ML20203D842
| ML20203D842 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/28/1997 |
| From: | Haslinger K, Mendrala C, Wrenn J ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML19317C790 | List:
|
| References | |
| S-PENG-DR-002, S-PENG-DR-002-R01, S-PENG-DR-2, S-PENG-DR-2-R1, SO23-411-57-3-2, NUDOCS 9712160310 | |
| Download: ML20203D842 (78) | |
Text
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sex 3-Y// (7-3-2 R is hereby comned that we analyses desenbod Report 35 Pages ;
in this desion report have toen pmpery and Appenda A _ 5 Pages complesey reconceed meh the requirements of Appeudix B 22 Pages Section lli of the A8WE Boner and Prosauro Appendix C 7 Pages !
vessel Code, t909 Edmion (no Addende) Appendix D 9 Pages DESGN REPORT ND. S-PENG-DR Op2. REV. 01 i
. ADDENDUM TO THE PRESSURIZER :
! l ANALYTICAL STRESS REPORT FOR RECENEDCOM SOUTHERN CAllFORNIA EDISON NOV 211997 i
SAN ONOFRE UNITS 2 AND 3 SITEFILECOPY ,
! . f ABB COhmuS110N ENGINEERING NUCLEAR OPERATIONS COMBUSTION ENGINEERING,INC, WINDSOR, CONNECTICUT ;
i
, This document is the property of Combuellon E,,,;..::t.ii, Inc. (C-E) Windsor, C i.em; cut, and is to ,
be used only for the purposes of the agreement with C E pursuant to which it is fumiehod. !
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! Thb Design Analysis b complete and vergled. ._.. .. .Et#iorizes he use of its results.
Pnspared By: C.LMandnde / /3MWf Date:' 9hdh Cognizant Engineer / ' '
Choded By: J.T. %4enn rh.I' t - '=> ~ Date: 8-27-97 independent R% ,
Approved By: KH.P " = [14 , 0J A 111/ Date: O'l[> ~ 87 Super 4 ear, Stromeural integnty and Teetng i This Design Report is certined to be in compliance witt the requirements of the ASME Boiler and !
Pressur= Vessel Code, hr*an 111, Desion 1, Nuclear Power Plant Component, ,,1989. Edibon, up to and including he (NONE) Addenda _ , I t
- *: so'LL-4su o i _s
@, meswee-ug' ,w Amay c==. Certfled By utun P.E.
I Registration No. N 15253 o a. meeves amuser as e me -nen. a og 0 8 E E -ca aed.memein neoe.u ew Stateof Connec26ut 0 i " &' . m %.
Date 9 -Le a 31,7 ae g C 1997 Concustion Engineering, Inc.,
N = _
All Rights Reserved i n.sy cm.sessen not, o.a. m - .
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8"_N ""*8*83 888888 --
9712160310 971212' '
S-PENG-DR 002, Rev. 01 Page 2 of 35 RECORD OF REVISIONS Rev Date Pages Changed Prepared By Reviewed By Approved By 00 62597 Original A.V. Bauer C.L. Mendrata K.H. Haslinger
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,g,97 4,5,16,20,24 27,32 C.L. Mendrala J.T. Wrenn K.H. Haslinger 33,35 Inserted Appendix C ABB Combustion Engineering Nuclear Operations
- G PENG-DR-002, Rev. 01 Page 3 of 35 ABSTRACT The structural integrity of the Southem Califomia Edison, San Onofre Units 2 and 3. Mechanical NozzJe 8 tal Asserntdy (MNSA), to be installed on the side pressurtzer RTD nozzle and the bottom pressunzer level ,
nozzle,is designed and fabricated under the requirements of Reference 5.1, Project Plan No. 83 NOME-IPQP-0156, to satisfy the requirements of the ASME Code, Sedion Ill. The acceptability of the design is established by the results of the detailed structural and thermal analysis contained in this report.
Al stresses and cumulative fatgue usage fadors within the scope of this report are satisfadory and rnaet the appropriate requirements from the ASME Boiler and Pressure Vessel Code, Sedion 111, 1989 Edition (Ne Addenda) (Reference 5.9). I ABB Combustion Engineering Nuclear Operations
G-PENG-DR-002, Rev. 01 Page 4 of 35 t -- -
16BLE OF CONTENTS EdnI20 Paoe No.
R e co rd o f R e visi o n s . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . .. . . . .. . . . . . . . . . . .. . .. . . . . . . . . . .
Abstract..............,........................................................................... ............................3 Ta ble o f Co nt e nt s . . . . . . . . . . . . . . . .. . . . . . .. . . . . . . . ... . .. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . .. ..
1.0 Introduction............................................................................................................S 2.0 Designinputs.................................................................................................................6 3.0 Analysis..................................................................................................................................8 3.1 M N S A D escription . . . .. . . . .. . . . . . . .. . . . .. . . . . . .. . .. . . . . . . . . . . . . . . . ... . . . . . . . . . . .. . . . . . . . . . .. . .. . . . . . . . . . .. . ... .
3.2 Loading C onditions ...... . .......... . .. .......... . . . .....................................................11 3.3 Det erminatio n o f Stre sses .... .. ... .. .. ... .... . .. ... .. .. ........ . . ... ...... . . . . . . . ... . .. ... .. ..... . . . . !... .... 2 4.0 Summary of I;esuits ...... . ................. ... . .............................................................................32 5.0 R eference s ... .. . .. .. ..... ... ... . ... . . . .. . . . .
.........................................................................34 LIST OF FIGURES ElGURE DESCRIPTION PAGE 1 Side Pressurtz er R TD N onje . .. . ... . .. . . .. . . .... .. ... .. . .. ..... ... . .. . .. ... .. . .. .. . . .. ... .. . . .. . . . .. . . .. .. ... .. 9 2
Bott om Pressurtz er Nonie ...... . . .. . ... . . .. ... .. ... .... . .. . .. .. . . . .. ... .. . .. ... ..... . . .. .. . .. .. . . . . .. ....... . ..
3 RTDTopPlate............................................................._...........................................17 l 4 C ompressnon C oll ar... ....... . ....... ... ... .. . ... .. .. .. ...... . .. .... . .. .. .. .... . .. . . .... .. . ... . . .. . . ... ....... 2 8 5 Bottom Pressurizer Compression Collar..... ... ....... ................. .. ......................... .... ..... 29 6 RTD Upper Flanoe......... . .. ............................................................................30 LIST OF APPENDICES APPENDIX A: CODE DATE R EC ONCILIATION . ..... .. .. .. .. .. ..... ... . . . .. ... .. . . ... ......... . ..... . . . ... ............ ..
APPENDIX B:
ANSYSOUTPUT..................................................................................................B.1 APPENDIX C: STIFFNESS OF FLANGE CONNECTION ................................... ........ ........ ....... ..... .. ... C 1 l APPENDIX D: Q UALITY A SSU RANC E FORM S . . . .. ...... ... . .. ... ...... . ... . ... .... .......... .. . . . . .. .. . .......... ! .
ABB Combustion Engineering NuCleaf Operations
S-PENG-DR.002, Rev. 01 Page 5 of:$
1.0 INTRODUCTION
1.1 OBJECTIVE The objective of this design report is to present the results of the evaluation of the Mechanical Nozzle Seal Assembly (MNSA) to be installed on the side pressurizer RTD nozzle and the bottom pressurizer level nozzle at the Southem Califomia Edison (SCE), San Onofre Units 2 and 3.
The MNSA is a mechanical device that ads as a complete replacement of the *J' weld between an inconel 600 instrument nozzle and the pressurtzer, its function is to prevent leakage and restrain the nozzle from ejecting in the event of a through-wall crack or weld failure of a nozzle. The potential for these events exists due to Primary Water Stress Corrosion Cracking.
The MNSA for the side pressurizer RTD nozzle and the bottom pressurtzer level nozzle have similar designs and operate under the same conditions. Since the side pressurizer RTD %zzle is targer in size, the analysis for the side pressunzer RTO nozzle MNSA presented here is considered bounding. Where differences exist, specific to the component, analyses are performed.
This revision is performed to modify the methodology used in calculating the load on the bolts connecting the MNSA to the pressurtzer.
1.2 ASSESSMENT OF SIGNIFICANT DESIGN CHANGES This report presents the detailed structural and thermal analyses required to substantiate the adequacy of the design of the SCE, San Onofre Units 2 and 3 Mechanical Nozzle Seal Assembly as a replacement of the nozzle 'J" weld. This analytical work encompasses the requirements aet forth in Reference 5.1 and is performed in accordance with the requirements of the ABB CENO Quality Procedures Manual QPM.101 (Reference 5.2).
I 1.3 ANALYTICAL METI:DD l Standard methods of elastic analysis were used in this evaluation. The ANSYS 5.3 finite element
- computer code (Reference 5.13) was used to perform the structural analysis of certain components as required. This analysis follows the requirements of the ASME Code Section til for Class I components and is analyzed for a 40 year life, i
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S-PENG-DR-002, Rev.01 Pa0e6 of 35 2.0 DESIGN INPUTS 2.1 DfdfCTION OF DESIGN INPUTS 2.1.1 The Mechanical Nozzle Seal Assembly is considered a pressure retaining component. The design pressure is 2500 psi and design temperature is 700'F. Operating pressure and temperature are 2'250 psi and 653'F, respectively (References 5.3, and 5.4, pg. 3). Ambient design temperature is 120'F (Reference 5.7).
2.1.2 MNSA materials, material properties and stress allowable limits are given below and are taken from References 5.8 and 5.9; Table 11.2 Table 12.2 Table I 5.0, and Table 1-6.0.
litm Material Compression Collar SA-479, Type 304 Lower Flange SA 479, Type 304 Upper Flange SA-479, Type 304 Top Plate SA 479, Type 304 Hex Bolts SA 453, Grade 660 Hex Nuts SA-453, Grade 660 Tied Rods SA-453, Grade 660 Socket Head Shoulder Screw SA-453, Grade 660 Material Allowable Stress Thermal Expanston Coeff. Modulus of Elastledy 700'F 4 (a)[X 10 inAn/'Fl (E) [X 10' pal)
Sm (ksi) Sy (ks0 120*F 200*F ,
653*F 70'F 700'F SA 453. Grade 660 26.8 . 8.27 8.39 9.00 28.3 24.8 SA-479 Type 304 18.0 17.7 8.60 8.79 9.61 28.3 24.8 2.1.3 Side pressurtzer RTD and bottom pressurtzer level nozzles materials are taken imm References 5.3,5.5,5.17 and 5.19. Material properties and stress allowable limits are taken from Reference 5.9; Table I 1.2, Table 12.2 Table I-5.0, and Table 1-6.0.
Component / Thermal Expansion Coeff. Modulus of Elasticity Material (a)[X 10* in4n/*F) (E) [X 10' psi) 400*F 653*F 70*F 700*F Safe End SA 182, Type 316 9.21 9.09 28.3 24.8 Safe End SA-479. Type 304 9.19 9.61 28.3 24.8 Nozzle SB 166 7.57 7.88 31.0 28.2 Thermowell Inconel 7.57 7.88 31.0 28.2 Valve SA 182, Type 316 ,
9.21 9.69 28.3 24.8 Pressurizer shell SA-533 Gr6 .B Sm = 26.7 ksi g 700'F Pressunzer shell SA 533 Grade B Sy a 43.1 ksi @ 700'F ABB Combustion Engineering Nuclear Operations
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ABB S-PENG-DR-002, Rev. 01 i
2.1.4 The bolts and tie rods have the following dimensions (References 5.8,5.14 and 5.19):
, Bolts (0.500 20 UNF.2A) Tie Rods (0.37516 UNC-2A]
Mapor diameter 0 5000 in 0.3750 in Minor diameter 0.4405in 0.3005in Basic pitch diameter 0.4675in 0.3344 in Minor area 0.1486 in' O.0678 in' Stress area 0.1599 in' O.0775 in' S6de RTD Bottom level Rod length 4u:w %+@ aw 3.50 in 5.50 in Effective thread length
- 2. ~ , ,
~. . 1 a' 4.395 in W 4.781 in
- Threaded area o~. W v l' #6 0.0775 in' O.0775 in' Rod area ". #
. i 0.1104 in' O.1104 in' where (Ref. 5.19):
(1) 4.395 in a tie rod length (9.5) . rod length (3.5) flange thickness (0.73) . nut thickness (0.5)
. free end rod length [not engaged] (0.375)
(2) 4.781 in = tie rod length (12.5) rod length (5.5) -flange thickness (0.75) nut thickness (0.5) - free end rod length [not engaged) (0.969) 2.1.5 Various components dimensions are taken from Reference 5.5, 5.6, 5.17 and 5.19 as indicated below (Note: Some dimensions are calculated / estimated from field measurements).
Side Prz RTD Nonle Ref. Bottom Level Nouje Ref.
Pressure D:smeter 1.330 in 5.5/5.6 1.062 in 5.5/5.6 Length of component m 8.00 in 5.19 13.00 in 5.19 Length of Safe End " 3.70in 5.19 5.50 in 5.19 Length of nonle 3.00 in 5.19 2.00 in 5.19 Length of Thermowell
- 1.3 in 5.19 Ju + r.n ? a .> +W
Length of Valve N6 ye:8M bnW 5.5 in 5.17 3
Pressure Area a (a r ) 1.389 in' 5.5/G.6 0.886 in' 5.5/5.6 Notes:
(1) From O.D. of the head (2) Calculated from measurements (3) Estimated from measurements 2.1.6 The Mechanical Nonle Seal Assembly design provides for 0.065 inches of compression of the Giafoil seal (gap between Upper and Lower Flanges, Reference 5.8). Such compression of the Grafoll creates pressure of about 3,500 psi, according to Reference 5.23. It is deemed to be sufficient to seal the possible leak area on the Nonie, because achieved pressure exceeds the design pressure of 2500 psi at design temperature of 611*F. Sealing capabilities of Grafoil were verified during the hydrostatic test at 3,125 psi and three thermal cycles from near ambient temperature to 650'F and 2,500 psi with borated water.
ABB Cornbustion Engineering Nuclear Operations
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' 3 PENG-DR 002 Rev.01 Page 8 of 35 2.1.7 Hydrostatic test pressure conditions are not analyzed in this calculation because the seal component will not be exposed to this condition dunng service. Hydrostatic testing was performed as part of tne seal qualification (Reference 6.10).
2.2 ASSUMPTIONS 2.2.1 If no crack is present, it is assurned that the MNSA is not loaded during normal operating conditions. The only load would be experienced ;f the nozzle is subjected to a 360' through-wal! crack at or above the J-weld. This load would be equal to the intemal pressure of the system against the area of the nozzle. This load would act against the top plate and ,
distribute through the rest of the assembly back into the pressurtzer shell. After this event occurs, the load would become cyclical from essentially zero at Cold Shutdown to its maximum at normal operating constions.
2.2.2 A coefficient of friction of 0.30 for Grafoil on inconel 600 is assumed. Reference 5.21, Table IV shows tests results of grafoil on stainless steel of 0.20 for a pressure of 12 psi. For this application, the load generated to compress the grafoil seal is significantly larder than 12 pai. Extrapolating the information in Reference 5.21, a factor of 0.30 is cons 6dered a reasonable assumption.
3.0 ANALYSIS 3.1 MHQ&DESCRtPTION The MNSA is a mechanical device that acts as a complete replacement of the trweld between an inconel 600 instrument nozzle and the pressurtzer. It replaces the sealing function of the weld using a Grafoil seal compressed at the nozzle outside diameter to the outer pressurtzer surface. The MNSA also replaces the weld structurally by means of threaded fasteners engaged in tapped holes in the outer pressurizer surface, and a restraining plate held in place by threaded tie rods. This feature prevents the nozzle from ejectin0 from the pressurtzer, should the trweld fail or the nozzle develop a circumferential crack.
Two mechanical nozzle seal assemblies are analyzed herein. Each MNSA consists of threaded tie rods, top plate, upper flange, lower flange. compression collar, seal retainer, Grafoil seat, retainer washers, and threaded fasteners. To prevent the nozzle from ejectino, the top plate is held against the nozzle safe end by four threaded tie rods and it is fastened by hex nuts, at the top and at the bottom. The other end of the tie rods is fastened into the upper flange.
Threaded fasteners, threaded into tapped holes on the outer surface of the pressurizer, generate the force necessary to compress the Grafoil seal. To keep the seat in place and avoid leakage, the load is transferred through the threaded fasteners into the oppor flange, and into the compression collar.
Both the lower flange and the retainer seal act as seal retainers. Since the bottom pressurtzer level nozzle is located at an angle with the horizontal, shear pins are set into the pressurizer shell to carry the shear load between the lower flange and pressunzer shell when compressirg the seal.
Drawings (Reference 5.8) for the pressurtzer RTD nozzle and the bottom pressurizer level nozzle (Reference 5.8) are presented in Figures 1 and 2.
ABB Combustion Engineering Nuclear Operations
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S PENG-DR 002, Rev. 01 Page 11 of 35 3.2 LOADING CONDrrlONS 3.2.1 Lgadino Due to Prusm The applicable loading is due to the pressure pushing against the entire cross section of the nozzle. i From section 2.1, the pressure area of the side pressurtzer RTD nozzle assembly is 1.380 in', and the pressure area of the bottom pressurizer level nozzle is 0.856 in'. Therefore the loads are:
Load (side pressurtzer RTD nozzle) = (2500 psi) (1,389 in') =,3,473 tbs Load (bottom pressurizer level nozzle) = (2500 psi) (0.886 in') = 2,215 lbs 3.2.2 (pMina Due to Them:al Exosnsion Under operating conditions, it is assumed that the tie rods temperature increases from a referer.ce temperature of 70*F to the ambient temperature of 120*F. and that the nozzle /thermowell/valvo and the lower flange are perfect heat sources and reach the operating temperature of 653'F (Section 2.1). These conditions proouce the maximum Oap closure between the nozzle and the MNSA top plate. On the other hand, a more reasonable temperature distribution is selected based on engineering judgment. In this case, it is assumed that the tie rod temperature increases from a reference temperature of 70'F to 200*F. and that the nozzleAhermowell/ valve, as well as the lower i
flange, reach the temperature of 400*F under operating conditions. These conditions produce the minimum gap closure between the nozzle /thermowell/ valve and the MNSA top plate.
The thermal expansion (maximum and minimum closure gaps) due to the displacement of the nozzle is calculated as follows (Reference 5.12, pg. 53):
l 6 due to thermal expansion of the nozzle = L a AT l
where: L is the len0th of the component (3ection 2.1) a is the thermal expaitsion coefficient (Section 2.1)
AT is the differential temperature (as applicable)
Maximum / Minimum Closure = Nozzle + Safe End + Thermowell/ Valve . Tie Rods . Flanges where: the tie rod length is determined to compare growths of equallength (not related to actual length, i.e., component length flanges length).
Side pressurizer RTD nozzle:
Maximum Closum:
(3.00 in.) (7.88 X 10*4 infin. 'F) (653 70)'F +
(3.70 in.) (9.09 X 104 inlin. 'F) (653 70)'F +
(1.30 in.) (7.88 X 10 inlin. 'F) (653 70)'F -
4 (6.905 in.) (8.27 X 104 inlin. *F) (120-70)*F -
(1.095 in ) (9.61 X 10 inlin. 'F) (653-70)*F = 0.03169 in.
1 ABB Combustion Engineering Nuclear Operations
G PENG-DR-002, Rev. 01 Fage 12 of 35 :
11 nu rm i Minimum Closure:
(3.00 in.) p.57 X 10 ' inlin. 'F) (400-70)'F +
4 (3.70 in.) (9.21 X 104 in An. 'F) (400-70)'F +
(1.30 in.) p.57 X 10 in An. 'F) (400-70)*F -
(6.905 in.) (8.39 X 10* InAn. 'F) (200 70)*F -
(1.095 in.) (9.19 X 10* InAn. 'F) (400-70)'F = 0.01114 in.
Dottom oressurizer level nozzle:
Maximum Closure:
(2.00 in.) p.88 X 10* inAn. 'F) (653 70)'F +
4 (5.50 in.) (9.61 X 104 inAn. 'F) (653 70)'F +
(5.50 in.) (9.69 X 10 4in An. *F) (653 70)'F -
. (9.531 in.) (8.27 X 104 in An. 'F) (120-70)'F -
(3.469 in.) (9.61 X 10 inAn. 'F) (653 70)*F = 0.04191 in.
Minimum Closure:
(2.00 in.) p.57 X 104 inAn. *F) (400-70)'F +
4 (5.50 in.) (9.19 X 10 in An. *F) (400-70)'F +
(5.50 in.) (9.69 X 10' inAn. *F) (400-70)*F .
(9.531 in.) (8.39 X 10* InAn. *F) (200 70)*F -
(3.469 in.) (9.19 X 10* InAn. 'F) (400 70)iF = 0.01450 in, where (Ref. 5.19) 3.469 in = (2.293 0.274) + 0.70 + 0.75)
A cold gap should be set to allow for free thermal expansion of the nozzle, but not to exceed the gap analyzed for in the following sedions.
3.2.3 Cold oao settina for the side pressurizer RTD nozzle A cold gap between the tie rods and the top plate should be set to account for the thermal expansion of the nozzle if the nozzle is ejeded, the imped load would produce stresses on the tie rods and top plate which need to be cons:dwed. A setting of 0.03*
- 0.005'is recommended for the side pressurtzer MNSA, it is recognized that the low end of this range is less than the maximum closure obtained in the previous sodion. Since the ideal conditions used to ottain the maximum closure are not anticipated dunng operation, the 0.025* minimum gap is concluded to be acceptable. The maximum cold gap sa:tting of 0.035' indicates that a ocp of 0.035-0.01114=0.02386'can exist during normal operation. Therefore, the stresses due to the impad load are determined assuming a gap of 0.025*. The stiffnesses of the tie rods and top plate are taken into consideration in the calculation of the stresses.
ABB Cornbustion Engineering Nuclear Operations
, S-PENG-DR@2, Rev. 01 Page 13 of 35 l i
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wrAn The total deflection due to the impact load is determined below, it is assumed that the energy at impad is converted into potential (spring) enef 0y, and that the total displacement is equal to the amount of displacement allowed by the gap plus the deflection of the nonle and MNSA after impact. All equations are taken from Reference 5.16, pgs. 317 and 3-20.
Kinetic Energy = Spring Energy i
-m l'2 = 1 K Ar 2 2 where: l'=g2as 1
i m(a s) = 2 K Ar where: F=ma l
i Fs= 2 K Ar:
Assuming that s e Gap + Ax, and a fridion coefficient of 0.30; then F = 0.7 F,,, , where F,n. is load t acting on the nonle (3,473 lbs) then:
(
0.7F(Gap + Ar) = 1 K Ar:
, 2 l
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l -K Ar - 0.7F Gap- 0.7F Ar = 0 [3.11 in order to determine the Ax, the stiftness of the tie rods and the too plate are calculated.
ABB Combustion Engineering Nuclear Operations
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S-PENG-DR-002, Rev. 01 Pass 14 of 35 .
l Stlffness of 4 Tie Rods (Section 2.0): l AE =4 (0.1104 in )(24 8=X10' k'" )
3.129,051737 K=4 l 3.5 in in A (0.0775 in')(24.8 X 10' )
K.,,,, =4 ' = 1,749,261 Ibf
= 4 lE 439$in in Stiffness of the Ton Plate fSection 2.0);
The equations for calculating the deflection of the top plate are found in Reference 6.11. Table 24, Caseis:
w a' y " p ( C, L,c, - M where:
D=
Ei i = 24.8X10' k'" (1.0)'in'
= 2,271,062 lbf 12 (1 - y *,) 12 (1 - 03')
and Ci, C,, L., and L3 are constants, and are calculated using the.oquations of Refnrence 5.11, pgs. 332 334 where; a = 1.906 in b = 0.5 in
- r. = 0.6650 in t = 1.0 in y = 0.3 E = 24.8 X 10' psi C,=0.8494 r Cr = 1.6151 l L3= 0.0264 L = 0.2924 Solving for the stiffness of the top plate:
i K -
3
= 10,760,000 $
%=E D C,
( 'b -4) 3 Deterrninetion of couivalen13tiffnt$$1 K,,,, =
I
= 1,016,100 E 3
-. _ +
3
-+
3 in K ,,, K w ,,, K,,, p, ABB Combustion En0lneering Nuclear Operations
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S-PENG-DR 002, Rev. 01 Page 15 of 35 l
l The equation [3.1) previously developed is used to solve for Ax:
1
-K &' - 0.7F Gap- 0.7F Ar = 0 2
Solving the quadratic equation using a load (F) of 3,473 lbs (calculated in Section 3.2.1) ard a gap equal to 0.025', we have a maximum Ax value of 0.0135g in. Solving for the impact force we have:
Force = K,y & = 1.016,100 S(0.01359 /n)= 13,808 lbf = 13.9 kips in 3.2.3.1 STRESS DUE TO THE IMPACT LOAD Stress in the ite rods From Reference 5.8: Tie Rod Diameter = 0.375 in.
Notch radius =0.040 in.
A = (n)[0.1875 0.040]3 = (n)[0.1475j2 = 0.0683 in' impact Force = 13.9 kips / 4 tie rods = 3.475 kips Stress = 3.475 kips / 0.0683 in' = 50.88 ksi Stress = 50.88 ksi < 2 8m = 63.6 ksl Ghter stress in the threads (0 375-16 UNC 2A)
The tie rods pass through the top plato and are held in place with nuts at the top and at the bottom. The top nut is the only one being loaded during impact. The nuts are of the same material as the rods. Therefore, the extemal thread are is used.
From References 5.14 and 5.18:
As = n n Le Kn max [l/2n + 0.57735 (Es min. Kn max)] = 0.288 in' where: n is number of threads per inch a 16 Le is the length of engagement (nut thickness) = 0.5 in (Ref. 5.8)
Kn max is maximum minor diameter of intemal thread = 0.321 in Es mia is minimum pitch diameter of extemal thread = 0.3287 to impact Force = 13.g kips / 4 nuts = 3.475 kips Shear Stress = 3.475 kips / 0.238 in' = 12.066 ksi Shear Stress = 11.07 ksi < 0.6 Sm = 16.08 ksi On the other skie, the tie rods thread into the Upper Flange and are locked down with lock washers. Since the Upper Flange is manufactured from a lower strength material than the tie rods, the strength of the Upper Flange thread is the entical element of this connection.
Therefore:
From References 5.14 and 5.18:
As = x n Le Ds min [1/2n + 0.57735(Ds min . En max)] = 0.414 in' ABB Combustion Engineering Nuclear Operations
- S-PEfCDR-002 Rev 01
. Page 16 of 35 maurium -
where, n is number of threads per inch = 16 Le is the length of engagement. Assume equal to 0.5 in (Ref. 5.8)
En max is maximum pitch diameter of intemal thread = 0.3401 in Ds min is minirnum major diameter of extemal thread = 0.3643 in linpact Force = 13.9 kips / 4 tie rods = 3.475 kips Shear Stress = 3.475 klps / 0.414 in# = 8.394 ksi Shear Stress = 4.39 ksi < 0.6 Sm = 9.6 kal Tha minimum allowable length of engagement of the tie rod into the Upper Flange may be calculated as a simple proportion:
Lem = (Shear Stress / Allowable Stress) x Assumed Length of Engager!.am s
= (8.39/9.6) x 0.5 = 0.437 in.
Shear tiress in the hex botts (0 500-20 UNF 2A)
The effect of impact on the bolt are evaluated in Section 3.3.3.
l Stress in the 100 olete The shear area is = n (D) t = x (1.33 in) (1.0 in) = 4.178 in' where: D 16 the diameter of the thermowell = 1.33 in (Reference 5.19) t !s the thickness of the top plate = 1.0 in (Reference 5.8)
Shear Stress = 13.9 kips / 4.178 in = 3.33 ksi Shear Stress = 3.33 kal < 0.6 Sm = 9.6 ksi ABB Combustion Engineering Nuclear Operations
- S-PENG OR-002, Rev. 01 Page 17 of 35 l Benina stress FIGURE 3 RTD TOP Pt. ATE
_ im .'w Y Y 4 - ,o s . A h *** : '
The impa A load is distnbded over the area of the top plate in confect with the nozzle. The impact load is applied at the location of the outer radius of the thermowell. From Reference 5.11, Table 24, Case 1s:
- r. = 0.6650 in (Reference 5.19) a= 1.906 in (Reference 5.8) b = 0.5 in (Reference 5.8)
W=F !(2 m) r = 13.0 kips / (2 n) 0.6650 in = 3.327 kipshn i
b/s = 0.2623 i 4 (t/s) = 0.5676
- M = % W a = 0.5676 (3.327 kiprAn) (1.906 in) = 3.599 kips-in o = 6 ( 3.599 kips-in) / (1.0)' in' = 21.59 ksi l
Bending Stress: o = 21.59 ksi < 1.5 Sm = 24.0 ksi l
3.2.4 Cold oso settino for the bottom oressurizer level norrie l
A cold gap between the tie rods and the top plate should be set to accoun for the thermal expansion of the nozzle. If the nozzle 3 ejected, the impact load would produce stresses on the tie l mds and top plate which need to be considered, A setting of 0.037*
- 0.005'is recommended for the bottom pressurizer MNSA. It is recogntzed that the low end of this range is less than the maximum closure obtained in Section 3.2.2. Since the ideal mnditions used to obtain the maximum closure are not antidpated during operation, the 0.032' minimum Osp is concluded to be acceptab!e. The maximum cold gap settin0 of 0.042* indicates that a gap of 0.042-0.0145=0.0275' can exist during normal operation. Therefore, the stresses due to the impact load ate determined assuming a gap of 0.028". The stiffnesses of the tie rods and top plato at? taken into coi ajerstion in the calculation of the stresses.
ABB Combustion Engineering Nuclear Operations l
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I i
ABB S#ENG&t-002, Rev. 01 Page 18 of 35 l
4 Stiffness of 4 Tie Rods (Section 2 Ot 2
AE K=4 =4-(0.1104 in )(24.8- =X10' 1,991,215 k'"b )
I 5.5 in in
' (0.0775 in')(24 8 X10' )
K,%,,, = 4 _A E =4 = 1,608,032 g l 4.78Iin in Mness of it.e ToD Plate (Section 2.01:
The AN8YS 5.3 finite element analysis code is used to determine the stiffness of the top plate which has an irregular shape. A 3-D symmetric model of the plate is generated using the 8HELt.93 type element. A half symmetry mode' of the plato is selected for the representative finite element mede!. The model was restrained at the locations of the i e rods in all directions. All dimensions are law. troin References 5.8 and 5.17. To simulate the impact load, a distributed load of 500 lbs was appfled at the outer diameter edge, where the valve contacts the plate at a radius of 1.03 inch Due to the re9dr_1 symmetry ths 500 lbs load is equivalent to 1000 lbs. The maximum deflection of the top pitts resulted in c value of 0.000199 inch. The output from this run is shown in Appendix 0. The r3frie la is determined as follows:
K m . = F / d = 1000 lbs / 0 or Q199 inch = 5,025.126 lbs/in Determination of coulvaltnt silffness:
I K,= , , ,
= 755,810
+
Ka+K_ a Kw Eq a ulon [3.1] developed in Section 3.2.3 is used to determine the Ax:
1
-K Ar' - 0.7F Gap- 0.7F Ar = 0 2
Sc4ving the quadratic equation using a load (F) of 2,215 lbs (calculated in Section 3.2.1) and a gap equal to 0.028', we inave a maximum Ax value of 0.01296 in. Solving for the impact force wo have:
Force,, = K, Ar Force, = K,yAr = 755.810 E(0.01296in)= 9,795lbf = 9.8 kips in
.- ~
ABB Combustion Engineering Nuclear Operations
G-PENG-DR-002. Rev. 01 Pa.go 19 of 35 3.2.4.1 STRESSES DUE TO THE IMPACT LOAD Stress in the tie rods From Reference 5.8: Tie Rod Diameter = 0.375 in.
Notch radius =0.040 in.
A = (n) 10.1875 0.040)' = (x)[0.1475)' = 0.0683 in' impact Force = 9.8 kips / 4 tie rods = 2.45 kips Stress = 2.45 kips i 0.0683 in' = 35.87 ksi Stress = 35.87 ksi < 2 Sm = 53.6 ksi Shear Stress in the threads (0.375-16 UN42A) l The tie rods pass through the top plate and are held in place with nuts at the top and at the bottom. The top nut is the only one being loaded dunna imped. The nuts are of the same matertal as the rods. Therefore, the extemal thread are is used.
From References 5.16 and 5.18:
As = n n t.e Kn max (1/2n + 0.57735 (Es min . Kn max)) = 0.288 in' where: n is number of threads per inch = 16 Le is the length of engagement (nut thickness) = 0.5 in (Ref. 5.8)
Kn max is maximum minor diameter of intemal thread = 0.321 in Es min is minimum pitch diameter of extemal thread = 0.3287 in impact Force = 9.8 kips / 4 nuts = 2.45 kips sheer Stress = 2.45 kips / 0.288 in' = 8.51 ksi Shear Stress = 8.51 kal < 0.6 Sm = 15.04 ksi On the other side, the tie rods thread into the Upper Flange and are locked down with lock washers. Since the Upper Flange is manufadured from a lower strength material than the tie rods, the strength of the Upper Flange thread is a critical element of this connection.
Therefore:
From References 5.16 and 5.18:
As a s n Le Ds min (1/2n + 0.57735(Ds min . En max)) = 0.414 in' where: n !s number of thread:, per inch = 16 Le is the length of engagement. Assume equal to 0.5 in (Ref. 5.8)
En max is maximum pitch diameter of intemal thread = 0.3401 in Ds min is minimum major diameter of extemal thread = 0.3643 in imp *ct Force = 9.8 kips / 4 tie rods = 2.45 kips Shear Stress = 2.45 klps / 0.414 in' =5.92 ksi Shear Stress a 5.92 ksi < 0.6 Sm = 9.6 ksi The minimum allewable length of engagement of the tie rod into the Upper Flange may be calculated as a ;.imple proportion:
El .
II ABB Combustion Engineering Nuclear Operations
S-PENG-DR 002 Rev. 01 Page 20 of 35 Le, , = (Shear Stress / Allowable Stress) x Assumed Length of Engagement =
= (5.92/9.6) x 0.5 = 0.308 in.
Shear Stress in the hex botts (0 500-70 UNF.2A)
The effect of impad on the bolt are evaluated M Section 3.3.3. l Stress in the topfgig i
The shear area is = x (D) t == (2.08 in) (0.75 in) = 4.853 in where: D is the diameter of the valve = 2.06 in (Reference 5.17) t is the thickness of the top plate = 0.75 in (Reference 5.8)
Shear Stress = 9.8 kips / 4.853 int = 2.02 ksi Shear Stress = 1.02 ksi < 0.6 Sm = 9.6 ksi Benaina stress The top plate finite element model developed in Sedion 3.2.4 was used to determine the stresses in the top plato. The effective applied load of 1000 lbs generated a maximum stress intensity of 2952 psl. Scaling this value:
2952 psi X (9820 lbs /1000 lbs) = 28.989 psi = 29.0 ksi Bending Stress: o = 29.0 ksi > 1.5 Sm = 24.0 ksi g 700T However, this allowable is at design temperature of 7001. This temperature is unrealistic for the top plate which is approximately 13 inches away from the pressurtzer head, Therefore, considering a temperature el 3001 a more realistic temperature for this
- component, this value is acceptable since the allowable stress at 300T is 30 ksi (Reference 5.9, Table 12.2).
Bending Stress: o = 29.0 ksi < 1.8 Sm = 30.0 ksi g 300T l
l l
l ABB Combustion Engineering Nuclear Operations
S PENG-DR-002, Rev.01 Page 21 of 35 3.3 DETERMINATION OF STRESSES Normal Operating Conditions (after weld failure occurs) 3.3.1 Tie Rods The following evaluation applies to both the side RTD and bottom pressurizer noule locations.
Three areas of the tie rods (Reference 5.8) need to be examined:
- 1. The notched area between the threaded area and the full thickness rod
- 2. The threaded / nutted connection at the top plate; and
- 3. The threaded / nutted connection at the upper flange.
- 1. At the notched area (Reference 5.8)
T6e Rod Diameter = 0.375 in.
Notch radius so.04C tr'.
A = (n) [0.1875 0.040)' = (n) l0.1475)' = 0.0683 in' P = 3.473 kips / 4 = 0.868 kips a = 0.868 kips / 0.0683 in' = 12.71 ksi < Sm = 26.8 ksi Gince the load on the bottom pressurizer level nonle is lower and the tie rods diameters are the same for both assemblies (Section 3.1), the above stresa value is considered bounding for the bottom pressurizer level nozzle.
Eauave Analysts For fatigue, assuming the nozzle is cracked through and that the load cycles are from 0 to 2500 psi, the cycle on the tie rods would be from 0 to 12.71 ksi. Reference 5.9. Table l 9.1 gives a fatigue life of infinite cydes (>10").
- 2. Ton Plate Connectbn to Tie Rods The tie rods pass through the top plate and are held in place with nuts at the top and at the bottom. TI e top nut is the only one being loaded. The nuts are of the same material as the rods. Therefore, the extemal thread is used.
Shear stress in the threads From References 5.16 and 5.18:
As = n n Le Kn max (1/2n + 0.57735 (Es min - Kn max)] = 0.288 in' where: n is number of threads perinch = 16 Le is the length of engagement (nut thickness) = 0.5 in (Ref. 5.8)
Kn max is maximum minor diameter of intemal thread = 0.321 in Es min is minimu.n pitch diameter of extemal thread = 0.3287 in Using the load of 3,473 lbs / 4 tie rods = 0.868 kips ABB Combustion Engineering Nuclear Operations
i ABB i
S-PENG-DR-002 Rev.01 Page22 of 35 Shear Stress = 0.868 klps / 0.288 in' = 3.014 ksi Shear Stress = 3.01 ksi < 0.6 Sm = 16.08 ksi l
- 3. Uoper Flance Connection to Yie Rods The tie Rods thread into the Upper Flange and are locked down with lock washers. The Upper fian0e is manufactured from the lower strength material, consequently, the strength of the urper flange thread is the critical element in the connection, hence:
From References 5.18 and 5.18:
As = n n Le Ds mh [1/2n + 0.5773S(Ds min En max)) = 0.414 in' where: n is number of threads per inch = 18 Le is the length of engagement. Assume equal to 0.$ in (Ref. 5.8)
En max is maximum pitch diameter of intemal thread = 0.3401 in Ds min is minimum major diameter of extemal thread a 0.3643 in Using the load of 3,473 lbs / 4 tie rods = 0.868 kips Shear Stress = 0.868 kips / 0.414 in' = 2.097 ksi Shear Stress = 2.10 ksi < 0.6 Sm = 9.6 ksi This 5;ress value is bounding with respect to the bottom pressurtzer level nozzle once the lowest engagement length value (0.5 inch) is used and thread sizes are the same.
3.3.2 Too Plate Side pressunzer RTD nozzig Shear stress The top plate will become loaded and the shear force will be equal to 3.473 kips. Shear stress is proportional 1o that calculated in Section 3.2.3.1. Hence:
l t = 3.33 ksi(3.473 kips) /13.9 ksi = 0.832 ksi t = 0.832 ksl < 0.6 Sm = 9.6 ksi t
l l
I I II ABB Combustion Engineering Nuclear Operations
S-PENG-DR 002 Rev.01 Page 23 of 35 Bendma in the Too Plate Likemse, the bending stress is proportional to that calculated due to the impact load in Section 3.2.3.1. The bending stress is:
o a 21.59 ksi(3.473 kips)/13.9 ksi = 5.394 ksi Bendmg Stress: o a 5.39 ksi < 1.5 Sm = 24.0 ksi Sottom pressurizer level nozzle:
Shear stress The top plate will become loaded and the shear force will be equal to 2.215 kips. The shear stress is proportional to that calculated in Section 3.2.4.1. Hence:
t = 2.02 ksi (2.215 kips) / 9.8 ksi = 0.457 ksi t = 0.457 ksi < 0.6 Sm = 9.6 ksi Bendina stress:
Using the top plate finite element model developed in Section 3.2.4.1 to determine the stiffness, a stress value of 2952 psi is scaled for the applied load of 2,215 psi under normal operating conditions as follows 2,952 psl X (2.215 lbs /1000 lbs) = 6539 psi = 6.54 ksi Bending Stress: o = 6.54 ksi < 1.5 Sm = 24.0 ksi 3.3.3 Bott Stresses Desion Sizina Four (4) 0.500-20 UNF 2A hex head bolts hold the assembly to the Pressurizer. Under normal operating loading, the load would pass from the top plate to the tie rods, to the top flange to the hex head bolts. The same loads applied to the tie rods may be applied to the bolts. The loading applied is for the side pressurizer location and envelopes the bottom pressurizer location.
Stress Area = 0.1599 in' (Section 2.1)
P = 3.473 kips / 4 = 0.868 kips o = 0.868 kips / 0.1599 in' o = 5.43 ksi < Sm = 26.8 ksi ABB Combustion Engineering Nuclear Operations
G-PENG DR-002, Rev. 01 Page 24 of 35 .
Bolt Pre-load The bots for both MNSA locations are being pre-loaded to 30 ft lbs (Reference 5.8). To determine the load in each bolt, the following equation is used (Reference 5.15, pg. 302): i T = 0.2 F d ; hence F =T / 0.2 d i where: T is the applied torque = 360 in-lbs j d is the nominal major bot diameter = 0.50 in. (Section 2.1)
Therefore, F = (360 in-pounds) / (0.20) (0.50 in) = 3.600 klps. This is greater than the loading which occurs during normal operation,3.473 kips / 4 = 0.868 kips. As a result, only the preload condition is analyzed for the bolting.
The total pre-load of 4 (3.600 kips) = 14.400 kips h4aximum Bolt Load Due to the flexibility in the design of flanged connection between the MNSA and the pressurtzer, the impact load during ejedion of the nozzle will increase the load on the bolts. The stiffness of the flange relative to the stiffness of the bots will determine what percentage of the impact load will be transmitted to the butts. The totalload on the bolt can be expessed by (Reference 5.24):
Fmax = Preload + K'd
< Ksa + Kn , F""*
The stiffness of the components is calculated in the Appendix C and shows the maximurrt bolt load to be:
Side oressurizer RTD nonle f '
i 958433R 13.9 Fmax = 3.6 + = 6.08 b.ps i
s9584338 + 3842170s 4 Bottom oressuriterlevel nozzle:
f '
3971477 9.8 Fmax = 3.6 + - = 5.45 b.ps (3971477+1279191; 4 The maximum bolt load. 6.08 kips, is used to evaluate the stresses in the bolt. The loads on the i side pressure RTD nozzle are limiting and will be used to represent both MNSA locations.
Tensile Stresa l
Stress due to the maximum bolt load is Stress a 6.08 kips / 0.1599 in' = 38.02 ksi Stress = 38.02 ksi < 2 Sm = 63.6 ksi.
l l
ABB Combustion Engineering Nuclear Operations l
l
S-PENG-DR-002, Rev. 01 Page 25 of 35 Shear stress in the threads (0.$.QQ-20 UNF 2N28)
The bolts thread into the pressurizer and are locked down with lock washers. Since the pressuri.ter is manufadured from a lower strength matertal than the bolts, both extemal and intemal threads must be mecked. Therefore:
Bolt thrend From References 5.10 and 5.18:
t As = n n Le Kn max [1/2n + 0.57735(Es min Ku max)) = 0.4 in where: n is number of threads per inch = 20 Le is the length of engagement. Assume equal to 0.5 in Kn max is maximum minor diameter of intemal thread = 0.457 in Es min is minimum pitch diaeeter of extemal thread = 0.4619 in Maximum isoft load = 6.08 kips Shear Stress = 6.08 kips / 0.4 in' = 15.20 ksi Shear Stress = 15.20 ksi < 0.6 Sm = 16.08 ksi l
I 1
ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002. Rev. 01 Page 26 of 35 Pressurtrer thread From References 5.16 and 5.18:
As = a n Le Ds min [1/2n + 0.57735(Ds min . En rnax)) = 0.541 in' whers: n is numt*r of tt: reads perinch = 20 Le is the length of engagement. Assume, Le = 0.5 in En max is maximum pitch diameter of internal thread = 0.4731 in Ds min is mirumum rna)or diameter of extemal thread = 0.4906 in Max Bolt load = 6.08 kips Shear Stress = 6.08 kipw / 0.541 in' = 11.24 ksi Shear Stress = 11.24 ksi < 0.6 Sm =0.5 (26.7 ksi)= 18.02 ksi The minimum allowable length of enga0ement of the hex head bolt into the pressunzer may be cakxilated as a simple proportion; based on the bolt threads.
Le.,,, = (Shear Stress / Allowable Stress) x Assumisd Length of Engagement =
= (15.20/16.08) x 0.5 = 0,47 in. l Stresses due to thermal expansion The thermni expansion of the upper flan 0e and the lower flange could produce stresses in the bolts.
Both the upper and lower flanges are of the same material, SA-479 Type 3M. The thermal expansion is determincd bekrw. Dimensions for the upper and lower flanges are taken from Reference 5.8.
Side oressurtzer nozzle Upper flange thickness = 0.73 in.
Lower flange thickness = 0.365 in.
Expansion = (0.73+0.365)in. (9.61 X 104 inAn/*F)(653 70)*F = 0.00613 in.
It is assumed that the bott growth occurs over the bolts length that is in contact with the clamp assemtdy. The thermal expansion of the bolts is:
Expansion = (1.095 in.) (9.00X 104 in/in/*F)(653 70)*F = 0.00574 in.
Therefore the stress in the bolt:
Stress = AS E / L = [(0.00613 0.00574) 24.8 X 10' psi) /1.095 in.
Stress = 8.83 ksi l
ABB Combustion Engineering Nuclear Operations
1 S-PENG-DR-002, Rov. 01 Pa',e 27 of 35 l ,
O B.9ttom orcssurizer nozzle:
Upper flange thickness (top)= 0.75 in.
Upper flange thickness (bottom)= 0.70 in.
Lower flange maximum thickness = 4.186 in.
Total thickness e 5.636 in.
Expansion = (5.636 in.) (9.61 X 104 inlin/*F)(653 70)*F = 0.03158 in.
it is assumed that the bott growth occurs over the bolts length that is in contact with the clamp assembly, then the the: mal expansion of the botts is:
4 Expansion = (5.636 in.) (9.00X 10 in/in/'F)(653-70)'F = 0.02957 in.
Therefore, the stress in the bott:
Stress = A5 E / L = [(0.03158- 0.02957) 24.8 X 10' psi) / 5.636 in.
Stress = 8.84 ksi The maximum thermal stress from the two locations is added to the Maximum Bolt Load to determine the fatigue of the bolt. This evaluation is conservatively ap' plied to both locations.
Primary + Cewndary = Max bolt load + Thermal Primary + Secondary = 38.02 + 8.84 = 44.84 < 3 Sm = 40.4 ksi Fatiaue Usaae Fador For a maximum primary plus secondary stress of 46.86 ksi, a stress fatigue usage factor is calculated. Using a stress concentration factor of 4 (Reference 5.9, Section NB-3232.3) and a Modulus of Elasticity ratio, Eam / E., w = 30.0/24.8 = 1.2097, the altamating stress intensity, S,e is calculated to be:
S. = 4 [ S,./ 2 (E / E,, )] = 4 [23.43 ksi (1.2097)] = 113.4 ksi The number of tilowable cycles, N , was determined using F'gure I-9-4 of Reference 5.9 for a component with a maximum stress less than 2.7 Sm. This transient is evaluated for 500 cycles cf heatups and cooldowns (Reference 5.3, pg. A-454), therefore:
U = 500 / 783 = 0.639 U = 0.639 < 1,0 ABB Combustion Engineering Nuclear Opera 3ons l
I S-PENG-DR-002, Rev. 01 Pq 28 of 35 3.3.4 Shear Pins Bottom oressurizer level noIII.g The bottorn pressortzer level nozzle is located at an angle with the MMSA. Shear pins are installed through the lower flange to resist slippage of the MNSA with respect to the pressurizer shell. The totalload bolt preload oi14.4 kips results in shear on ti.e two pins:
Shear Stress Diameter of shear pins (Reference S.8) = 0.76 in A pins = (al4) (D)' = (n/4) (0.76)' = 0.4536 In t P = 14.4 kips (cos 27'30') / 2 = 6.386 kips (Reference 5.8) t = 6.366 kips / 0.4536 in' = 14.08 ksi t = 14.08 ksi < 0.6 Sm = 16.04 ksi g2. gena Stress Diameter of hole (Reference 5.8) = 0.766 in in contact thickness (Reference 5.P)= 0.766 (tan 27'30') + 0.38= 0.778 A = D t = (0.766 in.) (0.778 in.) = 0.5959 in:
P = 14.4 kips (cos 27'30') / 2 = 6.386 kips (Reference 5.8)
- o. = 6.386 kips / 0.5959 in' = 10.71 ksi For the pins:
o = 10.71 ksi < Sm = 26.8 kal (vs Fy not in the Code)
For the pressurizer:
o = 10.71 ksi < Sy = 43.1 ksi 3.3.5 Sqmoression Collar o FIGURE 4 COMPRESSION COLLAR i - 4315* *"1 l W
! }
.L 0 23' ,
I 6 l I !
i 4
' '- 0187
- ; ,4A
. ;=
u:2- - "i ,
. '= uis- . ;
- I
, =
2m.
~
ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002, Rev.01 Page 29 of 35 Side pressurizer RTD nozzle:
The bolt preload,14.4 kips, acts as a shear force on the surface 0.180 inch inboard of the 2.675 diameter. See Fi0ure 4.
The shear area is equal to (x)(D)(t) = (n)(2.315 in) (023 in) = 1.672 in:
Therefore, the shear stress through the section Shear Stress t = 14.4 kips /1.672 in' = 8.61 ksi Shear Stress t = 8.61 ksi < 0.6 Sm = 9.6 ksi Bearino stress The bolt preload.14.4 kips, acts also as a bearing force on the surface between the outside diarneter of the compression collar and the inside diameter of the upper flange.
The beanng area = (n/4)(D'm - d'.%.) = (n/4)(2.675 - 22.318) in = 1.40 in' Therefore, the bearin0 stress is:
Bearing Stress = 14.4 klps /1.40 in' = 10.286 ksi Bearing Stress n 10.3 ksi < Sy = 17.7 ksi Bottom oressurizer level nozzle The shear area is equal to (x)(D)(t) = (n)(1.559 in) (0.325 in) = 1.592 in:
Therefore, the shear stress through the section Shear Stress t = 14.4 kips /1.592 in' Shear Stress t = 9.05 ksi < 0.6 Sm = 9.6 ksi roume o aoTTou rnessuntzen coe#RESsCN COLLAR
~
% .n , s i
wa4 .. ;
i,, j 3 t y ;
j: : F E d .~
c v. a[! ,
I 4 i A&:
- , u.
pj.-
ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002, Rev. 01 Page 30 of 35 Bearino stress l The bearing area = (n/4)(D'mm d'.%) = (n/4)(1.919 1.562 8
) 2in = 0.976 in' Therefore, the bearing stress is:
Bearing Stress = 14.4 kips / 0.976 in' = 14.75 ksi Bearing Stress = 14.75 ksi < Sy = 17.7 ksi 3.3.6 Stresses in the Uoner Flance Side Pressurizer RTD nonle The load is the same as denned above for the Compression Collar, i e.,14.4 kips, The shear area is equal to (n)(D)(t) = (x)(2.735)(0.50) = 4.296 in' (Reference 5.8)
Therefore, the shear stress throu0h the section:
Shear Stress t = 14.4 kips / 4.296 int = 3.35 ksi Shear Stress t = 3.35 ksi < 0.6 Sm = 9.6 ksi FIGURE 8 RTD UPPER FLANGE l= 2.313- r! fW r -
, A a l
li r-.
3 l -IS# e o.730-one b f
=
i 4 .,a-Due to the proximity of the bolts and support surface, bending stresses are small and are neglected.
Bottom oressuriter level noJAlt The load is the same as defined above for the Compression Collar, i.e.,14.4 kips. The shear area is z
equal to (s)(D) (t) = (n)(1.936 in) (0.375 in) = 2.281 in (Reference 5.8).
Therefore, the shear stress through the sectic,n:
Shear Stress t = 14.4 kips / 2.281 in! = 6.31 ksi Shear Stress t = 6.31 ksi < 0.6 Sm = 9.6 ksi Ukewise, due to the nature 'the loading, there are no bending stress in this component.
ABB Combustion Engineering Nuclear Operations
. SPENG-DR402, Rev.01 Page 31 of 35 3.4 SEISMIC LOADS Seismic loads are not considered within the scope of this analysis. A seismic qualification test program will be performed which will address the impact of seismic loads in the MNSA. (Reference 5.20).
ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002, Rev. 01 Page 32 of 35 4.0
SUMMARY
OF RESULTS All stresses are satisfactory and meet the appropriate allowable limits set forth in Section 111 of the ASME Boller and Pressure Vessel Code (Reference 5.9).
The results presented below were determined usin0 the assumptions defined and justified in Section 2.0. There are no additional contingencies or assumptions that are applicable to these resutts.
4.1 SIDE PRESSURIZER RTD NOZZLE Results of this analysis due to the impact load are summarized below- .
Component Stress Calculated Stress (6.si) Allowatxe Stress (ksi)
Tie Rods notch Tensile 50.88 53.60 Tie Rods- thread Shear 12.07 16.08 Upper flange - thread Shear 8.39 9.6 Top Plate Shear 3.33 9.6 BendinD 21.59 24.0 Tie rods minimum length of engagement = 0.437 inch.
Hex Bolts minimum tength of engagement into the pressurizer at preload = 0.47 inch. l Results of this analysis under normal operating conditions are summartzed below:
Conditson Stress Calculated Allowable Stress Usage Stress (ksi) (ksi) Factor Tie Rods - notch Tensile 12.71 26.8 0.0 Tie Roas thread Shear 3.01 16.08 0.0 0.50 20 UNF Bolts Design Sizing 5.43 26.8 N/A Tensile (Preload) 38.02 53.0 N/A Primary + Secondary 48.86 80.4 0.839 Bolts thread SheartPreload) 1520 16.08 N/A Pressurizer thread Shear (Preload) 11.24 16.02 N/A Top Plate Shear 0.832 it.6 N/A Bending 5.39 24.0 N/A Compression Shear 8.61 9.6 0.0 Collar Bearing 10.3 17.7 N/A Upper Flange thread Thread Shear 2.10 9.6 0.0 Shear 3.35 9.6 0.0 ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002 Rev.01 Page 33of 35
_ _ . .. i; . . . . . . . _ . . . . . . . . .. . . . . . . . _ . . .
4.2 BOTTOM PRESSURIZER LEVEL NOZZLE Results of t's t salysis due to the impact load are summartzed below:
Cornponent Stress Calculated Stress (ksi) Allowable Stress (ksi)
T6e Rods notch Tensile 35.87 53.6 Tie Rods . thread Shear 8.51 16.08 Upper Flange thread Shear 5.92 9.6 Top Plate Shear 2.02 9.6 Bending 29.0 24.0 @ 700*F 29.0 30.0 @ 300*F Tie rods minimum length of engagement = 0.308 inch Hex Bolts minimum length of engagement into the pressurtzer at preload = 0.47 inch. l Results of this analysis under normal operating conditions are summarized below; Condition Stress Calculated Allowable Usage Stress (ksi) Stress (ksi) Factor Tie Rods at notch area Sizing 12.71 26.8 0.0 Tie Rods thread Shear 3.01 16.08 0.0 0.50-20 UNF Botts Design Sizing 5.43 26.8 N/A Tensile (Preload) 38.02 53.6 N/A Pnmary + Secondary 46.86 80.4 0.639 Bolts thread Shear (Preload) 15.20 16.08 N/A Pressurtzer thread Shear (Prebad) 11.24 16.02 N/A Shear Pins Shear 14.08 16.08 0.0 Bearing 10.71 26.8 N/A Pin-Pressurtzer Bearing 10.71 43.1 N/A Top Plate Shear 0.457 9.6 0.0 Bending 6.54 24.0 N/A Compression Shear 9.05 9.6 0.0 Collar Bearing 14.75 17.7 N/A Upper Flange Thread Shear 2.10 9.6 N/A Shear 6.31 9.6 0.0 ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002, Rev. 01 Page 34 of 35
5.0 REFERENCES
-5.1 ABB Project Plan No. S3-NOME-IPOP-0156, "MNSA Design Analysis," Revision 00, June 1997.
5.2 ABB Combustion F'.Jineering Nuclear Operations Quality Procedures Manual QPM 101, Latest Revision.
5.3 " Analytical Report for Southem Califomia Edison San Onofre Unit No. 2 Pressurizer," Report No. CENC 1275, September 1976.
5.4 " Analytical Report for Southem Califomia Edison San Onofre Unit No. 3 Pressurizer, "
Report No. CENC-1276, September 1977, 5.5 ABB CE Drawing E234-987, Revision 5, " Nozzle Details San Onofre 11, 96 inch 1.D.
Pressurizer. "
5.6 ABD CE Drpwing E235-127, Revision 3. " Nozzle Details San Onofre lil, 96 inch 1.D.
Pressurizer. "
5.7 " Design Specification for the Mechanical Nozzle Seal Assembly (MNSA) San Onofre Units 2 & 3; " Specification No. S3-NOME-SP 0049, Revision 01.
5.8 A~a8 Drawing No.
- 1. E-MNSA-228-001, Revision 02, " Bottom Pressurtzer Mechanical Nozzle Seal Assembly"
- 2. E-MNSA-228-002 Revision 02, " Side Pressurizer RTD Mechanical Nozzle Seal Assembly" l 3. E MNSA-228-004, Revision 02," Mechanical Nozzle Seal Assembly" i
l 5.9 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section 111, 1989 Edition (No Addenda).
5.10 " Test Report for MNSA Hy Jrostatic and Thermal Cycle Tests," Test Report No. TR-PENG-042, Rev.00.
5.11 " Formulas for Stress and Strain," Raymond J. Roark and Warren C. Young, Fifth Edition, l
1975. McGraw-Hill.
! 5.12 " Mechanics of Materials, " Beer and Johnson, McGraw-Hill inc.,1981.
5.13 ANSYS Engineering Analysis System computer code, Revision 5.3,
( 5.14 " Machinery's Handbook," 22nd t:idition, H. H. Ryffel, Editor, Industrial Press, Inc., New York, June 1986.
I 5.15 " Fundamental of Machine Component Design,
- R.C. Juvinall, John Wiley & Sons, Inc.,
1983.
l l
l ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002, Rev. 01 Page 35 of 35 5.16 -Marks' Standard Handbook for Mechanical Engineers,
- E.A. Avallone and T. Baumeister 111, Ninth Edition, McGraw Hill.
5.17 Rockwell-Edward Hemavalve Drawing No. ACD 31820853.
5.18 ANSI Standards for Threufs, Appendix B, B1.1,1982.
5.19 Inter office Correspondence from J. Tursi to A. Bauer and C. Mendrala, " SONGS P&JSA Design input for Pressurizer MNSA Design Report *, Letter No. NOME-97-0430, dated 6-25-97.
520 " Seismic Qualification of the San Onofre MNSA Clamps for Pressurtzer instrumentation Nozzle and RTD Hot Leg Nozzles,
- Report No. TR-PENG-033, Rev. 00.
5.21 Union Cartade Grafoil, " Engineering Design Manual, " Volume One, Sheet and Laminatea Produds, by RA Howard.
522 Mini-specification S023-41157, Revision A. "RCS Mechanical Nozzle Seal Assemblies, San Onofre Nuclear Generating Station Units 2 and 3,* April 21,1997, 5.23 " Test Report for Verification Testing of RTD Nozzle Seal Assembly *, Report No. TR-PENG.
012, Rev. 00, February 95.
5.24
Analysis Number 8067 640 73 July 1980.
l l
l ABB Combustion Engineering Nuclear Operations
S-PENG-DR 002, Rev. 01 '
Pa2e A1 of AS APPENDIX A CODE DATE RECONCILIATION ABB Combustion Engineering Nuclear Operations
9 S-PENG-DR 002, Rev. 01 Page A2 of AS
. - . . . ..ii....,....__._.._ _ _ _ _. . - _ .._..... _ .. . . . . . . . . -_ ..
Construction Code Date Reconcillation for SCE Mechanical Nonle Seal Assemblies (MNS A)
The purpose of this reconciliation is to demonstrate fulfillment of the requirements for use of a later ediion of the Construction Code for SCE's Mechanical Poule Seal Assembly. This is intended to allow the use of ABB Combustion Engineering's Mechanical Nozzle Seal Assembly, which was built to a later Code edition, at SCE.
In accordance with Southern Califomia Edison Company (SCE) Specification No. 8023-41157, Rev. A (Reference 5.22), and San Onofre Units ll and til Pressurizer Design Specification No. 01370-PE-130, Rev. 09, the Original Construction Code associated with Design and Procuremont for the Mechanical Nozzle Seal Assembly is the 1971 Edition through Summer Addenda (hereinafter referred to as the Original Code). The Original Construction Code associated with the Installation is assumed to be the same as for Design and Procurement. The ASME Section XI program at SCE is govemed by the 1989 Edition, No Addenda (hereinafter referred to as the Section XI Code). The Construdion Code used for the Mechanical Nozz.le Seal Assembly project is the 1989 Edition, No Addenda, of the ASME Code, Section lli (hereinafter referred to as the Replacement Codo).
The SCE Mechanical Nozzle Seal Assembly Project involves both Repair and Replacement activities in accordance with the Section XI Code. Article IWA-4120 states that Repairs may be performed in accordance with later editions of the Construction Code, or Section 111, either in its entirety or portions thereof* The Replacement Code is therefore acceptable for the Repair activities, which includes Installation.
The Original Construction Code for Design und Procurement is the 1971 Edition of the ASME Code as noted above. The Section XI Code (Article IWA-7210) specifies that Replacements shall meet the requirements of the edition of the Construction Code to which the original component or part was constructed, unless the following attemativo is adopted (Article IWA-7210 (c)):
tc) Altematively, replacements may meet all or portions of the requirements of later editions of the Construction Code, provided that the following requirements are met.
(1) The requirements affecting the design, fabrication, and examination of the replacement are reconciled with the Owners Specification.
(2) Mechanical interfaces, fits and tolerances that r' vide satisfactory performance are not changed by the later edition of the Construction Code.
(3) Modified or alerted designs are reconciled with the Owner's Specification (Reference 5.22) through the Stress Analysis Report, Design Report, or other suitable method which demonstrates the satisfactory use for the specified design and operating conditions, whicheveris applicable.
(4) Materials are compatible with the installation and system requirements.'
These four requirements are addressed individually in Paragraphs (1) through (4), below:
- 1. Reauiremenf
- 11) The requirements affecting the design, fabrication, and examination of the replacement are reconciled with the Owners Specificat4n (Reference 5.22).*
ABB Combustion Engineering Nuclear Operations
I A
1 I
S-PENG-DR402, Rev.01 I Page A3 of A5
)
..+ .. . _ . . _ . . _ . . . .
Discussion The Owner has specified the Original Construction Code as the 1971 Edition, through Summer Addenda, of the ASME Boiler and Pressure Vessel Code, ABB Combustion Engineering Nuclear Operations, acting as the Owners Agent, prepared a design specification for the Mechanical Nozzle Seal Assembly in accordance with the Owners Reference 5.22, namely Design Specification for the Mechanical Nozzle Serul Assembly, SpectScation No. S3-NOME SP-0049, Revision 00.
The Design requirements, as specified in the Owners Specification (Reference 5.22) and Pressurizer Specification for ASME Code Class 1 components, are per Article NB-3000 %' the Original Code. The fabrication and Installation requirerner:ts are per A:ticle NB-4000 of the Original Code. And, the Examination requirements are per Article NS-5000 of the Original Code.
SimJlar Articles specify the Design, Fabrica* ion and Instattation, and Examination requirements of the Replacement Code. The corresponding Articles for Design, Fabrication and Installation, and Examination requirements of the Replacement Code are Articles NB-3000, NB-4000, and NB-5000, respectively.
An itemtzed companson of each of the requirements of Design, Fat,:ication and Examination (called Inspection in the original Code) for the Original Code and the Replacement Code is provided below:
Desian l The basic desion requirements defined in Article NB-30')0 of the Original Code are incorporated l_ in Article NB 3000 in general, and in particular Article NB-3200 of the Replacemer,t Code.
l Between 1971 and 1989 many more design criteria, categories ar.d definitions were added to the Replacement Code, resulting in a more comprehensive Desegn Code. Thus, the significant differences between the two Design Code editons are the volume of wntten material aMi the editorial / acronym changss.
l Overall, it can be observed that the Replacement Code is more prescriptive conceming vessel l design than is the Original Code, it is therefom concluded that, wrth respect to Design, the Replacement Code is reconciled to the Owners Specification.
Fabrication and instalbtion The intent of the Fabrication and installation requirements defined in Article NB 4000 of the l Original Code are also evident in Article NB-4000 of the Replacement Code. Similar to the l Design requirement reconciliation described above, the Fabrication and installation requirements i
defined in Article NB 4000 of the Original Code lack the depth associated with those of Article l NS-4000 of the Replacement Code. Once again the original intent of the Originci Code is maintained in the Replacement Code, but with a significant increase in breadth of mate:ial content. Additionally, the nuclear industry (including the Nuclear Regulatory Commission) acceptance of the Replacement Code requirements is evidence that it provides the same leve; of safety, if not greater, than the Original Code.
I Examination Similar to the Fabrication and Installation requirements, the intent of the Examination requirements defined in Article NB-5000 of the Original Code and Article NS-5000 of the ABB CornbuStion Engineering Nuclear Operations
I S-PENG-DR-002. Rev. 01 i Page A4 of AS l
Replacement Code are essentially the same. The Examination requirements defined in Article NB-5000 of the Original Code lack the depth associated with those of Article NB 5000 of the Rep:acement Code in terms of the examination procedures and techniques. Once again the originalintent of the Original Code is maintained in the Replacement Code, but with a significant '
increase in the technical area and most sgnificant changes in the acceptance standards.
The acceptance enteria in the Replacement Code may seem less stringent at first glance, but further examination proves the Replacement Code is at least equivalent to the Original Code.
Addltionally the nuclear Industry (including the Nuclear Regulatory Commission) acceptance of the Replacement Code requirements is evidence that is provides the same level of safety, if not greater, than the 0,1ginal Code.
Overall, it can be observed that the Replacement Code is more prescriptive conceming vessel examination than is the Original Code. It is therefore concluded that, *vith respect to Examination, the Replacement Code is reconciled to the Owners Specification.
- 2. Reouirement
- 12) Mechanical interfaces, fits. and tolerances that provide satisfactori performance are not changed by the later edition of the Construction Code.*
Discussion The relevant interfaces, fits, and tolerances are associated with the seal between the Split Packing (Grafoil) of the Assembly and the Mechanical Nozzle. The Mechanical Nozzle Seal Assembly acts as a replacement pressure boundary, instead of the nozzle to pressurizer weld.
l The Mechanical Nozzle Seal Assemtty is installed over the interface between the Mechanical
! Nozzle and Pressurizer O.D., and requires no modification of the Mechanical Nozzle for
[ installation.
r in summary, the interfaces, fits, and tolerances that provide satisfactory performance are evaluated in the Mechanical Nozzle Seal Assembly design report and consequently are in accordance with the Replacement Code.
- 3. Reauirement I
1
- 13) Modified or alerted designs are reconciled with the Owner's Specification (Reference 5.22) through the Stress Analysis Report, Design Report, or other suitable method which demonstrates the satisfactory use for the specified design and operating conditions, whichever is applicable."
Discussion l
l This Design Report has been prepared and demonstrates that the modified design is satisfactory l
for use for the design and operating conditions specified in S3-NOME-SP-0049 and the Owner's Specificaticn tReference 5.22).
l
- 4. Reauirement
- (4) Materials are compatible with the installation and system requirements.*
Discussion l
l ABB Combustion Engineering Nuclear Operations
S42ENG-DR 002, Rev. 01 Page AS of A5 -
l ll II I I I The SCE Mechanical Nozzle Seal Asse3Q is fabricated from SA-479 Type 304 austenitic stainicss steel, and SA-453 Grade 660 high c!!oy, high temperature botting material, which are compr.aole with the Mechanical Nozzle material (consistent of SA 182 Type 316 stainless steel for Safe End, and SB-166 (inconel) for the Nozzle). The Original Code does not have any material specification for SA-479 Type 304 austenitic stainless steel or SA-453 Grade 660 high alloy, high temperature bolting material, therefore no companson can be made between the Original Code and the Replacement Code.
Because the Replacement Code has been accepted t.y the nuclear industry (including the
.Muclear Regulatory Commission) and the Assembly's materials are similar in composition to the Mechanical Nozzle material, it is evidence that the Mechanical Nozzle Seal AssemNy material, SA-479 Type 304 and SA-453 Grade 660, is acceptable for use as designated by the Owners Specification. It is therefore concluded that, with respect to Material, the Replacement Code is reconciled to the Owners Specification.
p_gnclusion it has been shown in the pieceding paragraphs that the Replacement Code requirements are at least as prescriptive or more prescriptive than those of the Onginal Code. Therefore, it can be concluded that the requirements concerning the Construction Code date change for the SCE Mechanical Nozzle Seal Assembly are satisfied.
ABB Combustion Engineering Nuclear Operations
i j S-PENG-DR-002, Rev.e':
Page 81 of 822 APPENDIX B ANSYS OUTPUT ABB Combustion Engineering Nuclear Operations
6 4
S-PENG-DR-002, Rev,01 Page B2 of 822 Executing /ansys53 A>in/hp700/ansys.e53 l l l WELCOME TO THE ANSYS PROGR AM l l I ANSYS 5.3 NOTICES
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ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002, Rev. 01 Page B3 of B22 1.NSYS/Mechamcal AFTER YOU HAVE peals AND UNDERSTOOD THE PREVIOUS NOTICES.
PRESS <C & OR < ENTER > TO CONTINUE
""* ANSYS COMMAND LINE ARGUMENTS "*"
IWITIAL JOBNAME = 11!c MEMORY REQUESTED (MB) = 64 0 GRAPHICS DEVICE REQUESTED = XI1 START UP FILE MODE = READ GRAPHICAL ENTRY -YES DATABASE SIZE REQUESTED (MB) = 16
- " NOTE * *
- CP= 2.590 TIME = 13:16:11 There are no parameters and no abbreviations defined.
10158-961227 VERSION =HP 9000n00 RELEASE = $.3 UP071096 FOR SUPPORT CALL L L Beaudreau PHONE 860-285 3991 FAX 860-285-2901 CURRENT JOBNAME= file 13:16:11 JUN 18.1997 CP= 2.590
/SHOW SET Win { DRIVER NAME= X11 , RASTER MODE. GRAPHIC PLANES = 8 RUN SERTP PROCEDURE FROM FILE = /ansys53/doctJstart.ans
/INPtTT FILE = menust.tmp LINE= 0
/INPtrT FILE = /ansys53/docu/ start.ans LINE- 0 ABBREVIATION = VED EDIT /SYSJopt/ved/ bin /ved &
ABBhEVIATION= ANSYSWEB DELL'IID ACTIVATING TIIE GRAPHICAL USER INTERFACE (GUI). PLEASE WAIT..
/ INPUT FILE = plate 2.inp LINE= 0 CURRENTJOBNAMEREDEFINED ASpl2
""* ANSYS - ENGINEERING A4ALYSIS SYSTEM RELEASE 5.3 *""
ANSYS/Meci.anical 10158- % 1227 VERSION =HP 9000000 13:16:49 JUN 18.1997 CP= 3.590 FOR SUPPORT CALL L L Beaudreau PHONE 860 285-3991 FAX 860 285 2901 ABB COmbus!. ion Engineering Nuclear Operations
S-PENG-DR-002. Rev. 01 Page B4 of 622
"'" ANSYS ANALYS!5 DEFINITION (PREP 7)""'
ENTER /SHOW. DEVICE-NAME TO ENABLE GRAPHIC DISPLAY ENTER FINISII TO LEAVE PRFJ7 PRINTOUT KEY SET TO /GOPR (USE /NOPR TO SUPPRESS)
TITLE =
SCE MNSA non standud plate
= 0.8900000 PARAMETER R1
=
PARAMETER R2 1.030000 PAR / METER R.3 = 2 375000 PARAMETER R4 = 2.750000 PARAMETER TH = 0.7500000
"' PROPERTY TEMPERATURE TABLE NUM. TEMPS = 6 *"
SLOC= 1 100.0000 200.0000 300.0000 400.0000 500.0000 600.0000 PROPERTYTABLE ALPX MAT = 1 NUM.POthTS= 6 SLOC= 1 0.8550000E 05 0.8790000E-05 0.9000000E-05 0.9190000E 05 0.9370000E 05 0.9530000E 05 PROPERTY TABLE EX MAT = 1 NUM. PODRS= o SLOC= 1 0.2810000E408 0.2760000E+08 0.2700000E+08 0.2650000E+08 0.2580000E+08 0.2530000E+08 REFERENCE TEMPERATURE = 70.000 (TUNIF= 70.000)
AREA NUMBERING KEY = 1 LINE NUMBERING KEY = 1 XYZ TRIAD DISPLAY SET TO LEFT BOTTOM ELEMENTTYPE 1 IS SHELL93 8 NODE STRUCTUPAL SHELL KEYOPT(1 12)= 000 000 000 000 CURREIG NODAL DOF SET IS UX UY UZ ROTX ROTY ROTZ THREE DINENSIONAL MODEL REAL CONSTANT SET I ITEMS ITO 6 0.75000 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 FOR ELEMENT TYPE (S) ALLOWING MULTIPLE SHAPES:
i l
ABB Combustion Engineering Nuclear Operations l
S-PENG-DR 002, Rev. 01 Page B5 of B22 g . . .
TW' PRODUCE ALL QUADRILATERAL OR BRICK ELEMENTS. (MAPPED)
DEFAULT ELEMENT DIVISIONS PER LINE DASED ON ELEMENT SIZE = 0.300 KEYPOINT 1 X.Y.Z= 0.000000E+00 0.000000E+00 1.00000 IN CSYS= 0 KEYPOINT 2 X.Y.Z= 0.000000E+00 0.000000E+00 0.000000E+00 IN CSYS= 0 KEYPOINT .1 XY.Z= 0.890000 0.000000E+00 0.000000E+00 IN CSYS= 0 KEYPOINT 4 X.Y.Z= 1.03000 0.000000E+00 0.000000E+00 IN CSYS= 0 KEYPOINT 5 X.Y.Z= 2.37500 0.000000E+00 0.000000E+00 IN CSYS= 0 KEYPODir 6 X.Y.2= 2.75000 0.000000E400 0.000000E+00 IN CSYS= 0 LINE CONNECTS VEYPOINTS 2 3 LINE NO.= 1 KPl= 2 TANI= .l.0000 0.0000 0.0000 KP2= 3 TAN 2= 1.0000 0.0000 0.0000 LINE CONNECTS KEYPO! HTS 3 4 LINE NO.= 2 KPl= 3 TAN!= 1.0000 0.0000 0.0000 KP2= 4 TAN 2= 1.0000 0.0000 0.0000 LINE CONNELTS KEYPOINTS 4 5 LINE NO.= 3 KPl= 4 TAN!= .l.0000 0.0000 0.0000 KP2= 5 TAN 2= 1.0000 0.0000 0.0000 LINE CONNECTS KEYPOINTS 5 0 LINE NO.= 4 KPl= 5 TAN 1= .l.0000 0.0000 0.0000 KP2= 6 TAN 2= 1.0000 0.0000 0.0000 ROTATE LINES 1 2. 3. 4 ABOLTT THE AXIS DEFINED BY KEYPOlhTS I 2 l DEGREES OF ARC = -69.00 NUMBER OF SEGhENTS= 1 ROTATE LINES 5. 6. 7. 8, ABOUT TIE AXIS DEFINED BY KEYPOINTS I 2 DEGREES OF ARC = -21.00 NUMBER OF SEGNENTS= 1 ROTATE LINES 13. 14. 15. 16.
ABOUT'l1E AXIS DEFINED BY KETPOINTS 1 2 DEGREES OF ARC = -21.00 NUMBER OF SEGNENTS= 1
, ROTATE LINES 21. 22. 23, 24 ABOLTT TIE AXIS DEF!NED BY KEYPOINTS 1 2 DEGREES OF ARC = -69.00 NUMBER OF SEGMENTS = 1 DELETE SELECTED AREAS FROM 1TO 5BY 4 ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002, Rev. 01 Page B6 of B22 DELE 1ED 2 AREAS KEYPOINT 50 X.Y.Z= 3.75000 0 000000EW 0 000000E+00 IN CSYS= 0 LINE CONNECTS KEYPOINTS 2 50 LINF NO.= 37 KPl= 2 TAN!= -1.0000 0.0300 d0006 KP2= $0 TAN 2= 1.0000 0 0000 0.0000
- GET know I F"OM LINE ITEM =NUM MAX VALLLs 37.0000000 DRA0 LINES:
13.
ALONG LINES 37, ALL CURRENT ANSYS DATA WRITTEN TO FILE NAME= back.db FOR POSSIBLE RESUME FROM THIS POINT GENERATE 2 TOTAL SETS OF AREAS SETIS FROM iTO I IN STEPS OF 1 DX.DY.DZ= 0.000E@ 0.000E+00 0.000900 CSYS= 0 SUBTRACT AREAS AREA NUMBERS TO BE OPERATED ON = 2 AREAS OPERATED ON WILL BE DELETED AREA NUMBERS 10 BE SUB1RACTED = 5 AREAS SUBTRACTID WILL BE DELETED OUTPUT AREAS = 17 GENERATE 21DTAL SETS OF AREAS SETIS FROM iTD I IN fTEPS OF 1 DX,DY.DZ= 0.000E+00 0.000E+00 0.000E+00 CSYS= 0 SUB1RACT AREAS AREA NUMiiERS TO BE OPERATED ON = 3 AREAS OPERATED ON WILL BE DELETED AREA NUMBERS TO BE SUBTRACTED = 2 AREAS SUBTRACn!D WILL El". DELETED OLTTPUT AREAS = 5 OENERATE 2 TOTAL SETS OF AREAS SETIS FROM iTO I IN STEPS OF 1 DX.DY.DZ= 0.000EW 0 000E+00 0.000E+00 CSYS= 0 SUBTRACT AREAS AREA NUMBERS TO BE OPERATED ON = 4 AREAS OPERATED ON WILL BE DELETED ABB Combustion Engineering Nuclear Operations l l
l l
S-PENG-DR-002, Rev. 01 Page 87 of B22
_ ..y___.-.-- _ _ . - . . . , .__
AREA NUMBERS TO BE SUBTRACED = 2 AREAS SUBTRACTED WILL BE DELETED OUTPUT AREAS = 3 SUBTRACT AR*!AS AREA NUMBERS TO BE OPEMT1?D ON = 6 AREAS OPERATED ON WILL BE DELETED AREA NUNISERS TO BE SUBTRACTED = 1 AREAS SUBTRACTED WILL BE DELETED OtTrPUT AREAS = 2
"
- NO1 E *" CP= 4.940 TIME = 1316:55 NEW BACKUP FILE NAME= back.dbb.
ALL CURRENT ANSYS DATA WRITEN TO FILE r4AME= back.db FOR POSSIBLE RESUME FROM THIS POINT DELETE SELECTED AREAS FROM 9TO 13BY 4 DELETED 2 AREAS MERGE COTNCIDENT NODES WTTHIN MLERANCE OF 0.10000E 03 MERGE IDENTICAL MATERIALS WITHIN TOLERANCE OF 0.10000E 06 MERGE IDENTICAL E13.(ENT TYPES MERGE IDENTICAL REAL CONSTANT SETS WinIIN TOLERANCE OF 0.10000E 06 MERGE IDENTICAL ELEMENTS MERGE IDENTICAL COUPLED DOF SE15 MERGE IDENTICAL CONSTRADir EQUATIONS WITHIN TOLERANCE OF 0.10000E-06 MERGE COINCIDENT KEYPOINTS WITHIN TOLERANCE OF 0.10000E-03 KEYPOINT 4 USED FOR KEYPOINT(S) 29 KEYPOINT 28 USED FOR KEYPOINT(S) 32 KEYPOINT 30 USED FOR KEYPOINT(S) 31 LINE 2 USED FOR LINE(S) 45 LINE 4I USED FOR LINE(S) 44 LINE 43 USED FOR LINE(S) 46 GENERATE NODES AND ELEMENTS IN ALL SELECTED AREAS
" Meslung of area 2 in progress "
" Meshing of ma 2 completed " 40 elements.
- Meshing of area 3 in progress "
l , .
ABB Combustion Engineering Nuclear OperatlOns
l f
, S-PENG-DR-002, Rev. 01 Page 88 of B22
- Meshing of area 3 completed " 20 elements.
" Meshing of area 5 in progress "
" Meshing of area 5 completed " 60 elements.
" Meshing of area 7 in progress "
" Meshing of area 7 cornpleted " 24 elements.
" Meshing of area 8 in progress "
" Meshing of area 8 completed " 8 elements.
" Meshing of area 10 in progress "
" Meshing of area 10 completed " 40 elements.
" Meshing of area 1i in progress "
" Meshing of area 1i completed " 24 eternents.
" Meshing of area 12 in progress "
" Meshing of area 12 completed " 8 elements.
" Meshing cf area 14 in progress "
" Meshing of area 14 completed " 120 eternents.
" Meshing of area 15 in progress "
- Me:hing of area 15 completed " 72 elements.
" Meshing of area 16 in progress "
" Meshing of area 16 completed " 24 elements,
" Meshing of area 17 in progress "
" Meshing of area 17 completed " 75 elements.
NUMBER OF AREAS MESIIED = 12 MAXIMUM NODE NUMBER = 1632 MAXIMUM ELEMENT NUMBER = $15 SELECT ALL ENITITES OF TYPE = ALL AND BELOW ALL SELECT FOR ITEM =VOLU COMPONENT =
IN RANGE OTO OSTEP 1 0 VOLUMES (OF 0 DEFINED)SELECTEDBY VSEL COMMAND.
ALL SELECT ICR ITEhbAREA COMIONENT=
IN RANGE ITO 17 STEP i 12 ARF 1.S (OF 12 DEFINED) SELECTED BY ASEL COMMAND.
ALL SELECT FOR ITEM-LINE COMPONENT =
IN RANGE ITO 49 STEP 1 ABB CombustlOn Engineering Nuclear Operations
S PENG-DR-002, Rev. 01 Page 89 of B22 36 LINES (OF 36 DEFINED) SELECTED BY LSEL COMMAND.
ALL SELECT FOR ITEM-KP COMPONENT =
IN RANGE ITO 50 STEP 1 24 KEYPOINTS(OF 24 DEFINED) SELECTED BY KSEL COMMAND.
ALL SELECT FOR ITEM =ELEM COMPONENT =
IN RANGE ITO 515 STEP 1 515 ELEhENTS(OF 515 DEFINED) SELECTED BY ESEL COMMAND.
ALL SELECT FORITEM= NODE COMPONENT =
IN RANGE ITO 1632 STEP 1 1632 NODES (OF 1632 DEFINED) SELECTED BY NSEL COMMAND.
- " NOTE *" CP= 6.090 TIME = 13:16:59 DELETED BACKUP FILE NAME= back.dbb.
- " NOTE * " CP= 6.130 TIME = 13:16:59 NEW DACKUP FILE NAME= back.dbb.
ALL CURRENT ANSYS DATA WRITIEN TO FILE NAME= back.db FOR POSSIBLE RESUME FROM THIS POINT SELECT FOR ITEM-LINE COMPONENT =
IN RANGE 30 TO 33 STEP 1 4 LINES (OF 36 DEFINED)SELEC'IEDBYLSEL CONNAND ALSO SELECT FOR ITEM =LINE COMIONENT=
IN RANGE 3TO 25 STEP 22 6 LINES (OF 36 DEFINED) SELECTED BY LSEL COMMAND ALSO SELECT FOR ITEM =LINE COMPONEbT=
IN RANGE 47 TO 49 STEP I 9 LINES (OF 35 DEFINED) SELECTED BY LSEL COMMAND, SELECT ALL NODES (INTERIOR TO LlhT AND AT KEYPOINTS)
RELATED TO SELECTED LINE SET.
I13 NODES (OF 1632 DEFINED) SELECTED FROM 9 SELECTED LINES BY NSLL COMMAND.
SYMMETRY CONSRAINTS FOR COORDINATE SYSTEM 0 IN DIRECTION Y ON SURFACE DEFINED BY ALL SELECTED NODES I
ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002 Rev,01 Page B10 of B22
'" NOTE *" CP= 6,460 TIME = 13:17.00 Nodes on symmetry surfaces are rotated into coonhuate system 0.
TOTAL SPECIFIED CONSTRA! HTS = 339 SELECT FORITEM=KP COMPONENT =
IN RANGE 9TO 17 STEP 8 2 KEYTOINTS(OF 24 DEFINED) SELELTED BY KSEL col @MND.
SELECT NODES ASSOCIATED WITH EELECTED KEYPOINTS 2 NODES (OF 1632 DEFINED) SELECTED FROM
- 2 SELECTED KEYPOINTS BY NSLK COMMAND, SPECIFIED CONSTRAINT UX FOR SELECTED NODES 1TO 1632 BY I REAL= 0.000000000E+00 IMAG= 0.000000000E+00 ADDITIONAL DOFS= UY UZ ROTX ROTY ROT 2 SELECT ALL ENITTIES OF TYPE = ALL AND BELOW ALL SELECT FOR FIEM=VOLU COMPONENT =
IN RANGE OTO OSTEP 1 0 VOLUMES (OF 0 DEFINED) SELECTED BY VSEL COMMAND ALL SELECT FOR ITEM = AREA COMPONENT =
IN RANGE ITO 17 STEP 1 12 AREAS (OF 12 DEFINED) SELECTED BY ASEL COMMAND.
ALL SELECT FORITEM-LINE COMPONENT =
IN RANGE ITO 49 STEP 1 36 LINES (OF 36 DEFINED) SELEC'IED BY LSEL COMMAND.
ALL SELECT FOR TIEM=KP COMPONENT =
IN RANGE ITO 50 S1EP 1 24 KEYPODfTS(OF 24 DETTNED) SELECTED BY KSEL COMMAND, ALL SELECT FOR ITEM =ELEM COMPONENT =
IN RANGE ITO 515 STEP I 515 ELEMEhTS(OF 515 DEFINED) SELECTED BY ESEL COMMAND ALL SELECT FOR ITEM = NODE COMPONENT =
IN RANGE ITO 1632 STEP 1 ABB Combustion Engineering Nuclear Operations
S DENG-DR-002, Rev. 01 Page B11 of B22 1632 NODES (OF 1632 DEFINED)SEIICTED BY NSEL COMMAND.
'"a* ROLTTINE COMPLETED ""* CP = 6.570
""* ANSYS SOLUTION ROUTINE ""*
PERFORM A STATIC ANALYSIS THIS WDL BE A NEW ANALYSIS PRINT ALL ITEMS WITH A FREQUENCY OF ALL FOR ALL APPLICABLE ENTTITES WRITE ALL ITEMS TO THE DATABASE WITH A FREQUENCY OF ALL FOR ALL APPLICABLE ENT1 TIES SELECT FOR ITEM-LINE COMPONENT =
IN RANGE 26 TO 34 STEP 8 2 LINES (OF 36 DEFINED)SELECIED BYLSEL COMMAND ALSO SELECT FOR ITEM =LINE COMPONENT =
IN RANGE 18 TO 43 STEP 25 4 LINES (OF 36 DEFINED) SELECTED BY LSEL COMMAND SELECT ALL NODES (INTERIOR TO LINE, AND AT KEYPOINTS)
RELATED TO SELECTED LINE SET, 61 NODES (OF 1632 DEFINED) SELECTED FROM 4 SELECTED LINES BY NSLL COMMAND
- GET nnum FROM NODE ITEM =COUN VALUE- 61.0000000 SPECIFIED NODAL LOAD FZ FOR SELECTED NODES ITO 1632 BY I REAl, 8.19672131 IMAG= 0.000000000E+00 SELECT ALL ENTITIES OF TYPE = ALL AND DELOW ALL SELECT FOR ITEM =VOLU COMPONENT =
IN RANGE OTO OSTEP I O VOLUMES (OF 0 DEFINED)SELECTEDBY VSEL COMMAND.
ALL SELECT FOR ITEM = AREA COMPONENT =
IN RANGE ITO 17 STEP 1 I I I I II ABB Combustion Engineering Nuclear Operations f
l
S-PENG-DR-002, Rev. 01 Page B12 of B22 e i mI I II I I 12 AREAS (OF 12 DEFINED) SELECTED BY ASEL COMMAND.
ALL SELECT FOR ITEM =LINE COMPONEITT=
IN RANGE ITO 49 STEP I 36 LtNES (OF 36 DEFINED) SELECTED BY LSEL COMhMND.
ALL SELECT FORITEM-KP COMPONENT =
IN RANGE ITO SO STEP 1 24 KEYPOINTS(OF 24 DEFINED) SELECTED BY KSEL COMMAND.
ALL SELECT FOR ITEM-ELEM COMPONENT =
IN RANGE 1TO $l$ STEP I
$15 ELEMENTS (OF $15 DEFINED)SELEC1ED BY ESEL COMMAND.
ALL SELECT FOR ITEM = NODE COMPONENT =
IN RANGE ITG 1632 STEP 1 1632 NODES (OF 1632 DEFINED)SELECTEDBY NSEL COMMAND.
- "" ANSYS SOLVE COMMAND "*"
SOLUTION OPTIONS PROBLEM DIMENSIONALITY, , ,, . 3-D DEGREES OF FREEDOM. , , . . . UX UY UZ ROTX ROTY P.7TZ ANALYSIS TYPE . . . .. . . . . . STATIC (STEADY-STATE)
'" NOTE *" CP= 6.800 TIME = 13:17:02 Present time o is less tlan or equal to the previous tinne.
Time will & fault to 1.
- " NOTE * ** CP= 6.800 TIMEa 13:1102 Results printout suppressed for interactive execute.
" Reordering stillin progress "
" Reordering stillin progress "
LO AD STEP OPTIONS LOAD STEP NUhBER. . . .. I TIME AT END OF THE LOAD STEP. . .. 1.0000 NUNmER OF SUBSTEPS, . . . I STEP CHANGE BOUNDARY CONDITIONS . . . . NO PRIhT OUTPUT CONTROLS TTEM FREQUENCY COMPONENT ALL NONE DATABASE OUTPUT CONTROLS 11EM FREQUENCY COMPONENT l
ABB Combustion Engineering Nuclear Operations I l
I l
S PENG-DR-002, Rev. 01 Page B13 of 822 l l ALL ALL Range of element maximum matrix coeSicients in global coordinates Maximuma 727897419 at element 61.
Minimum = 36366047.2 as element 409.
"* ELEMENT MATRIX FORMULATION TIMES TYPE NUMBER ENAME TOTAL CP AVE CP 1 515 SHELL93 1.520 0.003 Time at erwi of element matrix formulation CP= 8.8200001.
Solution Preparation Element = 10 Cum. Iter = 1 CP= 9.040 Time = 1.0000 Load Step = I Substep= 1 Equilibrium Iteration = 1.
Solution Preparation Element- 210 Cum. Iter.= 1 CP= 9.380 Time = 1.0000 Load Step = 1 Substep= 1 Equilibrium Iteration = 1.
Solution Preparation Element = $10 Cum. Iter.= 1 Clw 9.900 Time = 1.0000 Load Step = 1 Substep= 1 Equilibrium iteration = 1.
Estimated number of actat DOF= 9441.
Maximum wavefront = 257.
Equation Solution Element = 460 Cum. Iter.= l CP= 14.910 Time = 1.0000 Load Step = 1 Substcp= 1 Eqailibrium iteration = 1.
Time at end of matrix triangutanzation CP= 15.3100303.
Equation solver maximum pivot = 257025034 at node 254 UY.
Equation sober minimum pivet= 1.530889572E-02 at node 1455 ROTZ.
"* ELEMENT RESULT CALCULAT10N TIMES TYPE NUMBER ENAME 'lVTAL CP AVE CP 1 515 SHELL93 1.250 0.002 I
"* NODAL .OAD CALCULATION TIMES l TYPE NUMBER ENAhE TOTAL CP AVE C5 l
1 515 SIELL93 0.110 0.000 l "* LOAD STEP 1 SUBSTEP 1 COMPLETED CUM ITER = 1
- " *ITME = 1.00000 11hE INC = 1.00000 NEW 'IRIANG MATRIX
"* PROBLEM STATISTICS ACTUAL NO OF ACTIVE DEGREES OF FREEDOM = 9441 R.M.S. WAVETRONT SIZE = 232.6
"* AKSYS BINARY FILE STATISTICS BUFFER SIZE USED= 4096 9.859 MB WRITTEN ON ELEMENT MATRIX FILE: p12.emat ABB Combustion Enginee[ing Nuclear Operations
5-PENG-DR 002, Rev. 01 Page B14 of 822 l.219 MB WRITTEN ON ELEMENT SAVED DATA FILE: pt2.esav 17.031 MB WRITTEN ON TRIANGULAR! ZED MATRIX FILE: pl2.tri 1.313 MB WRITTEN ON RESULTS FILE: p12.rst FINISH SOLUTION PROCESSING
- "" ROUTINE COMPLETED *"" CP = 17.750
""* ANSYS RESULTS INTERPRETATION (POSTI) *""
ENTER /SHOW, DEVICE-NAME TO ENABLE GRAPIDC DISPLAY ENTER FINISH TO LEAVE POSTI USE LOAD STEP 1 SUBSTEP 0 FOR LOAD CASE O SET COMMAND GOT LOAD STEP = 1 SUBSTEP= 1 CUMULATIVEITERATION= 1 TIME / FREQUENCY = 1.0000
[
TTILE= SCE MNSA non-standard plate SELECT FOR TrEM=U COMPONENT-2 DETWEENA 200^,",L-us AND 0.19000E 03 l KABS= 0. TOLERANCE = 0.100000E-12 l
133 NODES (OF 1632 DEFINED) SELECTED BY NSEL COMMAND PRINT U NODAL SOLUTION PER NODE SCE MNSA non-standard plate
""* POSTI NODAL DEGREE OF FREEDOM LISTING *""
LOAD STEP = 1 SUBS 1T!P= 1 l TIME = 1.0000 LOAD CASE = 0 i
l THE FOLLOWINO DEGREE OF FREEDOM RESULTS ARE IN GLOB AL COORDINATES NODE UZ 746 -0.19928E43 762 -0.1912IE 03 763 0.19297E-03 l 764 -0.19434E43 I 765 -0.19592E 03 766 -0. 9707E-03 767 0.19801E-03 768 -0.I9870E 03 769 0.19913E 03 770 -0.19576E 03 Il I I ABB Combustion Engineering Nuclear Operations
1
. S-PENG-DR 002, Rev. 01 Page B15 of B22 771 0.19902E43 772 0.19876E 03 773 019852E 03 SCE MNSA nonstandard pinte
'"" POSTI NODAL DEGREE OF FREEDOM LISTINO ""'
LOAD STE.P= 1 SUBSTEP= 1 TIME- 1.0000 LOAD CASE = 0 Ti!E IVLl4 WING DEGREE OF FREEDOM RESULTS ARE IN GLODAL OOORDINATES NODE UZ 774 019828E 0) 775 0.19805E43 776 0.19783E 03 777 0.19762E 03 778 01974IE 03 779 0.19722E 03 780 0.I9703E 03 781 019684E 03 782 0.19667E 03 783 0.19650E-03 784 0.19634E-03 785 0.1%19E 03 786 0.196060 03 SCE MNSA non-standard plate
- "" POSTI NODAL DEGREE OF FREEDOM LIS'ITNG "*"
LOAD STEI* 1 SUBSTEl* I TIME = 1.0000 LOAD LASE = 0 illE FOLLOWING DEGREE OF IT2.EDOM RESULW ARE .*N Gl.OBAL COORDINATES NODE UZ 787 4.1959IE-03 788 0.19578E 03 789 0.19577E-03 807 0.19085E 03 808 019200E-03 809 019321E 03 810 -0.19394E-03 8110.1947 tE-03 812 0195i4E-03 1018 019101E 03 101) 0.19081E 03 1020 -019062E-03 ABB Combustion Engineering Nuclear Operations
S-PENCvJR-002, Rev. 01 Page B16 of B22 1021 0.19043E 03 SCE MNSA non-standard plate
""* POSTl NODAL DEGREE OF FREEDOM LISTING '""
LOAD STEP = 1 SUBSTEP= 1
??aE= 10000 LOAD CASE = 0 TPE FOLLOWING DEGREE OF FREEDOM RESULTS ARE IN GLOBAL COORDINATES NODE UZ 1022 019024E 03 1024 0.1900$E 03 1037 4.19255E 03 1038 -0.19214E 03 1039 0.19175E 03 1040 0.19137E-03 1041 019100E 03 1042 0.19064E 03 1043 0,19030E43 1046 0.19432E 03 1047 -0.19410E 03 1048 0.19388E43 1049 0.19367E 03 SCE MNSA non-stsndard plate
- "" POSTI NODAL DEGREE OF FREEDOM LISTING '""
LOAD STEP- 1 SUBSTEP= 1 TIME = 1.(KKX) LOAD CASE = 0 71tE FOLLOWING DEGREE OF tREEDOM RESULTS ARE IN GLOB AL COORDINATES NODE UZ 1050 -0,19346E 03 1051 019326E 03 1052 0.19306E 03 1055 -0.19286E 03
- 054 -0.19267E-03 10$$ 0.19249E 03 1056 -019230E-03 1057 019212E 03 1058 0.19194E 03 1059 -0.I9177E 03 100 -019160E 03 1061 019143E 03 1062 419125E-03 ABB COmbustlOn Engineering Nuclear Operations
. S-PENG-DR 002, Rev. 01 Page B17 of B22 SCE MNSA non standard plate
' "" IOSTI NODAL DEGREE OF FREEDOM LISTINO ""*
LOAD STEP- 1 SUBSTEP= 1 TIME = 10000 LOAD CASE = 0 THE FOLLOWING DEGREE OF FREEDOM RESULTS ARE IN GLOBAL COORDINATES NODE UZ 1063 0.19107E 03 1064 -0.19096E43 1065 0.1934$E 03 1066 0.19500E 03 1067 0.194$8E 03 1068 4.19417E 03 1069 0.19378E 03 1070 -0.1934IE 03 1071 0.1930$E 03 1072 0.19270E 03 1073 0.19338E 03 1074 0.19683E-03 1073 -0.19659E43 SCE MNSA non standard plate
'"" POST) NODAL DEGREE Of FREEDOM LISTINO "*"
LOAD STEP = I SUBS 1EP= 1 TIME = 1.0000 1.OAD CASE = 0 THE FOLLOWING DEGREE OF TREEDOM RESULTS ARE h GLOBAL COORDINATES NODE UZ 1076 0.19635E 03 1077 0.19613E 03 1078 0.19590E 03 1079 0.19569E 03 1080 0.19348E 03 1081 -0 A*527E 03 1082 -0.19507E 03 1083 0.19487E 03 1084 0.19468E 03 1685 0,39449E-03 1086 0.19431E 03 1087 0.19413E 03 1083 0.19396E43 SCE MNSA non-nwierd plate i ..-uw'ur.r.
- - r r- i i..-,
ABB Combustion Engineering Nuclear Operations l
l
S-PENG DR 002. Rev. 01 Page B18 of B22
""' POSTI NODAL DEGREE OF FREEDOM LISTING '""
LOAD STEP = l SUBSTEP= 1 TIME- 10000 LOAD CASE = 0
'n(E FOLLOWING DEGREE OF FREEDOM RESULTS ARE IN GLOD AL COORDINATES NODE UZ 1089 0.19379E 03 1090 0.I9360E43 1091 0.19342E 03 1092 -0.19331E 03 1093 0.197$1E 03 1094 0.19703E43 1095 0 IC658E 03 1096 0.19616E 03 1097 019575E 03 1098 -0.19537E 03 1099 -0.19500E 03 l100 0.I9464E 03 l101 0.19432E-03 SCE MNSA non-mandard plate
""' POSTI NODAL DEGREE OF FREEDOM LISTING ""'
LOAD STEP = 1 SUBSITP- 1 TIME = 1.0000 LOAD CASE = 0 Tl!E FOLLOWING DEGREE OF TREEDOM RESULTS ARE IN GLOBAL COORDINATES NODE UZ l102 0.19844E 03 1103 0.19819E 03 1104 -0.19795E-03 1105 0.19771E 03 1106 0.19748E 03 1107 0.19726E-03 1108 0.I9704E 03 1809 0.19683E 03 Ii10 0.19662E 03 Iil1 0.19642E 03 III2 0.19623E-03 1813 0.19604E-03 Ii14 0.19585E 03 SCE MNSA non-standard plate
"*" POSTl NODAL DEGREE OF FREEDOM LISTING '""
ABB Combustion Engineering Nuclear Operations
S PENG-DR-002, Rev. 01 Page B19 of B22 i LOAD STEP = 1 SUBSTEP= 1 TIME = 10000 LOAD CASE = 0 i T1(E FOLLOWING DEGREE OF FREEDOM RESULTS ARE IN GLOBAL COORDINATES NODE U2 1115 019366E-03 I116 -0.19548E 03 1117 -0.19531E-03 lil8 0.19511E43 Ii19 0.19492E 03 1120 -0.19482E 03
' 1821 019562E 03 1122 0.19813E-03 1123 -0.19768E 03 1124 0.19726E 03 1125 0.1%86E 03 1826 0 19649E 03
!!27 0.19615E-03 SCE MNSA non-standard plate
- "" POSTI NODAL DEGREE OF FREEDOM LISTINO "*"
LOAD STIP= 1 .CUllSTEP= 1 TIME = 1 0000 LOAD CASE = 0 71[E TOLLOWING DEGREE OF FRELDOM RESULTS ARE IN GLOBAL COORDINATES NODE UZ l128 0.19582E 03 1129 -019552E-03 1831 0.19044E 03 AULXIMUM ABSOLLTTE VALUES NODE 746 VALUE 4.19928E 03 SELECT ALL ENTITIES OF TYPE = All AND BELOW ALL SELECT FOR ITEM-VOLU CONGONE.'TT=
IN RANGE OTO OSTEP 1 0 VOLUMES (OF 0 DEFINED) SELECTED BY VSEL COMMAND, ALL SELECT FOR TIEM= AREA COMPONENT =
IN RANGE ITO 17 STEP l 12 AREAS (OF 12 DEFINED) SELECTED DY ASEL COMMAND.
l ABB Combustion Engineering Nuclear Operations
, S PENG DR-002, Rev. 01 PaDe B20 of B22 N ,.-,-------'ii...A - -
m -, . . 7 , . - , - -
ALL SELECT FOR ITEM LINE COMPONENT =
IN RANGE I TO 49 STEP 1 36 LINES (OF 36 DEFINED) SELECTED BY LSEL COMMAND.
ALL SELECT FOR ITEM =KP COMPONENT =
IN RANGE ITO $0 STEP 1 It KEYPOINTS(OF 24 DEFINED) SELECTED BY KSEL COMMAhD.
ALL SELECT FOR ITEM =ELEM COMPONEhT=
IN RANGE ITO $15 STEP 1 515 ELEMENTS (OF $15 DEFINED) SELECTED BY ESEL COMMAhV.
ALL SELECT FOR ITEM = NODE COMPONENT =
IN RANGE ITO 1632 STEP 1 1632 NODES (OF 1632 DEFINED)SELECTTiD BY NSEL COMMAND.
SELECT FOR ITEM-S COMPONENT-INT BETWEEN 2500.0 AND 0.12677E+31 KABS= 0.1DLERANCE=0.250000E-04 17 NODES (OF 1632 DEFINED) SELECTED BY NSEL COMMAND PRINT S NODAL SOLUTION PER NODE SCE MNSA non standard plate
"'" POST) NODAL STRESS LISTINO "*"
LOAD STEP = 1 SUBSTEP= 1 TIME- 1.0000 LOAD CASE = 0 Sl! ELL NODAL RESULTS A.RE AT TOP NODE $1 $2 S3 SINT SEQV 235 2084 4 1587.0 504.27 2588.7 2379.3 522 2356.9 781.79 150.19 2507.1 2194.9 748 2418.8 636 66 252.71 2671.5 2356.3 750 2437.6 514.27 378.81 2816.4 2492.9 752 2404.1 412.55 513.76 2917.8 2582.4 754 2311.4 326.67 -641.01 2952.4 2607.0 756 2156.7 252.73 744 69 2901.4 2553.2 758 1941.1 188 54 810.94 2752.7 2413.5 760 1673.3 133.29 -828 40 2501.7 2185.7 823 2328.9 647.63 211.86 2540.8 2238 4 851 2329.0 529.38 316 $7 2645.6 2340.2 879 2281.8 428 05 -429 54 2711.3 2400.3 881 2172.9 444.16 358.13 2531 0 2240.3 907 2181.5 340 94 537.35 2718.9 2403.3 ABB Combustion Engineering Nuclear Operations
S-PENG-DR 002, Rev. 01 Page B21 of B22 I
SCE MNSA non standard plate )
'"" POSTA NODAL STRESS LISTING '""
LOAD STEP = l SUBSTEP= 1 TIME = 1.0000 LOAD CASE = 9 SIIELL NODAL RESULTS ARE AT TOP NODE SI S2 S3 SINT SEQV 909 2065.6 356.58 448.21 2513.8 2223.5 at5 2026.1 265.38 626.45 2652 6 2337.9 a 1817.8 199.71 4 84.51 2502.3 2197.9 MINIMUM VALUES NODE 760 760 760 760 760 VALUE 1673.3 133.29 828 40 2501.7 2185.7 MAXIMUM VALUES NODE 750 235 522 754 754 VALUE 2437 6 1587.0 150.19 2952.4 2607.0 SCE MNSA non4tandard plate
- "" POST) NODAL STRESS LISTING *""
LOAD S1IP= 1 SUBSTEP= 1 TIME- 1.0000 LOAD CASE = 0 SHELL NODAL RESULTS ARE AT TOP NODE SI S2 S3 SINT SEQV
- "" ESTIMATED DOUNDS CONSIDERING TIE EFFECT OF DISCRET1ZAT10N ERROR ""*
MINIMUM VALUES NODE 760 750 235 135 235 VALUE 1671.9 131.88 885.57 2207.4 1998.0 MAXIMUM VALUES NODE 235 235 235 235 235 VALUE 2465.7 1%8.3 122.97 2970.0 2760.6 SEl.ECT ALL ENTITIES OF TYPE = ALL AND DELOW ALL SELECT FOR ITEM-VOLU COMPONENT =
IN RANGE OTO OSTEP 1 0 VOLUMES (OF 0 DEFINED) SELECTED BY VSEL COMMAND.
ALL SELECT FOR ITEM = AREA COMPONERT=
. . _ _ _ . . . . _ . _ . . . . ..l. . . . . . . . . . . _ . . . _ . - . . . . . . _ . . _ _ . , . . .
l ABB Combustion Engineering Nuclear Operations l
S PENG-DR-002, Rev,01 Page B22 of B22 IN RANGE ITO 17 STEP I 12 AREAS (OF 12 DEFINED) SEl.ECTED BY ASEL COhBtAND ALL SELECT FOR ITEhbLINE COMPONENT =
IN RANGE 1TO 49 STEP i 36 LINES (OF 36 DEFINED) SELECTED BY LSEL COhntAND.
ALL SELECT FORITEh5KP COMPONENT =
IN RANGE ITO SOSTEP 1 24 KEYPOINTS(OF 24 DEFINED)SELECFED BY KSEL COMMAND ALL SELECT FORITEM-ELEM COMPONENT =
IN RANGE ITO $15 STEP 1 515 ELEMENTS (OF 515 DEFINED) SELECTED BY ESEL COMMAND ALL SELECT FOR ITEM = NODE COMPONENT =
IN RANGE I *IO 1632 STEP 1 1632 NODES (OF 1632 DEFINED)SELECITI)BY NSEL COMMAND.
EXIT Tl!E ANSYS POST) DATABASE PROCESSOR
- " ROU11NE COMPLETED ""' CP = 18.830 ABB Combustion Engineering Nuclear Operations
l
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S-PENG-DR 002, Rev. 01 ;
Page C1 of C7 APPENDIX C STIFFNESS OF FLANGED CONNECTION 4
ABB Combustion Engineering Nuclear Operations
AB S-PENG-DR-002 Rev. 01 Page C2 of C7 l
l l
I l
C.1 Objective This appenckx calculates the stiffness of the components in the flanged connection between the MNSA and the pressurtzer. Et ,h MNSA location has a different stiffness.,
C.2 Side Pressurizer RTD Nor21e Stiffness of Hex Head Bolts:
The stiffness of the bolts is calutated using the same methods described for the tie rods in Section 3.2.3 of the main text. Dirnensions are taken from Reference 5.8.
2 AE (015W In )(248 X10' )
= 9,584,338 Ibf Kw,=4 =4 l 1.65$ 1n n where: A = cross section of bolt, Section 2.1.4
. l = effedive length of bolt,
= thread engagement + lower flange + upper flange + washer
= 0.5 + 0.365 + 0.73 + 0.06 = 1.655 inch Silfine5Lof Overall Flanne.
The side pressurizer MNSA has two components which represent the flanged connection to the pressurizer, the upper flange and the compression collar. The stiffness of each of these compoents is calculated using the same method described for the top plate in Section 3.2.3 of the main text.
l Upper flance:
l The following equattorts are found in Reference 5.11, Table 24, Case Ia. All dimensionse are taken from Reference 5.8.
w a' y = p (C, ct I, 4) where.
D=-
E f' = 24 8X10' k'" (0.73)'in' = 883,482 lbf 12(1 - y ') 12 (I - 0.3' )
Ci, Cr, L , and L3 are constants, and are calculated using the equations of Reference 5.11, pgs. 332 334 using the following dimensions. Since the flange does not have a rectangular cross section, the dimensions are selected to produces the lowest flange stiffness.
I I I I ABB CombuStlon Engineering Nuclear Operations
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, S-PENG-DR-002, Rev. 01 Page C3 of C7 Rf D UPPER FLANGC
.- a st :l 4
~
- *ir ;-
,W A A I
1
'y T_e w , , ,37 1r _ _
'l,
, c206s- - - * - - -
W F a sir
=f a = outer radius,1.906 in b = inner radius,1.263 in r, = radius of applied load,1.203 in
! = thickness,0.73 in y = Poisson's ratso,0.3 E = elastic rnodulus,24.8 X 10' psi Ci = 0.3254 Cr = 0.3851 L3 = 0.0052 Le = 0.2423 Solving for the stiffriess of the upper flange:
w 2xi* = 5,074,435 lbf A,,%, = y = a ;-( -1) - C,L, in D C, Cornpresion Collar:
COMPRESSION COLLAR
^-
2.3is' =i w
0D45 )
I s
0 0^E a
gsgo-44
,= 1.azr :--
ll
= =-
l t.ir -
1
,= 2.srs- :,
a = 1.1575 in b = 0.661 in
- r. = 0.784 in t = 0.73 in ABB Combustion Engineering Nuclear Operations
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- AEE S-PENG-DR-002, Rev. 01 Page C4 of C7 l
l
)
v 0.3 E = 24.8 X 10' psi Ci = 0.4145 C, = 0.5369 L3 = 0.0046 L4=02357 EI i 24.8X10'
'"* k (0.73)'in' D= 3
=
8
= 883,482 lbf 12(1 - 7 ) 12(1 - 03 )
N=# -=
a,
= 1 $,821,942 E
)> in D (Cr, C,
Determinanon of equivaknt flange stiffness:
These components act in series against the bolt. The effective stiffness of the two components is calculated below.
K% =-
I
= 3,842,170 E in 4
Kn K, ABB Combustion Engineering Nuclear Operations
S PENG-OR-002, Rev. 01 Page C5 of C7 C.3 Bottom Pressurizer Level Norrie Stiffness of Hex Head Bolts:
The stiffness of the bolts is calutated using the same methods described for the tie rods in Section 3.2.3 of the (nain text.
(01599 in')(24.8 X10' )
Kw = 4 A E=4 = 3,971,477 lbf 1 3.994 in in where: A = cross section of bolt, Section 2.1.4 I = effectrve length of bolt.
= thread engagement + average lower flange + upper flange (top) +
upper flange (bottom)+ washer
= 0.5 +i4.186 7.5 /2* tan (27.5')] + 0.5 + 0.7 + 0.06 = 3.994 Stiffness of Overall Flanoe:
The side pressurizer MNSA has three components which represent the flan 0ed conriection to the pressurizer, the upper flange (top), upper flange (bottom) and the compression collar.
The stiffrw ss of each flange is calculated using the same method described for the upper fl&nce of the side pressuriree MNSA. The compression collar is tall and narrow and therefore considered to have only axial stiffness.
Upper flanus (top):
The following equations are found in Reference 5.11 Table 24, Case 18. All dimensionse are taken from Reference 5.8.
a = outer radius,3.25 in b a inner radius,1.156 in
- r. = radius of applied load.1.156 in t = thickness,0.5 in y = Poisson's ratio,0.3 E = elastic modulus 24.8 X 10' psi C, = 0.6687 Cr = 1.1174 L3= 0.0259 Le = 0.2934 D=
Et
= 24.8X10' #" (0.5)'in' = 283,883 lbf 2
12(1 - y ',) 12(1 - 03 )
Solving for the stiffness of the upper flange, top:
ABB Combustion Engineering Nuclear Operations
- -- ai- - . , -
S-PENG-DR 002, Rev. 01 Page C6 of C7 m _, _ _ _ _ _ .
2r r*
K**=E= y a'
= 401,286 E in
- ( C,L,-L,)
D C, Upper flange (bottom):
The fa, lowing equations are found in Reference 5.11, Table 24, Case 1s. All dimensionse are taken from Reference 5.8.
J = outer radius,3.25 in b = inner radius,0.781 in r, a radius of applied load. 0.968 in
! = thickness,0.7 in y = Poisson's ratio,0.3 E = elastic modulus,24.8 X 10' psi C, = 0.9089 Cr = 1.7841 L3= 0.0303 Le = 0.2816 gi 24.8X10' D= =-- '" (0.7)'in' 12(1-y ) 8 8 = 778,974 lbf 12(1 - 03 )
SolvinD for the stiffness of the upper flange, bottom:
K,. w -5 = # #*
= 1,217,462 5 y , C,L, a_
m D C, Compresion Collar:
no rrou rne ssuRcLR COMPRES$10N COLLAR l __ t I- t on y 4 4 os:s
! i l' j
(' ; .: .! .'
n s.
( .l j W isse h
ABB Combustion Engineering Nuclear Operatioris
y S PENG-DR-002, Rev. 01 Page C7 of C7 (O'"0' '" )( A #I* E K =AE-= = 6,098.198 lbf I
3.24 in in where: A = cross sechon of collar, rJ4'(1.559'.1.19') = 0.7967 in' I = average effective leng*h, '
= [3.644 + (3.6441.559' tan 27.5')] / 2 = 3.24 in l Dehornnation of equivalent flange stiffness:
The three flanges act in paralkl with the botts. The overall flance and the compression collar act in series whh the bolt. The effective stiffness of the components is calculated below.
K%= , ,
= 1,279,191b in (K ,y. , + K,,,,,, ) 4 K.
l ABB Combustion Engineering Nuclear Operations i
i l
I F S PENG-DR002, Rev. 01 )
Page D1 of D9 APPENDIX D QUALITY ASSURANCE FORMS i
ABB Combustion Engineering Nuclecr Operations
S PENG-DR@2, Rev. 01 Page D2 of 00 DESIGN REPORT REVIEW CIIECKLIST lagrwctioeti The Indeper&nt Reviewer is to complete this checklist for exh Design Report. This clwcklist may be incorporated in'.o the Design Repon or rnaintained separate.
Titic Addendum to the Pressurirer Analytical Stress Report for Southem Caltfornia Edison San O_ nofre Units 2 And 3 Document Nunnben S-PENG DR-002 Revision Nurnben 01
- _ [j Ur j . ;[ - : 9/
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,,Q!N (Yes : '.N/Ah I. thive all drawings been prepared and independernly renewed in accordance with QP 3,77 YO Are Checklists for the Design Analysts (QP 3.4) and Drawmg (QP 3.7) review attached to O the Design Report or on file with the CEO as quality records?
- 3. llave the analyses been separately prepared and independently reviewat in accordance with O I QP 3.47 : or
- 4. Is the analyses to be independently reviewed in cor. junction with the compilation and WD venfication of the design report?
5 llave all applicable TCRs, DCRs, NCRs, etc. been listed and reconciled in the Design O I Report?
- 5. Arc all applicable drawings and aralyses used for design and construction in a6rcement #D with, and identified and described in the Design Report?
7 Are the correct revision levels of all design output documents listed? O
- 8. llave provisions tus.n made for a copy of the Dvmcr's Review of the Design Report to be O Y attached to:he Design Report?
9, Does the Design Report contain sufficient details and trferences to permit certification by a #O Registered Professional Engineer (RPE)?
- 10. Is the Design Report in accordance with the format requirements of the procedure? IO Cominentslifmoy) > >
.~J 'Nt+i' ?"' -
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Checklin completed by:
9 l Independent Re&wn
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l -
ABB Combustion Engineering Nuclear Operations
ABB S PENG-DR-032, Rcv. 01 Page D3 et D9 Verification Plan
Title:
Addendum to the Pressurizer Analytical Stress Report for Southem Califomia Edison San Onofre Units 2 And 3 Document Number: S.PENG.DR 002 Revision Number. OI _
jangym Desc:ibe the snethod(s) of venfication to be ernployc1 i.e Design ReTiew. Alternate Analysis.
Qualdication Testing. a combinauon of these or an alternative. The Design Analysn; Verification Checklist is to be used for all Design Analyses. Other elemerus to consider in formulaung the plan ase. methods for cheding calculationt cornpanson of results with similar analyaes. ete-Dfggjption of Verification Methot Melhoel o E VsetIIcasIon is desty n 'eVlew) mel"d*G :
- v'e.tofy 4ha.L o.gorop/ta Lc ana./y L.tca./ nteM u)ve 144sA C n rec.t.Iy ,
- hurly t%L a.Il fa.imic<.1 pero msl.evs anocis4.ed will, 64e. assely tica.1 melkeds were coweefIy Selec. Led from ,Lru.cerble .scu./ces,
- bview nti.me<ac<.] calca la.fwus far acca,tecy .
Approved by: }
Venficat2on Plan prepared by; } 9 K. lL Haslinger ((( p , h , krn kht t J .
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ABB Combust. Engineering Nuclear Operations
S-PENG DR-002, Rev. 01 Page D4 el D9 Design Analysis Veri;k.ition Checklist (Page 1 of 4) lastructionst " Die Independent Reviewer is to complete this checklist for cach analysis and it is to be incorporated into the completed analysis. If a major topic area (gerristly unnumbered. told face type such as Use of Computer Software) is not applicable. then N/A next to the topic nay be checked and the check boxes for all items under it rnay be left blank. Where there is no check tox under N/A (not applicable) for a numbered item, such a response is generally inappropriate, if N/A is checked in such a situation, docurnent the basis at the end of this checkint in the Gv aments section.
Title:
Addendum to the Pressurtzer Analytical Stress Report for Southem Cahfornia Edison San Onofre Urfts 2 And 3 Document Namiben S-PENG-DR-002 Revision Numben 01 Yes N/A
'()veMit AssessaienO ' ' :' ':m .
- 1. -
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- 2. Are all linnitations and costlegencies on the results/ conclusions documented? [
%ss6genIwet'airCagabeumiBlmslageEs[Ff, " Reviewer $ and M.stersN 2 $l . IfJ." W N i f.
- t. Havs C p.ams r.asi.ewi ' ' ' r Rev6 ewers and Memars. If sprisc.ble, be.n a.igiud and approwd by mousenent? g
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0 Design Analysis Verification Checklist I "IIM ' l Il - . -
ABB Combustion Engineering Nuclear Operations 4
S-PENG-DR 002: Rev. 01 e PagAD5ofD9 (Page 2 of 4)
Desop Andyde Centends - '; : !" 1 , M. ,'
r i ! ", " , ' Yes WA-Obje:Ww et the Desip Andysis . " i 7' ,
\ 7 M..?, .n e i Hu infwwntmo ammary to derse en ink leen valuded or ufamW7 7
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1 Are dw anahtxel iecisequa (aremds) decret f ia suffiness deua se rese own appropnmuess7
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11 llave analyucaliedvaupas tnrerparsed by referemis es gmmc analyssa, lead plass analyse or pevies cycle analynes bees p m aner venrad? Q [
D1 7ar swukrcerians ce departures Darti pmously appoved analyticalischrsg.se or Ceevernianal triguerenng Analyse heimihnes (OP 3 l9) Q A Are uney skleumsuiad and justdsedt
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- i. Are u. d h e nsdoswi e g'
- 2. Are p. dois bem snermey wisised and w% io ver sounet 7
3 Are toforences as dent u remible to die ensinal source w f . comamung conocibeubuleuana er supuist 7
4 Is the reinenw ocessaan apprepnasaiy spesirst to en inAreneuse .iluse 7
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Design Analpis Verification Checklist
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ABB Combastion Engineering Nuclear Operations
1 i
I 4
yy S-PENG-DR 002 Rev,01
, 3 Page D8 of D9 i (Page 3 of 4)
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7 *6 ,, , 4 e,; Nes7 N/At 1
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to e pones a plue wkth ammun that emne re tepnoses . tech are etw cumam.r's responsibdn> so clear will be urhad.d as wansnumak to.w cwoomert Q t Has a e.inperwon a. ow resutu with ihnee of a povwus c>tte w sanilar analysis b.en made and si,uticars difIsr.nces whnadt O [
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7O 2 la the enfwmat6.a lb.a relevant inerstwe neardusbeckyou.d des adequately documented and referered' t A,.i a c.w w .onea .nd. m .pi e w id?
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3.
Q Dan the dutnbution of the revuean incide h se the d.tnbuten of em previous revnion'
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ABB Combustion Engineering Nuclear Operations
y S-PENG DR-002, Rev. 01 0 Page D7 of D9 Design Analysis Wrification ChecMist (Page 4 of 4)
Yes N/A r . .e as I i
o Have etw tale and docurram number .sen Fonerved wnhas stanp?
fl. r{al the tevisi.a nun.ber twee ennemented by one?
For a "psy stanc package":
- 1. Are pays enrested in amerdance umh pu reginal analysis?
]
- 2. Are instruciness p,vided fw de innertaan and deletion of revised pages?
[
3 lies a new Tak rap been prepered enth en rease asents c retwams the change paaage?
O 4 lias the enginal Title Page been retaaned 'e preserve the approval reswd?
Q
- 3. Has a #ww Design Analysis in Process Approvals (wen been prepared?
Q
- 6. Has the enginal Design Analyses la Procams Aprovah fvrin been retaened to pro arve en approval reswd?
O Costinnt.all (f(aft /p a * 'hh ! ,
l[j0,OhI,)OFlll;ik]"!M.f/' $f:i' d[ Skb[5((Ekh.'.hk I
ABB Combustion Engineering Nuclear Operations
S-PENG-DR-002, Rev. Oi e Page D8 of 09
~
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, independent Reviewer's Comuments'" - *a
'"W' C-t . 7 > Reviewer's Canonent , ; , Meeposee r Aother's Response 4. . Response i blier t ^ * < i '
' Required? r! ' '
'Accesed? l Alb A)F Checklist completed t)y:
1 Independent Reym er
. d.T Wreau.
huwd Name
- a. lw un a f1
/ Sognesure B 97 limae v
ABB Combustion EnDineering Nuclear Operations 1
S-PENG-DR-002, Rev. 01
. Page D9 of D9 Design Report Review Certificate This Det.irn Report has been reviewed by the undersigned in accordance with the requirements of the ASME Boiler and Pressure Vesset Code, Se f:ri 111. Division 1, Nuclear Power Plant Cornponent,1989 Eddion, no Adderda, and to the best of the reviewers knowledge ard belief is based upon the Design, Service, and Testing Loadings stated in the derJgn specification.
Stress Report Vendor. GE Nuclear OoeraWms Revision; _ 01 ,_.
Report No. S PENG-DR-002 -
Date: f/19/W Revisiort 09 Design Spectrication: 01370-PE 130 Date: 12-10-93 Revision: 01 D0 sign Specification: D3-NOME SP-f)p49 Date: 6-24-9'i-Plant Owner, Southern Cattfornia Edison Sal1Onofre 11 & 111 Desegnee. Combusbon Engineering,Inc.
ABB Corntestion Engineenno Nuclear Operations Windsor,Connechout Certwied by: d'l li3 M6 # Pmfgssional Enoineer b![0/h7 Title Date Narne \
(T 19990 ABB Combustion Engineering Nuclear Operations