ML19261D825
| ML19261D825 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/22/1979 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906260463 | |
| Download: ML19261D825 (72) | |
Text
{{#Wiki_filter:%< - i .: _ 500C Chestnut Street Tower II Director of Nuclear Reactor Regulation Attention: Mr. S. A. Varga, Chief-Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Varga:
In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 Enclosed is additional detailed information for Sequoyah Nuclear Plant relating to the seismic qualification data package submitted for NRC's Seismic Qualification Review Team (SQRT) by my letter to you dated February 7, 1977. This data is being submitted in response to P. Y. Chen's request, made in a telephone conversation on April 25, 1979, that TVA provide:
- 1. Applicable seismic floor response spectra for each of the equipment items for which seismic qualification data was provided in the data package.
- 2. For those items of equipment which were qualified by tests, a demonstration that the seismic qualification requirements had been satisfied, i.e., that the test response spectra envelope the required response spectra consistent with the proceduree of IEEE 344-1975.
The enclosure provides this requested information for each of the equip-ment items of interest. For each of the seismic qualification tests, general discussita and data points illustrate that the tests satisfy the seismic qualification requirements with a margin of conservatism. 2312 082 c'o\e q/
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7906260 76,0
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Mr. S. A. Varga, Chief This response completes the followup action items related to NRC's seismic audit of Sequoyah safety-related equipment qualification. Very truly yours,
/ ,
o
<.. . 1 J. L. Gilleland Assistant Manager of Power Enclosure 2312 083
. f 4 ENCLOSURE SEIShtIC QUALIFICATION OF SAFETY-RELATED EQUIPMENT - RESPONSE TO NRC QUESTIONS RELATING TO SEISMIC QUALIFICATION DATA PACKAGE SUBMITTED FEBRUARY ,, 1977 2312 084
. t Auxiliary Feedvater Pumps Auxiliary - Control Building - Turbine Driven - Elevation 669 (base slab ) Motor Driven - Elevation 690 Applicable floor response spectra are attached. Ground motion spectra are applicable to elevation 669 ror the turbine driven pump. Figure B-3 is the horizontal OBE; the corresponding vertical motion is equal to two-thirds of the horizontal. Maximum earthquake levels, SSE, are equal to twice the OBE levels. Figures c-3 and D-3 are the horizontal OBE spectra applicable to the motor-driven pump, Because the equipment orientation in the building is not necessarily defined at the time ot equipment contract award, the equipment qualification would reflect the application of the envelope of the N-3 and E-W spectra in ench of the equipment horizontal axes. The auxiliary - control building is rigid in the vertical axis; therefore, the ground motion vertical spectrum (two-thirds of the level of figure B-3 for OBE) is applicable to all building elevations. Again, the SSE levels are obtained by doubling the CBE levels. 2312 085 (1)
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. / Heat Exchanger - Comronent Cooline Water Auxiliary - Control Building - Elevation 714 Applicable floor response spectra are attached. ilorizontal OBE spectra Figure c-9, n-3 Figure D-9, E-w Vertical ODE spectrum Two-thirds of the figure B-3 levels SSE levels are equal to twice the OBE levels. The general com.ments regarding the auxiliary building spectra presented for the auxiliary feedwater pumps are also applicable to the heat exchanger spectra. 2312 089 G (1)
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. t Main Steam Isolation Vsives The WIV, as, an inline mounted device, is seismically qualified for the maximum response of the piping system (at the valve location) into which it will be installed. This criteria for TVA's Sequoyah plant is 3 g horizontal (two perpendicular axes ) and 2 g vertical. To ensure compatibility between the valve qualification and the piping system analysis response levels, the 3 g/2 g acceleration levels are considered as dynamic input motion to the valve at any frequency within the range of 1 to 33 Hz. As previously stated (seismic qualification data package submitted for faC-CQRT review) the MSIV's are qualified by analysis in conjunction with the vendors generic testing program. Attached are copies of bulletins provided by the MSIV vendor, Atwood and Morrill, which su marize the generic testing of their valve design.
- 1. Development of Msin Steam Isolation valves for I;uclear Power stations.
- 2. Technical Bulletin 77-02, Pipe End Load / Static Lend Test of 22-inch MSIV.
3 Technical Sulletin 77-03, sonic ilow Test of a Main steam Isolation V,1ve. 2312 093 (1)
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g * [ hh]' , C'RN . %- -992 by Norman F. Prescott Atwood & Morrill Co., Inc., Salem, Massachusetts The Wy e ty pe Ntain Steam hola. moderated type. The primary coolant background for the Company to make tion Yah e with an .ur/sprmg operator of the PWR .3 circulated through heat a logical tranution from Nas y work n today the st.mdard deugn for Pail- exchangers to produce steam whereas to cornmercul nuclear work Atwoo t mg Water Reat:or mstallations. Thn m a boding water reactor (or BWR) & N1ornll Co. was one of the first vah e same s ab c. with some modi 0 canons, as designed by General Electric. steam manufacturets to take a special inter-has also become the most frequently is obtamed directly from the reactor est in the specilications for these new used design m Pressuri/ed Water Re- sessel wahout the use of a secondary N1am Steam Isolation Vah es. 'I bey actor instalianons. It is the type of heat eschanger As a result of the became actisely eneaged m a de m sabe wluth has had more esperi- direct contact with the reactor. the and engineering procram which L ' mental testmg than any other design. steam supplied in a BWR is radio- to the msesagation of several types and as dependable operatmg espen- actis e. of valves and ditierent methods of ena unh a h ntory of suesessful .\!ain Steam Iso l anon Valves were operation, with a selechon procew installahons piosides the highest lesel ene of the most important safety re- considering the fu;Iowing vahe et conhdence m as use. Atwood i lated items neccoary for the operation desmns. Mornil hase m servae or on order - of a BWR plant. and the type of sake eser 400 Wse Type Valves for BWR best suded for this service became the GATE VALVES and PWR sers ice. subject of intensive studv. A perfor-mance specification was' written. de- A gate vaM would hase a low BACKGROUND AND scribine the necessarv functions and pn'wwe p and could rneci the DEVELOPMENT desirable features of'a valve suitable tightness requirements. howey er. the Ihe succen m the use of nudear for BWR use These included'. operanog faces agamst a dalerentul power by the United States Nan soo" of 1000 pu or more would be verv ( ) Lc'v pressure drop. high. A standa rd mothr opera tor led to a con .Jeraton for commercial . u ou!J :cly on e!ct toc power and tooid purposes. I he tu o major U.S. turbmc " - manufactureis that had been promi. (3) 'I,he abiluy to open agamst a dit.- neither (1) meet the closme i.me of 3 ,g g gg g nent m the Nas al Nuclear Program terential pressure' fail fe non m le d h g' entered the tield of commereul nu. (4) Closmg time adjustable between clear power. u uly each takmg a dif. 3 to 10 seconds ferent prmciple for development (5) Means for testing through partial PLUG. BALL AND u i tmghouse. Lombusnon Engi- stroke and return. BUTTERFLY VALVES neenng and Babcock & Wdcos chose (6) Simpheity and rehabihts of Acceptable prewure drops could be to f..llow and develop the prewunted operanon.
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oinamed wah vanous other forna of water ieattor as used by the Umted valves. such as p!ug valve 3. hail s altes States Nau. w hile General Llectoc The espenence and design ability and buttesdies. each wah unrestocted pioneered u uh a durerent m e t h ed. of Atwood & Morrill as proven in the port openings similar to the gate Hoth 9stenn were of the light water Navy nuc!e.ir program prosided tife valve. These Jeugns were aiso reject-T ' ,.7au u 79
- 1 2312 094 .
. i ed sur the same reason that the opera- main valve to be of the balanced type. movement of the valve stem. This tes forces neuded to open and close Since the design of a balanced type opening of the pilot substamially would be sery hyh. and seat tight- valve was usually found in a globe equalizes the pressures above and r.c w micht be ditheult to obtain or or angle valve. it was necessary to below the main disc. so thal further maintain, recon >ider the unacceptable pressure movement of the valve stem causes . drops of these body shapes. The line the mam valve to open. The Atwood GLOBE OR ANGLE VALVES of reasoning eventually led to the Wye & Morrill de ign uses a spring acting T he body shape of a globe valve shaped body that provided straight- to open the pilot whenever the main ha 'he hichest pressure drop of most through flow with the least internal disc is off the seat. This spring forces of the sahes considered. An ancle obstruction. , the main disc toward the seat without boJs has a prenure drop le>s th'an "Ihe only detas! left in the specifi- allowing the pilot to close. thus pro-a givbe valve. but still higher than cation for the ideal valve o meet was viding a smoother clusing operation deured. the adjustable closing time of 3 to IG of the main vahe. This also became
, , , seconds. Some speed control could be a patented feature of ti Atwood &
realized by the use of throttling valves Morrill design. It was apparent that the final Isola- in the air discharge from the main tion Vahe design must be a et mbina- The final A&N1 valve incorporated operating cylinder. but the stem forces all of the features desired by the spec-tion of the desirable features of both would vary during the closing of the salve and operator, and the study abo iticanon. and in 1964 became the de-vahe. and a compressible fluid such sign adopted by General Electric Co. considered operators to obtain the as air would make precise speed ad- for their Doiling Water Reactors. The bee overAt design. justment quite di!1icult. valve is bric0y desenbed as follows: ELECTRIC OPERATION The A&N1 Ntain Steam Isolation The u e of electric power would be Valve is a butt welded end. Wye type
"" ] body. hasing a single seated construe-limited to motor operators which are tion with internal pilot. The vahe too d."v to meet the required 3 to 10 l operator is dc>igned for a nominal air seconJ doime of these large valves.
Although some ball-screw operators j y**"i e pressure of 100 pug and is composed of a pneumatic cylinder and an equal ca n p.s ude last stem mos emen t. other p.oblems would then an>e from
; [ dnplacement hydraube cyhnder for impa t on closure and the need to i e speed control. The main valve is air i
opening, air and spring closing. with absorb the closing energy without j _ a control panel composed of redun- ( wear or damace to the val.e. 3 dant solenoid operated valves and \ HYDRAULICS
- hydraulic speed controk. The vahes m may be tested through a stroke of Hydraube pressure could produce
" approximately 10"c. and arranged to pon s. and 3 peed. The disadvantage
' ' ' automatically return to the fully open woulJ occur m the amount of auul. - -a ' '
posinon after the test stroke has taken sary celuipment m the foim of pumps. n , ..,, '.. , , , [, , ,,, [.m . . . ., j. ,, < place. Limit switches indicate the accumula toi3. and control valves, all open, closed and test stroke. of whath would be vulacrable to dam- f,,,ca, asm,g A,yacmm ,a .gof sf;;f n age and the poribihty that the m.un n io<fc / pr anmc o"ic lo..ccn ismi m valve would fail to close if accumula- m "m/8 A&M VALVE INSTALLATIONS tor pressure was lost. The first valves were ordered by It became esident that a non.com, General Electric Co. from Atwood & PNEUMATICS pressible 11uid w ould nive more Aforrill Co. m 1965 for a BWR instal-A low prenure compressed air and dependable adjustment, arid an cyial lation in Tarapur. India. This order spring >> stem would have many de- displacement hydraulic tylinder was was closely followed by similar sabes sirable features. such as low first cost. installed in series with a pneumatic for the Nine Nhle Point station of reliabditt and cleanliness. and the
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operating cylinder havmg an adjust. Niagara N!ohaw k Power Co . the O)s-simplest form of tored energy. l he able hs draulic bypass to cmrtrol ter Creek Station of Jers2y Central one dhadiantan uoald be the rela- spteJ. ~ihn Atwood & Alanill ms en. Powr & Light. the Ntonusel!o htanun tn ely small stem forces that could tion was unique and was granted a of Northern States Power Co.. and be generated by the low pressure air. patent. continuing succenively up to the The pressure balancine of the main present time of 1976. MM has e in-FINAL SELECTION OF BWR valve to accommodate tIie use of the stalled or on order 248 stain Steam VALVd. AND OPERATOR low pressure air cylinder was obtained Is lati n valves in I1WR plants. (Inch. ding Patented by the choice of a single seat pilot * *
- operated valve. This de. sign is com- ATWOOD & MORRILL VALVES A&M Faatures) posed ora main dhe or seated portion. /
In .. seu . of all the design options. the low piessure compressed air and and a cylinder chamber extendmg FOR PRESSURIZED WATER REACTORS ( upward and htted mto the bonnet spimg system otrered the most desira- poroon of the body. The pilot vahe The >uccessful use of air and spring ble means of operation but the rela- which is part of or attached to the operated Wye type Main Steam hola. tn ely low stem loads would requa t the valve stem is opened by the nrst tion Whes for flailing W.aer 1(eac. 2312 095
. a tors has proven their dependability.
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conventional seal such as piston rings. 1969 - A 26" full size valve. also with and has led to their use as Alain Steam Testing has shown the seal to be very various val.e openings. Isolation Valves for Pressurized Water effective. Reactors. The valves for PWR systems . . . 1970 - A 26" full sited vah e for are larger than those for the Boiling various valve openings and poppet Water Reactors. with the additional TESTING PROGRAMS conngurations. requirement that valves must clo3e The onEi nal A&M valves were con-with flow m either direction. structed more than 10 years ago. In Atwood & Morrill Co. initiated the mappygg- %q bi-directional valve by the use of an addition to successful operating expe- NW ,
.. articulated" internal pilot that will rience. extensive testing has been ear-tied out continuously since that time 1% / ,
perform all of the functions of the e s ~ conventional pdot for opening in the f r verification and improvement of i normal 0ow direction. The articulated the design. The following is a li>t of ,. feature of the pilot will also allow it tests awomplished and/or scheduled ^.s, to open on reversal of flow and permit pressurization of the balancing n A&M type valves.
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chamber.With the main poppet under (1) 1966 - A 24" production valve w, - was hot tested at a temperature of ' h.. balanced conditions, the sprmg clos-ing mechanism will move the main 650 - 700* F and a pressure of 1000 f. &
- d valve to its seat Another requirement w hich the psig, and stroked repeatediv to prove the ability of the valve to'open and IQ:' " " . 4.]. ~'. Tef close under operating pressures and > r# 4 valve must nicet is that of tightness temperatures. .vonnan r trcrcou trefr>. author, an / f under a reverse flow condition. Al- coat, pu,j,c, y,gm,c,, ,,,,,, ,.,,,,, iers g,3, r, p
though the main valve is of single seated construction there is a slip-fit (2) 1969 - A 20" Main Steam Isola- '#"' 'h"f
'"" """# #"""K /'"'" 'c""/" /"Il u <
in the balancing cylinder that would tion Valve was tested under guillotine break conditions by General Electrie allow back-Row leakage. Atwood & Morrdi Co. msented and patented a and Commonwealih Edison at the . State Line Station of the Common- -A un med 24" produe-skirt seal that is normally disengaged tion v was tested under pressure wealth Edison Co. Some 40 flow tests from the cylinder wall throughout the '" "**CI """ I $l V"I"C' tormal hte of the valve. !t will expand under simulated accident conditions m e w Us of the body."The valve C.and wntact a special hard-surfaced showed that the desien would com-~ w s studied under both brittle lacquer pletely and reliably shut off flow. The area within the cylinder wall only nd strain gage methods with internal uhe, a back tlow condition anses. flows were combinations of postulated actual conditions of water, mixtures Pressures raised in increments to 1800 of steam and water, and steam. P"S .The pressure was returned to
. g, . zero in the same increments, and the
! MY (3) Development and flow testme body stresses showed complete lin.
' E *! Id 'M was conducted by Atwood & Morrill canty and were well within the design
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t Co. at the Alderi Research Labora- values f the ASME Code. d , =d Y .-- tories of the Worcester Polvtechnie
^' { '
P. Institute to obtain body desidns with (5) 197a, - A Licensee of Atwood &
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rr , ,. Morrill Co. in Japan. Sippon Sea!ol. rr rr er , manufactures MSIV's for the Japa-
%~ 1' E V',, e I,. dQ.@i [* , : TITtK,'p[ . nese nuclear plants. Their tests in-N rl clude opening and closing under full ih-r...II.I,il N ,J...4; 5I I2I " q.i, ~' g g a . , - . .
working temperature and pressure
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Z Tig ' conditions. These tests.as well as other operational tests, were required hv the
.- i ; J p nese gosernment before permit-
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tme any Main Steam isolation \ ah e i ':' '.'> An a t is mn . sun Iml.amn ral.c n><.d/c./ -- ' ! on a kniraulu teu !.wp)or vertfacanon ofreverse .
- gg J)e installed in nuclear plants.
flaw clawrc sharas scrnncs w... - . .n ~ [ ' (6) 1974 - A 26" valve wuh an artie-ulated pilot was tested for closure The seal is 3 elf-energized from the 0 w path characteristics that would with bi-directional Dow. This type of res crse direction and will expand out- E'M the least pressure drops. This valve speci6cd for i>WR use wa's orie. wardly and tightly against the hard resung was made with modek as wcll inated by Atwood & Mornli Co. Th'e nrfaced aica. The feature and a ' van- as full sized valves. Such tests were: purpose of this valve is to close on 'I
\ age of the >kirt seal is the complete . receipt of signal including condaions freedom as the valve moves from open 1968 -- S" and 10" modeh tor forward of a guillotine pipe line break caher to close in the normal direction. 'I he and reverse direction Dow. on the upstream or downstream of the skirt seat in its disengaged position valve. This test conducted at the also eliminates excess friction that 1969 - A 20" full sized valve for* Alden Research Laboratory proved would be generated by other types of various amounts of vahe opening. the principle for bi-directional closure.
Wo b% o enW 3RL b 2312 096 -
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$ A Technical Bulletin by Atwcod & Morrill, Salem. .',1assacnusetts 01970 U.S.A.
2:'e: H f""2" W :fli d Development of Main Steam isolation Pipe End Load / Static Bend . w Test of 32-inen MSIV u,,s t,,.. v.o, , em, S, en, Atwood & N1omll Co , designers and manufacturers of high-quality special P 7I i ' pressure and pipe end loads, and while sabes for more than three quarters of a ' ' century, is well known for its N1am ~l
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h[ r the operator was subjected simulta-neously to an equivalent seismic load. Steam Isolation Vab es for nue' ear pow er The several pipe end loads were consid-stations. The company has been produe- 4 ing these reliaNe "Y" type sabes since 7 cred the maximum worst-case loads that the 6rst commercial nuc! car power sta- p yE ) hg . would be associated with a guilletine tions were budt, and today counts more (h g
,a u, pipe break resulting from an uiiset than 400 vahes instal led in and on order (earthquake) or other emergency for Hodmg Water and Pressurized Water
., y c-
}3 e ' s condition.
Res. tor systems worldwide.
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t Design History )1 4 4 . Test Valve Since Atwood & N1orrill first began
- s. .* ' tlk; ,. j Re valve used for the Pipe End Load /
developing sabes suitable for main s" M Seismic Bend Test was a full-scalc 02-steam service, it has used as the basis for k'[p'$.,'ra],cias , in.) production valve conforming to design'perfonnance specifications'w hich '-- ' ASN1E Section Ill, Class 2 requirements. estabitsh the fo!!owiag salve features as [0 *y' rP '
,, (( It was scheduled for service in a three-ben"; ev.ential or highly desirable: 7 Water Reactor plants in the U.S. loop 900 N1W Pressunzed Water Reactor
. O, .tmg rehability plant.
th > jn sunpheity Pipe End Load / Seismic Bend T@t shutit Test Program Test Fixture
- Lo 4 ;newure Jrop
+ An a%hty to open against dif ferential The purpose of this test was to show that The valve test fixture, developed by prmure the Atwood & Nfoml! vabe would oper- Atwood & N1omll*> Engineering Statt, An aJpstable closing time ate as designed and within specified time was designed so that axial, torsional, and
+ A n. cans of testing through partial requirements while subjected to internal bending loads could be applied to the strok.e and retum The present Atwood & Niorrill valve, a "Y" type glebe valve with an air /spnng .
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operaung >y3 tem, combines a number at, "- hT4/QVQh. Q "b' ,y. [hD59EfMIQ@ features to meet these critena. Af g , i d )hh. gSa. e
.MK.M The early success of Atwood & Stomil _; O "Y" type valves in Boiling Water Reac-
' %.YC$. }
e-J - tor plants led to their consideration for and use in Pressurized Water Reactor plants. For PW R installations, the valves p
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+ * %. s
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.m,p 3 N1.a nit art:eulated pdct, and the patented skirt seal w hich enaNes the vabe to pro-
;p-%i. Q*[.irl? $ %. arf ,,' ,_ _
.~$
. g[f '.; .
( vide shutoff w nh dow in either direction. D, a **ai* y, ,, ...Y g#g'8 *M /ryJ p"i Qualification Test Programs Frnn the time it produced its first Stain k ' [LV , M@p[ht b -<
-jSh(JM 3 h$
Steam Isolation Vabes in 1966, Atwood
& mmll has conducted both static and
- h. ,' ; L
,gh_ [h's t, ,f
,%g %
2 'q - t% g op ational tests to qualify its designs 7
, t '
O
, d k.,Qffh3
/ggy g a.ii to ensure that the valves met current speiticatiens. One of the more signiti-e 6 x A,ct , j i ) ,_ g ..n g v : j ;-j :g 4
?p f,',
c.u.t tats in this ongning program was a r g,. g]p] g.yh MO4-ifM; te. Pg,e End Load and Seistme Bend Test. The test was a demonstration of operabd- The 32-in. test s alve mounted between son. thics stos - r.1 utes .n the pipe-load fixture at Atwood & Momirs Sa:em, V - msetts ity by full seale prototype testmg. one of plant. The come ned we.gnt of the r,xture ar'd va!'.e onceucem tons. the preferred methods described in viewing the test are personnel from comesteand in emattonal cus-USNRC Regulatory Guide 1.48. tomers of Atwood & Momil. i!, l i '
.\
f L 2312 097
"'
- L
-, Y.*,;c
- j. y.q. 'E1,2 ci.. ?lCf""h' %
y, ; %.-:u. p :y 4 -: 4 s .n. *%&.ga pr -- 4 ww;;;;,,.r.et it snn%y.y. fx.d ..
*? 4 ,. -
lW
~
e W.P. .. ^ w
$alf 'N1 x ' '*" T} 11.g[ p%
G t. . . l &~
? hffW
~
.s +q q u% Nmw%m:l%i m u&h%. . fw
'~5tN5@$k$kl%$hg,N,tN s%eW*ern i - . e%c % qp h ,w'iscM
., ;f, i d ed@..rM N.. .k P~ 'fL Nii N ,
%5d@k $$ ****'"'*S
valve body whilc hydrostatic pressure @%nH5===rzB;g===fsp'lters " ~ "w m" g "g'. W ChT] was maintained within the valve, and ;c - ~3 %
' ' r while an equivalent. seismic load was U- ir ;h' ,q%
. * - ~ ~ ' , , ' ^'f".$'
hJ "'fl Y +f.$.M' ;;'w' 'g79,M[rg h 3
- applied simultaneously to the operator. %{ k ]p Q Strain gages and other instrumentation
/; . cMph - GbI,f .k e hi, i were attached to the test valve at strategic locations so that both dynamic and static
[q l'
.j f*f
h MKMQ y
, , . c. t M ,, Q. "n
- j measurements could be made to deter-mine stem loads, body stresses, closure <-
N . 7 d "'F - times, and other pertinent data.
,,, ; +,j .' gh g *
- - gg-wy y g y;. ; 4 g., ., y M f g 4 J/J
\
,\
N b%f f -: Axial Load Test -f +Ji A de R.
\
During the asialload test. the vahe body was subjected to hydrostatic pressure so.
. P*- g. 3./.frg.5% ^f's
- e. ' g.:w g'gr,.p..n.% yA.,g,p.x.
# g 12. Q '= g g-. g; % "
~Ne!a'j m ., t h..<.,,;r that the loads on the end plates wcre .'-g g [ h [v,7k g""5 - .-a!T Wd.' h 4EE-44~* Q - $
transmitted through the body flanges to create an axial or tensile loa,d on the s M*dA .ziMh-L. M ' E M 'f,,* A [ h r -iK4_} hh.j/ y.d valve. By analysis. Atwood & Morrill Winng from instrumentation on the tes. alve was brougnt to a centrol had determined that a tensile load would center wnere informaton was taken from visuai readout de Aces. be more severe than a compressive load. (7' '; Internal pressure was increased gradually - 3' " "Kob"" 4 m,; '$ %g r u m -* w r~ :.1 m r , ,-..-. ev ..,-a,7.
.y f f'. U'E.A to approximately 1300 psig. With an ef- h,.; 3. ..myqw~h. IG9 ?! b,h:'.,E'Ti '
$U .K:. : &; ,22gnF-i .
M4 v... fcctae .ad. plate area of nearly 700 sq. r.: - K.. m. . . . , , 9 . c r. .g. - Iy, ,.. ~!i-in., the resultant force on the valve body I$%se..ua.y [. L,yys . -N N. e %:!:. F ?.'* .;.'fMJ-' . ' f,4 was an axial load of about 900,000 lb. E ,,-
%g " .[p<.VT fJ~e _ @;dm'f,3'I ggg . . .l.,,*[ [k.
gl'%*" ggj.2
. Nya . -
'9 ~
,After operating the valve to demonstrate f .Qg, 1 %
its ability to close withm the required
, ::v.4 H '
i
- . rf..9 time, i seismic load was applied to the #
p M*. lO *E*~
,]lM:@1-k,; ..g$3!N ,'
g i.m . . M'i i.42 operat.: structure at its center of gravity, and bt,Jy stress measurements were p ;" t,3. M O QEk IG7 l taken as the load was increased. At the f- m
- u , DUMMTZ"'" UMEDs'- " *tix^ ^ '
maximum seismic load of 30.000 lb D5 \ l / (equivalent to 3 g horizontally and 4 g 4 /r .f'. ' ' 3Y ",-} E/ Q'iYdF[,M W6'eh- '2 vertically), the valve was agam cy- {T'. ., s . , w, ., ' 1< / . .
.~
- e x . ~.-
cled under full load, and dynamic measurements and closure times were {,' .". .} f.g ..jf' .' ." ^
- 7: p,y , ,g"{ , , :q , ,
' ',g.pMrsiitab%%.M$.?W.Tt.STg.7,q:!try- NO.C AXI Atl.' TEST) 0." +2 Q' -
W.E::i w w a. % w Gu n di.c.: ' m recorded.Ky}m M @@(A . - 2312 098
. s Torsional Load Test h"" tC @i% S N C F " M *- V ""' W M'W. 5 5 . 9[E.A .i" W .,M .2MQ Imniediately following the axial load ,,j.73;rg%g.p gg,,,y,%MV ..,,.j
- D.-/; .-
-;g _
test. and with the valve body still pres-surized and the operator under seismic y gl7]E
- c. . .. ,. 8 p-
- .w g*g* g,g,r --
,;.Q , " , y-;g':?:f.gfg.g.g; w
. gjg.py,.g> ./.3
;tms W -
loading, a torque or torsion load of . . ~ . . . . . ,- m
- g Z. .,,--. .- $':g.e.
7.Vf'fg j,g.' f4E
., f* , ,
, l 2.600.000 ft Ib' was imposed on the v'Q ;. j,.M g . c --
vahe body by bydraulic cylinders whieh q v. M 2.es0.0 o FT.La s. y , .
,. ..g{..lQ twisted the forward or free end plate. The .'- .l rear or fned end plate was rigidly at-
' '.." ,5. , . O .c ' , - ' ifhltj yfg j ' ' g _. I f. %
g., tached to the test frame to hold one end of , T' the body sceure,
! w f Q'y,, .y _
. Agg ;N3.5, g
.i, Body stresses and other static mea. .
x .h,d y surements were recorded as pro- \ 6 '
.,$. G: ~.8:. _
.gNtQfrg
' M,. . ..-c... ~.vphN .
gressisely higher loads were apphed to the vahe body. The valve was operated
,,,y
,4A . q.g,g.
i:.agd.,.-A;in%{ggy,1 g( v'g j K-@%c scietal times while maximum torque _r; .,, ,
^
wa., applied. and closing times were recorded. h# .I k l[j%m$rbgQgt-wwj@g[g
,[. TEST,,qO.2gogslo,,
2.* thfP-sgg c M ,- Note that the resultant force on the frame was great enough to {.g, g .(. > ..p hft one of the support legs (inset) approxim&tery % in. off the floor. d Bend!ng Load Test
% .i .
For the bending test. the fixture was con-verted to apply a bending load to the Q } Y [ U Y. F f % 7. [ E U M N @ 7 E W M ] cr a t ed b tween he end r . A ni r ..'v-pi n . ,w - Kg. .W4 maximum benJing moment of 2.500,000 ft Ib' was imposed on the vahe body gg j;, ' g: b7 7, ,.p.-
.ggg,g:;,Gy,4 ,.,. y 4.g.y. = :. h. y,. .yg-u
,j, yf , .. ,.y nyy g g. g i .g,g.f
.C,.
M together with the internal pressure of
/T T. V'M a
.,.a~,.
.a s
' Y. m..Y;,
..- /'.?.?
1300 psig and seism.ic load of 30.000 lb a; yN.e - sy j g n o.ooo tas.' p,#.g g ,r.s
. c-W-
W.~drf d * %6. t i r-on the operator. g. ~,42
- v. .w($. ~p. .k, .
m's w.. f . g, b The salve was operated at maxi. ght *g' . .. g',{O ., c1 ,,,,,,, gwc.
-ib;q" y y '%[) g(fggk, .j mum loading and the closing times and g y other dy n.ume me.asurements weic re- - % -,,. g'*'65]t-* s u
corded. Body stresses had been mea- NNA Dg.'- d~r .,ar. ten 4 a y/**p,,Ua.-n- Me .h.m.4ins ky sured as the bending load was increased incrementally. M. 4W;;G.g.b ..
=, ,-,.c f g- w.e{
,.yg gj g
,y,:40.s
*tQr.s.g'n.jp_
eg g_i ~p? rc 5. p
- Qv.% y . e$.gfr;< . ,-, w W?* 14 w .p<s.?j
- W % % %s:: lui.W L' ,.nl
- ;. s '.70%. G AWUE$Mt.M T .?* $ib.,
2*9*Kiur : > . . .g
*The fortes and mments imposed on the valve -
%. e.g
# *Gy [jy[*
<w 7 *M7g egl;[N '7f(gh. +M"*.y[a [4,p()p%
I .. ends were calculated as the lo Jing that would v, . s j.V. e . 5e. s .* occur u hen the y se!J strength for the attached pip-
- h. dQd %h,' p .f f'hh.[ dh%jhe<* T , pE,j.s .]
ing of a typical PWR plant was developed. Smassa W'.s sunasastaammerasavaareEw NEEF""W'"EQT1*T.m*'*2,**fl"'MMMP*'B'F'"'*~_;u e m **T."M "O _ Test Results oU[,; ; W ckf D Simply stated, the Pipe End Load / Static Bend Test showed that: hL 3 h _ $]j( j U _ ,
- 1. Under all modes of testing, the valve closed in less than 5 seconds as required by the c'esign specifications.
- 2. Closure times were essentially the same under both full-load and no-load conditions, 73jd nao ,
U//
- 3. For all test modes, stresses in the valve body remained within acceptablelimits as allowed under the ASME Code.
In essence, the valve opera ted under allload conditions as designed, and within the specified requirements. Therefore, Atwood & Morrillconsiders
- the test program a complete and realistic simulation of pipe end load and seismic load conditions.
v . c-
Future Valve Testing Atwood & Morrill is committed to the continuing development of Main Steam isolation Valves for both Boiling Water and Pres-surized Water Reactors. To this end, the company is fully pre-pared to carry on test programs which have, since 1966, verified the design excellence and performance reliability of Atwood & Morrill valves. QRi? UC , 41, ' ' L F.I M; *
- 4.: ' .
N r. , _' _Y W f b,,h Y ; N$dk$ i ~ 37 M SIV nstalled vi test fixture. The hydraulic cyhnders are connected to the " free ** end plate to create a torsion Upper and lower hydrauhc cylincers were attached be-load on the valve body, tween free
- end and " fixed" and plates to create bend-log rnoment.
TgifFD fIIPlM 5 If eOh &i[M
- MJ h r =
g VALVES and ControlEquipment for PCWER PLANT DIL rNOUSTRY MAPINE & INDUSTRIAL SERVICE . NUCLEARg INDUSTRY [y-jhG 6 i ,' E r khvood & Morrill Co.,lnc. ['zy.h .PI ENGINEERS
- CESIGNERS e MANUFACTURERS / SALEM. MASSACHUSETTS Ots10, U.S.A.
ikhaY}S}
. e n,e s .. ..aa . . . . . .e e . .
2312 100
Technicai Uollet n // 03 { ,,,r gy gs q2ggyy , ; - p y g,3 m ' pa yTA ,'.L k j I
'kT. ~~b" kj b h[ j E[ h 1
"M :. t"m% w M r 2Y Y'O ' *E M;k M
$ A Technical Bulletin by Atwood & Morrill. Salem, Massachusetts 01970 U.S.A.
- - ':-- m m-aw - - - ,,m, - uu,, m n *z7-narvurm.v --r w m m
- syn;i. -
Part of A Continuing Program by I n Atwood & .\forrull Dedicated to the De-veloperserat of .\tasire Stearrs isolatiors l Son =a s r="iow Test OT. a Valves for Nuclear Power Stations. Atwood & Mernli Co., designers and , QQ QQQ Qf f f&Q manufactan:rs of high-quahty special ulves for more than three quarters of a I ig" N .rL J
]. j steel with stainic3s steel and hard. faced trim. The operator was an air and spring century , is well known for its Main I 7
{ l __ n system of the " fail closed" design. The y; ' " Steam hotation Vahes for nuclear power . stations The company has been produc- I bi-directional vahe design is presently p being furnished for acthe service in ing these reliable 'f Y" type valves since the hrst commercial nuclear power sta-lf'.
; p
-N 4 i
5-l PWR plants, and conforms to ASME rions were oudt, and today counts more . , 4 ,1 Class 2 requirements. Q! ( g* than 400 valves installed or on order for Bothng W ater and Pressunzed Water ,i Test System Reactor systems worldwide.
- Aftercan fully resiewing the capabihties Design History I y f available now test facihties, Atwood Since Atwood & Morrill tirst began 3 & Morrd! chose a nitrogen blowdown deseloping vabes suitable for main { q system to produce the required some steam sersice, it has used as the basis for deugn ' performance specifications' !'
i kg m flow. The flow test system located at the au .i Naval Ship Engineenng Center facihtie , which estabbsh the following vahe { '{,p - of the Philadelphia Nasy Yard.consnted features as being essential or hin,hly , of (1) three accumulator tanks having .i desirable. ,
, , maximum pressi.re rating of 1609 psig
- Operatmg rehabihty ,
e each and a combined storage capacay of
- Design simphcity I , , 3000 cubic feet, (2) entrance piping and
- Tight shutoff I -
an inlet header, and (3) exit pipmg and an
- l ow pressure .; rop l, ,,,.A % ,,g, j exhaust stack system.
- An abihty to open against diffeential
.Qi[
- ^?
pres 3nre -
;d
- The entrance piping, designed and fur.
- An adjustable closmg time
- A means of te ting through partial ,
nished by Atwood & Morrdi, connected stroke and return. w% $w. . .) E The prewnt Atwood & Morrill valve, a w%
"Y" ty pe globe vahe with an airisp-ing A 32 inch MSiv ready for cackagir g and ship- -y 7,m g 4
operatmg system, combines a number of , ment to an 1100 MW PWR sta:;on. teatures to meet these entena. h L. bg.,M A,$,, .;.vQf,,P"$:
/
The early success of Atwood & Mornli ( The purpose of the Sonic Flow Test was .f 'g .4 gg,y g "Y" type s ahes in Boiling Water Rese. to show that the Atwood & Morrill Main - .s*S
$Q t Q'I ~g@J 3f~y y, for ,Mants led to their consideration and ' Steam holation Valve would close use n Pressunzed Water Reactor plants. ; within specified tim.: limits against high hO q M; he-for PWR in>tallations, the vabes incor- "
+ ,
WQ porate the esclusise Atwood & Morn!! reserse now rates and pressure differen- '
' "'g T ~Q
- tiah such as would occur after a steam U" ,[MN DEC articulated pdot and the patented skirt se) ghich enaNes the vahe to pnnide line break in a nuclear power station. T he -
' MEk shutoll agamst ifow m either direction, idea of a pipe rupture n based on the Nt1 '
I Qualification Test Programs gy y A.[C*(M. From the hme it produced its first Main piping could be Jescloped Junng an t n -g fri,d. ,' $li Steain bolanon Valves m 19f36, Atwood
& Mornll hon conducted both static and carthquake or similat esent to cause a guillotme break or complete separation g
' (f' p % g. y,MMWg i of the pipe. Y
,d operanonal tests to qualify its designs and to ensure that the valves met current gecifications. A test of considerat,'e ) Test Valve i,v p.
, {j,a ,- -eg
, .j,.
, ;.3 ," j
\(7)fpl,,
sigmlicance in this ongoing program was a Some Flow Tc5r designed to comply ! The valve selected for the Dow test was a {E=g
-- O ' h- %-
withoneof the preferred methodsof test. : 26 m.ch production valve modined to ing described in USNRC Regulatory represent an esen larger 32 inch valve. Om cf thenai steps danna the pmpara: ion tor Guide l .48,i c., full scale prototype test- l Both vahes are dcsigned to close and ing. This test w as the first ever perf ormed - shut off Gow m either direction. Basic ' f,$[p,[7,e7c"{# cl, syg],[ on a vabe as large as a 26 inch vahe. rna,ung the hooeup un :ne vaw in ino open
> construction of the test vahe was carbon pos. tion reacy to inp closed
" ?P - ,
1 2312 101
h i' J ""I % . E 7 gg positioned in the system so that flow thru dh4 d h ' El I the valve was opposite to the direction of
~Mk2 -sEs 3 pf; 3 ,
n rmal steam flow which would be from j{m # y T,ct hg . ,pgE '- i the c. a generator to the turbine. Such a reverse flow condition woutd oecur in the g g
;g _
~w ' ,C esent of a gui!!otine or major pipe failure
.= ~
~ 9d3::;3m upstream of the Main Steam isolanon MIN b ,- 'E Valve. For each test, the storage tanks
# U were filled with nitrogen, and the en-E ,
; ,, ,t trance piping, valse, and exit piping up W.b *' E, 3 to the rupture Jisc were pressurized The M
C N e ' ' ._J'
; y' explosive charge on the rupture di: sas 3j i 9 5 - -
, $ then detonated to initiate flow, and .aer a u i l ,, -. ' ' i .4 short predetermined time delay w;uch p, Q y '
\.
pernutted sonic Dow to be estabbshed, i e p ," ; the valve was signalled to c'ose. h h h+- ic 1gh. f.,E f ;A
.-Q-The first test was made at approximaicly 50 per cent of full test pressure to verify 70s . i ".*
- the operabihty of the system and in-gfy ?"
N .. K~
;w. a M,,,_ d D g strumentation. The second and third test,
,._.* - = . % ,J -i were run at full pressure and demon.
strated that the speed of closure could be k Q
# "),_ ""
, e ,p g-t h w e.
,' . sI " '7""JC
' 9,f7fyd *,.T Q6]*
7d $, $L": _,~
.r/
%Md tJ .
3 V '
$ r.T ~8.#Es- l $g..-
#., 4 fgw r N%. ; "' n%=sQ o^g?.
s-
% $- g \'. y 3. My;&*f e .
,e g s 4 r -
,. .~
k B OlI$h.,,,, S $@dE$ $ #- Q7G **' ~- @ Top. The entrance piping of the test system connected the storage tanks to the
.,-- g; _, ~. 0 4
t 1 header up3 ream of the valve. (The spool pece in the foreground is part of the esit 2 M***1__. . M(, .Q$} } ppeng, and Contains one of the large holding flanges used to secure the rupture esc.) Bottom. The exit piping (minus the spool piece) downstream of the valve The Above. Shaped explosive charges were taped large flange on the exhaust header mates with that of the spool piece to hold the across the dished steel rupture d.sc to fracture rupture discs. The bndge like foundaten was specially des gned to absorD the thrust the disc pnor to t:ow. Below. Tuo frac:ure par-produced by the sonic flow. 3 tern permitted the system pres 3Ue and f'ow ta fald the d Sc ec]r9ents baC4 C!0dr;ly witrlout tragmenting tne disc. three storage tanks to a 26-inch header detonated, would tracture the disc to ini-pipe upstream of the valve. The exit pip- tiate the system flow. pr g--gggmy g _- *
.a , . --
ing also supplied by A&M, compnsed a
.6-inch flanged spool piece immediately g
.g
, gg,.
y* ,.sh stmmented to reco..! mlet and outlet ,y q downstream of the salve, holding llanges ;.g for the steel rupture discs, and a three pressures and temperatures, operstmg g . . pipe exhaust stack. The exhaust stacks cylinder pressure, poppet chatnber pres-74 NhgU. d . were supported on a special foundation sure, stem strain, closing time, and other . 4 ,%N fp d -. deugned to withstand an initial thrust of essential data needed to determine valse ,
*g .
f 1,000,000 lbs. and a steady-state thrust PC'f"unance. * * ' . :'jt; of 500,000 lbs. Reverse Flow Test , .. @ify Each rupture dise was fitted with a shi, ped esplosisc charge which, when A series of five reverse flow tests were performed dunng which the valse was di'.$ 2312 102
controlled,and the valve would not "run " Poppet Position vs Time" For' Test A major purpose of the forward flow test away" and close too rapidly or with de- Nos. 4 and 5 note that the curves are was to demonstrate that the design mod-structise force. Following minor design nearly linear which means that the mo. ifications that had been made to enable modifications to the valse, the fourth and tion of the poppet remains virtually inde. the valve to close against reverse now. fifth tests were conducted at full f.ow and pendent of tiuid flow thru the valve. It is would not a!ter i:s ability toclose against pressure. The salve closed smoothly not sescrely affected by localized forec3 forward flow as originally demonstrated within the speatied time, and without developed by the flow stream. by the " State Line Test" in 1967. excessise forces on any of the compo- Another purpose was to demonstrate nents. 'lhe closure times are summarized Forward Flow Test , that, w ith the same control >etting as used in the table below. After the rescrse flow tests were com- during reverse flow testing, the salse pleted, two additional tests were con- would again close within the specified One of the most significant aspects of the ducted with tiow from the normalinlet to time limit. rescr>c Ilow tests is shown in the graph. the normal outlet of the valve. The method of testing was the same as for the reserse flow tests, viz. the system was pressurized up to the rupture disc. Forward and flow was again initiated by detonat-Reverse Flow Tests Flow Tests ing the dise explosive charge, with the Test Numt:cr 1 2 3 4 5 6 7 valse signalled to close af:er a predeter. Starting Pressure, psig 470 1300 1300 1200 1292 660 1280 mined time delay. The forward now clo. Closure time, secor'd3 4 14 12 3 3 3 3 sure times are also summarized in the _ table at left. 12 m K.odN.,*, g m ir/ m i[r% . % di.w., .q g .
?!&Y? $$f -
POPPET 9 M.k0YEfiflW&$ b # .g" g . ", ,*4 9'8"* g. POSITION ' hid VS. 8[ $ YfN.N.Y'IEh TIME j 6 M t{- Nr*4(gi@,$
$ N[2h-l(Q l'- Md 4 0.PM t.Ndd ".'.M
$8IOWkWI.'3\' MYM f, f@y.;
- k VWj M;.p.p.. 5
- w. '4 0'
g^a j ' g6
" N". ':: l' _ j'Ag
.5 :
0 .5 "1 1.5 2 2 3 seconds test 4
** Poppet Position vs Time" test 5 .y m m m s mvT*-Pr? w *=ser m _=*rres g g j lest Results Detailed analyses of the data recorded during the Sonic Flow Te.st show conclusively that: %
- 1. The Atwood & Morrill"Y" type Main Steam isolation Valve will close satisfactorily against both forward and reverse flow and within specified time requirements. 2312 l03
- 2. Because of the balanced disc design, valve closure can be controlled, and for a given control setting, it is virtually inde-pendent of fluid flow rate, fluid press"re, or fluid properties.
- 3. Closure against reverse or forward flow will not damage the valve or prevent subsequent operation.
Atwood & Morrillhas demonstrated thatits "Y" type Main Steam Isolation Valve meets or exceeds current requirements and the important criteria required for a bi directional shut-off valve in Main Steam service.
" j - '
[ ' L jllF1l!If
'D i
!t 1 J m n
Future Valve Testing Atwood & Morrillis committed to the continuing development of Main Steam isolation Valves for both Boiling Water and Pres-surized Water Reactors. To this end, the company is fully pre-pared to carry on test programs which have, since 1966, verified the design excellence and performance reliability of Atwood & Morrill valves.
'1 h
D3hMy"gP- I r Mk., 7;. v_ - 3 N-.
~
$i\:N'.'I iU. '
i i
.hPR@)s@S
- a.4 3 i N Q.(' '). - bound Nitrogen was transferred W;d 7^N N,7*$ I'e :{})]
9 '5" to the system for eaWow test. iMk j Y .- ? k Qt ' f Q,dy
$ M Y-{dt ib$NWSk;;hLstGB ss R 2 D %--I , '2k 'h \{
g _ ; . ~ g" " ' m; g-
=
. p .
t w lJ M *- -
%.w fMAf, - Ndh
$_$k
~.4 -. _ _' , - _ ,
to Y -
^
- ro7;n A television circuit enabled "hvo monitonng of each test, while a printed record of the various 4 g'.t- _
t synals was recorded on the oscillograph pnnter M A'*
- M
% ~ % ~ ~ .. mumg
.._e pNg$$4)
N J[, VALVES and ControlEquipmentfor '
}3}g }94 POWER PL ANT . OIL INDUSIIIY . MARINE & INDUS TRIAL SERvtCE
- NUCLEAR INOusinY ~*}$
Aw Cl. >p s k.ood & h]arriR 00,lnc. I & I %, 'p-
- ENGINEt9s
- DESIGNERS
- MANUTACTURERS 1 SALEM. MASSACHUSETTS 0197% U.S.A. l.;.k avs M S. I c1970 by Aes it id & Morreil Co . Irsc. 5m'c r* .
Fnn The vaneaxial fans for which the seismic qualification analysis report was previously submitted was qualified for installation throughout the Sequoyah plant. Sbre specifically, the fans are installed at various elevations in the reactor and auxiliary - control buildings. The floor response spectra for the top elevation of each of these buildings envelop the response spectra for any lower floor elevations. Thece maximum floor response spectra for the two buildings are attached. . Reactor building - Interior concrete structure Horizontal OBE spectra Figure D-30, U-S Figure D-60, E-W Vertical OBE spectrum Figure E-6 liorizontal SSE spectra Figure F-30, N-S Figure F-60, E-W Vertical SSE spectrum Figure G-6 Auxiliary - Control building IIorizontal OBS spectra Figure C-24, N-S Figure D-24, E-W Vertical CBE spectrum Two-thirds of the figure B-3 levels SSE levels are equal to twice the OBE levels. The maximum accelerations from these spectra are: OLE SSE Horizontal 3.5 g 4.0 g (D-30) (F-30) Vertical O.21 g 0.42 g (E-6) (G-6) 2312 105 (1)
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Auxiliary Air System Ccmcressor Auxiliary - Control Building - Elevation 73h
- Applicable floor response spectra are attached.
Horizontal OBE spectra Figure C-lE, N-S Figure D-12, E-W Vertical OBE spectrum Two-thirds of the figure B-3 levels SSE levels are equal to twice the OBE levels. The seismic qualification test report (Wyle Laboratories report No. 42583-1) has been previously submitted for NRC-SQRT review. The equipment was subjected to a series of single frequency (sine beats,10 cycle / beat), multi-axis tests. The input acceleration levels to the equipment were: Horizontal 0.54 g - Equal components of 0.38 g in each principal horizontal axis of the equipment. Vertical 0.25 g Horizontal and vertical inputs were applied simultaneously. The sine beats were applied at frequencies corresponding to the observed natural frequencies of the equipment, i.e. , 9,15,19, 21, 30, and 33 Hz. The test input acceleration levels were such that the corresponding response spectural acceleration was far in excess of the applicable floor response spectra peaks. The test procedure in effect applied the most severe seismic conditions (floor response spectra peaks) at the most critical frequencies (eculpment resonances). This testing represents a considerable amount of conservatism over sbr. ply enveloping the required response spectra. The attached plots illustrate the degree of conservatism provided by the CSE tests. 2312 115 (1)
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FREQUENCY HERTZ 2312 120
GE Voltage Relays - Type IAV The IAV relays are qualified for installation in the 6900-volt shutdown board logic panels. The panels are located in: Auxiliary - Control building - Elevation 734 Applicable floor response spectra are attached. Horizontal OBE spectra Figure C-12, N-S Figure D-12, E-W Vertical OBE spectrum Two-thirds of the figure B-3 levels SSE levels are equal to twice the OBE levels. Pertinent excerpts from the Westinghouse teet report have been previously submitted for URC-SQET review. The logic panels were subjected to a series of single frequency (sine beats,10 cycle / beat), multiaxis tests. The input acceleration levels to the equipment were: Horizontal 0.44 g Vertical 0.13 g The sine beats were applied at frequencies throughout the seismic frequency range, i.e., 1, 3, 7,11,15,19, 23, 27, 31, and 35 Hz, which included observed natural frequencies of the panels. There were no panel resonances below 18 Hz. The conservatism of this test procedure is the same as that discussed for the auxiliary air system compressor. Similarly, attached plots illustrate the degree of conservatism provided by the SSE tests. The most severe seismic condition for the panel mounted relays can be established from the panel test data with its associated floor response spectra. For this particular situation, the maxiu=um horizontal seismic (SSE) response of the panel would be obtained from the response spectrum at a frequency corresponding to the lowest natural frequency of the equipment, i.e., 0.44 g at 18 Hz as shown on figure D-12. This maximum restonse acceleration of the panel in turn represents an appropriate inout acceleration criteria for the panel mounted relays. The panel is rigid in the vertical axis; therefore, the appropriate input acceleration to the panel mounted relays in the vertical axis would correspond to the zpa of the vertical floor response spectrum, 0.1 g SSE. The relays were in fact tested to considerably higher levels than those which could reasonably be established as discussed above. The actual test criteria for the relays was based on, and equally reflects, the high degree of con-servatism inherent in the panel assembly test procedure. Accentable input acceleration criteria for relay qualification Horizontal 0.44 g) Vertical 0.1 g ) 1 to 33 Hz 2312 121
Input acceleration neoliyd as relay test criteria. Horizoital 1.6 g ) Verticci 0.16 g) O to 20 Hz Horizontal 0.44 g) Vertical 0.13 g) 20 to 35 Hz The relays performed satisfactorily under application of the above test criteria and are therefore considered qualified for this installation. Note: This relay qualification would not be extended to any other installation without appropriate justification peculiar to that inst allation. 2312 122 9 J TENNESSEE VALLEY AUTHORITY 12/17/73' RESPONSE ACCELERATION SPECTRUM O
- SNP AUXILIRRY BLDG
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Static Inverter - System Cceponents Auxiliary - Control Building - Elevation,749 Applicable floor response spectra are included in the attachment. Horizontal OBE spectra Figure C-15, N-S Figure D-15, E-W Vertical OBE spectrum Two-thirds of the figu2 e B-3 levels SSE levels are equal to twice the OBE levels. The seismic qualification test report (Ogden Laboratories report No. F-73165) has been previously submitted to NRC-SQRT for review. Additionally, a present-ation was submitted to NRC which illustrated the conservatism of the SSE testing imposed on the static inverter assembly. A copy of the TVA to ::RC transmittal letter with the information partaining to the inverter qualification tests is attached. 2312 128
50CC Chestnut Street Tower 11 3AN 3 1979 Director of Luclear Reactor Regulation Attention: Mr. S. A. Varga, Chief Light liater Reactors Branch :;o. 4 Division of Proj ect Management U.S. Luclear Regulatory Cocaission Washington, DC 20555
Dear Mr. Varca:
In the Matter of the Application of ) Docket hos. 50-327 Tennessee Valley Authority ) 50-328 In response to a verbal request by Don Lasher of the NRC staff during the telepnene conversation of September 21, 1973, enclosed is additional caterial on seisraic testing of neutron detectors and Balance of Plant (BOP) Class lE equipment qualification. The LOP Class lE qualification data includes the 125-volt vital battery charger, tuotor control centers, and seisuic qualification test of the static inverter. Also enclosed is a draft of TVA's revised response to Q6.36. Very truly yours, J. E. Gilleland Assistant Manager of Power
.nclo.< ur o (2) 2312 129
SEQUOYAH NUCLEAR PIANT SEISMIC QUALIFICATION TEST OF STATIC INVERTER STATIC PORER, INC.
Reference:
06d en Technology Laboratories, Incorporated Report F-73165 September 1973 The static inverter was subjected to a number of slow sine sweep tests followed by a series of sine dwell tests for qualification to safe shutdown earthquake levels. The sine dwells were performed at frequencies corresponding to the observed natural frequencies of the equipment. The test input acceleration levels vera such that the corresponding response spectral acceleration was far in excess of the applicable floor response spectra peaks. The test procedure in effect applied the most severe seismic conditions (floor response spectra peaks) at the most critical frequencies (equipment resonance). This testing represents a considerable amount of conservatism over simply enveloping the required response spectra. The attached plot illustrates the degree of conservatism provided by the SSE tests. The updated applicable floor response spectra are also attached. 2312 130
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TENNESSEE VALLEY AUTHORITY 12/17/73 g RESPONSE ACCELERATION SPECTRUN m SNP AUXILIARY BLOG d- NASS POINT NO. 9 oat 1 PING RATIO 0.020 OPERATIONAL BASIS EARTHOUAKE FLOOR ELEVATION:748.50 N-S HORIZ0!!TAL ACCELERATION - 8 8 c;- N u N 8. O u N 8 s-S
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Motor Control Center and Switchgear A. Motor Control Center (MCC) Auxiliary - Control building - up to elevation 749 Diesel generator building - up to elevation 740.5 Applicable floor response spectra are attached. Auxiliary - Control building Horizontal OBE spectra Figure C-15, U-S Figice D-15, E-W Vertical OBE spectrum Two-thirds of the figure B-3 levels Diesel - Generator building Horizontal OBE spectrum Figure 10 - Applicable in each of two perpendicular horizontal axes. Vertical OBE spectrum Two-thirds of the figure 10 levels SEE levels are equal to twice the OBE levels. Excerpts of the seismic qualification test report (University of Cincinnati report for Arrow Hart, Incorporated, dated March 1972) have been previously submitted for NRC-SQRT review. Initially, a typical 5-section MCC was tested as a complete assembly to determine its dynamic characteristics, i.e., natural frequencies, mode shapes, damping, etc. Low level sine sweep excitation and mechanical impedance transfer function analysis techniques were applied. From this testing, it was determined that the lowest horizontal natural frequency was 15 9 Hz in the side-to-side axis. The MCC was found to be rigid in the vertical axis. The most severe seismic condition for the combination starter units, as installed in the MCC assembly, can be established from the MCC assembly test data with its associated floor response spectra. For this particular situation, the maxi =um horizontal seismic (SSE) response of the panel would be obtained from the response spectrum at a frequency corresponding to the lowest natural frequency of the equipment assembly, i.e. , 0.92 g at 16 Hz as shown on figure 10. This maximum response acceleration of the MCC assembly in turn represents an appropriate input acceleration criteria for separate tests of the starter units. The "CC assembly is rigid in vertical axis; therefore, the appropriate incut acceleration to the starter unit in th'e vertical axis would correspond to the zpa of the vertical floor response spectrum, 0.49 g SSE. 1 2312 135
The combination starter units were subjected to a qualification test program wnich conservatively envelops their installed maximum seismic requirements as discussed above.
- 1. Each of the combination stcrter unit configurations was tested (slow .
sine sweep) to an input acceleration level of 0.72 g in each of three mutually perpendicular axes. 2 A representative unit (heaviect, most sensitive) was subjected to additional testing in each of its two perpendicular horizontal axes to a 1.2 g input acceleration level.
- 3. Although test records were not retained for documentation, it should be noted that the starter units were tested to levels far in excess of that required for seismic qualification for Sequoyah installation.
Slow sine sweep testing was conducted at frequencies up to 50 Hz and at acceleration level in excess of 6.5 g's. Similarly, other devices were seismically qualified separately to levels which exceed the requirement for MCC installation. Relays, circuit interrupter units, and motor starter units with auxiliary contacts were tested (slow sine sweep) up to a frequency of 50 Hz at 2.0 g inout acceleration. The design configuration of each of these devices was such that each clearly had a "most sensitive axis"--along the axis of the moving parts of the devices. Because of this single axis mode-of-failure characteristic, the sirgle axis tests applied along the most sensitive axis of the devices provided adequate demonstration of seismic qualification. All of the devices withstood the test program with no equipment failure or misfunction during the tests, nor any degradation of equipment performance following the tests. The devices are therefore considered seismically qualified for installation in the MCC's. Note: As with the GE relays, qualification of these devices would not be extended to any other installation without appropriate justification peculiar to that installation. 2312 136
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TEtJNESSEE VALLEY AUTHORITY 12/17/73 g RESPONSE ACCELERATION SPECTRUN m SNP AUXILIARY BLOG NASS POINT NO. 9 OAMPING RATIO 0.020 OPERATIONAL BASIS EARTHOURKE g FLOOR ELEVATION:748.50 m N-S HORIZONTAL ACCELERATION h 7 5g E d u J Jg a. Jo- N C u j N !=*_ u 3 N J d S N ~ 8.
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PERIOD IN SECONDS F4ugE c.15
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- ~ m . e=== a= p===t m paag powg m p==g meg sang as TENNESSEE VALLEY AUTHORITY 01/08/74 a GROUr10 RESPONSE SPECTRUM q SEQUDYAH NUCLEAR PLANT o~ OAMPIrlG RATIO 0 020
, HORIZONTAL GROUND ACCELERATION g i OPERATIONAL BASIS EARTHOURKE
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o TENNESSEE VALLEY AUTHORITY mr n RESPONSE ACCELERAT10N SPECTRUM DIESEL GENERATOR BUILDING BASE SLAB EL.721.0
OAMPING RATIO 0.023 SEQUDYAH NUCLEAR PLANT OPERATION AL BASIS E ARTHOUAKE m
NOTE: THE HORIZONTAL OBE SPECTRUM FOR ELEV. 740 IS OBTAINED BY MULTIPLYING THIS BASE SPECTRUM d BY 1.10 e o- @ O = w S tf z a a b $e N y m N a O m M U Y N Ei - di. z O; N u a E: 4
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- RESPONSE SPECTRUM N-o BRO ADENED BY 10%
0.37 g. E MAX. SLAB ACCEL. (.74 G SSE)
.49 G VERT) -
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'l.00 1.20 1.40 1.60 1.80 0 0.20 0.40 0.60 0.80 PER100 IN SECONDS FIGURE 10
Motor Control and Switchaear B. 6900 volt Switchgear Auxiliary - Control building - Elevation 734 Applicable floor response spectra are attached. Horizontal OBE spectra - Figure C-12, N-S Figure D-12, E-W Vertical OBE spectrum Two-thirds of the figure B-3 levels SSE levels are equal to twice the OBE levels. Excerpts from the seismic qualification test report (Environmental Tectir.z Laboratories report No. 3720) have been previously submitted for NEC-C(hT review. The equipment was subjected to a series of single frequency, multiaxia seismic shock tests, i.e., decaying sinusoid. The input acceleration levels were: Horizontal 2.k g Vertical 1.75 g Horizontal and vertical inputs were applied simultaneously. The single frequency tests were conducted at 4, 6, and 10 Hz. There were no equipment natural frequencies below 17 Hz. The single frequency test input motion was in the nature of a slowly decaying sinusoid. Although a precise response spectrum for this particular input wave form is not readily available, the conservatism of the test should be obvious from the comparison of test ineut acceleration levels relative to the required response spectra levels. However, for the purpose of illustration, the conservative assumption is made that the response spectrum for the test
=otion can be approximated by that of a Seycle/ beat sine beat. With this assumption, the degree of conservatism provided by the horizontal test ce=ponent is illustrated by the attached plot. The vertical axis is even more conservative than the horizontal.
2312 141 (1)
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- HM TENNESSEE VALLEY RUTHORITY 12/17/73 RESPONSE ACCELERRTION SPECTRUM SNP RUXILIARY BLOO
,- MRSS POINT NO. 8 DANPING RATIO 0.020 OPERATIONAL BASIS EARTHOURKE FLOOR ELEVATION =732.S0 8 N 6 HORIZONTAL ACCELEt<RTION 6
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SNP AUXILIARY BLDG MASS POINT NO. 8 DAMPlNG HATIO 0.020 OPERATIONAL BASIS EARTHQU AKE FLOOR ELEVATION = 732.50 E.W HORIZONTAL ACCELERATION 1.00 - NOTE: THE E-W SPECTRUM ENVELOPES THE N4. 3 0.80 5' .73 G O 7 7 HZ (1.46 G SSE)
.6 2 u . HZ
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.16 G ZPA y
(.32 G SSE) N __ b u 0.00, i - - 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.? ' O.80 0.90 PERIOD IN SECONDS FIGURE D.12
- m m
- - - - - > > = <a poorg m >=e sw m ps TEtit4ESSEE VALLEY AUTriORI TY 01/08/74 GROUf10 RESP 0tJSE SPECTRUM S SEQUDYAH NUCLEAR PLAT 1T
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- 10. 'I .- SINUS 010 TEST INPUT. -
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m FREQUENCY. HERTZ 2312 145 t \
Motor Control Center and Switchgear C. 480-Volt Switchgear Auxiliary - Control building - Up to elevation 749 Applicable floor response spectra are attached. Horizontal OBE spectra Figure C-15, N-S Figure D-15, E-W Vertical CBE spectrum Two-thirds of the figure B-3 levels SSE levels are equal to twice the OBE levels. Excerpts from the seismic qualification test report (letter report from Westinghouse Switchgear Division) have been previously submitted for NRC-SQRT review. The equipment was subjected to a series of single frequency (sine beat,10 cycle / beat) single axis tests. The input accele-ration levels, applied in each of three mutually perpendicular axes, were: Up to 10 Hz - 0.8 g 10 to 13 Hz - 0.8 to 0.5 g (linear) Above 13 Hz - 0.5 g The sine beat tests were conducted at 5,10,15, 20, and 25 Hz and at equip-ment natural frequencies established from low level frequency sweep tests. Observed natural frequencies were: Pront-to-back axis - 15 Hz Side-to-side axis - 6.5 Hz Vertical axis - None below 25 Hz The conservatism of this test procedure is the same as that discussed for the auxiliary air system compressor. Similarly, the attached plots illustrate the degree of conservatism provided by the SSE tests. 2312 146 (1)
. . ~ . . . - - -- _
TENNESSEE VALLEY AUTHORITY 12/17/73 a RESPONSE ACCELERATION SPECTRUM m
~
SNP RUXILIARY BLOG
~
NASS POINT NO. 9 OAMPING RATIO 0.020
, OPERATIONAL BASIS EARTHOURKE g FLOOR ELEVATION =748 50 u;
N-S HORI7DNTAL ACCELERATION 3
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1.80-- TENNESSEE VALLEY AUTiiORITY 12;12.73 RESPONSE ACCELERATION SPECTRUM SNP AUXILLARY BLOG MASS POINT NO. 9 1.5 G = 3.0 G SSE 0AMPlNG RATIO 0.020 y 9.43 HZ OPERATIONAL BASIS EARTHQUAKE 1.50 - e FLOOH ELEVAT10N = 748.50 f E.W HORIZONTAL ACCELERATION NOTE: THE E.W SPECTRUM ENVELOPES
, Tile NS.
3 5 1.20 - 3 s y 0.90 - - 10.8 HZ ,f 7.7 112 h- W .82 G = 1.65 G SSE 3 0.60 - 12.2 HZ r
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u _ 0.30 -
- - ZPA .19 G = .38 G SSE 33 HZ CD 0.00 .
0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.1 PERl00 IN SECONOS FIGURE 0.15
w - .- .- ----- - - TENNESSEE VALLEY AUTHORITY 01/08/74 GROUND RESPONSE SPECTRUt1 S SEQUOYAH NUCLEAR PLANT
$~ DAMPING RATIO 0 020
- HORIZONTAL GROUND ACCELERATION g (
OPERATIONAL BASIS EARTHOURKE
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HORIZONTAL AND VERTICAL RESPONSE SPECTRA m DERIVED FROM SINE BEAT (10 CYC/ BEAT) TEST INPUT MOTION. TEST INPUT ACCELERATION WAS: 0.8 G @ 5,6.5*, & 10 HZ 10.i
- SIDE.TO. SIDE AXIS ONLY np
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2.s a .: s . 100. FREQUENCY. HERTZ 2312 150
Diesel Excitation System Diesel generator building - Elevation 722 - Base slab The applicable floor response spectrum is attached. Horizontal OBE spectrum Figure 10 - Applicable in each of two perpendicular horizontal axes. Vertical OBE spectrum Two-thirds of the figure 10 levels SSE levels are equal to twice the OBE levels. The seismic qualification test report (Exide Power Systems Division Technical report No. QCC-12) has been previously submitted for NRC-SQET review. The equipment was subjected to slow sine sweep, multiaxis test. The input acceleration levels to the equipment were: Horizontal - 0.7h g Vertical - 0.74 g Horizontal and vertical inputs were applied simultaneously. The frequency sweep rate was sufficiently slow to ensure full resonant buildup throughout the sweep range of 1 to 30 Hz. The conservatism of this test procedure is the same as that discussed for the auxiliary air system compressor. Similarly, the attached plot illustrates the degree of conservatism provided by the SSE tests. 2312 151 (1)
TENNESSEE VALLEY AUTHORITY 3.66 G @ 4.75 HZ RESPONSE ACCELERATION SPECTRUM 3.60 r (7.3 G SSE) OIESEL GENERATOR BUILDING BASE SLAB EL. 721.0 OAMPING HATIO 0.020
- SEQUOYAH NUCLEAR PLANT ,
l OPERATIONAL BASIS EARTHQUAKE 3.00-
$ 2.40 3-5 p. =t c 5.9 HZ 3.3 HZ ' $ ' .81 0 1 -O- - 18G U (3.6 G SSE)
E
= -
E-ni E 1.20-U _ 0.60-
- 1. HZ 0.37 G. ~ ~
.37 G MAX. SLAB ACCEL. ( 74 G SSE) tn N
0 ! ' t - t . : t-- . . . . . 0.60 0.80 1.00 1.20 1.40 1.60 1.80 0 0.20 0.40 PERl00 IN SECONOS FIGURE 10
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.,' , L RESPONSE SPECTRA DERIVED lUi ' he . '
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100. FREQUENCY. HERTZ 2312 153
125 Volt DC Batteries Auxiliary - Control building - Elevation 749 Applicable floor response spectra are attached. Horizontal OBE spectra Figure C-15, N-S ~ Figure D-15, E-W Vertical OBE Spectrum Two-thirds of the figure B-3 levels SSE levels are equal to twice the OBE levels. The seismic qualification test report (TII Testing Laboratories report No. 55h7) has been previously submitted for ERC-SQET review. The batteries, installed in the battery rack, were subjected to a series of single frequency (sine dwell), single axis tests. The input acceleration levels to the equipment were: Horizontal Parallel to plates - 1.6 g Perpendicular to plates - 1.3 g Vertical - 0.51 g The sine dwell tests were applied at frequencies corresponding to the observed natural frequencies of the equipment, i.e. , Horizontal Parallel to plates - 12 Hz Perpendicular to plates - 11 Hz Vertical - No resonance below 33 Hz, tested at 33 Hz The conservatism of the single frequency sine dwell test procedure is the same as that discussed for the auxiliary air system compressor. Attached plots illustrate the degree of conservatism provided by the SSE tests. For this particular equipment configuration, single axis testin6 is justified due to the absence of cross-axis dynamic coupling. 2312 154 (1)
_ - - - ; ~ - - - - - - - . TENNESSEE VALLEY AUTHORITY 12/17/73 o RESPONSE ACCELERATION SPECTRUM 9, SNP RUXILIARY BLOG MASS POINT NO. 9 OAMPING RATIO 0.020 OPERATIONAL BASIS EARTHOUAKE FLOOR ELEVATION =748.50 _ N-S HORIIDHTAL ALCELERATION
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TENNESSEE VALLEY AUTHORITY 12/12/73 RESPONSE ACCELERATION SPECTRUM
.80- SNP AUXILIARY BLOG MASS PolNT NO. 9 OAMPlNG RATIO 0.020 OPERATIONAL BASIS EARTHOUAKE FLOOR ELEVAT10N = 748.50 1.5 G = 3.0 G SSE E.W HORIZONTAL ACCELERATION 9.43 HZ 1.50-NOTE: THE E W SPECTRUM ENVELOPES Tile N S.
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