ML18059A546

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Determination of Axial Stress in Palisades Nuclear Plant Pressurizer Porv,Spray & Surge Nozzle Safe Ends
ML18059A546
Person / Time
Site: Palisades Entergy icon.png
Issue date: 11/23/1993
From: Hammer P
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
Shared Package
ML18059A543 List:
References
P-MECH-CALC-019, P-MECH-CALC-019-R00, P-MECH-CALC-19, P-MECH-CALC-19-R, NUDOCS 9312080134
Download: ML18059A546 (34)
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{{#Wiki_filter:* ATTACHMENT 3 Consumers Power Company Palisades Plant Docket 50-255 REPLY TO NRC REQUEST FOR INFORMATION REGARDING THE PRESSURIZER SAFE END CRACK CRITICAL FLAW SIZE AND MARGIN TO FAILURE ANALYSIS C-MECH-CALC-019, "Determination of Axial Stresses in the Palisades Plant Pressurizer PORV, Spray, and Surge Nozzle Safe Ends," November 23, 1993 November 30, 1993 33 Pages ,,_9~3T2oso1:r1-s31T3o ------ :-"' PDR ADOCK 05000255 ~ I S PDR I I '---..___/

Contract 2003045 Jl 1111 ,.,1111 ASEA BROWN BOVERI Calculation Number P-MECH-CALC-019 Calculation __ 2_3 __ Pages Appendix A-5 ' B-5 Pages Microfiche N/ A Revision ___ o_o ____ _ Title Determination of Axial Stresses in the Palisades Nuclear Plant Pressurizer PORV, Spray and Surge Nozzle Safe Ends Author _P_. I_._H_a_mm_e_r_* -'f'~T>* =-....;~,=~~* ~~=. =--------- Date ___;,,,,:,11_,_/~23""'-+-{....... 9 3........._ __ Calculation contains safety related design information: Yes __xx_ No __ Date _JJ_-_M .... _9_:?_ Distribution B. Boya (2), B.T. Lubin Summary

Purpose:

To determine axial stresses in the PORV, Spray and Surge nozzle safe ends due to pipe loads and internal pressure. Method and Results of Review: This calculation was verified by the method of Design Review and satisfies, where applicable, the items on Checklist #2 of the Quality Assurance Procedures Manual, QAM-101 Form # 0013320 !Rev. 7/901 ABB Combustion Engineering Nuclear Power

Rev. Date 00 11/z.3/q3 Jl 1111 jll\\1119 ASEA BROWN BOVERI RECORD OF REVISIONS P-MECH-CALC-019 00 Calculation Number Rev. 2 of ?.3 Page Number Pages Affected -ALL-Prepared by -P. T. if a.rnrne.i-Approved by ""B.T. Ubin ABB Combustion Engineering Nuclear Power Onrrn H 0090257-fl IR~v 7'901

jl 1111 ,.,1119 ASEA BROWN BOVERI TABLE OF CONTENTS P-MECH-CALC-019 Calculation Number 3 of 23 Page Number Section 1.0 PURPOSE........................ 2.0 SCOPE...................... 3.0 DATA AND ASSUMPTIONS.................. 3.1 Dimensions.................... 3.2 Forces and Moments................ 3.3 Internal Pressure 3.4 PORV Nozzle Crack Location........ 4.0 ANALYSIS......... 4.1 Axial Stresses due to ~xial Forces 4.2 Axial Stresses due to Bending Moments 5 5 6 6 7 8 8 9 9 9 4.3 Axial Stresses due to Internal Pressure...... 11 4.4 Maximum Axial Tensile Stress........... 12

5. 0 RESULTS.

....................... 13 6. 0 REFERENCES....................... 2 3 ABB Combustion Engineering Nuclear Power ~"rm a 0090257-8 fRP.v 7 190! 00 Rev.

Al 1111 ,.,1111 ASEA BROWN BOVERI P-MEGI-CALC-019 Calculation Number Lf. of 23 Page Number TABLE OF CONTENTS - continued LIST OF TABLES AND FIGURES Table lA: PORV Nozzle - ow + Thermal Load Axial Stresses (N-S-E-W) Table lB: PORV Nozzle - ow + Thermal Load Axial stresses (A-B-C) . 14 .. 15 Table 2: PORV Nozzle - OW + Thermal Stratification Load Axial Stresses (A-B-C) ..... 17 Table 3: Pressurizer Spray Nozzle - ow + Thermal Load Axial Stresses (N-S-E-W) .......... 19 Table 4: Pressurizer Surge Nozzle - ow + Thermal Load Axial Stresses (N-S-E-W) .......... 21 Figure 1: PORV Nozzle - DW + Thermal . 16 Figure 2: PORV Nozzle - OW + Thermal Stratification 18 Figure 3: Pressurizer *spray Nozzle - OW + Thermal . 20 Figure 4: Pressurizer Surge Nozzle - OW + Thermal.... . 22 LIST OF APPENDICES APPENDIX A: Nozzle Loads APPENDIX B: crack Profile and Orientation ABB Combustion Engineering Nuclear Power ~nrm # 0090257-8 !Rev. 7 1901 00 Rev

  • 1.0 PURPOSE 1111 1119 ASEA BROWN BOVERI P-MECH-CALC-019 00 Calculation Number Rev.

5" of 23 Page Number On September 16, 1993, a crack in the CPCo - Palisades Plant Power-Operated Relief Valve (PORV) nozzle safe end was discovered as the plant was heating up to Hot Standby conditions (see Reference 1). This calculation is part of the Engineering Services provided to Consumers Power Company per Reference 2. This calculation is being performed to determine axial stresses in the PORV Nozzle to aid in the determination of the loads responsible for crack initiation. The conditions for which stresses will be determined include normal operating, as well as a postulated thermal stratification condition. This calculation is also being performed to determine axial stresses in the Inconel Pressurizer Spray and Surge nozzle safe ends as a result of normal operating loads. 2.0 SCOPE Each of the following types of loadings on the nozzle safe ends will be evaluated to determine their contribution to total axial stresses for all three nozzles:

1.

Axial forces due to pipe and pressurizer thermal expansion and due to gravity (deadweight)

2.

Bending moments due to pipe and pressurizer thermal expansion and due to gravity (deadweight)

3.

Internal pressure The resultant effect of these three types of loadings will be ABB Combustion Engineering Nuclear Power Fnrm II 0090257-Fl !Rev. 7'90l

II 19 ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number of 23 Page Number determined by first evaluating the stress effects for each of them separately and then algebraically adding them. 3.0 DATA AND ASSUMPTIONS 3.1 Dimensions It is assumed that the stresses resulting from the various loads act upon a uniform cross-section of inside diameter, D., and outside diameter, D. There is no consideration 1 0 given to stress intensification or stress concentration factors. 00 Rev

  • The dimensions which will be used for the nozzle safe ends are conservatively taken to be the same as the pipe to which they are attached.

These dimensions are as follows: PORV Spray Surge D. (in) l 3.624 3.624 10.50 D0 (in) Pipe Size*. 4.50 4-inch, SCH 120 4.50 4-inch, SCH 120 12.75 12-inch, SCH 140 Nominal pipe sizes for the respective lines come from Reference 3. Pipe schedules come from Sheet 1/CC, Rev. 17, of Reference 4. Dimensions for the pipe come from page 27 of Reference 5. ABB Combustion Engineering Nuclear Power O~rm a 0090257-B !RP.v. 7'901

II 19 ASEA BROWN BOVERI 3.2 Forces and moments P-MEGI-CALC-019 00 Calculation Number Rev. 1 of 2.3 Page Number Forces and moments produced by gravity (deadweight, or OW) and normal thermal expansion (Thermal) are given in Appendix A. Of these forces and moments, the ones that are applicable to this calculation are given below: PORV - DW PORV - Thermal Spray - DW Spray - Thermal Surge - DW Surge - Thermal F (lb) y -231 -3116 -372 -639 -2358 952 M (ft-lb) x 158 -2151 -158 -1051 -5749 3557 M (ft-lb) z -273 -798 -1352 -1893 -14360 10138 Forces and moments produced by the (postulated) thermal stratification (Th. Strat.) condition for the PORV nozzle were determined in Reference 6. The forces and moments which apply to this calculation are given below: PORV - Th. Strat. -3579 M (ft-lb) x -2155 ABB Combustion Engineering Nuclear Power Cr,rm a 0090257-Fl IRP.v 71901 Mz (ft-lb) 7955

3.3 Internal Pressure Al 1111 ,.,1919 ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number 9 of 23 Page Number The internal pressure used in this analysis is 2085 psi, which is the normal service pressure for all three lines (page l/CC, Rev.12 and page 2/CC, Rev. 18 of Ref. 7). 3.4 PORV Nozzle crack Location In order to determine the axial stress produced by the various loads at the PORV nozzle crack location, it is necessary to determine the orientation of the crack with respect to the global axes X and z. 00 Rev. Per Reference 8, it is seen that the first horizontal run of the PORV line from the pressurizer is oriented at a (-)30° horizontal angle from the N-S axis. It will be assumed that the midpoint of the crack is located on a line at a horizontal angle of +120° from the first horizontal run of the PORV line from the pressurizer (see location B on Figure 1) ; this line corresponds to the global (-)Z axis. Location B roughly corresponds to the midpoint of Section C on the figure on pages B3 and 85 of Appendix B. The ends of the crack will be approximated to be located at +/-40° with respect to B (see A and c on Figure

1)
  • ABB Combustion Engineering Nuclear Power

~"'"' :t 0090257-fl !Rev 7'901

4.0 ANALYSIS jl II ,.llll ASEA BROWN BOVERI 4.1 AXial stresses due to Axial Forces P-MECH-CALC-019 Calculation Number 9 of ? '2 Page Number The contribution to the total axial stress due to thermal expansion and deadweight axial forces acting on a nozzle safe end is determined using the following equation: ax ::::; F I A y x (Ref. 9, p. 5) where: ax is the axial stress; Fy is the force acting in a direction coincident with the nozzle axis; and Ax is the cross-sectional area of the safe end. 00

  • Rev.

The axial force, Fy, produces a uniform stress for all points in the safe end cross-section. (For the Surge nozzle only, the sign of the force will be effectively reversed to account for the fact that global vertical forces acting on the nozzle - at ~he bottom of the pressurizer - have an opposite effect compared to the other two nozzles - at the top of the pressurizer.) 4.2 Axial Stresses due to Bendinq Moments The contribution to the total axial stress due to thermal expansion and deadweight bending moments acting on a nozzle ABB Combustion Engineering Nuclear Power F~rm # 0090257-Fl IAev 7'901

jl 1111 ,.,1111 ASEA BROWN BOVERI P-MEGI-CALC-019 Calculation Number 10 of Z.!i Page Number safe end is determined using the following equation: a = Mc / I x where: (Ref. 9, p. 133) a

  • is the axial stress; x

M is the bending moment at a point (for all three nozzles, bending is provided by the Mx and Mz components) ; 00 Rev. c is the distance from the neutral axis to the point on the cross-section; and I is the Moment of Inertia for the cross-section. The stress at a point due to a bending moment is a function of both its radial location and its circumferential location. This calculation will determine stresses at various locations on the cross-section of each safe end at both the inside and outside surfaces. In order to determine the stress at a point as a function of location on the circumference, the following equation is used: where: ~~rrn ti 0090257-fl IRf'v. 7 1901 8 is the circumferential angle with respect to the +X (South) axis (e.g., see Figure 1); ABB Combustion Engineering Nuclear Power

1111 1919 ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number II of 23 Page Number the net moment (i.e., MxsinO + MzcosO) produces a tensile stress when it is positive and a compressive stress when it is negative. (For the Surge nozzle only, the signs of the moments used in this term will be effectively reversed to account for the fact that global moments acting on the nozzle - at the bottom of the pressurizer - have an opposite effect compared to the other two nozzles - at the top of the pressurizer.); and c is either the inside radius or the outside radius (for either the inside surface or outside surface, respectively). 00 Rev. For all nozzles, stresses will be calculated for the inside and outside surfaces at the +X (South), -X (North), +Z (West) and -z (East) axis locations. Additionally, for the PORV nozzle, stresses will be calculated for the approximate location of the crack. 4.3 Axial Stresses due to Internal Pressure The contribution to the total axial stress due to internal pressure is determined using the following equation: ax = F I Ax or ax = PAi / Ax where: ABB Combustion Engineering Nuclear Power Cn,.,, d nQ90257-B !Rev. 7 1901

jl 1111 ,.,1111 ASEA BROWN BOVERI P-MECH-CALC-019 00 Calculation Number - Rev. IZ of 23 Page Number F is the force produced by a pressure (P) acting over the inside area of the safe end (Ai= nof/4); and

  • Ax is the cross-sectional area of the safe end (Ax =*n(D~-of)/4)).

4.4 Maximum. AXial Tensile stress This calculation will also determine the maximum axial tensile stress, and its circumferential location.on the cross-section, for each of the nozzles, using the following equation: ax = ax (axial force) + ax (maximum moment stress) + ax (pressure) where: o,,,m a 0090257*A IRP.v 7 901 ax (maximum moment stress) is calculated using the resultant moment, Mt (Mt= (M~ + M;)o.5) ABB Combustion Engineering Nuclear Power

5.0 RESULTS jl,., ASEA BROWN BOVERI P-MECH-CALC-019 00 Calculation Number Rev

  • 13 of z:,

Page Number The axial stresses for the PORV, Spray and Surge nozzles are presented on the following pages. The Tables were developed using Lotus 1-2-3, v. 3.4a. Stress values are calculated by_ Cell Formulae, using appropriate input data. ABB Combustion Engineering Nuclear Power Cnrm d 0090257*8 IRP.v 7'901

jl 1111 ,.,1919 ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number ILf of Z.3 Page Number TABLE 1A: PORV Nozzle - DW +Thermal Load Axial Stresses (N-S-E-W) Inside D 3.624 inches Outside D 4.5 inches Fy -3347 lb Mx -1993 ft-lb Mz -1071 ft-lb Pressure 2085 psi Fy Stress -0.60 ksi Pressure Stress 3.85 ksi Max. Moment Stress (ksi) Max. O'all Stress (ksi) Min. O'all Stress (ksi) N 180 INSIDE 2.00 1.40 5.25 OUTSIDE 2.48 1.88 5.73 (+) s 0 -2.00 -2.60 1.25 -2.48 -3.08 0.77 Mt x-sectA INSIDE OUTSIDE 4.22 5.24 7.47 8.49 -0.97 -1.99 Axial Stress (ksi) E w 2263 ft-lb 11.66 inches "4 5.59 inches "2 Location 242 deg. 90 -90 deg. -3.72 3.72 Moment only -4.31 3.12 Moment + Fy/A -0.47 6.96 Moment + Fy/A + Pressure -4.61 4.61 Moment only -5.21 4.02 Moment + Fy/A -1.37 7.86 Moment + Fy/A + Pressure ABB Combustion Engineering Nuclear Power "~rm Jt n090257-fl IRP.v 71901 00 Rev.

1111 1911 ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number 15 of Z.3 Page Number TABLE 18: PORV Nozzle - OW+ Thermal Load Axial Stresses (A-8-C) Inside D Outside D Fy Mx Mz Pressure Fy Stress Pressure Stress 3.624 inches 4.5 inches -3347 lb -1993 ft-lb -1071 ft-lb 2085 psi -0.60 ksi 3.85 ksi Max. Moment Stress (ksO Max. O'all Stress (ksi) Min. O'all Stress (ksO (+) Axial Stress (ksi) A 8 130 90 INSIDE -1.56 -3.72 -2.16 -4.31 1.69 -0.47 OUTSIDE -1.94 -4.61 -2.54 -5.21 1.31 -1.37 Mt I x-sect A 2263 ft-lb 11.66 inches "4 5.59 inches "2 INSIDE OUTSIDE Location 4.22 5.24 242 deg. 7.47 8.49 -0.97 -1.99 c 50 deg. -4.13 Moment only -4.73 Moment + Fy/A -0.88 Moment + Fy/A + Pressure -5.13 Moment only -5.73 Moment + Fy/A -1.88 Moment + Fy/A + Pressure ABB Combustion Engineering Nuclear Power "~"n d 0090257-Fl IR~v 7"901 00 Rev.

-x NORTH jl 1111 Jll\\1111 MAX (+I ASEA BROWN BOVERI -z EAST B +z WEST P-MECH-CALC-019 Calculation Number Page Number ~----___._.., +X J ) SOUTH I ~3QD Note: This Figure should be viewed in conjunction with Tables 1 A and 1 B. FIGURE 1: PORV NOZZLE - DW + THERMAL ABB Combustion Engineering Nuclear Power

  • nrm a 0090257-8 IRP.v. 7'901 00 Rev.

jl 1111 ,.,1919 ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number It of 23 Page Number TABLE 2: PORV Nozzle - OW+ Thermal Stratification Load Axial Stresses (A-8-C) Inside D Outside D Fy Mx Mz Pressure 3.624 inches 4.5 inches -3810 lb -1997 ft-lb 7682 ft-lb 2085 psi Fy Stress Pressure Stress -0.68 ksi 3.85 ksi Max. Moment Stress (ksi) Max. O'all Stress (ksi) Min. O'all Stress (ksi) (+) Mt x-sectA INSIDE OUTSIDE 14.80 18.38 17.97 21.54 -11.63 -15.21 7938 ft-lb 11.~ inches "'4 5.59 inches "'2 Location -15 deg. Axial Stress (ksi) A B c 130 90 50 deg. INSIDE -12.06 -3.72 6.36 Moment only -12.74 -4.40 5.67 Moment + Fy/A -8.89 -0.56 9.52 Moment + Fy/A + Pressure OUTSIDE -14.97 -4.62 7.89 Moment only -15.66 -5.30 7.21 Moment + Fy/A -11.81 -1.46 11.06 Moment + Fy/A + Pressure ABB Combustion Engineering Nuclear Power ""'m d n090257*R IRPv 7'901 00 Rev.

-x NORTH II 19 ASEA BROWN BOVERI -z EAST B +Z WEST P-MECH-CALC-019 Calculation Number 10 of 23 Page Number +X SOUTH MAX (+) ~30° Note: This Figure should be viewed in conjunction with Table 2. FIGURE 2: PORV NOZZLE - DW + THERMAL STRATIFICATION ABB Combustion Engineering Nuclear Power o~,m d 0090257-fl *I Rev 7 '901 00 Rev.

jl 1111 ,.,1919 . ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number 19 of 23 Page Number TABLE 3: Pressurizer Spray Nozzle - OW + Thermal Load Axial Stresses (N-S-E-W) Inside D 3.624 inches Outside D Fy Mx Mz 4.5 inches -1011 lb Pressure Fy Stress Pressure Stress -1209 ft-lb -3245 ft-lb 2085 psi -0.18 ksi 3.85 ksi Max. Moment Stress (ksO Max. O'all Stress (ksi) Min. O'all Stress (ksO N 180 INSIDE 6.05 5.87 9.72 OUTSIDE 7.51 7.33 11.18 (+) s 0 -6.05 -6.23 -2.38 -7.51 -7.69 -3.85 Mt I x-sectA INSIDE OUTSIDE 6.46 8.02 10.12 11.68 -2.79 . -4.35 Axial Stress (ksO E w 3463 ft-lb 11.66 inches "4 5.59 inches "2 Location 200 deg. 90 -90 deg. -2.25 2.25 Moment only -2.44. 2.07 Moment + Fy/A 1.41 5.92 Moment + Fy/A + Pressure -2.80 2.80 Moment only -2.98 2.62 Moment + Fy/A 0.87 6.47 Moment + Fy/A + Pressure ABB Combustion Engineering Nuclear Power ""'m d 0090257-8 IRev. 7'901 00 Rev.

-x NORTH MAX (+) II 19 ASEA BROWN BOVERI -z EAST +z WEST P-MECH-CALC-019 Calculation Number ZO of 2.3 Page Number Note: This Figure should be viewed in conjunction with Table 3. +X SOUTH FIGURE 3: PRESSURIZER SPRAY NOZZLE - OW + THERMAL ABB Combustion Engineering Nuclear Power ~'"lrm tJ 0090257-8 fRP.v. 7'90l 00 Rev.

II 19 ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number 21 of 23 Page Number TABLE 4: Pressurizer Surge Nozzle - OW +Thermal Load Axial Stresses (N-S-E-W) Inside D Outside D Fy Mx Mz Pressure Fy Stress Pressure Stress 10.5 inches 12.75 inches -1406lb -2192 ft-lb -4222 ft-lb 2085 psi 0.03 ksi 4.39 ksi Max. Moment Stress (ksO Max. O'all Stress (ksi) Min. O'all Stress (ksQ N 180 INSIDE -0.38 -0.35 4.05 OUTSIDE -0.46 -0.43 3.97 (+) s 0 0.38 0.41 4.81 0.46 0.50 4.89 Mt . I x-sect A INSIDE

  • OUTSIDE 0.43 0.52 4.86 4.95 4.00 3.91 Axial Stress (ksO E

w 4757 ft-lb 700.55 inches ""4 41.09 inches ""2 Location 27 deg. 90 -90 deg. 0.20 -0.20 Moment only 0.23 -0.16 Moment + Fy/A 4.63 4.23 Moment + Fy/A + Pressure 0.24 -0.24 Moment only 0.27 -0.21 Moment + Fy/A 4.67 4.19 Moment + Fy/A + Pressure ABB Combustion Engineering Nuclear Power f:~rm 11 <1()90257-Fl IRev 7'901 00 Rev.

-x NORTH I ASEA BROWN BOVERI -z EAST +z WEST P-MECH-CALC-019 Calculation Number

z of 2..3 Page Number MAX

(+)

+~ +X SOUTH Note: This Figure should be viewed in conjunction with Table 4.

FIGURE 4: PRESSURIZER SURGE NOZZLE - DW + THERMAL ABB Combustion Engineering Nuclear Power o~,m 11 0090257-'l IR~v 7 '90! 00 Rev.

6.0 REFERENCES

jl 1111 ,.,1919 ASEA BROWN BOVERI P-MECH-CALC-019 Calculation Number 23 of 23 Page Number

1.

Consumers Power Company, Palisades Plant, "Pressurizer Safe End Crack Engineering Analysis and Root cause Evaluation - Docket 50-255," October 7, 1993. 00 Rev.

2.

Consumers Power Company, Palisades Generating Plant Purchase Order C0008242, 09/29/93.

3.

Consumers Power company, Palisades Plant Piping and Instrumentation Diagram, Drawing No. M-201, Rev. 31.

4.

Consumers Power Company Palisades Plant Piping Class Sheet, Palisades Drawing No. 5935-M-260.

5.

CRANE co. Engineering Data catalog, VC-1900A, 1976.

6.

"Thermal Analysis of the Palisades PORV Line Including the Effects of Thermal Flow Stratification," ABB-CE Calculation No. P-MECH-CALC-017, Rev. 00.

7.

Consumers Power Company Palisades Plant Piping Class Summary, Palisades Drawing No. M-259.

8.

Consumers Power qompany Palisades Plant Stress Isometric - Pressurizer Safety & Relief Valve Discharge, M107, Sheet 2154, Rev. 05.

9.

Singer, Ferdinand, strength of Materials, Second Edition, Harper and Row, New York, 1962. ABB Combustion Engineering Nuclear Power Onrm

  • 0090257-8 IRP.v 7'90!

APPENDIX A Nozzle Loads P-MECH-CALC-019, Rev. 00 Page Al of AS Fax correspondence from s.c. Ramalingam (Consumers Power Co., Palisades Nuclear Plant) to P. Hammer (ABB-CE), October 21, 1993.

OCT 21 '93 13:09 FROM CPCO PALISADES SUPPOR TELECOPfER MESSAGE CONSUMERS POWER COMPANY 27780 Blue Star Highway Covert, Mf 49043 P-MEQ-I-CALC-019, Rev. 00 Page A2 of AS PAGE.001 Far Assistance and Yerif1cat1on Calli "lll!Jllllllll TO: IWIE1 PAVL. HfrtlUI#?.. FJRJI: 0$.B=f;/;9 TELEPHONE1 (d'ri,jJ ;(&57-.'lf,qt. m.ECOPIER NUllBERz ~g):Jos=.3.;:253 FROM: NAllEs SV-BEsH C. 8/tMttL TNG/H'1 FIRlh CONSUlfERS pmmt CO!lflMY, PALISME$ PUKC TELEPHONE:.....J** TELECOPIER NUllBER:............ l__ __ DATE TRAHSJIITTm: 'o/~fls PASES TO FOLLOlh __ .3 __ _ CONJIENTS: G:\\NECO\\FORMS\\FAXFORM

0 0. ~ 0:: ' °' r-1 0 Lf1 I "1; 84-l 6 0 IM 5 "1; ~~ I !O 0.. 0.. N ISi ISi UJ (!l a: [J._ Cl: 0 [J._ [J._

J UJ lO UJ Q a:

UJ ~ _J CI [J._ 0 u [J._ u

E:

0 Cl: ll. CIJ ISi.. [') [') (1J (\\J 1--u 0 PORV Nozzle Loads (ADLPIPE node 605) With four stiff elbows Force fib.* Moments fft_.b.) CASES Fx Fv Fz Mx Mv Mz: Deadwelaht -44 -231 18 158 . 24 -273 Thermal -5237 -3118 -2293 -2151 -1883 -798 Force fib.I Moment ft-lb.) CASES Fx Fv Fz: Mx Mv Mz OTC* -1700 -529 -1087 -2222 582 3483 OBECw/ Steam) 79 37 48 102 93 123 OSErwl Water. 88 43 54 108 98 136 OTC ="' Once Through Coollng loads Directions +X South -X North +Y UD .y Down +Z West -Z East

OCT 21 '93 13: 10 ~ 156 E. A. S. FROM CPCO PALISADES SUPPOR .14-1+9 CALCOLA'l'ION SHEE'l' P-MECH-CALC-019, Rev. 00 Page A4 of AS PAGE.003 Sht '2./ of --- JOB NAME: PALISADES NUCLEAR Pt.ANT 200-91 CALC. HO. EA-SP03359-0l EAS JOB NO. CUSTOMER: CONSUMERS POWER CO. BY ~ DATE /1/S~ CJm DATE 11/'1/4 '/ EQUIPMENT LOAD SCMMARY "EQUIPStJM" Rev. 1 EQUI~DiSIGNA'l'IOH: ------~RESSUlllZER, T-72) NODE POINT:

>55, Surq* Nozzle

.,-----------==-""""'-------=-=..... --------.a..--...,;;;...._...............-.-.....,,_...._,..__ LOAD FORCES (lb) MOllBH'l'S (~t-lb)

~-

~---

COMBINATIONS FX FY FZ =;-=:::::::=:,,,,,,,,=======----- -=a----- ------- ------- OEADWEIGBT 18 - 2358 -1 THERMAL 9 9!52 6323 SEISMIC OBE 838 °1810 2344 SEI:SMIC SSE 1676 3620 4688 SAM ODE 0 0 0 SAM SSE 0 0 0 NORMAL 27 -1406 6322

~-

UPSET [+] ( l) 865 404 8666

~--------

UPSET [-] (1) 820 4168 2345 FAULTED [+] (1) l 703 2214 11010 FAULTED [-] (1) 4689 =~~------ = ALLOWABLES 310000 *

=====~--=s="""""== -'=-===--~ =......=====-= =;;-=---

MX MY MZ

==*-w -5749 -377 -14360 -~----- 3557 -68855 10138 12924 13396 29639 25848 26792 59278 0 0 0 ---~--- 0 0 0 -2192 -69232 -42:il2 10732 13019 25417 18673 82628 43999 23656 26415 55056 31597 96024 73638 =---- =-* 130000 **

  • ALLOWABLE SHEAR FORCE = 210 OOOlb.
    • ALLOWABLE BENDING MOMENT=7~,000ft-lb SEE PAGE A'rl'ACH C1 TO CB lo:"" /S'~, 2 3)

QUALIF:ICAI'l'ON. I (+Y) I --..... +x) II (NORTH = -X) (WEST = +Z) (UP = +Y) LOAD COMBINATIONS: . (+Z) NORMAL = OEADWEIGHT + THERMAL UPSET ri DEADWEIGHT + THERMAL + SEISMIC OBE + SAM OBE UPSET. "" DEADWEIGHT + THERMAL + SEISMIC OBE + SAM OBE FAlJLTE +j "" DEADWEIGHT + THERMAL + SEISMZC SSE + SAM SSE FAULTED '"" DEADWEIGHT + THERMAL + SEISMIC SSE + SAM SSE NOTES: f H FOR t~~ CASE ONLY POSITIVE THERMAL LOADS ARE USED IN SUMMATION FOR CASE ONLY NEGATIVE THERMAL LOADS ARE USED IN SUMMATION

P-MECH-CALC-019, Rev. 00 Page AS of AS OCT 21 '93 13: 10 FROM CPCO PALISADES SUPPOR Pi:lGE.004 F.:!.&& nq.qg E. A. S. CALCOUTIOM SBEB'l' Sht Z!_ ot __ JOB HAllBs EAS JOB HO. CUSTOJIER: PALISADES NUCI.li:AR PLANT 200-91 CALC. HO. EA-SP03361-0l COllStJJIBRS POWER CO. BY ~ DATE '3 /o/9L CD DA'l'E ~/11 t!fZ EQUZPllBH'r UJAD StDlllARY "'EQUXPBUJI" Rav. 1 EQCJ:PMBll'l' DBS:IGHA'fiOH: ------>CT-72 PRBSStJRJ:ZBR SPRAY irozzLi) HODB POUl'r: l "RDB a* LOAD COKBIHA'l'IOH& FORCES (lb) JIDllBHTS (ft-lb)

* *----------~

FX FY FZ JIX KY IDS DBADWBIGB'l' 54 -372 26 -158 -209 -1352

--~

TBBRKAL 310 -639 -46 -10!51 -745 -1893 SBISJa::C OBE 251 753 487 1373 I 27!53 2729 SEISJllC SSB 502 1506 974 2746 5506 54!58 ---~.. --- SAM OBB 0 0 0 0 0 0 SAM SSE 0 0 0 0 0 0

*-------1-------*-~----* *-------*-------*-------

*-------1-------1------ ----- -------- -------

*------- ------- ~---- -------- ------ ------

NORMAL 364 -1011 -20 -1209 -954 -3245

~-------------- ------- ------- ----- -------

--~- ---~ UPSET [+] (1) 615 381 513 1215 2544 1377 UPS BT [-] (1) 197 1764 507 2582 3707 5974 FAULTED [+] (1) 8&6 1134 1000 2588 5297 4106 FAULTED C-J (l) 448 2517 994 3955 6*60 8703 =-- ALLOWABLBS 60000 7100

  • ALIDWABI& SBBAR FOR.CB -

19000 LBS

    • ~

BDl>llG MOKEHT= *SOOP"l'-LB (REF. 15A, 38) I (+Y) I (+X) I (HOR'l'H = -X) (WBS'l' = +Z) (UP - +Y) LOAD COMB:IHAT:IONS: (+Z) ~~&+j UPSET FAULTE + FAULTED -) NOTES: BJ ~: f~] = DEADWE:IGHT + THERMAL

a DEADWE:IGHT + THERMAL + SEISMIC OBE + SAX OBB

= DEADWB:IGHT + THERMAL + SE:ISJIIC OBE + SAM OBB = DEADWEIGHT + THERMAL + SEI:SMI:C SSE + SAM SSE DEADWEIGHT + THERMAL + SE:ISMI:C SSE + SAX SSE CASE ONLY POSI:T:IVE THERMAL LOADS ARE USED IH StJJOIATI:OH CASE ONLY HEGATJ:VE THEmlAL LOADS ARB USED :r:B SUMMAT:IOH

    • TOTRL PAGE.004 **

APPENDIX B P-MECH-CALC-019, Rev. 00 Page Bl of 85 Crack Profile and Orientation pages Bl through B3 Fax correspondence from J. Wong (Consumers Power Co., Palisades Nuclear Plant) to B. Lubin (ABB-CE), November 19, 1993. pages B4 through B5 Fax correspondence from J. Wong (Consumers Power Co., Palisades Nuclear Plant) to. P. Hammer (ABB-CE), November 22, 1993 (first two pages).

P-MECH-CALC-019, Rev. 00 Page 82 of BS NOU 19 '93 12:46 FROM CPCO PALISADES SUPPOR PAGE.001 CONSUMERS POWER COMPANY 27780 Blue Star Highway Coven. Ml 49043 T. 1*1,._,_..

  • Far.... --... v......... cal:

"""----..A~B-.-B._..C.._G Tll1_..... __.z..o;;..;;....;.:,_-_2-_S...._~_-_t.t-_?_~_"° __ _ TI UJ' F....... ________ Conuuwu* J p V l. Aj:l.ac.. L.'4 -;~ \\Wl-Or<. . ~e

NOU 19 '93 12:46 FROM CPCO PALISADES SUPPOR P-MECH-CALC-019, Rev. 00 Page BJ of BS PAGE.002 METALLURGICAL SECTION LOCATIONS \\) JEvJ LOOt<WGt UP fR.o/Y\\ p~so RtZctl NOTE: CONDITION OF ROOT UNKNOWN FOR SECTIONS B & E. ALL DIMENSIONS ARE APPROX. EXTENT OF r.o. CRACK APPARENT BY VISUAL EXAM ABOUl

  • 2Y,z*. ';)/

~* K~ '\\~ R~~~ CUT CUT ""~ KNOWN EXTENT OF LACK OF FUSION BY CROSS SECTION c~* BETWEEN CROSS SECTIONS>

    • TOTAL PAGE.002 **

NOV 22 '93 13:02 FROM CPCO PALISADES SUPPOR P-MECH-CALC-019, Rev. 00 Page 84 of 85 PAGE.001 CONSUMERS POWER COMPANY 27780 Blue Star Hlghw*y Covert. Ml 49043 Th;' ~I Tea -.. P~JL -f:ffirno1.ter ABS-CE T........ 2.0~ - 2.-S~ - "J..q..5" q_ t:1h1 ale........, "U:>3 -1..BS -~ ~~ T11

  • 1 Niau.. ________

.......,.... __ 3 ___ _ Conuaw** r:". Tt l.L..I ~-- .5ec.."'=loN:

-z G00"39t:ld P-MECH-CALC-019, Rev. 00 Page BS of BS ---~x . (So~)}}

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