered for seats m and around nuclear reactors. Compression set tests were conducted at room temperature and 25% deflection, for the numt:er of days noted, while under radiation from cobalt etnps in air. Generic or Radiation Hardness in Tensile Elongation Modulus in Tear Compression Set Test Base Polymer Dosage in Pts on Shore Strength in in % @ Psi @ 100% Strength Days CS in % of (Compound Rads

'A" Sca e Psi @ Break Break Stretch in Ib/in.

Deflec-Original r No) (Pts Chanoe) (% Change) (% Change) (% Change) (% Change) ted Deflection

silicone Original 69 807 117 668 63 93 7.6 63(0) 93 31.4 (5455 70) 107 72 (+3) 733(-9) 89 (-24) 93 90.5 108 85 (+16)

Silicone Onginal 66 1010 149 695 70 93 3.8 (S604 70) 1 07 69 (+3) 1020 (+1) 129 (-13) 833 (+25) 62 (-11) 93 20.0 29 (-59) 93 92.4 108 85 (+19) 939 (-7) 31 (-79) Ethylene Original 78 1450 213 689 164 93 16.2 ) Propylene 10' 78 (0) 1220(-16) 176i-17) 740 (+7) 148 (-10) 93 46.6 71 (-57) 93 96.2 (E515 80) 108 84 (+6) 1030(-29) 79(-63) 70 2080 233 554 174 93 6.7 10' 73 (+3) 2140 (+3) 194 (-17) 808 (+46) 163(-6) 93 28.6 Orep:nal 1 Ethyfene 70 (-60) 93 90.5 I Propylene (E740 70) 108 79 (+9) 1700 (-18) 96(-59) Fluorocarbon Original 75 1510 190 634 128 93 14.7 (V747 75) 107 76 (+1) 1580 (+51 130(-32) 1120 (+77) 87 (-32) 93 66.7 82 (-36) 93 93.3 108 88 (+15) 1180(-22) 29(-85) 7 Polyutethane Original 66 3560 582 342 306 56 17,1 l (P642 70) 10' 67 (+1) 3570(0) 491 (-16) 444(+30) 374 (+22) 56 55.2 146(-52) 56 91.4 108 66(0) 1420(-60) 201 (-65) huoro. Original 68 1050 180 520 72 128 13.3 128 67.6 silicone 107 72 (+4) 668 (-36) 97 (-46) 128 97.1 p af'c (1.677 70) 108 84 (+16) PouWER absGeestteister19ecanasta terr l 6 L- - - - -

- s w.:..m ..n., a. a . appffcations where 10' rads dosage ties after exposure to 10' reds. At not be recommended because they will be exceeded between schedu!ed this dosage, two milicones, two all tested out at marginal or ex-Oltriles and one ethylene propylene cessive compression set.The results overhaufs. compound exhibit acceptable com-for polyurethane are particularly Table 1 documents several com-pression set. A second ethylene revealing; the tensile, tear and pounds frsquently considered for propylene compound, as well as modulus tests were either uri-nuclear seals, showing their original polyurethane, pofyacrylate, 71uoro-changed or actuaffy improved by 10' properties and those same proper. carbon, and fluorosilicone, would rads, but the compression set rose from approximately 17% to over 55%. j Temperatures and fluida Service temperatures and/or fluids f p,.w. 9 m,_ ,74% m r/MMA often degrade an elastomer faster and more severely than gamma s.P., .fM W W Y"' M. ,,..[y- %.... g .c g

f j radiation. This is illustrated clearly
s M

w ( W-D,, -j,4 and 2. While Table 1 shows the ( by comparisons between Tables 1 N %' %'.. : 'i' s 1 i effects of gamma radiation without H 6M 'EM%d dhM j fluid or temperature influences, Tabfe 2 shows the effects of fluids O % Compression Set - C X 100 g I D and temperatures frequently on-i countered in nuclear reactor en-t [ l vironments but without the camma g 9 radiation. It is interesting to note W that the pofyurethane degradation M, m d T T documented in Table 2 was the ?'CS=10%}. [CS=30%4 [CS=60%* result of temperature, but that it i/ O- -- 3 - k would doubtless have been at-l '( \\ tributed to radiation if it had oc-UT d I curred in a reactor. o' i [ .t I The combined effects of radiation, U SEALING FORCE VS COMPRESSION SET temperature and fluid are seldom a N, I simple addition of their individual f effects, but are eynergistic. How-Td i Figure 1. Compression set (the percentage of initist deflection which is ever, knowledge of all three char-unrecovered when a seat is released) cirectly affects the force that a acteristics for each compound wil! compression seat can maintain on its seating lines. This factor, which is help in the selection of the best E increased by raciation,is a prime critonon for the selection of asals for compounds for testing. essctors. Z Table 2. Effects of fluid immersion in principal reactor fluids on polyurethane and othytene propytene elastomers consicerad for sea's in and arounc nuclear reactors. Note severe effects of temperature excursions Q on properties of potyurethane compounds compared to the properties of most othytene proryienes. Gener,c or immersion Test Fluid Hardness in Tensile Elongation Modulusin Volume Compression Base Polymer immersed 3 hrs @ 340F Pts on Shore Strength in in % @ Psi @ 100% Change Set in % of (Compound + 3 hrs @ 320F A** Scafe Psi @ Break Break Stretch, in % Original No) + 18 hrs @ 250F (Pts Chancet (% Chencat (% Chancat (% Chancet De'le-tion Polyurethane Original properties 95 7240 470 1590 (P4611) GE SF 96 Silicone (200 ds) 89 (-6) 4250(-41) 537 (+14) 1370 (-14) -0.8 119.2 GE SF1154 Silicone 89 (-6) 3650 (-50) 550 (+17) 1400 (-12) - 0.3 cancelled Water 89 (-6) 4680(-35) 576 (+231 1180(-26) + 2.3 96 5 Polyurethane Original properties 66 3780 699 350 (P642 70) GE SF 96 Silicone (200 c/s) Deteriorated - 1.7 cancelled GE SF1154 Silicone Deteriorated- -2.2 sancelled Water Deter. orated-Ethylene Original properties 73 2390 177 991 Propylene GE SF 96 Siticone (200 c/s) 73(0) 2BP (+17) 207 (+17) 865 (-13) - 1.5 19.9 (E740-75) GE SF1154 Silicone 70 (-3) 2660 (+11) 198 (+ 12) 800(-19) +3.0 17.8 Water 74 (+1) 2600 (+9) 182 (+3) 873(-121 0.0 14.4 i ) Ethylene Origina! properties 88 2330 146 1230 $f., Prcovtene GE SF46 Silicone (200 c/s) 91 (+3) 2330(0) 146 (0) 1500 (+22) -2.5 44.9 (E652 90) GE SF1154 Silicone 89 (+1) 2430 (+4) 143 (-2) 1490 (+21) +0.4 cancel at Water 90 (+2) 2450 (+5) 145 (-11 1430 (+16) - 1.0 42.0 Zc CD Ethylene Originat c*operties 61 1450 273 279

3 Propylene Gi. SF 96 Silicone (200 c/s) 61(0) 1680 (+16) 317 (+16) 296 (+6)

-4.5 29.6 I,o, LD U I ~ (ES29 65) 'GE SF1154 Silicone 60 (-1) 1520 (+5) 273 (+2) 290 (+4) -2.1 28.4 3. W ate < 61 (0) 1590 (+101 298 (+9) 276(-1) -0.1 29 8 N6-Ethylene Originar properties 74 1610 239 563 6 I-Pronytene GE SF 96 Silicone (200 c/s) 72 (-2) 1350(-16) 209 (-13) 578 (+3) - 3.4 25.4 OU (E692 75) GE SF1154 Silicone 72 (-2) 1620 (+1) 219 (-8) 549 (-2) +0.8 30.5 Water 73(-11 1100(-32) 171(-28) 545 (-3) + 0.2 16.7 np/J e - =n

JUL 2 1979 APPENDIX II r[n-m p-...,,,,.., ~ ;... .~.- = -- nw, n - mu._,..,%s i, !,,u !<e 9(p a = = b Y; y[o [, 15, ',. - 'sur M j'.. i= L r n l f s Pw'. sL.__....._. ri ur.. _.., './ ".. i._ L..n._'difN. *W' diam' s..o RADIATION CROSS-LINKING OF 6 HALAR@ FLUOROPOLYlV!ER c

S e

Section Contents gpo Radiation-Sensitized HALAR Grades % Effect of Radiation on Tensile Properties $j Effect of Radiation on Thermal Stress Cracking Radiation Resistance f-Custom Irradiation of HALAR i e C ggg 1205 10-017h X {I T gg/J7 u F-muu

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WNTi'.-CSU2 ', ' ~ O, C N M 1205 10-017 1 W CUKE POWER COMPAb Y - RAOIATION CROSS LINKING OF HALARe FLUOROPOLYME:1 DESIGN E ~ When expsed to ionizing radiation, HALARS fluoropolymer cross links and, thereby, becomes infinitely high in molecular weight. The formation of a cross linked network accounts for the unique properties of irradiated HALAR fluoropolymer and is the reason it can be classified as a " radiation-resistant" polymer. i l H Radiation-Sensitized HALAR Resin The radiation sensitized grade HALAR 502 resin was developed to permit efficient cross-linking at low dosages, typically 10 megarads, compared with as much as 30 megarads for the unsensitized grades. In addition to cros linking more ef ficiently, radiation sensitized HALAR resin has improved radiation resistance,i e.,it has better retention of properties on exposure to high dosages (100 1000 megarads, of radiation. Radiation sensitized gradesof HALAR resin also contain proprietary additives that minimize the evolution of acidic gases and in oxidative chain scission reactions. These grades are recommended if postcross linking is to be performed or if HALAR resin parts are to be used in applications where radiation resistance or high temperature resistance is re quired. Effeet of Radiation on Tensile Properties Tables R l and R il show the effect of radiation on the tensile properties of HALAR resin at 23*C and 200*C. The most dramatic etfect of radiation is to increase the breaking elongation and work to break of HALAR resin at elevated t> 150*Cl temperatures. A cobalt 60 dosage of 10 megarads, for example, increases HALAR resin's breaking elongation at 200*C from 25% to 410E The work to break of irradiated HALAR resin is increased at five megarads by a factor of 50. The increased work to break of irradiated HALAR resin accounts for its en-hanced toughness and better cut through resistance at elevated temperatures. The properties of HALAR resin at I ambient temperature are not significantly affected by low dosages (5 megarads) of radiation. Higher dosages cause a progressive decrease in breaking elongation. 1 Effeet of Radiation on Thermal Stress Cracking [ T Radiation cross linking of HALAR fluoropolymer greatly increases its resistance to thermal stress cracking. A 4-dosage of 10 megarads renders HALAR resin strips completely resistant to thermal stress crackingat200*Cin 3 mandrel wrap tests (Fed. Spec. L P 390C, Part H). Unitradiated H ALAR resin cracks within two hours at 200'C in this wrap test because of the very high stress levels imparted to the specimen. Radiation Resistance Radiation resistance refers to retention of properties on exposure to large dosages of ionizing radiation. HAL R resin ranks amongthe most radiation resistant of polymers. Radiation sensitized grades of HALAR resin rnaintain useful properties even after exposure to 200 megarads of cobalt 60 irradiation.The overall radiation resistance of HALAR resin compares favorably with ultra high molecular weight polyethylene and ismuch superior to PTFE and FEP polymers. PTFE and FEP are adversely effected by changes as low as 2 megarads The comparative radiation resistance of HALAR fluoropolymer, PTFE, and FEP is illustrated in Table R Ill. Cobalt 60 dosages of greater than 25 megarads cause PTFE and FEP to become weak and fragile. Exposure to a dosage greater than 50 megarads reduces the strength of PTFE and FEP to a level too low to be measured by standard instron techniques, HALAR fluoropolymer, on the other hand, maintains useful pruperties even after exposure to dosages of 200 megarads. I CUSTOM IRRAOIATION OF HALAR FLUOROPOLYMER Industrial irradiation is normally accomplished by exposing a material to cobalt 60 or to high enrrgy electrons. ~ A cobalt 60 source emits gamma rays which are capable of penetrating thick sections of matter. When exposed l to cobalt 60, most, but not all, organic polyrrers undergo cross linking reactions. Cobalt 60 cross linking is a l relatively slow process which requires hours of exposure to achieve high cross link densities. Irradiation by l

.e high-energy electrons is accomplished by exposing a material to the rays emitted by an electron beam rr achine.

l ? High-energy electrons have low penetrating power and are only effective in cross linking thin-wall (> 1/8 in.) .c items such as wire, tubing. shcet, etc. In contrast to cobalt 60 irradiation, electron beam irradiation is a rapid process which can be comp!eted in a matter of seconds. For materials that can be rapidly cross linked, electron beams may be used in line with processing equipment such as wire coaters or tubing extruders. 33dM : j

- m._ 1

y. -

There are a number of facilitics throughout the country w g I dosage, and the volorae of the package. Isomedix, Parsippany, New Jersey, is a typical facility equipped for cobalt.60 irra be ir. curie cobalt 60 sources which are located in a heavily shielded room. Product to radiated is placed on one of several turntables in the shielded room. The source, w tains two 150,000 be pool of water, is brought to a point near the product and held there for a preset t rotatsd to give a high degree of radiation uniformity. Dosage depends primarily exposed to the source. Distance from the source is the be accommodated with some sacrifice in radiation efficiency. Typical 1973 prices quoted by isomedix for custom irradiation are $1 per cubic in excess of 50 cubic feet. Isomedix can irradiate wire and cable on spools of various sizes.The 1973 price i exposure. For a 4,000 foot reel, this corresponds to $3.75 per thousand feet, a $1.36 per thousand feet. Specific prices are dependent on quantities involved. Radiation Dynamics, Westbury, New York, is a typical custom irradiator equipped f irradiation. The company maintains two Dynamitron 1500 KV,10 MA beam scan over 2 f t. wide conveyor belts in a room shielded by several feet of concrete. Th $100 an hour or S550 6 day.Their conveyor system can handle 800 f1 / hour at 5 2 object that can be accommodated measures 24 in. x 48 in. In general, objec in. can be irradiated by electron beams. Objects with thicker walls should be irradiated Radiation Dynamics is equipped to irradiate wire and cable having outside diameters dosage of 5 megarads,the 1973 price is 53.00 per thousand feet. J NF 120 5 :.0-0171 t TA8LE R-l EFFECT OF ELECTRON-BEAM IRRADIATION ON THE TENSILE PROPERTIES OF HALAR FLUOROPOLYMER GRA DOSAGE Yield stress Break stress Yield along. Break elong. Modulus Work to break i I

C (megarads) psi psi psi psi Temp.

t 5 11,000 23*C (73*F) 0 4650 8100 4.5 225 2.0 X 10 5 10,800 f 2 4700 8050 4.5 220 2.0 X 10 5 10.300 5 4600 7700 4.0 210 2.0 X 105 g,400 10 4550 7500 5.0 215 2.0 X 105 7,100 25 5450 8100 4.5 175 2.5 X 10 3 35 200*C 0 265 215 10 25 2.8 X 10 2 295 235 35 145 2.3 X 103 310 (392* F) 3 1,150 5 335 435 30 430 3.5 X 10 3 1,350 10 295 575 35 520 2.7 X 103 25 370 770 35 355 3.4 x lu DOCUMENT h. CONTPOL DATE 7c i M 51981 j j DUKE POWER r NY l I 27hf DESIGN ENG: 1 f { /00 e-

.v- -\\; TABLE R-Il EFFECT OF COBALT-60 IRRADI ATION A ON THE TENSILE PROPERTIES OF HALAR FLUOROPOLYMER GRA Temp. Dosage Yield stress Break stress Yield along. Break elong. Modulus Work to break

C (megarads) psi psi psi psi 5

9800 23'C (73*F) 0 4250 7750 4.5 235 1.8 X 105 9600 2 4500 7650 4.5 215 1.7 X 105 9400 5 4650 7550 4.0 200 1.8 X 10 5 8800 10 4520 6850 4.5 170 1.7 X 105 6200 25 4470 4600 4.5 105 1.7 X 10 3 35 200*C (392* F) 0 265 220 10 ~25 3.4 X 103 720 2 310 250 30 275 3.5 X 103 2000 5 315 630 30 490 3.7 X 103 2100 10 325 710 35 410 3.7 X 103 1550 25 310 580 35 390 3.6 X 10 CNdi 1205 10-0171-TABLE R-lit r s.. COMPARATIVE R ADIATION RESISTANCE OF FLUOROPOLYMERS Tensile break.ing stress (psi) -- Cobalt 60 el ngation at break (%) dosage HALAR (megarads) FLUOROPOLYMER PTFE FEP 0 7000/210 3000/300 3000/290 50 4600/105 900/<5 1500/<5 100 4200/65 500 4000/20 1000 2800/10 ~ I

Too low to be measured.

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~ .,. Z.. ..r-.r-is APPENDIX III Control Components,Ippy p g h) jjj f t i j U f-j G-4 a sut;5 diary'of BabCo:K &WilcoX i D. W. Smeller From M. Coleman File No. or Ref. 18789 1 Cust. Duke Power D MW Actuator Speed Tests with Aeolied Side load Subi. 1.0 SCOPE _ To set up and operate valve / actuator assembly per TP-532. 1 1 2.0

SUMMARY

OF TEST RESULTS 2.1 With the valve body pressurized to 2500 PSI, per customer's request, stroking time without any side load was: Time to Open Time to Close .71 seconds .91 seconds .61 seconds .92 seconds .71 seconds .90 seconds 2.2 With valve body pressurized to 2500 PSI and a side load of 2130 lbs, force applied to lower actuator end cap, stroking speed was: Time to Open Time to Close .75 seconds .91 seconds .74 seconds .94 seconds .74 seconds .90 seconds 2.3 Valve / actuator performance with 3000 lbs force applied to the lower actuator end cap was: 2.0 seconds to open,1.1 seconds to close, and 1.8 seconds to fail close from the full open position. This extreme side load condition is not required per TP-532, however it was perfortred by CCI's Research and Development group to illustrate the performance and structural integrity of the valve / actuator assembly. The stroke times mentioned above were taken with a hand held stop watch. The stroke times mentioned in paragraph 2.1 and 2.2 were taken by electronic stop i clocks actuated by switches at the top and bottom of the actuator shaft's stroking range. 2.4 The valve / actuator assembly did move to the full close position with ~ 1.oss of electrical power and.with 1,000 PSIG remaining in the valve body. g ge*j C N1 120 5 10-0171 30 C + a g6v .9 f[,g[J7

u.. R G-5 .~ Actuator Speed Tests with Applied side Load - 6/6/80 3.0 PERFORMANCE REQUIREMENT With 80 PSIG air supply to the actuator and a side load of 2204 lbs force applied to the lower actuator end cap, the 3.1 T')is valve / actuator assembly is a fail closed device and should move from the full open position to the full close position with the loss 3.2 of electrical power and with a valve body press!!re > 500 PSIG. ze ad-w M. COLEMAN s c@ b.

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