Text

Assessment of Vibration Characteristics & of Seismic Qualification. Interoffice Memo Encl
	ML20050C778
Person / Time
Site:	Zimmer
Issue date:	04/07/1982
From:	; SARGENT & LUNDY, INC.
To:	;
Shared Package
ML20050C776	List: ML20050C775; ML20050C778; ML20050C780; ML20050C781;
References
	EMD-031375, EMD-031375-R00, EMD-31375, EMD-31375-R, NUDOCS 8204090348
	Download: ML20050C778 (132)
	v • d • e

{{#Wiki_filter:pg.77. m,., EXHIBIT A,, S-I .t* SGTS Equipment Train es'e. 9:.,.E?ID-0 313 7 5 [- ' g =c _ caict rer <~,/ C X GT.GT hLU.'.'DY ' No. lycosSA.s lVocssa n,.. o o e,i, 8-27-81 ! l I r.. ore ceas. c-.c ac. X Safetv-Ref:ted Non-kfetv-R::4ted P:ee Cl of C 42 C:st The Cincinnati Gas & Electric Cn Prepered dy I. Elaindy Det, 8 8 R:vkned tra Octe 7,o:ets tin. H. Zirmer Nuc1 car Pcwer Station-1 Date Preit:o. 4130-15 Ecuis.Ho. ivr:0Wm Approved by ASSESS!1ENT OF VIBRATION CHARACTERISTICS AND OF SEISMIC QUALIFICATICN t I. OBJECTIVE To assess the vibration characteristics of the above equipment as I determined analytically and by impedance testing, and to deteruine adequacy of equipment under the additional loadings, particularly in regard with the high resonances determined by impedance test. II. I!:TRODUCTION Ov In conducting this assessment, one must recognize the practical limitations of available analytical and experimental techniques. For example, the finite ele:nent method is limited when representing a structure by number of nodes, number of elements, nodal masses, idealized boundary conditions and by the tiype of nodal stiffnesses, functional relations between the nodes. On' the other hand, experimental technicues such as impedance' testing is also limited by the number of 1ccations utilized in ymm on 53 applying vibration input and in mearuring vibration response. Do Other limitations include inaccessability to certain areas, c-0 og 7g coherence of signals, cross coupling betvcen natural modes of o$o equipment and cress coupling with other natural =cdes of attached g muo co4 structures. xx assessment of the results obtained by both methods, Therefore, has to consider these listed limitations and consequently has to. .n

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EMD-031375 Cales. For SGTS Equipment Train Cale. no hSARGEUThl020Y no. lvG0ssa s lvG0ssB Rev. 0 0 oste 8-27-si tamwr.we J C " %^" X Safety-Related Hon-hfety-Re'ated Pa;s C2 of C 42 ] ElectricCo) Prenred by T. Elaindv Date 8 - 2 7 - P ' Ctent The Cincinnati Gas & Pro,ect 1.b. H. Zim:cr Nuclear Pczeer Station-1 Rreimed by Date l Proi. No. 4130-15 Equip. No.lVG05SMB Approved by Date l III.

SUMMARY

OF IMPEDENCE TEST RESULTS The SGTS equipment, train structure (4 ?,7" x 8 2" x, 81") wan repre-sented by the wire diagram shown on page C10 The SGTS equipment structure was excited using the TRASITEK hydraulic shaker configured ~he maximum force used in this test was with the large weight. T ~ 2500lb. The two locations selected for placing the hydraulic shakers are shown on page C24. It must be noted that the mounting of the shaker on the top of the equipment train would not have significant effect on the resonances determined by the test. The h only effect of this added mass would be limited to artificially lowering the magnitudes of the natural frequencies determined by the test. Since the added mass of the shaker is very small compared with the total mass of the equipment Uain, its offeet will be within the tolerance of the experimental results. ~ The Impedence Test showed 13 resonances, the mode shapes of these resonances are shown on page C11 through C23 The follouing is a list that describes all 13 resonances reported. Frequency I!z Description l 25.91 Global mode, bending along ::, X directions 28.9 Local mode 31.02 Global mode, bending mode along Z directic: 41.07 Local mode g) y, 44.21 Global mode, bending along Z direction 47.53 Local mode

I Cales. For SGTS Equioment Train Cafe. 7:o.EMD-0 313 7 5 t (SAGGERTi!.IJUDY No. IVGOSSA & IVG95SB Rev. 0 0 Date 8-27-81 1cn31NCG AO i C "'C ^" Safety-Refsted Non-&fety-Refsted Pare C3 of C 4_2 y Client The Cincinnat' Gas & Electric Co, Prer: red by I. Elaindy Date 8-27-E l Proiect h'n. H. Zirner Nuclear Power Station-1 Revievred by Date Proj. No. 4130-15 Eoip.No IVG05SAJB Approved by Date Frequency Hz Description 56.08 Local mode 62.44 . Global mode, bending along Z direction 67.85 Global mode," bending along Z direction 68.2h ' Global mode, bending along Z direction 76.68 Global mode, bending al'ang Z direction 86.54 Global mode, bending along Z direction '90.6 Global mode, bending alonz Z direction The above listed results show nine global modes and four local modes. O The results also show that seven resonances are above the horizontal , ZPA level of 50.0 112. IV. SU?O!ARY OF ANALYTICAL RESULTS The seismic qualific'ation of SGTS equipment train was prepared by American Air Filter Co. on Sept. 3 r 1975. (1) In this qualification report the equipment was represented by finite element model as shown on page C25. The detailed model consists of 116 nodal points, 278 beam elements of 11 types, 98 membrane elements of.116 " thickness, 16 plate elements of.ll6" thickness.The detailed data concerr.ing the rzrber of concentrated masses, their locations and the boundary conditions utilized in this qualification report are not available. O G ~ .h* s

T Cafes. For SGTS EcuirTrent Train C !:. No.EMD-0 313'7 5 SARGEUThlUudY 2. IVGOSSA & IVG95SB Re e. 0 0 Date 8 81 4 Ncinm er's_ g c mc ac,o X Safety-Refettd l Non-Ssfety-Rebted Pc;a C4 of C42 Ctent The Cincinnati Gas & Electric Co. P.:pered by I. Elaindy Oste 8-27-81. O Project Mn. H. Zirner Nuclear Pcuer Station-1 R vianet, by Date Prol. No. 4130-15 Equip. No. IVGCSSA&B Approved by Date The results of this analysis show that the SGTS equipmetkt'. train has three fundamental resonances at 14.64 Hz, 3l.9Hz, and 40.4 Hz. s The report shows that the first mode is localized in the front part . of the equipment, blower side. The second mode is bending mode along Z direction which is similar to 25.91 Hz resonance reported 1 in the impedance test. The third mode is vibration along Z direction with maximum displacement occurred at the plane X* = 51.0", the amplitude of vibration decreased to 9% from the maximum at X = -140.0" (front of equipment) and at x = 27.0". This mode is similar to the 44.21 Hz mode reported in the impedance test. V. RESONANCES IN AGREEMENT WITH IMPEDENCE TEST RESULTS Impedence Test Analytical Results 25.91 Hz 31.9 Hz 44.21 Hz 40.4 Hz VI. RESONANCES PREDICTED ANALYTICALLY WHICH APS NCT PREDICTED EXPERIMENTALLY Only one frequency falls in this category, 14.64 Hz. This frequency resulted from the conservative approach utilized in modeling the front end of the equipment. The result of the impedence test showed that there is no resonance at this frequency. It is, therefore, concluded that the loads dencrated by this stip'ulated resonance are not likely to be applied on the structure.

Coordinates referenced here are based on global axes of finite. ele-

. ment model. E

EMD-031375 Caks_ For SGTS Equipment Train Cafe. No .SARGEUThLUNDY No. IVG05SA & IVG95SB Rev. 0 0 a re 8-27-81 1anomaane. I c - c.^ X Safety-Re!ated Non-Safetv-Rebted P:;e C5 et C42 Cf.ent The Cincinnati Gas & Electric Co. Prepared by I. Elgindy Date 8-2 7-31 Project W:n. H. Zinver Nuclear Power Station-1 Reviewed by Date Proi. No. 4130-15 Ecure.ma. IVGOSSA&B Approved by Date t VII. RESONANCES PREDICTED BY THE IMPEDANCE TEST AND WERE NOT PREDICTED ANALYTICALLY 8 There are ' eleven resonances which f all in this category. Thece resonances are essentially horizontal' vibration along Z and X axis with low percentage of crsss coupling along the vertical'Y axis. Among these eleven resonances, seven are above the horizontal ZPA level of 50 Hz and therefore, shall have no effects on the structure integrity of the equipment. The remaining four resonances indicate that three of them are local modes affecting h one or two locations on the front side of the equipment where the access doors are 1ocated. The fourth resonance is# a global mode. VIII. EFFECTS OF THE FOUR RESONANCES WHICH ARE BELCW T*rlE 2PA LEVEL A. Global Modes The single resonance which falls in this category is 31.02 Hz. Its dynamic loads are limited to the front half of the struc.ture including both sides as shewn on page 13. This vibration is approximately similar to the resonance of 14.64 Hz which was predicted analytically due to conservative medeling of the structure. Based on the latest horizontal respense spectra shown on pages 26 through 33, the maximum G 1evel loads are 0.6g's at 31.92 Hz. and the equipment was cualified at the maximum responses C) which occurred at 14.64 Hz. for horizontal accelerations under OBE condition of.69g along X and 1.43g along Z dire-tion and under

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Cafe. No.EMD-0 313 7 5 r Cates. For SARGEijTi:1.UT10Y R e,. 0 0 01,8-27-81 s .a naINeenne. Safety-Reisted Non-Safety-Refated Page C6 of C42 c m.c aoo Client The Cincinnati Gas & Electric Co. Pre:ared by I. Elgindy Date 8-27-81 Project Mn. H. Zimer Nuclear Pcwer Station-1 Reviewed by Date Proj. No. 4130-15 Equio. No. Approved by Date l ~ s 9 SSE conditions of 1.12g along.X direction and 2.11g along Z direction. Furthermore, the equipment was requalified on August, 1981, EMD-030459'Rev. (2). The requalification calculations showed that under the latest response spectra, the maximum stipulated stresses are well below the allowable limits Ref. (1, 2). It is therefore, concluded that the global mode of 31.02 which was predicted only by the impedance test is conservatively considered in the analytical qualification by considering the O high analytical response at 14.64.Hz, which resulted only from the conservative model utilized and was not found by the impedance test. B. Local Modes Three local modes fall in this category, these resonances are: Prequency Hz Description 28.9 Maximum response at location 26 o'f wire diagram X*26 = 249", Y26 = 48" and Z26

11" 41.07 Maximum responses are at locations 26 & 21 of wire diagram (see page 10) X21 = 112",

Y21 " 40"' Z = 0.0" 21 47.53 Maximum response at location 21 of wire O diagram

Coordinates references here are based on global axes utilized in the impedance test.

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Cafe. No.EMD-0 3137 5 Cares. F or SARGEi1Ti:LU.*JDY ,,, c o o,,. 8-27-s1 i = eNGtNetMS C "" ^" O Safety-Refsted Non-Safety.Refatto Pa;, C7 of C42 Client The Cincinnati Gas & Electric Co. Prearea by Date Project hb. H. Zirrrer Nuclear Power Station-1 Reviawed by Date Proi. No. 4130-15 Equip. No. Approwd by Date The three local modes have maximum response at two locations as indicated above. 7n the vicinity.of location 26, there are no, instruments which may be' subjected to these local vibrations and the structural members (beams and platesj have enough safety margin to withstand the relatively small dynamic loads resulting from these local modes. In the vicinity of location 21, two "liglit switches are mounted which are not safety-related instru-ments. Preliminary analysis indicated the following: 1. No qualification is required for these light switches. O 2. The only function performed by these light switches is to provide control for two light bulbs located inside two SGTS chambers. This function is totally independent of the safety-related functions performed by all safety-related devices of SGTS equipment train. 3. The effects of these three local rcedes on the structural integrity of the SGTS housing is insignificant compared with the overall response of tiie SGTS housing. Due to above listed results, it is concluded that no detailed qualification analysis to quantify the ef fects of the local modes on the light switches is warranted. 9 O e e

ege,, p, ecc. u,EMD-0 313 7 5 [SAflGEiiT4LUTJDY ,,,, 0 0 o,,,

swammene.a Safe.c-Refsted Non-Scfety-Re!ated Pa o C8 of C 42 C "'C ^

Client The Cincinnati Gas t.

Electric Co. Prepared by Date f Project hb. H. Zi:mer Nuclear Power Statien-1 Reviert:d by Date Proi. No. 4130-15 Eaulo.No. lVG05SA&B Approved by Date l It is therefore, concluded that the three local modes reported shall have.no ef fec't on the operability or the, structural ingegrity of any and all safety related devices of SGTS equip-ment train. IX. OUALIFICATION FOR ADDED HYDRODYNAMIC LOADS The seismic qualification report (1) released in may 1974, was based on the original response spectra shown on pages C34 through C42. In the early part of 1980, the hydrodynamic loade O were eaaea ena new response seectre were seaeretea es shown on pages C26 through C33. As a r'esult, requalification report (2) for the structure was issued and requalification efforts for the instruments were initiated. l The requalification of the equipment structure concluded that I under the new response spectra which includes the additional hydrodynamic loads,the structure is adequate. t It must be noted that the requalification calculations are based on the original qualification report (1). l i O l 9

. _ _. ~ ___ c,,e, uoEMD-0 313 7 5 f c,,,,,,,, .SARGEi1T.E LU.'jDY n,,. 0 0 o,,,8-27-81 ! 1suaimesne. Safety-Refsted Non-Safety-Related Ps;9 C9 of C42 C "'C ^G ( Client The Cincinnati Gas & Electric Co. Prepared by I. Elgindy Oste 8-27-81 f Project hh. H. Zimmr Nuclear Poacr Station-1 Reviewed by Date Proj. No. 4130-15 Ecuip. No. Approved by Date X. CONCLUSIONS Based on the above, assessment, it is concluded that the analytical model is conservatively. adequate in representing the SGTS structure. Two of the three fundamental frequencies determined analytically have bcen verified experimentally by the impedance test. The exclusion of the third fundamental resonance has been conserva- 'tlvely compensated for in the qualification calculations by a similarly located high response low frequency resonance. It is furthermore, concluded that the seismic qualification (Ref. 1) O ana the reaualitication (Ref. 2) considering the additional hydrodynamic loads are based on sound and verifiable techniques. XI. REFERENCES 1. Seismic Qualification of SGTS equipment train IVG05SA & SB, EMD-001658, dated September 3, 1975 2. SGTS Ilousing Requalification Report, Equipment No's IVG05SA, IVG05SB EMD-030459, dated (August 21, 1980) 3. Impedance Test Report for SGTS equipment train No. IVGOSSA, EMD-032720, dated (August 7, 1981) ,4. Final test report,SQRT in-plant impedance _ testing, Zimmer Co. 1, Transitek, Inc. EMD-032470. O G G e

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nivn s 'venwsmv VERTICAL RESPO!!SE SPECTRA / (DD;IGI! BASIS EAiiTl!C.UAK':) 4-F '5-F 6]-F, 1sEACTOR / EL. 627 '-9,,11L :G. SL%B& 570 '-o,,, , 593'-o

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n ry is is , te to y u to .y i,6 i i.. i a i i i i ii ii6i i i FOR EQUIPMENT:.. LOCATED WITHIN A o, rI t, u DISTANCE = 2t FROM THE WALL WHERE. - %m 3, 't IS THE THICKNESS OF THE SLAB. Q <n.;' .3 se c. ~ r-- u 9C1 P-E l _ to. E cj .n<: t3 u 3% DAMPING i O .c he. j o J tl pas m e te :n 3 5 1% DAMPING l \\/e/. com to O F s LC h ~ 1.* c3 M. I ' O--'./ /o 2% DAMPING l- ~ LO Imm

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Calc. No. EM D-o 3 / 3 75 #

Rcw Dato: ProJ. Nc: 4/3o-15 { Fila No: EMD- , p.y f C I;. 'nf C /,"

Cates. For Reactor Core Isolation Cafe. floEE-03137 5 SAGGEijTi:LU!jDY -enastname. - pumn Rn. 0 0 cata l 2-17 -2 coo 11nc, l c ~.c ac.o X Safety-Ret tsd . l. Nen-Sfaty-R Isted Ps a D1 cf D25 i _Cl.ent The Cincinnati Gas & Electric Co. Fue: red hv N. Muni - Date l2-17 e _; Peopc Rn. II. Zinrcr Nuclear Poacr Station-1 Ridewed by Data l Proi. No. 4130-15 Equip. No. lE51C001 Approved by Det. l EXHIBIT "B " OIMECTIVES The objectives of this study are: (1) To compare and draw conclusions on equipment qualification procedures based on a comparison of the Impedance test result and the qualification report. i (ii) To assess the importance of the additional hydrodynamic loads. This is of concern in view of th( high frequency resonances reported in the Impedance test. O Qualification Renort (2) In the qualification report the pump, pump supports, base as well as the associated piping were modelled. The finite element model con-sluts of 50 plate elements, 76 beam elements and has a total of l 119 nodes (p.D10).The pump itself is substantially a rigid member mounted on relatively flexible supports. The base to which the pump supports are attached is firmly attached to the slab by means of four anchor bolts as wall as a grout pad on,the periphery of the base. in the dynamic finite element analysis the pump was modelled as a rigid member. The model included suction and discharge piping up to rentraints sufficiently distant from the pump such that the pine end fixity conditions irnosed in.the medel do not influence cump behavior. O e .--%+--w-

j Cales. Fe r c,ie,n,,~EMD-031373 i : SARGEijT

1.UfJDY Rev. 0 0 Dat:12-17'.81 !

scuanneena C'*C"" E Safety-Related Non-Safety-Related Page D 2 of D25 l i ClientThe Cincinnati Gas & Electric Co. Prepared by Datel2 81 ! ~ ProiettWm. II.Zimmer Nuclear IbwerStation-1 ' Reviewed by Date l l Prol. No. 4130-15 Equip.No. lE51C001 Approved by oat. l 1 An Eigenvalue analysis of the pump-system indicated the presence of leven cigenfrequencies. Ilowever, in all cases the pump itself ex- ] e hibited only rigid body motion. Some of the' system frequencies were ~ primarily associated with pipe v'ibration-the remainder with vibrhtion i J of the pump support. In the analysis (Ref. 2) the required response spectrum used was a combined seismic and hydrodynamic floor spectra. Stresses obtained at the most critical locations in the vicinity of the support and pump were within allowable limits. IIence the equip-ment was qualified. Impedance Test (1) At the time of The equipment tested was the RCIC pump (lE51C001). testing all hydraulic and instrument connections to the pump were completed and the pump was coupled to the turbine. The geometry for the pump as tested is shown on page D9. Pump resonances were excited by the impulse technique using the large (5 pound) hammer. Responses were measured at the outboard end of the pump. G 9

3 f.'s't. No.EMD- 0 313 7 5 j Cales. For SAUGEijThlU.*.'DY f-oo i

? 'v-Date 12 Pl.

C".c a so X Safety-Related Non-Safety-Refsted f_.~e D 3 of D25 O Chent The Cinci nati Gas & Elec'tric Co, Prepsred by Date ] 2 91 I V Protect Mn. !!. Zi.rer Nuclear Power Station-1 Rrrieved by Date 1 Pro l. No. 4130-15 Equip. No. IE51C001 Anreved by Date l A total of six resonant frequencies,were determined ranging from 39ilz to 9111z. These frequencies are characteristic of solid-rigidly mounted equipment. These frequencies correspond to support vibratory motion. The pump itself is observed to respond as a rigid body member. List of Frequencies Determined from the Iroedance Test and the Qualification Report: Qualification Report (Analysis; Ref. 2) g The following eleven equipment resonant frequencies have been determined: No. Frequency Oualitative Description of Associated Mode 1. 9.343 112 Primary pipe mode 2. 18.68 IIz. Primary pipe mode 3. 25.88 liz. Combined pipe and support mede 4. 36.32 IIz. Primary support mode 5.. 62.86 112. Primary support mode 6. 68.28 liz. Primary support mode 7. 72.0 !!z. Primary support mode 8. 81.1 !!z. Combined pipe and support nede 9. 84,92 IIz. Combined pipe and support mede Q 10. 91.34 liz. Primary support mode ll. 93.82 IIz. Primary support mode 9

cerci. For cate. t'o.EMD-0 313 7 5 j SARGEfjThlUf DY R ev. 0 0 oet.12 s i i 1eNGINSNM D ] C "'C ^G O X Safety-Reisted Non-Safety-Rafeted Pap D 4 of D25 j cient The Cincinnati Gas & Electric Co. Prepered by ' Datel2-17-8 7 Proint h*n. II. ZimTer Nuclear Power Statien-1 RsWewed by Date 1 l Prof. No. 4130-15 Equip. No. lE51C00~1 Approved by Date i i In the Impedance test, piping assoc, lated with the pump was not included. Thus, the frequencies obtained from the analytical results need to be examined carefully to determine primary - support vibratory motion or pipe vibratory motion. Modes wherein significant -vibratory motion occurs at the supports form a basis for comparison i with Impedance test results. The frequencies associated with these modes along with the axis (es) of vibration are listed below. In all cases pump rigid body motion is observed. 6 No. Frequency (IIz.) 2 Y X* 1. 25.88 x 2. 36.32 x. x x 3. 62.86 x x x 4. 68.28 x x x l S. 72 x x x l

Refer to p.Dll 7.

93.82 x x x for co-ordinate l system Frequency No. 1 is a combined pipe and support mode. The remainder are primary support modes, j Impedance Test (1) : Six resonant frequencies were determined, of which the lowest frequency was 3911:. Frequencies ranged from 3911z to 9011z. All of the mode.shapec 1 l ~

Cafe. No.EMD-0 3137 5 l I Cales. For SAGGEUT.h tU :DY nev. 00 a.te12-17-81! 1a No.Nesme [ c ~ ec ac" X Safary-Related i Non-Safaty-Reisted Pace D5 of D25 DateI2-17-81 f ElectricCo) Prersted by Chent The Cincinnati Gas & Project Rn. II. Zinner Nuclear Poder Station-1 T:cvirmed by Date l Proj. No. 4130-15 Entrip. No. lE51C001 Approved by Date associated with these frequencies i,ndicated bending at the supports only. Rigid body movement of the pump was observed. The following eigenfrequencies were obtained: (Mode shapes p. D12 thru D17) Axis of Frequency Predominant Vibration 1. 39.02 IIz. Rigid Twisting Mode Z Rigid Twisting Mode Z 2. 59.4 6 IIz. Rigid Twisting Mode Z 3, 60.72 liz. Rigid Longitudinal Mode X 4. 89.2 !!z. Rocking Mode (up & down) Y 5. 90.08 112. 6. 90.9 I!z. Rigid Lateral Mode (side to side) Z Comparison of Results Obtained from the Impedance Test and the Oualification Report In the Impedance test 3 rigid twisting modes in an in-planc direction perpendicular to the shaft axis are observed. In addition, a 90 liz frequency common to all the axes is observed. In the Qualification Report (2) resonant frequencies along each of the three axes ranging from 36.3211: to 93.8211: are observed. In addition, i a combined pipe and support frequency of 25.8811z is observed only 'along the axis of the pump. The 25.88 liz frequency is predominately a a pipe frequency influencing the supports at the pice support attach-ment and therefore not addressed to in this comparison. e .. -. - + -. - -.

i care.No. MD-03137 5* E 1 Cates. For i SAi!GEijThluf1DY R. 00 oste 12-17-8 C"C^"O X Safety-Related fJon-$:fety-Re'eted Pc;; D 6 of D25 i a NCflN OGSIS. Date 12-17-8 : Cient The Cincinnati Gas & Electric Co, Prepared by Data Rwiewed b/ Project Wm. H. Zimier Nuclear Power Station-1 oete Prol. No. 4130-15 Equip. N o. lE51C001 Approved by 2 from the Qualification Report compares well with Frequency No. In the Impedance test frequency No. 1 from the Impedance test. In the this frequency was indicated only about the Z. axis. analytical results however, a more plausible vibration along each i of the 3 axes is obtained. Two closely spaced modes, frequenies No. 2 and No. 3 about the Z axis compare favorably with frequency No. 3 from the Qualification Report (2). Again in the modal analysis vibration along each of i the 3 axes is obtained. h i An intermediate frequency (Nos. 4 and 5, p.D4) is obtained in the t ~ modal analysis. This frequency is not picked up in the Impedance test. The next equipment frequency corresponding to Nos. 4, 5 and 6 in the Impedance test are in essential agreement with frequencies Nos. 6 and 7 obtained in the modal analysis both.with regard to.the frequency as well as the axes of vibration. In the qualification report the pump assembly is modelled as a rigid member. In the Inpedance test, accelerometers were placed on the the motion observed was for the casing casing of the pump, tience, and an accurate representation of the mass distribution was not passible. l In the finite element modelling a much more accurate representation of l llence the results obtained in the Qualification the mass was possible. Report are more realistic than the Impedance test result obtained. ~ ^'"" w s-~.

""N*w

.e,,.., - + - m m

?extsvar core. No.EMD-0 313 7 5 SAi1GHJT4LU;;DY 3,,. o o o,,12 n -ancmanne. dear g_ s,,.,md Non-Sefety-Refsted Pep D 7 cfD25 C"C^oo i cl.ent The Cincinnati Gac t, El t:. ' ri c Co, Prenrad by ' Dat: 12-1 M ' Project W:n. II. Zi trer !!uclur Poaor.'Wstion-1 P.eviewed by Date l Proj. No. 4130-15 E: s No. l~,;C001 Approved by

Det, a

v It should be noted that the pump is physically connected to the turbine; this connection is not represented in the finite element model. In the finite elemer,t model the piping associated with the pump is considered, therefore, some pipe frequencies are obtained. Pipe frequencies are precluced in the Impedance test due to (i) the placement of the accelerome* ers and (ii) no attempt was inade to excite the associated pipin,;, Thus, certain anomalies are to be expected in a comparison be* Ween the Qualification Report and the Impedance test. 9 Oualification for flydrodynn:. ic Loads In the Qualification Report both the seismic and hydrodynamic loads were considered (pp.D18-25',ne ; smic and hydrodynamic response spectra). The frequency range from 9, :liz to 9411z covered the entire range of the response spectra. The "luipment was qualified for this frequency range. (2) <cnclusion: The dynamic behavior of the pump assembly observed in the Impedance test was utilized in the pr nparation of the finite element model of the pump. The analytical tv, del constructed is more representataive than the Impedance test in 1.redicting equipment dynamic characteristics. j A renponse spectra analysin f'or the seismic and hydrodynamic loads h'aed that the stresses ar,,1 def1.cctions were well within allowable t i .7--.____,,

c,ic. ne.EMD-0 3137 5 l caks. ro, l-SNIG2fjTSLU"DY ne.00 a.tel2 n inneeNeene ~ C "'c aoo X Safety-Releted Non-S$fety-R*ted Pese D 8 of D25 + i 1 Cisnt The Cincinnati Gas & Electric Co. Prepsred by Date!2-17 9 *, j Project Mn. H. Zimer Nuclear Poaer Station-1 Hevimeed by 0.te j i Pr H. No. 4130-15 Eouio.No. lE51C001 Approved by Dete l 1 i limits (2). The pump therefore, is' qualified.

l I

l

References:

l I i l. Impedance Test Report for RCIC Pump (IE51C001), Zimmer Nuclear {' I Power Station. EMD File No. 032716. (In Preparation) I i i l 2. Qualification Report for RCIC Pump. CQD File No. 000999. I l i l 1 lO i P I \\ l l l ~ O 4 e s e -=~w e- >...m ..e

g

--,-v._. 7 -g --r. 9 -7 4

j o i -l 1 P HY S ICM. L A w U T-D.= RC C POMP. SM^E.T 3 0;' t r> !!EVI'"O riS ~- 7llACTICitAL TOLE 2ANCES UNtESS t 0TED ,.N ~ ~ ' 1 - Qt,(.e --- --- - -- - AtACatx1NG = 1/w tan:cAno:t E-'- F-k=e%u WEIGHTS ~ L u-- ' 2.P -f i - ~ ~ Q. PUM P.-. Sioo r s, - rj. M-l fj g-i B = to ea i C :. t WC BASE - toSo t a o i -{M' gi L r" D = t v,'; REACTO P CCgs...ESOLATIOM .y G D ' - A '- B q .,- en ' E - t G V3b y{f'~ F l's" 4 ,.y....G = M,,,J-c o o u.iM G PUMP. w enca. e }g i j i. 3.- H = to '/.:. 1_ . C --I,R- ="J1 l ,._4 a. a/tG 1=n ~ G D t 1 c.,

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h ' ', I IMPEDArJce . Test WlRE D/A GRArM. .} i s 2 SHAPE 6 COft*LETE X DIR l ~ l 61 .EX-Cotto,F= 89.300 HZ ( O.3, 0.5, '1.0, 0.0)aVIEU

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6 9 O O ~

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' 5 '_ -..m M q J 4'.g i k . k% g, 3 h g'. f ~ m -a f l l %-]s\\,. 'r A. ~% 3 i i i l i, I FIGURE 4.5.9 A SECOND RIGID TORSIONAL MODE OF THE RCIC PUMP MEASURED IN THE I DIRECTIO i THE N0DE POINT IS SLIGHTLY SHIFTED FROM THE MODE SHAPE AT 39.02 HZ. l e 0 0 g s 3 ' ~ ' ~ ~ " ' a

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'l ' 4 j.; _ i ' w. ~ e' 0 i g. t. // %t .. ~ e% a .i 1 4 i o FIGURE 4.5.B e i l \\ A RIGID. TORS 10nA1. MODE OF ThE RCIC PUMP AT 39.02 HZ MEASURED IN THE I DIRECTION i i e 9 o. 4 1 t-

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j..,%s ,+- w :e. : a. 3 1 /. k. i l V:., l z. .s i m l k'-' t;. -- x n, I Ng ~ 0 l m 9 l t 5 FIGURE 4.5.11-A RIGID LATERAL SPRINGING MODE OF THE RCIC Pul4P AT 90.9 HZ MEASURED If! THE Z i r t O O d O l

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i %4-r e t e i. FIGURE 4.5.6 l A RIGID X DIRECTION MODE SHAPE FOR THE RCIC PUMP MEASURED AT 89.3 HZ l O o

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-~- - ~ 4: Celes. For PlfR ficat Exchanker~Imphdance Cafe. No.EMD-03137 5 I 3ARGEriTLLUfJDY 7cce n.v. 0 0 oste 2-12-82 ~ i c -ec ^o o Safety-Es'ated l Non-Sefety-Refsted Page III cl !!37 i \\ Cient The Cincinnati Gas & Electric Co, Prepared by Talat Korman o.,,2/12/82 Project Wm. II. Zintrer Nuclear Power Station-1 newwwed by Dete Proi. No. 4130-15 Equip. No. 1El2-B001 Approved by Date EXHIBIT *C ". i 1. Objective The objectives of this study can be summarized as follows: (i) To compare and draw conclusions on equipment qualification procedures based on a comparison of the results of the Impedance Test with the existing qualification report. (ii) To assess the importance'of the additional hydrodynamic loads, especially in the high ( frequency range of fn = 3 3 to 10 0 112. 2. Summary of the Analysis of G.E. RilR !! cat Exchanger is located in the Reactor Building of the Zimmer Power Station at the elevation of 475'-6". A sketch of the equipment is shown on page !!3 (See Ref. 1, F. 3). A static and dynamic analysis was completed by the General Electric Co. to qualify the heat exchanger. The equipment was modeled using the three dimensional beam elements consisting of 134 nodes and 154 elements. The employed finite element model is shown in detail on page 114 (Ref. 1). The external shell, the ( internals and the supporting systems are considered in the model.

Celes. For RHR Heat Exchancer Impedance Cele. No.EMD-0 31375 SARGENThLUNDY Test Re,. 0 0 o,,,2-12-82 > eevoweases. .~ c-caoo Safety-Related Non-Sofety-Related Page H 2 of H37 r Cisnt The Cincinnati Gas & Electric Co, Propered by Talat Korman Oste 2-12-6 2 Project Wm. H. Zimner Nuclear Power Station-1 Revened by Date Proi. No. 4130-15 Equio.No. lE12-B001 Approved by Date 2. Summary of the Analysis of G.E. Cont'd Due to one dimensional characteristics of the beam 'i. element, the internals and the exterior shell of the heat exchanger were modeled along the middle axis of the equipment, whereby the radial flexibility (i.e. shell breathing modes) of the shell structure was ignored. The heat exchanger is supported at two elevations by structural steel and the details of the supports are presented on pages H3 and HS. SAP Computer Program was employed and the same finite element model was used to complete the stati~c analysis due to nozzle external loads, dead weight and to perform the dynamic analysis. The response spectrum ( method was applied and the latest available val'ues of seismic, SRV and LOCA loads were combined by absolute sum and used as input it, the dynamic analysis. The following frequencies were found (See Page H6): fn(Hz) = 14.52, 18.03, 18.10, 20.46, 21.54, 30.71, 31.13, 36.74, 39.65, 52.50, 71.29, 72.68, 80.28, 115.53 The final stresses due to static and dynamic analysis is listed on page H8. C i

4 -. O !c. No. E!!O-o 2:375 = ib.' 0 0 E.*03; 3 = ll 0 2-- f,,, RHR' HEAT EXCHMGER ( INVESTIGATED LOCATIONS , gc e of M c aa.n Investicated locations I g (L 1. Upper support to shell (A) and (C) l^)' I - Bijlaard stresses due to support load g), - Pressure and remote nozzle membrane stress s s # - Dynamic membrane stress I 2. Upper support anchor bolts - Reaction load tension and shear stress ] 3. Upper support I b - Bracket and attachment weld (6,/ 4 Lower support to shell (A) and (C) 6 - Bijlaard stresses due to support load I (c'), - Pressure and remote nozzle membrane stress - Dynamic membrane stress k[ D 5. Lower support. k i - Bracket and attachment weld 6 i!i; 6. Lower support anchor bolts i, e ,'g si. - Reaction load tension and shear stress 3 7. Shell-l s - Pressure and remote nozzle membrane stress - Dynamic membrane stress s 8. Tubes - Dynamic bending stress Pressure membrane 9. Flange assembly O. Shell outlet nozzle to shell junction FIGURE I ~ '~ ^ ' ~ I Z ~U

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ABS, ALLOWABLE SUM.

STRESS 1. Upper support to shell: - Location "A" principal stress 16,500 28,875 - Location "C" principal stress 2. Upper. support anchor. bolts: - Interaction criteria 13,700 26.460 l 3. Upper support bracket and attachment weld: - Principal stress 4,100 14,150 l 4. Lower support to shell: - Location "A" principal stress 19,800 28,875 i /~- - Location "C" principal stress 18,500 28,875 \\ /w. I 5. Lower support bracket and attachment weld: WLT fj l - Principal stress M 14,150 6. Lower support anchor bolts: - Interaction criteria .99 1.0 7. Shell - Principal stress 11,700 17,500 8. Tubes - Principal stress- < 11,000 14,770 9. Flange As.sembly 31,200 39,400 l l

10. Shell Outlet Nozzle to shell junction

. - Location "A" 21,600 28,875 - Location "C" 21,700 28,875 (} NOTES: 1 " Stress" in this table implies maximum primary membrane principal stress. 2. Stresses restilting from Faulted load case combination are compared with Upset allowables eliminating need to investigate Upset, emergency and Faulted conditions separately. Plant: Zimmer PWA ll78KN Rev. 0. ~ -.. e

---w Celes. For Rl!R !! cat Exchanger Impedance Cale. No.EMD-03137 5 SARGENT$LUilDY Test Rev. 00 oste 2-12-82 owninessie. Safety-Related idon-Safety-Releted Pege 119 of }{37 C " 'C ^ " (_ Client The Cincinnati Gas & Electric Co, Prepared by Talat Korman oste 2-12-82 ~ Project Wrn. H. Zinner Nuclear Power Station-1 Revowed by Date Proi. No. 4130-15 Equip. No. lE12-B001 Approved by Date 3. Summary of the Results of TRANSITEK, Inc. The wire frame model of the heat exchanger prepared by TRANSITEK is shown on page 1116 (See Ref. 2, P. 4 ). The model consists of 45 nodes. To determine the resonance frequencies, the heat exchanger was excited by a hydraulic shaker placed at the bottom of equipment to an acceleration level o'f 0.3g. The force level required to produce this level of acceleration was approximately 1500 pounds force peak. Random force ( ) exitation was used for all three directions of testing. An acceleration response was measured at each of the 45 numbered points shown on the wire frame model. The force was applied at point 1 for the y and z directions and at point 2 for the x direction. The resonance frequencies determined in x, y and z directions and the corresponding mode shapes are shown on'pages 1117-1137 (Pef. 2). From the first eight modes ( which represent the modes.with biggest modal participation, three are representing the bouncing modes along the y axis with the frequencies: fl,3,7 (IIz) = 12.87, 17.48, 29.06 The other three modes are representing the rocking mode in x direction with the frequencies: f2,5,6(II ) 14.65, 22.08, 27.23 =

. _.. = _. c,,,3p,RHR Heat Exchanq6r Impedance Calc. No.EMD-0 3137 5 SARGENThlUNDY no. 00 De,,2-12-821 7est >euesueene. Safety-Related Non-Safety-R efsted Page H10 of H37 l C"C" (" cmt The Cincinnati Gas & Electric Co, Propered by Talat Korman Dete 2-12-8 2 Project Mn. H. Zimner Nuclear Power Station-1 Revissed by Date Proj. No. 4130-15 Equip. No. lE12-B001 Approved by Date 3. Summary of the Results of TRANSITEK, Inc. Cont'd The fourth and eighth modes are describing the rocking mode in z direction and their frequencies are: f,8(Hz) = 20.26, 36.19 4 -Among the remaining modes, the breathing mode with f=93.50 Hz might be singled out, which describes the shell behavior of the equipment. 4. Comparison of Results l The frequencies determined in the qualification report are, ( as shown on page H12-overall in good agreement with the test results of Transitek, Inc. It should be emphasized here that the difference of the first fundamental frequency .between the analytical and experimental method is in the acceptable range: A = 14.52-12.87 = 12% 12.87 l l There are few resonance frequencies which are recorded during l the test but not determined'in the qualifi' cation report: fn (Hz) = 14.65, 27.24, 47.19, 58.4, 60.5, 71.2, 87.8, 93.50, 95.9, 96.2 The difference in the frequency content between the analysis and test is created due to the following: 1. The equipment, which is in reality a'shell structure, .~( is represented by three dimensional beam elements. l

celes.Fo,RHR Heat Exchanger Impedance core.N.EMD-031375 l SARGENT5LUNDY Test Re,. 0 0 De,e2 8 2 > sevoweene. (, Safety-Related Non-Safety-Related Pege H l l of H37 C "'C ^G Client The Cincinnati Gas & Electric Co, Prepered by Tc' at Korman Deve 2-12-8; Project Wm. H. Zimrer Nuclear Power Station-1 Reviewed by Date Proi. No. 4130-15 Equip.No. lE12-B001 Approved by Date a 4. Comparison of Results Cont'd 1. Cont'd Beam model will not provide the shell breathing modes. 2. Although.the effect of piping is considered in the static analysis by calculating the stresses due to nozzle loads, piping,was not modeled in-the frequency analysis. 3. The upper support in actuality is designed to accommodate thermal expansion in the radial and vertical directions. ( The real boundaries are therefore difficult to model .r analytically. The obvious effects of the assumptions 1 and 3 are lacking of the breathing mode with f = 93.5 Hz and the rocking mode with f = 14.65 Hz in the qualification report, which are recorded in the test. l The frequencies found by qualification report and recorded by Transitek, Inc. are listed on pages H12 and H13 for the l purpose of comparison. In general the agreement is very good. 5. Qualification for Pool Dynamic Loads Since the heat exchanger is already qualified in the original report for a combination of seismic and pool dynamic loads l l (see Ref. 1, P. 7), it is not necessary to perform here l any further analysis in this respect. l

f calc. N r. MD-0 313'7 5 [ E Celes.Fo, ' RHR Heat Exchanger Impedance SARGENTELUNDY Test Rev. 0 0 oete2-12-821 enesueeme. C,_ Safety-Related Non-Safety-Related Page H12 of H37 l C *""C ^ client The Cincinnati Gas & Electric Co, Propered by Talat Korman Det.2-12-82 Project Mn. H. Zimner Nuclear Power Station-1 Reviewed by Date Proj. No. 4130-15 Equip. No. lE12-B001 Approved by Date Confirming Frequencies G.E. Transitek, Inc. Directions of Modes l 14.52 12.87 Y 18.031 17.48 y 18.10, 20.46 20.26 Z 21.54 22.08 X 9 30.71 29.06 Y l 31.13, 36.74 39.91 X 39.65 36.19 Z 52.50 57.33 Y 71.29 69.87 X 80.28 83.33 Y 6 -...+-.- -.-%<-

Celes.Fo, RilR licat Exchancer Impedance Ceic. N r.EMD-0 3137 5 l Test Rev. 0 0 oote 2-12-82; ). SARGENT%LUNDY oweepesema Safety-Releted Non-Sofety-Related Pe2e fil 3 of H37 C " 'C ^

Client The Cincinnati Gas & Electric Co, Prepared by Talat Korman Deve 2-12-8 2 Project Wm.11. Zimmr Nuclear Power Station-1 Reviewed by Date Proj. No.

4130-15 Equip. No. lE12-B001 Approved by Date Non-Confirming Frequencies Transitek, Inc. Direction 14.65 27.24 X 47.19 X 58.4 X 60.5 Z 71.2 Y 87.8 Z 93.50 X 95.9 Z 96.2 Y As shown on page 117, only the first 9 modes have high modal participation factors. Based on this fact, only the first two. modes from the list given above: 14.65, 27.24 would have any significant effect to the fn (IIz) = stresses in the structure. As a result of a discussion with i Dr. Plummer from Transitek, Inc. we concluded that we can ignore 14.65Hz, since it represents a rigid body the effect of f = n 4 motion (rocking mode). Only contributing mode, not obtained in the analysis,is f = 27.2411z. Ilowever, a large enough n conservatism in the analysis exists, since the emergency stresses are compared with the upset allowables (see P. 11 8 ). 4

Colcs. For IJR Heat Exchancer Imoedance Cele. N r.EMD-0 3137 5 SARGENThLUNDY Test Rev. c o oote 2-12-82 eNSWamme l C "C " Safety-Refsted Non-Safety-Refsted Page H14 of H37 I ( Client The Cincinnati Gas & Electric Co, Prepared by Talat Korman oote2-12-82 Project Mn. !!. Zimter Nuclear Power Station-1 Reviewed by Date Prol. No. 4130-15 Equip.No. lE12-B001 Approved by Date 6. Conclusion As a result of this study, it can be concluded'that resonance frequencies of the qualification report -coincide in majority with the test frequencies re-- corded by Transitek, Inc. There are few frequencies in the test report which are not confirming with the analysis. This difference between the analysis and test is caused by the simplifications made in the analytical modeling. ( I f 1 t I l ~

.. ~.. Cates. For RHR Heat Exchancer Impedance Cale. NoEMD-031375 l i SARGENT.5LUNDY 7 cst ,,, 0 0 o,,e2-12-82i ....e... C " 'C ^ Safety-Related Non-Safety-Refeted Page H15 of H37 Clont The Cincinnati Gas & Electric Co, Prepered by Talat Korman Date 2-12-8 2! Project Mn. 'H. Zimner Nuclear Power Station-1 Reviewed by Date Proi. No. 4130-15 Equip.No; lE12-B001 Approved by Dete 7. References 1. "Zimmer RHR HX. DRF Extracts. SNUB #9851T 2769T, Results of Dynamic Analysis" G.E. Document. 2. "RHR Heat Exchanger (lE12B001A), Zimmer Nuclear Power Station, Unit 1", Report of Transitek, Inc. E ~ e 6 8 b O l t 9 4 L .m_

_.. _. _ -.. _. ~..... _ C) n r, ( ) i 2 M Af l 3 44 3 39 i 35 28 N 31 L7 g?4 W ~ 92 / 26 32 a5 i b Y 31 is X M~ 11 1E N13 1 A 1M"4 mwmn $ h5$ WI I, x $ o. g 2 = z k o s7 I / anew T t o o jii 6 l i W 3..'; i N 3 a P hNo j j + on.am i Pg l / FIGURE 4.4.1 WIRE FRAME MODEL OF THE RHR HEAT EXCHANGER [. THE, NUMBERS ON THE FIGURE ARE PLACED TO THE IMMEDIATE RIGHT OF THE GEOMETRIC LOCATION USED'IN ANALYSIS 0F THE DATA 4 P

1 'afc. No. EMD- 03ts7S j Rev: oo Date: 2.12. 8z

~

i Proj. No: 41s o - # F TI -80029-4 I File No: EMD~ March 31.1981 Page nsy of n 37

4. f i

F TABLE 4.4.1 i i MODAL PARAMETERS OF THE RHR HEAT EXCHANGER MEASURED IN THE X DIRECTION Damping Mode Shape Frequency (Hz) (%) of Critical 1 14.654 2.5 2 22.082 - , 4.1 3 27.237 4.5 4 39.391 1.5 5 47.191 2.8 6 58.445,- 1.7 s 7 69.876 2.9 14.3 I 8 93.537 i o TABLE 4.4;2 l .r MODAL PARAMETERS OF THE RHR HEAT. EXCHANGER MEASURED IN THE Y DIRECTION Damping Mode Shape Frequency (Hz) (%) of Critical 1 .12.876 5.3 ~ 2 17.489 4.6 3 29.066 1.2 4 (X Direction Mode) 39.688 4.9 5 (X Direction Mode) 46.740 3.2 6 (XDirectionMode) 57.331 3.3 7. 71.207 3.4 8 83.336 1.7 9 96.223 2.0 m ~J 4.4-10 . =..

. =

.,_._._._m \\ 203 ^al. flo. Ef.iD- 03 375 R2v: oo Date: 2.st.az. TI-800 29-4 ~85 March 31, 1981 ile No Ef. D - Page yggot psy. TABLE 4.4.3 j MODAL PARAMETERS OF THE RHR HEAT EXCHAfiGER MEASURED IN THE Z DIRECTION i Dar. ping Mode Shape Freque'ncy (Hz) (%) of Critical 1 20.263 11.5 i 2 36.196 - 5.1 3 60.504 1.2' 4 87.829 2.0 5 95.953 3.4 s i

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.s CARGENTO LUNDY ENQlNEERS CHICA20 EXHIBIT D Fatigue Evaluation of Equipment I. Introduction With the identification of SRV and LOCA hydrodynamic loads, concern was expressed as to the possible effect of fatigue upon the qualification of safety-related equipment. This concern was based upon the large number of cycles associated with the SRV and LOCA hydrodynamic loads in comparison to the small number of cycles associated with the postulated seismic events for which the equipment was qualified. The issue of fatigue has been addressed as a joint effort with the LaSalle Station using a two pronged approach. This two pronged approach consists of testing and analyzing representative types of equipment. The equipment evaluated for fatigue is: A. Mechanical fluid components 1. two motor operated gate valves 2. vertical pump 3. horizontal pump 4. heat exchanger B. Electrical components and instrumentation 1. three local instrument racks 2. fourteen miscellaneous devices II. Fatigue Evaluation Results A. Fatigue Evaluation by Analysis Three pieces of eqbipment, a vertical pump, a horizontal pump, and a heat exchanger were analyzed and the cumula-tive usage factor from all postulated loadings (seismic, SRV, and LOCA) was shown to be less than unity in all cases as shown below: Total Cumulative Description Usage Factor RCIC Pump (horizontal) 0.0055 LPCS Pump (Vertical) 0.221 RIIR Heat Exchanger 0.373

CARGENT Q LUNDY ENGINEERO CHICA33 The actual fatigue analysis of LPCS pump and RHR heat exchanger have been submitted to the Staff for the LaSalle County Station, and so is not provided again for Zimmer. B. Fatigue Evaluation by Test 1. Two motor operated valve assemblies were successfully tested. The input consisted of all postulated loadings (seismic, SRV & LOCA) enveloped for both the Zimmer and LaSalle Stations. In addition, after completion of the qualification testing (including fatigue) fra-gility testing was performed with input up to the shake table limits without loss of function. The test method was triaxial, multifrequency, and the test specimens were: 4' inch 300# MO Powell Gate Valve 16 inch 150# MO Anchor-Darling Gate Valve 2. Three local instrument racks were successfully tested. The input consisted of all postulated. loadings (seismic, SRV, & LOCA) enveloped for both the Zimmer and LaSalle Stations. The test method was independent biaxial multi-frequency and the racks test are: 72" local instrument rack 48" local instrument rack 30" local instrument rack 3. The following electrical devices and instrumen-tation were tested: a. Barton 760 Level Indicating Transmitter b. Robertshaw SP-222-C Pressure Switch c. General Electric 828E309AA Voltage Preamplifier d. Schutte & Koerting Model 20 Flow Transmitter e. Schutte & Koerting Model 91 Flow Transmitter f. Rosemount 535E Temperature Transmitter g. Pyco N145C3224 Thermocouple Temperature Element h. Asco 8323 Solenoid Valve

CARGENT O LUNDY ENGENCRRD CHIC A30 i. Yarway 4418C Level Indicator / Switch j. Barksdale D2H-M80SS Pressure Switch k. Barksdale PIH-M340SS-V Pressure Switch 1. Barksdale PIH-M85SS-V Pressure Switch m. Barksdale BIT-M12SS-GE Pressure Switch n. Barksdale DlT-H18SS Vacuum Switch The input consisted of all postulated loadings (seismic, SRV & LCCA) enveloped for both the Zimmer and LaSalle Stations. The test method was independent biaxial multifrequency. III. Conclusions A. Mechanical Fluid Components The fatigue evaluation of five representative mechanical fluid components demonstrates that these types of components have such large design margins that fatigue due to the postulated design loads is not of concern. B. Electrical Components and Instrumentation Response should be by Nutech (attached). IV. References 1. " Fatigue Analysis of RCIO Pump", December 31, 1981 CQD File #000750 2. " Dynamic Qualification Report on Two Valves", SDRC Report 10959 December 24, 1981 3. " Summary Report for Limitorque Valve Operators Testing Program", January 4, 1982, CQD File #000731 4. " Summary Report for Fatigue Analys'is for LPCS Pump" EMD File #028847 5. " Summary Report for Fatigue Analysis of RHR Heat l Exchanger" EMD File #028847 6. Vibration Test of 72 inch Local Instrument Panel for Wm. H. Zimmer and LaSalle County NPS, SWRI Project 802-6056-001, November 7, 1980.

-o et CARGENT O LUNDY ENGINEERS CHICA *4

7. " Vibration Test of 48-inch Local Instrument Panel for Wm. H. Zimmer and LaSalle County NPS, SWRI Project 402-6056-001," December 30, 1980

8. " Vibration Test of 30-inch Local Instrument Panel for Wm. H. Zimmer and LaSalle County NPS, SWRI Project

02-6056-001," January 23, 1981

9. " Vibration Test of Barton 760 Level Indlcation Trans-mitter Switch and Robertshaw SP-222-C Pressure Switch for Wm. H. Zimmer and LaSalle County Nuclear Power Station" SWRI Project No. 02-6056-008, December 4, 1981 10, " Vibration Test of a Voltage Preamplifier and Sensor and Convertor for Wm. H. Zimmer and LaSalle County Nuclear Stations" SWRI Project No. 02-6056-009, January 13, 1982

11. " Vibration Test of a Group of Four Temperature and Flow Instruments for Mm. H.

Zimmer and LaSalle County Nuclear Power Stations", SWRI Project No. 02-6056-004 August 3, 1981

12. " Vibration Test of ASCO Solenoid Valve 8323" SWRI Project No. 02-6056-007 October 16, 1981

13. " Vibration Test of Six Level Indicator Pressure and Vacuum Switches for Wm. H.

Zimmer and LaSalle County Nuclear Power Stations" SWRI Project No. 02-6056-003 G e

0 9 4 l l Conclusions - Fatigue Testing Electrical Components and Instrumentation. Some of the seismic class IE components mounted on the local + panels are subjected to vibratory loads. These vibratory loads are categorized as hydrodynamic loads which include the Safety Relief Valve (SRV) discharge loads and Loss-Of-Coolant Accident (LOCA) associated loads. These hydrodynamic loads are addressed during the seismic testing as fatigue tests. For these tests, two independent random signals excited a biaxial shake table with test response spectrum envelop of the required response spectrum. The test frequency range was 1 to 200 Ex for a test duration of 400 seconds (consists of 200 time histories with 2 second time in-terval each) for the SRV Test and 200 seconds (consists of 100 time histories with 2 second time interval each). These test duration simulate hydrodynamic loads which exceed that expected for 40 years of plant operation. Operability was demonstrated before and after these fatigue tests. 1 1 1 )

+ .... --. -.. -... -. ~. - - S A R G E PI T d LUNDY. /l INTER-OFFICE MEMORANDUM n EXHIBIT E -nnt-rnm tL C_Munir - 30 x6719 Date 11 -n 1 ('} Project No.310. _1.5

.q /Div..Rechanical/Componnnt_ Qual i f i ca tion _._ Spec. No.

v File No._ COD _-000750 Page No. 1 of 1 Cient CG}E Sin. Zi m r Unit 1 Soyect Patigue Analysis _of the_Rer.IIcnlating_Cor.e Tsolation Cqpling__Eump (St.PRTv-RELATED1 (Send to QA) To; M. M. Hassaballa 30 CC: Y. A. Patel 30 30 T. Korman R. M. Tjernlund 30_ 'KD1/ NIM 30 CQD File 30 A fatigue analysis was performed on the RCIC pump. The analysis indicated that the pump assembly can adequately withstand the cyclic loading due to seismic and hydrodynamic loads. The' number of cycles per event as well as the load combinatiori.:..ere per the requirement of the project as provided by project gi, ap (R. Tjernlund). Should you require any related information on this analysis, please ~ let me know. NIM /ws 4 l t

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% NN N N = , % =m,,,. % =~.. .== -,. 10 2 4 10 ,10 gg3 10 105 106 6,; NOTE: E = 30 X 10 k = =- UTS < 80.O ksi UTS 115.0-130.C ksi Interpolate for UTS 80.0-115.0 ksi FIG. I-9.1 DESIGN FATIGUE CURVES FOR CARBON, LOW ALLOY, AND HIGH TENSILE STEELS 3 e, FOR METAL TEMPERATURES NOT EXCEEDING 700'F ~ Table I-9.1 Contains Tabulated Values and a Formula for Accurate I Interpolation of These Curves O ...,O O V
\\'- g O Q l 71 T'. c ws N % $8 D * ] 4 O Y 'n i y y d' 1 s so y P~ d .a u i t ds x N ' ~, O ,d i N -o N v i h f! i %s p r, 1 ~ s s. g N v. r 4t y h U' N M 3 107 e ~ " ~ ~ _:r" - w O si Z p ~ ,- W.- ~
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'.9 n 3. E S ~-- 7.$,1 ~~ ~ ~ O T. l U / l j-10 0 5 '10 3 3 4 '6 10 102 10 10 10 r5 NuWr of cycin,# Z pj NOTE: 6 E = 26.0 X 10 gg e m vs FIG. 3-9,2 DESIGN FATIGUE CURVE FOR AUSTENITIC STEELS, NICXEL-CHRCMIUM-IROM ALLOY, NICKEL-IRON-CHROMIUM ALLOY, AND NICKEL-COPPER ALLO ( FOR TEMPERATURES NOT EXCEEDING 800*F Table I-9.1 Contains Tabulated Values and a Formula for Accurate Interpolation of This Curve e 4 e e s 9 O 9 g e e e .. -o o 4 o.. ep l ~ v --}}

ML20050C778

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