ML20216A891

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Rev 0 to 22S-2-004M-207, Piping Stress Analysis of Subsystem 2RC-02
ML20216A891
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 04/18/1997
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20216A875 List:
References
22S-2-004M-207, 22S-2-004M-207-R00, 22S-2-4M-207, 22S-2-4M-207-R, NUDOCS 9709050156
Download: ML20216A891 (200)


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{{#Wiki_filter:..... ZRA97018 ENCLOSURE 2

                  - Zion Station Calculation No. 22S-2-004M-207 Piping Stress Analysis of Subsystem 2RC-02 r>

4709050yk[d$'s5 poR A poa m P

Sw /lH, e7 >. ZION CALCULATION COVER SHEET Zion Calculation No: 22S-2-004M-207 DESCRIPTION CODE: M04 SYSTEM CODE: RC ZION NUCLEAR STATION TITLE: PIPING STRESS ANALYSIS OF SUBSYSTEM 2RC-02 REFERF,NCE NUMBERS Type Number Type Number A EI)V SSL NPD SSYS 2RC-02

  ~D 3 )R            TBD-Zl-004                       SSYS                 2RC-03
  ~b 'I             __Zl-E XT- 12 2 9                  SSYS                2 3C-04
  ~PlOG                PIPSYS/PC Ver. 2.3              SSYS                2 3C-05 lOJ               9432-794 (S8 L) lOJ               4794 (Comed     l as   )            __2 1CO2TH l s  )              2 9CO2DGN COMPONENT EPN:                                             DOCUMENT NUMBERS:

EPN Comp Type Component Number Doc Type Document Number See Att. A S12 N/A _.pWG C M-516 CA _C- E \ G .22S-2-004- V -157 CA _C- E i _22S 2-002. V -2' 2 CA _C- E \ G 22S-2-002. V -2' 4 CA _C- E \ G 225-2-2013-006 CA _C- E N G 22S-2-202S-017 CA C- E \ G 22S- 3-300S-030 CA _C- E N G 775-3' -004M-215 3C 3-DCN 001289M 3 ROC ZEP 5.10 REMARKS: Total Number of Pages: 171 REV. REVISION APPROVED NO. DATE O Original Issue L , sh(8 //-/F -9 7

' tfective 5/24/96 PAGE NO.: .1.

s

S ., Athef.eenf 8 Comed c ic. xa 225-2-00m.202 gg Rev. No. 0 Cales. For: Pipe Support R6ES-2120 Node 183 Page f0 SJM*As n.w I X l Safety-Related l-] Non Safety-Related Project: Zion hoject No.: 09432-Prepared by: MA Date: l E% 47 Reviewed by: yy,p.r Date: j,)f -p7 A' V/ 4 Pd_h = 38.517 lbf Therefore, the self weight excitation loads are, FX ,w =Pd h- - FX ,w = 38.517 lbf S ( P'* 3 + Wbracket + Wclamp

  • Wpil FY ,, = (1 g 4 a s.)- g gg S

FZ ,w : Pdh - FZ 33 = 38.517 albf B Reaction at A: At top of top flange in line with pin. 3 FX :FX 33e + FX sw FX = 3 963+10 lbf Along with W14 FY = FY sse + FY 3w FY = 2.35610' lbf Vertical direction 3 FZ :FZ3se , FZ sw FZ = 4.267+10 lbf Perpendicular to W14 ey 3.25 in Distance from center of pin to top of top flange MX :FZ e y 4 MX = 1.387 10 *in Ibf MY :0 in Ibf MZ = FX e y MZ = 1.288 10' *in Ibf The reactions are in global axis, the effect of small skew is very insignificant. Therefore the effect is ignored. s 9

1 i ALLacd-ed B Comed caic. No. 22s.2.oo4u.2o7 gy Rev. No. O Cales. For: Pipe Support RSC-S.2120 Node 183 Page II yp,e n1 ' prs = [X ] Safety.Related { ] Non Safety-Related Project: Zion Project No.: 09432 787 Prepared by: N1 Date: l M 9 Reviewed by: i Date: e 79f( 7.y,/ n > no- f4ag Check the weld between rear bracket and the 1"X5"X5" plate Weld properties: based on 1" fillet weld kipsilooo Ibr ksi.5 E2 b :2.25 m d :2.23 in y: 6bi A w. : 2-(b. d) A w= 8.96 in S 7 :(3 b + d).d- S7= 6.675 in t 3 2 Sx :b S x= 6.705 *in i I p: I p= 14.986 in* Conservatively use the reaction at A to compute the weld force per inch. llFY MX MZ3 2 2 2 F /FX MY b- \+i- I,MY FZ d-weld ~ '(u A S x S 7j lA, g 2.!p) lA w 2-l p Fweld = 4.3l 10 3 b m t

                  'l m                 1/4" fillet weld weld : 4 F y_ weld 2 70 ksi E70XX electrode 0.3 F F                            v weld Iweld-1.6 w capacity =

Based on the weld for SSE load with 1.6 E allowable factor F w capacity

                             =5.94 b m

F pl_ capacity ::0.95 tweld F

                                                       - pl_ capacity = 4.936 5                             Governs y3                                           m
   \,

[. wr#

Atto c4.med 6 comed p3y Calc. No. 225 2 004M 207 Rev.No.O Cales. For: Pipe Support RSeS-2120 Node 183 Page la Jeud hm [ X ] Safety-Related 1,,) Non-Safety Related Project: Zion Project No.: 09432 Prepared by:

                                                                                                                        %AI[*'  Date: J.2 M 7 Reviewed by:                                             s, Date: j.7j G
x. rue 'w 1C wcld := F ICweld = 0.873 < l.0, therefore, O.K.

pl_ capacity Check the weld between the 1"X5"X5" nlate and I.P W14*30 steel beam: Since the loads for this weld are same as those for the rear bracket and same size of fillet weld were provided, the weld properties are higher than the previous one. Therefore the Interaction Coeflicient (l.C.) will be less than 0.873 by engineering judgment. No addition calculation is needed. Check intermediate plate.1"X5"X0'-5" long For simplicity, consider the plate as a fixed beam member subjected to vertical load, Lw = 8.96in Length of weld t p = l in Thickness of plate Wp= 5 in Width of plate P =Fweigt w L , = 5 in Span of the member L M=P-' M = 24.135 in kips 8 2 w .t S p =- E E Sp= 0.833 in 3 F b=b P Fb = 28.962 *ksi Fab = 0 95 F y IC Fb plate = F-- ICplate = 0.847 - < l.0, therefore, OK ab

AfhcAmeM 8 comed Calc. No. 225-2-004M-207 Rev. No. 0 (2uiL5 Cales. For: Pipe Support RSes 2120 Node isa Page I3 [ X ] Safety-Related 1 ] Non-Safety-Related Project: Zion Project No.: 09432-Prepared by: Nk Date:f 2 fro Reviewed by: 3, Date: g. y -

                                                                                        -ve          c Check local stress for IP steel beam W14X30 Per Ref. 2, the section dimensions for W14X30 are, d = 13.86 in -           -

br =6.7333 in t t = 0.383 in t g. = 0.27 in K = l in K g := b in 16 For flange attachment: b g. = 5 in b , = S in Per Ref. 4, on the IP steel, the misaligmnent is, e x = 0.25 in Flange bending stress bej = 2 b pt b, beg = 18.467 in Effective width bw e p -- - k, g D p= D p=1.031 m D D t =2d b, D t= 0.412 g 2 Sr= beg 6 St= 0.451 in' Mr .= FY D p+MXDt M= r 8.15 in kips f Mr fg= 18.052 ksi if = S g F, g = 19.08 ksi . Per Ref. 6, Table 37.6.6-2a fIf If

  • p IC g = 0.946
                                                    <l.0, therefore, O.K.

(

1 Atoc A ~c L 6 comed Calc. No. 225-2-004M-207 Rev. No. 0

                                                                                                  /&f/J Cales. For: Pipe Support R9es-2120 Node 183                                                                                    Page

{ X ] Safety-Related l ) Non-Safety-Related Project: Zion Project No.: 09432-767 Prepared by: Reviewed by: h Date: l- 28 4 7 a Date: ; - 7; - m m a. y,g,d Combined web stresses-Per Ref. 4, b e; :18.46 m bc2 : b , + 5 K be2 =10 m b ,3 = b , + 2 K b ,3 = 7 in 2 Sw= 0.224 in 3 Sw :bei 6 a 0.70 Since IP beam size smaller than W21 and free to rotate M w : FZ K + MX + FY e x Mw = 18.723 m kips f;w . FY 3 _Q _ ,_ M w b ,34% b ,3 tweb , S w f gw = 62.543 ksi Fa_lw = 24.74 ksi Per Ref. 4, Table 37.6.6-2a f* I Ic iw = 2.528 > 1.0, therefore N.G. Ic iw = F, jw Total stress: fgw + ftp Ic total :-- Ic total = 1.599 > 1.0, therefore N.G., local stiffner is required CONCLUSION: Based on the preceding calculation, it is concluded that the as built support is not adequate for the latest revised loads. t t

Aff.a.cA Sc*f 8 comed Calc. No. 225-2-004M 207 Rev. No. O R.LA6 - Cales. For: Pipe Support RSCS-2120 Node 183 Page 5

                                                                                                              ,m g, ,, y.

[ X ) Safety-Related 1,,) Non-Safety-Related Project: Zion Project No.: 09432-187 Prepared by: / h Date: 1 31- 0

  • Reviewed by: /4 M/d' Date: Fina47
s. ww.n f FCR 970014 Due to local stress failure, FCR proposes to provide stiffner on beam W14x30 on one side.

The stifTner on other side cannot be provided due to interference Two L3x3xl/4,1" apart are proposed as shown on FCR. LOCAL STRESS CIIECK with stiffners Reactions at top of flange: FX = 3.9633 10 lbf - MX = 1.38710' in Ibf FY = 2.35610' lbf , Aevt ewun$ s Comm er: \ For Wl4X30 Section dimensions A st., M Awort, oF sryet. cousruv~ MY = 0 *in Ibf (,A gb i n o N FZ = 4.26710' lbf MZ = 1.288 10' *in lbf d# b' d = 13.86 in t c = 0.383 *in K = 1 *in El " Io id t

       - b f= 6.733 *in                              tg    . = 0.27 *in           K g = 0.688 *in     o A,LT 4 6 ucese-i' c reitWes 6
  • Mon cA S AT cuts c w s ruw For flange attachment:

b w= 5 tn b a= 5 in e x= 0.25 in Since the stiffner provided on one side only, effective width considered is b (Ocmenv ) b ej :b ,+ 2-(d- 2 K) I + 2-f beg = 23.593 in (

4 i Affa.cdsod S comed Calc No. 225-2-004M 207 Rev. No. 0 Cales. For: Pipe Support-RSGB-2120 Node 183 Page S

                                                                                       ,n,   pwL

[ X ] Safety-Related [ ] Non-Safety-Related Prepared by: Date: J- 31 -3') Project: Zion PEoject No.: 09432-M7 Reviewed by:

                                                               %                    #r--/:-9.-   Date: if,w 37 W.wisit I'

Sr b,j f e 8 S r= 0.577 *m D p= 1.031 in D t= 0.413 M r = FY D p + AE D g M r= 815 in kips I Mr flange _with_stitYner '* I tlange;with_stiffner = 14.129 ksi Fa_nange .= 19.08 ksi f flange with stifInct

                                                ~

IConge bending stess *

                                                     ~

F a_nange IC nange_ bending _ stress = 0.741 < l.0, Therefore O.K. [6"W d J

1 ' AtGe k+Bd S Om Calc. No. 225-2-004M-207 Rev. No. 0 - Ac.Rh Cales. For: Pipe Support-RSCS-2120 Node 183 Page M

                                                                                                 ,,v ,,m l X ] Safety-Related [ ] Non-Safety-Related                       Prepared by:               M                                           Date: 1- 3 )- %

Project: Zion Project No.: 09432-187 Reviewed by: /4. g 4 ' Date: h7N4 7 1%

d. n 'wa r Combined Web Stress :

The web subjected to total moments about X axis is M w FZ K + hL FY e x Mw = 18.723 in kips The section to resist Mw will be as below I b l , i I l , I ' r__ __ _l_. - . _ _ _ __ _ _ i t 1 I,

                                              ,,, I Mw is about Y-Y axis Compute section property about Y-Y.

bes beg b ,3 = 23.593 in t = 0.25 in b = 3.0 in d = 2.75-in t w= 0.27 s 2 2bt tw+d+ +2dtt g. + +b c3 2bt+2dt+b e3 t w x = 0.848 *in ( o

V puaehed 8 comed Calc. No. 225-2-004M-207 Rev. No. 0 i Cales. For: Pipe Support It9CS-2120 Node 183 Page p l X ] Safety-Related [ ] Non-Safety-Related Prepared by: M Date: 131-87 Project: Zion PFoject No.: 09432-157 Reviewed by: LW$ Date: DINf7 g .8 %gf l yy 22' +2bt t w+d. -x + 2 t. -x +b c3

                                                                           . 2.d t tw+                            .
                                                                                                                       +b es t g   x-
       ! y_y = 12.939 *in' X

top : t w+d+4-x S y_y IJ 8

              ,                              S y_y = 5.342 *in top Mw I

web _with_stiffner {y y - I web _with_stifInera 3.505 ksi F a_ web : 24.74 ksi f jC web with_stiffner web with stiffner F a_ web Ic < l.0, Therefore OK # d rw rWE s do T& : web _with_stiffner = 0.142 g ga g,g w < t.u

                                                                   .L.                                      apr upgf A L Aur )Mrd l'F Check weld of stiffner ancies to flance of WI4X13                                                       gypa re. os Angles L3x3xl/4 are welded to flange on external side only.

They are proposed to be installed 1" apart back to back. Conservatively and for simplycity consider sum of minimum weld property of anglehvhich will be less than actual minimun'pveld property if computedconsidering both angle welds together,4 {doMewv b i

1 Attache *~t G Om Calc. No. 225-2-004M-207 Rev.No.O RCM Cales. For: Pipe Support RSC5-2120 Node 183 Page 14 [ X ] Safety-Related [ ] Non-Safety-Related Project: Zion Prpject No.: 09432 'M7 Prepared by: Reviewed by: MM Af'-- m $ Date: 9] Date: Ji m 17

                                                           ~1%

t(. M wit:? b : 3 in d :3.in 2 S _., b fb+4d w 6 it2d b Su= 5 in 2 Mw I weld 3w fweld " 3 745

  • m for 3/16 in. weld, t: 3.in 16 Fy_ weld = 70 ksi Fy = 36 ksi p  :
                               .3 Fy_ weld t l.6 2

F w capacity

                            = 4.455 b m

0.95 F F -t base _ metal _ capacity : F base _ metal _ capacity = 3.702 b m 45 IC : 3.702 IC = 1.012 ~ 1.0 OK since conservative yy/ i

s Ad* k^8"U b Calc. No. 225-2-004M 207 w, Rev. No. 0 Cales. For: Pipe Support RSES 2120 Node 183 Page 2

                                                                                                                  ,m ,, m_

[ X j Safety-Related [ ] Non Safety-Related Prepared by: M Date: 1 T1 Project: Zion P'ioject No.: 09432-787 Reviewed by: /6 MPH Date: MN17 K.ft'Gwlf Weld of stiffner to web is adequate by Engineering Judgement since web stress is small. CONCLUSION FCR is acceptable - A DOf li i-

2 PW: L 3/?l97 hf&c$ wad 0 Comed Calc. No. 225-2-00m 207 RCL5 Rev. No. O Cales. For: Pipe Support RS66-2123A Node 227 Page 2I

                                                                               .Sen o one.

[ X ] Safety-Related [ ] Non-Safety-Related Prepared by: MM Date: l'7A M Pro. lect: Zion Pro.iect No.: 09432- W Reviewed by: At&4 7 M Date: i- % -M A'. d. A r n File Name: rcr2123a.med PIIRPOSE / OBJECTIVE: To qualify the support RCRS-2123 A of subsystem 2RC-02 at node 227 for the increased loads per revised stress analysis. METIIODOI,0GY AND ACCEPTANCE CRITERIA: The support components will be evaluated by detailed calculation per project design criteria to determine acceptabusy of the support. In case the dimensions or design data are not available , the conservative assumptions will be used to perform the calculation. ASSliMPTIONS: No unverified assumptions for this support DESIGN INPITT /

REFERENCES:

1. Ziori Design Criteria DC-SE-01-ZN Rev. 7.
2. Zion Seismic Design Criteria DC-SE-002-ZI Rev. 3
3. SDS E37, Rev. 6.
4. AISI manual of Steel Construction,7th Edition.
5. PSA Catalog..
6. Design Drawing for support RCRS-2123 A, Rev. 2
7. STAAD-III User's Manual, Program No. 03.7,065-20.2

( 2

1 Allacf ~s A C g Calc. No. 225-2-004M-207 pq Rev. No. O Cales. For: Pipe Support RSC5-2123A Node 227 Page 2L f . m ,r:. / o - l X ] Safety-Related [ ] Non-Safety-Related Project: Zion Project No.: 09432- W Prepared by: M Date: 113 V Reviewed by: /Wc.4X Date: i le-D H't A.4.hrn

      - cal CUI ATION:

Data for desien: Per design drawing (Ref. 6), PSA-10 W / 2" $ schedule 80 pipe extension and 6"$ pipe clamp at El. 638'- 4" was installed. Pipe clamp is Fig. N636, E=10" Rear bracket for PSA-10, E=2.75"; Size 2.72" X 3.06" Component Wt.i Per Ref. 2 & 5

          %'psa 10 = 60.89 lbf        Wt. of PSA-10
          %' bracket = 6.15 lbf       Wt. of rear braket
          %' clamp = 45 lbf           Wl. of pipe clamp Wp = 4.18 lbf               Wt. of 2" pipe w , = 6 lbf                 Wt. of stiffner plate at clamp Seismic Response Spectra: Per Ref. 2, at 2% damping, the peak acceleration values of SSE at El. 654'-0" are as follows: (Reactor Bldg Spectra # RB10) 8 h = 2.35 g -        For both NS and EW a 3. = S 2.35 g + 1.0 g 3

From the revised stress analysis, tne maximum SSE movements are as follows: , AX = in AY = 2.5 in AZ:=. .in

 .(

5 1

t i Afirch-med B . L Comed Calc. No. 225-2-004M-207 gra Rev. No. O Cales. For: Pipe Support RSC-6-2123A Node 227 Page 23 lwc sw- [ X ] Safety-Related [ ] Non-Safety-Related Project: Zion Project No.: 09432 '28:7 Prepared by: [f%M Date: 1 2A U 7% Reviewed by: g4 Date: t-3 o -11 : e'. e m z The new design load for emergency condition is XMS lbs.

                                                                                                                                                    ,gekl 1(197 3

v680 Fz sk = 854tribf TSlO MIf7b/ Design axis X and Z used in this calculation are 26.38' skew to the global axis. For simplicity, AX and AZ being very small, are considered along design axis without transforming. The effect is negligible. 0 126.38-deg 0coga = asm 3 875 0 cold = 10.111 deg Snubber coordinate length (cold) X s= 29.875 sm(0 cold).mX 3= 5.245 in y = 5.25 in + 0.375 in Y 3 =0in Z 3= 29 875 cos(0 cold) in Z 3= 29.411 in = X g_h

  • Xs + E X g_h = 5.62 *in Y g_h = Y ,

Zg_h = Z , + AZ Z g_h = 29.349 in  ; D pp_h

  • X g_h + Y g_h + Z g_h D pp_h = 29.882 in 0h = asm D pp_h 0h = 10.85 deg Calculate dead wt reaction at rear bracket pin p /Wbracket + Wsp) 40+ (Wpsa_10 pt W ) 25 + (Wclamp)-(5) d_h ,

40 Pd_h = 58.444 Ibf Pd_v

  • Wsp + Wbracket + Wpsa_10 t *W p P d_v = 99.72 lbf t

x

A6"A*Cd S Comed c*. No. 225-2-00W-207 ggfy Rev. No. O Cales. For: Pipe Support RSCS-2123A Node 227 Page 24 Situ n Pnw-l X ] Safety-Related [ ] Non-Safety-Related Project: Zion Pro.iect No.: 09432-M Prepared by: Reviewed by: fge g Mdi Date: 1 ES 97 h Date: i-3o V

                                                                                                             /2.6./*wc Oh = asin                 Oh = 4.78 deg               Vertical angle, hot condition Desien loads in the base olate axis:

Odev =5 deg Conservatively use 5' deviation ah ah - 8

                                                                             ,,2 4 3 & k ir FX =F z_sk sin (0dev + 0 cold) + Pd_ hah                           FX =1-250 ;e' lbf g (>g @ y g j p ay g,75,                 g ge FY = P d_v7 + Fz_sk sin (0dev + 0 ) h                            py.;c[c';gr                                       p     'h -[

97 E 673 3K IP FZ^=Fz_skcs(0 cold) pz . gyce. : c -;;r Check the weld between rear bracket and shim nlate: (All around weld) Weld properties: based on 1" fillet weld kips a 1000 lbf ksis si e 3. h b = 3.06 in d = 2.72 in y Aw = 2-(b + d) A w= 11.56 in ,

                                                                           ~

S x =(3 b + d) d S x= 10.789 in 2 3 lye

                 '+

(' 3,p 2 Sy = b. Sy= 11.444 in f,e 8' b I p=

                +d/

I p= 32.183 in' e --

                                                                                                                 - f. ---           k Conservatively transfering into weld axis, the loads for weld design are,                                              \

g sg, \ Y*m FXw = FX cos(0) + FY sin (0) FX w

                                                  = 2 F59- 1^' ibf 2 957 k:P 3

FY w = FX sin (0) + FY cos(0) FY w

                                                  = '.;7; :0 itr .2 6 6 i kif S ddW 3 16177 FZw.=FZ                                FZw = o.330-ie' -iLi Ff73 88f e

MXw .= FY w _MX w = 2000 li a 9 7.E leIf. IN 3/

                                                                                                                                          /
                                                                                                                                        .se

s A1MacA+cd S Comed Calc. No. 225-2-00m-207 g g4 . z s t?., A rJ oh. tG Rev. No. 0 Cales. For: Pipe Support R5C5-2ili LA 105 Page 25 Smtm /Mir" l X ] Safety-Related 1 ] Non-Safety-Related Project: Ziva Prepared by:

                                                                                                                                     %              Date: 125 97
                                                         , Project No.: 09432-                                      Reviewed by: gg                 Date: 1-5o 1)

A 16 / M n MY w : FXwe MY w = 10.041 in kips MZw :0.0 in-kips 2 fFZ w MX w MY w FX w I fFY w F + d- b I

                                                        *            +                              + MZ w          .        . MZ    -

weld d ( wA S x S y \A w 2l pj 4A w w2l pj Fweld " - S ' E Y'"  : t 5 in - 5/16" fillet weld 7 Di weld : 16 Fy_ weld :70 ksi E70XX electrode 0.3 F yyeld weld-1.6 t p , [2 allowable factor F w capacity = 7.425 Fpl_ capacity = 0.95 t F = 6,17 - weld pl_ capacity Governs Fweld #' ic < l.0, therefore, O.K. weld =y IC weld = o wr pl_ capacity 3

                                                                                                                                                           ]i Check weld between shim olate (1/2") to 1"X5"X0'-5" olate To W4X13 Compared to above weld calculation, the weld at this location are larger and loads are smaller, therefore the weld is accepatable by engineeringjudgment. No additional calculation is needed.

Check shim olate: For simplicity, consider the plate as a fixed end beam member subjected to a pull out force. Pt :Fweld 11.56-in Length of weld is 11.56 in. P t= 2 ? ' ' ' C' M 29 3q kip d' 3%I'7 s 0}

MrY s 0 A LLo c0 me

     -comed                                   geis Calc. No. 225-2-004M-207 Rev. No. O Cales. For: Pipe Support RSCS 2123A Node 227                                    Page 26 J ht$9 ATG

[ X ] Safety-Related. [ ] Non-Safety-Related - Project: Zion Project No.: 09432-M7 Prepared by: %M Date: l 7.5 0 19u Reviewed by: g c2.7 Date: l-So-D it . /3. rn Lshim = 5 in Length of shim b shun . = 5 m Mg= Pt 'Lh M g = 17.775 in kips v=0.3 Poisson's ratio 8 1 + 0.5 . t shim

  • m t shim = 0.75 in g, 2 gg3 2
                                 ! shim                              3 Consider as beam plate Sg =bg dl-y        6          )          Sshim = 0.515 in f                                    I b_shtm = 34.508 ksi b shim
  • Sshim Fa_stum = 0.95y F . Fa_ shim = 34.2 ksi grb shun = 34.508 ksi -Thcicfm O.K; g p H.A b I 0M X
  • 7to s s c. a s A c cO PT AB L 4  %)M 7 IC shim = p _ shim ICshim =.1.Ge9 X 1.0,O.K. ges;.r ptavs ,3 coassoccc.o a_ shim gg g ,g pg g gg mmy %f M 4 Check local stress in W4X13 at R.B. attachment A d 6 'v8'" ## " ' - ^ ## U"D - '# h %

Since the W4X13 at R.B. attachment was stiffened by two stiffner plates, therefore the local stress check is not required. It is O.K. by engineering judgment. Check the frame (Items 8. 3.and 4h The STAAD-III computer program (Ref. 7) is used to check the adequacy of the members and connections. Based on the results,all members pass the code checks. The maximum Interaction Coefficient (IC)is 0.627 at member no.1. Also the weld connection at joints are checked, the maximum weld size required is 3/16" fillet weld. A 1/4" fillet weld is provided. Based on that it is concluded that the frame and its connections are O.K. Check basenlate: The plate is 1" X 12" X 12" with 4 - 5/8" $ rods (A36).. ..Thru. Bolt b s = 9 in Bolt spacing b\ lx'=4'2/ I x= 81 in2 moment ofinertia of bolt based on unit area s

ANcA***S S comed ''"' "'"*8"""*"'"S~2'23A c.ic. No. 22S-2-oo4u-2o7 Node # 227 Project: Zion: Rev. No. O Preject No.: 09432 769 lx] Safety-Related [ ] Non-Safety-Related Page No. 2'I 7% Preppared By: dw?- MM Date: 3-4 -97 Reviewed By: lCd1M Date: \ ~7 ~ 3 ~7

                                                ~

3rowiser />A ru. ile Name: rcr2123a med "'"" " * """"*"'**"'""#' Check the frame (Items 8. 3. and 41: The STAAD-III computer program (Ref. 7) is used to check th'e adequacy of the members and connections. Based on the results, all members pass the code checks The maximum Interaction Coeflicient (IC) is 1.007 at member no.1. This IC is acceptable since the faulted loads are compared with OBE allowable = 0.66Fy . Check base plate: The plate is 1" x 12" x 12" with 4 - 5/8" $ rods (A36).. ..Thru. Bolt b , : 9 in Bolt spacing

              /b 12 1 x :4                 i s= 81 in 2          moment ofinertia of bolt based on unit area ly :l x           !) = 81 in 2

1p 1x +ly I p= 162 in2 Add 10% attachment relocation Results from STAAD-III analysis and revised the axis to the plate local axis F g :4 27 kips Z axis in STAAD-III model Fyy : 1.89 kips X axis in STAAD-III model F2, : 4 76 kips e = 0. I 12 in e = 1.2 in M g : 30 45 in Lips + Fgje M x_p = 36.162 in kips M yy :46 64 in Lips + Fgje M yy = 52.352 in kips M g = 0.21.in kips . i F g+F y ]e M z_p = 7.602 in kaps

                                                                                                              - . . - - - - - - - - J

Aftaeh me d S comed Cales. For: Pipe Support RCRS-2123A Node # 227 Calc. No. 22S-2-004M-207 Rev. No. O Project: Zion Project No.: 09432-TiB1 [x] Safety-Related [ ] Non Safety-Related 'Page No. 2r Preppared By: / t/M C Date: 3 -C- 91 Reviewed By: M Date: 3 -7 *)7

                  $HitISH PA ML File Name: rcr2123a.med                                                                                                   """' " " " '" * "'"" *"

b s b, Tz E.M xy .M y T -6.107 kips per bolt A y [ b ,]2 b , ]2 V: -E . M y, . . . JM zJ V = 1.45 kips per bolt h P. t Ps 5 d in bolt diameter b :8 2 A h :a Ab = 0.307 in Not threaded 4 T , : .95 Fy Ab T , = 10.492 kips

  \' , 10 ksi A b 1.6                                 V , = 4.909 kips T   V l*lt
  • T
  • 7, Conservatively use linear. combination Ic bat' 0.877 <l.0 O.K.

Check Plate stress-L p:[4.5- 1.2 in + 2 m t

p. :LOm b p: 12 m 2

t M p 2TLp M p= 60 464 in kips Sp :b p- Sp= 2 in 3 M f by

  • f Iby = 30.232 ksi Fby = 0.95 Fy P

IC p: IC p= 0.884 < l.0, therefore O.K. l

4 l hff.o.c 0 med 8 l Cales. For: Pipe Support RCRS 2123A Cale. No. 22S 2-004M 207 Rev. No. O Project: Zion Project No.: 09432-1N lx) Safety Related l J Non Safety-Related Page No. 24 ( m [ Preppared Hy:////nl /f4/c( Date: 9-4-o Reviewed Hy: l(.N i Date: "V7 - b ~7

                         .Smt 1.sH /Arct. "

File Name: rer2123a med ""'"#"'#'""""""""""""' Check olate: Beating Plate 10" x 3" x 0'-3"6h each thru. bolt fc :4000 psi Reactor Bldg concrete wall concrete strength - p=07 Coeff. of friction b-tween concrete and steel plate y = 07 Factor for concrete Ref. 3 D + ) in Dia. of bolt hole n :\8 8' ' dn21.0in Dia. of nut t: in Plate thickness A b: ild*21) n Un 2 A g, = 27 +in PB: T+ p,Adb 3 P p = 3.029 10 psi Pa_b : 2 o y 0.85 f c 3 3 P , 9 = 4 76 10 psi > PB = 3.02910 psi Therefore, O.K. Weld at joint I and 4: ( W4x13 to Base Plate ) Forces and moments @ joint 1. . . see pg. 9 of STAAD output Fx 4 76 kip - Mx = 0.21 in kip Fy : I 89 kip My 46 64 in kip Fr ; 4 27 Lip M2 : 30.45 m kip c (

p g s c [k m C J A Cales. For: Pipe Support RCRS-2123A comed Node # 227 Calc. No. 22S-2 004M-207 Rev. No. O Pr: lect: Zion Pr: Ject No.: 09432-W9 [x] Safety-Related l J Non-Safety Related Page No. 3 0 Preppared Hy: //u > A /a /r I Dat,e: B s-97 Reviewed Hy:, \b tN Date: b"7-S} JHI$ UH M72 L File Name: rcr2123a med '"""""'"'"""'*""*"' Weld properties a W4x13 all around weld per pg. 49, Calc. 24.1.1, REV. 0 4 i Aw : 19 99 in - 1 u-2 l Sw z : 10 99 in e Fz v i,

                                                                                /l 2                                                                                                              \

Sw y :27.77 in _ u.j g Fx g i 4" Jw r 80 08 in'

             !! Fx     M3 7                      Mz ' 3 / Fy,, Mx 2 inj2.            Ms2inja q ( Aw Sw y    Sw ,j , k Aw         Jw / \Aw            Jw /

f r= 4 694* kip in -i w: we F3 : % ksi

                                                        ~

Fr : 0.3 70 ksi 0 707 t e w 1.6 F r= 5.939 kip in ' .. weld metal, faulted 095F.$ Pr - t w F'r = 4 936 kip ui' ... base metal, faulted (govern) 1 fr

    .1C weld
  • p~ IC wdd = 0.951 < l.0 OK Weld @ all otherjoints are acceptable since the weld prop. and size are same asjoint I and applied forces and moments are less than joint 1 CONCI.USION:

- Based on 6e preceding calculation, it is concluded that the as built support RCRS-2123A is icquate for the latest revised loads.

                                           =                                                                                 __

CcmEd caic. rcr ripe srpport RcRs.2123A ccic. Nc. 22S.2 004M-207 Project: Zion [s] S:fety Related [ ] Non Safety Related Rev.No:o Project No: 09432-557 Page No. 31 ( 7% PAGE NO. I lNtCP lbt

  • put $ M 3I4I91 pot!.5et PRTW S T A A D . ll!

Rethion 17.0a

  • pg yspt3 818, Propnetary Progpm of
  • RESEARCil ENGINEERS, Inc.
  • 3lT 37
  • Date= MAR 6,1997
  • Time = 10.51:49 *
1. STAAD SPACE FRAhtE PIPE SUPPORT llANGER RCRS 2123 A
2. UhTT INCil KIP
3. JOINT COORDINATES 4.1000000 5.2 16.00.00.0 6.3 16.00.0 25.0 7.40.00.0 25.0
8. $ 16.0 0.0 3.5
9. *
10. htEhtBER INCIDENCE
11. I 1 2 12.223 13.334
       !4.425
15. *
16. htEMBER PROPERTIES 17.12 3 4 TABLE ST W4X13
18. *
19. CONSTANT
20. E 29000.00 ALL
21. BETA 90 ALL 22.*
23. DEN O.000284 ALL 24.*
25. SUPPORT 26.14 FDID 27.*
28. PRINT MEMBER INFORMATION

Attac hmcd & CcmEd Calc. F:r Pipe S:pped RCRS-2123A Calc. No. 22S-2-004M 207 Project: Zl:a lal S:fety Related l] Non Safety Related Rev. No: 0 Project No: 09432 1W 7% Page No. 32 FRAhiE PIPE SUPPORT HANGER RCRS 2123A - PAGE NO. 2 [hepen ni R 4 *. hiEhiBERINFORhiATION /SMIl Ibfrl 334/77

~
                                                                        .S m tr,s n y a T C.L.

hiEMBER START END., LENGTil BETA JOINT JOINT (INCil) (DEG) RELEASES bt4iCW ed b} '. i 2 1 2 2 3 16 000 90.00 25.000 90.00

                                                                        \&lA WM 3     3    4      16.000 90.00 4     2    5      3.500 90.00
""*"""' END OF DATA FROh! INTERNAL STORAGE """"""
29. PRINT hiEhiBER PROPERTY ammu>

m

Aff a.c Amad 8 CcmEd Ccic. Fer Pipe Srpport RCRS 2123A Ccic. Nr. 22S-2 004M 207 Project: Zio] [x] Safety Related [] Non Safety Related Rev. No: 0 l Project No: 09432-1R 7% Page No. 33 l FRAME PIPE SUPPORT llANGER RCRS 2123 A - PAGE NO. 3 MEMBER PROPERTIES. UNIT . INCH p p w sl BM g MEMB PROFILE AX/ g uli15t1 f A'T C L-12/ !Y/ LX/ t AY AZ SZ SY -DDWC" h.

  • 1 ST W4X 13 3.83 11,30 3.90 0.15 '

l.16 1.87 5.43 1.92 2 ST W4X 13 3.83 11.30 3.90 0.15 1.16 1.87 5.43 1.92 3 ST W4X 13 3.83 11.30 3.90 0.15 l.16 1.87 5.43 1.92 4 ST W4X 13 3.83 11.30 3.90 0.15 1.16 1.87 5.43 1.92

       "*""""' END OF DATA FROM INTERNAL STORAGE """"""
30. LOAD 1 PIPE LOADS
31. JOINT LOAD
32. 5 FX 2.434 FY 1.752 FZ 8.673
33. SELFWEIGHT X 2.35
34. SELFWEIGitT Y 2.57 35.*
36. PERFORM ANALYSIS PROBLEM ST ATISTICS NUMBER OF JOINTS / MEMBER + ELEMENTS / SUPPORTS = 5/ 4/ 2 ORIGINAL / FINAL B AND WIDTil = 3/ 2 TOTAL PRIMARY LOAD CASES = 1, TOTAL DEGREES OF FREEDOM = 18 SIZE OF STIFFNESS MATRIX = 324 DOUBLE PREC. WORDS .

TOTAL REQUIRED DISK SPACE = 0.01 MEGA BITES

     ++ PROCESSING ELEMENT ST!FFNESS MATRLX.                        10:51:51
     ++ PROCESSING GLOBAL STIFFNESS MATRIX.                        10:51:51
     ++ PROCESSING TRIANGULAR FACTORIZATION.                         10:51:51
     ++ CALCULATING JOINT DISPLACEMENTS.                          10:51:51
     ++ CALCULATING MEMBER FORCES.                            10:51:51 37.*
38. SECTION 0.0 0.25 0.5 0.7510 ALL 3 9. *
40. LOAD LIST ALL
41.
  • J

p ften.ef. m c d C CemEd Calc. F:r Pipe Srpport RCRS-2123A Ccle. No. 22S-2-004M-207 Project: Zion [x] S:fety Related [] Non Safety Related Rev. No. O Project No: 09432 9F'Ith Page No. 38v i ' FRAME PIPE SUPPORT HANGER RCRS 2123A - PAGE 110. 4 g

                                                                               }huni $W) Slll41 Smcisn P A%L-JOINT DISPLACEMENT (INCH RADIANS) STRUCTURE TYPE = SPACE g

JOINT LOAD X TRANS Y,,TRANS Z-TRANS X ROTAN Y ROTAN 2 ROTAN LAl3A thb7 1 1 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 2 1 0.00068 0.02409 0.01336 -0.00156 0.00061 -0.00215 3 1 0.00032 0.00335 0.01237 -0.00086 0.00045 0.00029 4 1 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 5 1 0.00342 0,03001 0.01364 0.00166 0.00065 0.00215

CcmEd caic. F:r ripe s;pport Rcas-2123A AMacLe't 8 Calc. N:. 22S-2-004M 207 Project: Zios lz) S:fety Related [] Non-Safety Related Rev. No: 0 Project No: 094321M 7% Page No. 36 FRAME PIPE SUPPORT HANGER RCRS 2123A - PAGE NO. 5 Prepuyul SN'. htVA {stfol .1 \C l91 SUPPORTREACTIONS UNIT}UP INCH STRUCTURE TYPE = SPACE smma Nrn t

    --                                                                                          }

RateweJ s1: JOINT LOAD FORCE X FORCE Y FORCE Z MOM X MOM Y MOMZ M 17 )] 1 1 -4.76 1.89 -4.27 0.21 -46.64 30.45 4 1 2.17 0.31 -4.40 0.12 -44.47 -4.41 i

l . Af{a.cf med B CemEd Ccic, Fcr Pipe S:pport RCRS 2123A Ctic. No. 22S-2-004M-207 Project: Zio2 [x) S:fety Related [ ] Non Safety Related Rev. No: 0 , Project No: 09432 9F1714 Page No. 36 FRAhtE PIPE SUPPORT llANGER RCRS 2123A - PAGE NO. 6 Pit pared 8 r,

                                                                                   .S*/wint f s4< l Blt.IT1 hiEMBER END FORCES STRUCTURE TYPE = SPACE                                5 H 8i L5 H P ATT L ALL UNITS ARE-K!P INCH                                                                b*

hiEhiB LOAD TT AX1ALSIIEAR Y SIIEAR Z TORSION htOht Y hiOht Z l 1 1 1 4.76 4.27 1.89 0.21 30.45 46 64 2 -4.72 -4.27 1.94 0.21 -0.21 21.73 2 l 2 4 40 2.28 0.20 0.21 5.90 30.27 3 4.40 2.22 -0.27 -0.21 0.12 25.93 3 1 2.22 4.40 0.27- -0.12 -0.21 25 93 4 2.17 -4.40 0.31 0.12 4.41 44.47 4 1 2 8.67 2.44 1,74 -0.00 -6.11 8.53 5 8.67 2.43 1.75 0.00 0.00 0.00

          *"""""*" END OF LATEST ANALYSIS RESULT '""""""*

43.*

44. PARAhiETER 45 CODE AISC
46. FYLL 36 ALL 4 7. *
48. RATIO 1.00 ALL
49. TRACK 1.0
50. CliECK CODE ALL

s A f h c(A

  • C n!S E CemEd Calc. Frr Pipe S pport RCRS.2123A Ccic. Ns. 22S.2 004M.207 Project: Zioa lx] S-fety Related l } Non. Safety Related Rev. No: 0 Project No: 09432.VM ~1% Page No.37 FRAhiE PIPE SUPPORT liANCER RCRS 2123 A - PAGE NO. 7 fyppemd IM'-

pupa Mc( SltIM STAAD Ill CODE Cl!ECKING -(AlSC) .5 hm isH P ATt t. e e e n se e e e e e e e......... he df.Wed % *. ALL UNITS ARE . KIP INCL [(UNLESS OTIIERWISE NOTED) hiEhiBER TABLE RESULT / CRITICAL COND/ RATIO / LOADING / FX hiY hiZ LOCATION I ST W4X 13 FAIL AISC. Hl.3 1.008 1 4.76 C 30 45 46.64 0.00 l- - - - l lMEM= 1. UNIT KIP.INCil, L= 16.0 AX= 3.83 SZ= 5 4 SY= 1.9 ( l KllR.Y= 15.9 CB= 100 YLD= 36.00 ALLOWABLE STRESSES: FCZ= 23.76 l lj FTZ= 23.76 FCY= 27.00 FTY= 27.00 FA= 20.84i FT= 21.60 FV= 14.40 l 2 ST W4X 13 PASS AISC.1121 0.401 1 4.40 T 5.90 30.27 0.00 j . .-

                                                                      }

lMEM= 2. UNIT KIP.INCil, L= 25.0 AX= 3.83 SZ= 5 4 SY= 1.9 l l K!/R.Y= 24.8 CB- 1.00 YLD= 36.00 ALLOWABLE STRESSES: FCZ- 23.761 1 FTZ= 23.76- FCY= 27.00 FTY= 27.00 FA= 20.29 FT= 21.60 FV- 14.40 l l_ - 3 ST W4X 13 2.17T PASS AISC. ll21 0.456 l1 4.41 44.47 16.00 l- ' IMEM= 3, UNIT KIP.INCil, L= 16 0 AX= 3.83 SZ= 5 4 SY= 1.91 l Kl/R.Y= 15,9 CB= 1.00 YLD= 36.00 ALLOWABLE STRESSES: FCZ= 23.761 1 j.. FFZ= 23.76.-FCY= 27.00 I'FY= 27.00 FA= 20.84 FF= 21.60 FV= 14.40 l t 4 ST W4X 13 PASS AISC. H2 1 0.289 1 8.67 T 6.1I 8.53 0.00 i , 1MEM= 4, UNIT KIP.1NCil. L= 3.5 AX= 3.83 SZ= 5.4 SY= 1.9 l l KL/R.Y= 3.5 CB= 1.00 YLD= 36.00 ALLOWABLE STRESSES: FCZ= 23.76 l IFTZ= 23.76 FCY= 27.00 FTY= 27.00 FA= 21.45 FT= 21.60 FV= 14.40 l 1- -.---  ;

   """""*"* END OF TABULATED RESULT OF DESIGN """""""
51. *
52. LOAD LIST ALL
   $3. PRINT ANALYSIS RESULTS

s Affa.e A e B d 8 CcmEd caic. rer Pipe S2pport RCRS-2123A Ccic. N . 22S-2-004M-207 Project: Zio2 l } S:f:ty Related [] Non Safety Related Rev. No: 0 Project No: 09432-W17% Page No. 3F FRAME PIPE SUPPORT llANGER RCRS 2123 A - PAGE NO. 8 pgpyn/ g3 - gyg /WI S kl97 SHwosM PATW JOINT DISPLACEMENT (INCH RADIANS) STRUCTURE TYPE = SPACE g; gy,d 3j - JOINT LOAD X TRANS YJRANS Z-TRANS X ROTAN Y ROTAN Z ROTAN N I 1 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 2 1 0.00068 0.02409 0.01336 0.00156 0.00061 0.00215 3 1 0.00032 0.00335 0.01237 0.00086 0.00045 0.00029 4 1 0 00000 0.00000 0.00000 0.00000 0.00000 0.00000 1 0.00342 0.03001 0.01364 0.00166 0.00065 -0.00215

                                                                            - ..        _ _ _ - - - -        I

4 Attacimed 8 CcmEd Ccic. F:r Pipe S2pport RCRS-2123A Ccic. N:. 22S-2-004M 207 Project: Z602 ls] S:fety Related [] Non Safety Related Rev. No: 0 Project No: 09432-W 794 Page No. 39 FRAME PIPE SUPPORT liANGER RCRS 2123 A - PAGE NO. 9 (> p p es t 6 % .. 4pa.1 tu k l 3 I&I'1 ' 3 pats 1H PnTL L SUPPORT REACTIONS -UNITIUP INCil STRUCTURE TYPE = SPACE ht%'t Me d ' JOlbrr 1,OAD FORCE X FQRCE Y FORCE Z MOM X MOM Y MOMZ h 4, 1k7 9] 1 1 4.76 1.89 -4.27 0.21 46.64 30.45 4 1 2.17 0.31 -4.40 0.12 44.47 -4.41

s. A (f n e $ m e s.S $

CemEd caic. F:r Pipe srpport RcRs-2123A Ccle. Ne. 2:S-2-004M-207 Project: Zion [x] Safety Related [ ] Non Safety Related Rev. No: 0 Project No: 09432 W 7 M Page No. 40 FRAhiE PIPE SUPPORT HANGER RCRS 2123A - PAGE NO. 10 fye pen NI R Y. f) gust (le tcJ 3 14197 hiEhfBER END FORCES STRUCTURE TYPE = SPACE ~" ALL UNITS ARE - K!P INCH Kay(pWed (5]*. h!EMB LOAD JT AX1A1 " SHEAR Y SIEAR 2 TORSION MOM Y hiOht Z l 1 1 4.76 4.27 1.89 0.21 30.45 46 64 2 4.72 -4.27 1.94 0.21 -0.21 21.73 2 1 2 -4.40 2,28 0.20 0.21 5.90 30.27 3 4 40 2.22 -0.27 0.21 0.12 25.93 3--1 1 2.22 4.40 0.27 -0.12 -0.21 25,93 4 2.17 -4 40 0.31 0.12 -4,41 44.47 4 1 2 8.67 2.44 1.74 0.00 -6.11 8.53 5 8.67 2.43 1.75 0.00 0.00 0.00

    ........** **" END OF LATEST ANALYSIS RESULT """""""
54. *
     $5. PRINT FORCE ENVELPPE NSEC 2 9

e

l Comed Ccic. F r Pipe Support RCRS 2123A Ccic. N:. 22S-2-004M 207 Project: Zio: [xj S:fety Related [] Non Safety Related ' Rev. No: 0 Project No: 09432-W 7f4 Page No. 4/ FRAME PIPE SUPPORT HANGER RCRS 2123A - PAGE NO 11 p,epcu ed BT'- MEMBER FORCE ENVELOPE pp,% fae.I .nltl*n

                                                                                                                   ,,m  p gt r L ALL UNITS ARE KIP lh!CH                                                                       k \1 t d e d % I MEMB DISTANCE                FY LD kM4A 3k n MZ LD              FZ LD                        MY LD 1     0.00 MAX. 4.27 1           46.64 1 .1.89 1              30.45 1 MIN. 4.27 1        46.64 1     1.49 I        30.45 1 8 00 MAX. 4.27 1            12.45 1     1.92 1           15.21 1 MIN. 4.27 1 12.45 1 1.92 1                       15.21 1 16.00 MAX. 4.27 1           21.73 1      1.94- 1          0.21 -1 MIN. 4.27 1 21.73 1 1.94 1                        0.21 1 l-.---.--

l MAX / MIN FORCES FOR MEMBER I.AMONGST ALL SECT LOCATIONS

        }           FY/ DIST LD         MZ) DIST LD l           FZ DIST LD          MY DIST LD            FX          DIST LD I

l MAX. 4.27 0.00 1 46.64 0.00 1 l 1.94 16.00 1 0.21 16.00 1 4.76 C 0.00 1 l MIN. 4.27 16.00 1 21.73 16.00 I l 1.89 0.00 1 -30.45 0.00 1 4.72 C 16.00 1 1 2 0 00 MAX. 2.28 1 -30.27 1 0.20 1 5.90 1 MIN. 2.28 1 -30.27 1- 0.20 1 5.90 1 12.50 MAX. 2.25 1 1.97 1 0.23 1 3.23 1 MIN. 2.25 1 1.97 1 0.23 1 3.23 1 25.00 MAX. 2.22 1 25.93 1 0.27 1 0.12 1 MIN. 2.22 1 25.93 1 0.27 1 -0.12 1 l l MAX / MIN FORCES FOR MEMBER 2,AMONGST ALL SECT LOCATIONS l FY/ DIST LD MZ/ DIST LD l FZ DIST LD MY DIST LD FX DIST LD 1 1 MAX. 2.22 25.00 1 25.93 25.00 1 l 0.27 25.00 1 -0.12 25.00 1 4.40 T 0.00 1 l MIN. 2.28 0.00 1 30.27 0.00 1 l 0.20 0.00 1 5.90 0.00 1 4.40 T 25.00 1

                       *.                                          Af ta.e#,n.cd 6 CemEd            .caic. rer Pipe S:pport RCRS-2123A        C:Ic. Nr. 22S-2-004M-207 Project: Zio2      [x] Safety Rel:ted [] Non Safety Related                                               Rev. No: 0 Project No: 09432-189 744                                                                                 Page No. 42 3   0.00 MAX. 4 40 1 25.93 1 0.27 1               0.21 1                                                  g9      3l4191 MIN. 4.40 1 25.93 1 0.27 1 8.00 MAX. 4.40 1      9.27 1 0.21 1                                        Ib 0.29 1    2.01 1                                    SF'$lD MIN. 4.40 1        9.27 1     0.29 1    2.01 1 16.00 MAX. 4.40 1         44.47 1    0.31 1    4.41 1                        hpg (( Q e MIN. 4.40 1 44.47 1 0.31 1              4.41 I
                                                                                 \dLLik s oy

4 AM:tebed b CcmEd ceic. F:r ripe S:pport RcRs.2123A Ccic. Nc. 22S.2 004M 207 l Project: Zi:n [x] Safety Related [] Non. Safety Related Rev. No: 0 Project No: 09432-W M4 Page No. 43 i FRAhiE PIPE SUPPORT liANGER RCRS 2123 A - PAGE NO. 12 ynpared g1 .

                                                                                                             //md/khl 3l497 S H i tt.S H OAT C L i --

l l hiAX/ MIN FORCES FOR MEhiBER FY/ DIST LD MZ/ DIST LD 3.AMONGST ALL SECT LOCATIONS g(g k (b}

  • FZ DIST LD MY DIST LD FX DIST LD i

g1 , I hiAX. 440 0.00 1 25.93 0.00 I l 0.31 16.00 1 4.41 16.00 1 2.17 T 16.00 1 l MIN. 4 40 16.00 1 44.47 16.00 I l 0.27 0.00 1 0.21 0.00 1 2.22 T 8.00 1 4 0.00 MAX. 2 44 1 8.53 1 1.74 I 6.Ii 1 MIN. 2.44 1 8.53 1 1.74 1 6.11 1 1.75 MAX. 2.44 1 4.26 1 1.75 1 3.06 i MIN. 2.44 1 4.26 1 1.75 1 3.06 1 3.50 MAX.- 2.43 1 0.00 1 1.75 1 0.00 1 MIN. 2.43 1 0.00 1 1.75 1 0.00 1 j.. - l MAX / MIN FORCES FOR MEMBER 4,AMONGST ALL SECT LOCATIONS ( l IT/ DIST LD MZ/ DIST LD l FZ DIST LD MY DIST LD FX DIST LD l l MAX 2.44 0.00 1 8.53 0.00 l l 1.75 3.50 1 0.00 3.50 1 8.67 T 0.00 1 l MIN. 2.43 3.50 1 0.00 3.50 1 1 1.74 0.00 1 6.11 0.00 1 8.67 T 3.50 1

            ]                                                                  .-
            """"" END OF FORCE ENVELOPE FROM INTERNAL STORAGE *""*""

56 *

57. FINISH 1
                  . . . . . . . . . . . . . .
  • END OF STAAD ll! * """""""
                    **" DATE= MAR 6.1997 TIME = 10:51:53 ""

For questions on STAAD.!!!/ISDS, contact:

  • RESEARCH ENGINEERS. Inc at Ph:(714)974 2500 Fax: (714) 974 4771
                  ...................... u .................................

t COMMONWEALTH EDISON COMPANY CALCULATION NO. 22S 2 004M 207 PROJECT NO. 9432 357 f % PAGE NO. H Attx benf 8 PREPARED BY: /AMI M/r/ DATE: 3 U REVIEWED HY:k#53 , DATE3/W7 Shirish Patel C . n: , , ~ ,: - PliRPOSE: Evaluate Suppon M 2-RCk SR2 for a revised load. The support was checked in a detailed calculation that follow. This calculation will be determine if that calculation is still valid.

REFERENCES:

See the calculation for this support which follows. METIIODOLOGY AND ACCEPTANCE CRITERIA: A comparison will be made of a revised suppon load versus the load used in the following calculation. Ajudgment will be made as to applicability of the calculation. See the calculation for this suppon, which follows, for further criteria. ASStiMPTIONS: See the calculation for this support which follows. DESIGN INPITT: PIPSYS Run Dated 3/5/97 ATTACIIMENTS: None CAI.CITLATION: Loads. Revised Checked in Calculation ODE _ Loads PSL_B_ revised .: 1.326 kip PSL_B_desiped .: 1.286 kip SSE_ Loads PSL_C_ revised : 1.403 kip PSL_C_desiped : 1.365 kip IC -- IC3g 3 =i.03) IC -- SL B :I SL_B_desiped SL C : P SL_C_desiped

                                                                                 -                          IC SL C = 1.028 Per review of previously prepared cale. the critical IC = 0.595 for weld of PSA-3 to Item 7.

IC weld :0.595 IC weld _ revised :ICweld IC SL B IC weld _ revised = 0.614 ' < l.0 OK

 liMMARY AND CONCLilSIONS:

Based on above calculations all other IC for the Support M-2-RCl47-SR2 are less than 1.0, hence the previous calculation, prepared on 2/17/97 is still valid.

                              ' COMMONWEALTH EDISON COMPANY                                             b!7!J'7 CALCULATION No. 22S 2-004M 207                   l PR2 JECT NO. 9432 977%                    l PAGE NO. 4I Mtst >cm L g i

REVi$loN No. 0 l l l l PREPARED BY: hjv/ g DATE: (76r5 77 l REVIEWED BY: / / M a-M'[ DATE: 1 /E 4) Aum McGuve MATHCAD PLUS 5 0 S&L PROGRAM No. 03.7.548 5 0 K. L Sabharwal PURPOSE / OBJECTIVE Evaluate Support M-2-RC147-SR2, Node Point 96 - Y skew, of subsystem 2RC-02. REFERENCES I DESIGN INPUT

1. Zion Drawing M 2RC147-SR2, Revision B.
2. Zion' Design Criteria DC-SE-01 ZN, Revision 7.
3. American Institute of Steel Construction, AISC, Manual of Steel Construction,9th Edition.
4. Pacific Scientific Company, Catalog PSA 3, dated 5-76.
5. Seismic Design Criteria for Zion S .ation, DC-SE-002-Zl, Revision 3.
6. Navco Piping Datalog, Edition Nr.10, Dated June 1,1974. (Pipe size information).
7. NDIT-Zl-EXT-1228, Revision ',.
8. Zion Drawing, B-432, Revision V.
9. NDIT ZDE-97-012, Revision 0.

METHODOLOGY & ACCEPTANCE CRITERIA The support components will be evaluated by detailed calculations per the methodology outlined in the project design criteria, Reference 2. The acceptance criteria will be per the design criteria, Reference 2, and the AISC manual Reference 3. ASSUMPTIONS Major assumptions (requires verification)- None. Minor assumptions (no verification required)- As noted in the calculation. ATTACHMENTS None. CALCULATION Units: U.S. Customary except as noted. kip .1000-lbf Support loads are given for OBE/ transition loads (SL B) and SSE/ transition loads (SL C). Per Reference 7 the loadings are not considered of the subcompartment loads of the Pressurizer Enclosure which this support attaches to. For simplicity the loadings will be called OBE and SSE Support loads as per the latest analysis dated 13Feb97: SL A: P SL_A = 0 kip SL B: P SL_B = 1.286 kip SL C: P SL_C = 1.365 kip t P SL C - ratio C to B : PSL_B

                              --                                   ratio C to B = 1.061
                                                                          -~

RC147SR2.MCD,1

COMMONWEALTH EDISON COMPANY CALCULATION No. 22S-2-004M-207 l PROJECT No. 94321pr 7% l PAGE NO. 46 l Attu b est 8 REVislON NO. O l l l l PREPARED BY:

                                       /,Qq._                   DATE:                   /7pp 7 l REVIEWED BY: f./[M r[DATE: f./f 9)

Aevin McGuire MATHCAD PLUS 5 0 S&L PROGRAM No. 03 7 548 5 0 A. L. Sabharwat CALCULATION (continued) The loading SL B is checked with OBE allowables while loading SL C is checked with SSE allowables. As the ratio of C to B load is 1.06 vs an increase in allowables from OBE to SSE is a minimum of 1.37, check SL B loads, with OBE allowables as controlling. Support information. Per the support drawing, Reference 1, the mechanical shock arrestor is a model PSA-3 with a forward bracket, rear bracket and pipe clamp. Determine the dead weight of the components. Use Reference 4 for component weights. W psa3_ snub = 26.ibt Weight of a PSA-3 mechanical snubber. W psa3_tbrack : 5 ibt Weight of a PSA-3 forward bracket. W psa3_endatt 2 3 lbf Weight of a PSA-3 rear bracket. Assume a total support (component) weight, including the clamp and wall connection pieces of: W p3,3 : 200 lbf Seismic Response Spectra.- Per Reference 5, El 654'-0", OBE 2% damping and SSE 5% damping. Peak values, OBE page A39, SSE page A40. a h_OBE : 0.9. a h_SSE i'4 2 a 2 v_OBE a 3_a h_OBE + 1 v_SSE 3.a h_SSE + 1 a v_OBE = 1.6 a v_SSE " 1933 Ose SSE g values for the OBE check. a h : a h_SSE a y: a v_SSE a h = 1.4 a y = 1.933

    \

RC147SR2.MCD,2

 ). _ .
                                 ' COMMONWEALTH EDISON COMPANY CALCULATION No. 22S-2 004M-207                   l PROJECT No. 9432.W7 7%

Amh ed B l PAGE No. 47 REVISION No. 0 l l l l PREPARED BY: j DATE:

                                                  /7/fg17 l REVIEWED BY: g/huk DATE: 7, J - 9 7 Aeon McGuve     MATHCAD =LUS 6.0 s&L PROGRAM No o3 7.548-$ 0        K. L. sabharwal CALCULATION (continued)              61 Applied piping load and excited self weight.

P SL_C = 1.365

  • kip P sw y : W psa3 a y
                ,                                  P sw y = 0.387
  • kip P sw h : W psa3 a h

_ P sw h = 0.28 kip Determine load at the end attachment. SSE Pipe movements from the piping analysis are: AX ns : - 0.234 in AYy: 2.829 in AZ ,, 0.174 in Aboriz_ max : . AX ns + ^Z ew Ahonz_ max = 0.292 in Geometry of the snubber in the cold position is: Lsnub : 19.375 in L y: 648.92 ft - 8.in - 647.25 ft - (6 in + 3 in N L y = 5.04 'in 2 L h * ;l snub - L v L h = 18.708 *in Determine the geometry of the snubber in the hot position. Neglect the lateral movement for the ' axial load on the end attachment. Consider the highest lateral movement as a load on the end attachment. L v_ hot

  • L v - AYy L v_ hot = 2.211 in L h = 18.708 in l

snub _ hot : Lv_ hot + l h L snub _ hot = 18.838 in RC147SR2.MCD. 3

                                  'COMMSNWEALTH EDISON COMPANY CALCULATION NS. 22S 2-004M-207'                            l PROJECT NO. 9432-1W 7M                l PAGE NO. 4F R4Lsc9 nc. i &

REVISION NO. 0 l l l l PREPARED BY: hgp DATE: /7/M 97 l REVIEWED BY:fl /MWelf DATE: 7.;r. 37 Aewn McGuire MATHCAD PLUS $ 0 s&L PROGRAM No. 03 7 548 5 0 K. L sabharwel CALCULATION (continued) Load distribution at the end attachment. Local coordinate system will be:

     'out', out of plane of the wall; ' vert', Vertical; and 'in', in plane of the wall.

Lh P out P SL_C.l +P sw h P out = 1.636 kip snub _ hot P in : P SL_C-(sin (5 deg)) + P sw h _ P in = 0.399

  • kip P vert : P SL_C.g
                                            +P gw ,

y P vert = 0.547 kip snub _ hot Check weld of item 6. C6 x 8.2 x 12 inches long, weld to the embed plate.1/4 inch fillet weld on two sides. Load at embed plate. Consider eccentricity from the end attachment to the face of the embed. e rear _ bracket : 2.25.in From PSA catalog. Reference 4, end attachment eccentricity. b fl_C6 : 1.92.in C6 x 8.2 flange width, Reference 3. d C6 : 6 in C6 x 8.2 depth, Reference 3 L C6 : 12 in C6 x 8.2 length, t pi_7 : 0.5 in item 7 Plate thickness. b pg ,7 : 4in item 7 Plate width (or length). eccentricity from hole of end attachment towards face of wall: L ecc_emb : (b fl_C6 + t pl,7 + e rear _ bracket i L ecc_emb = 4.67 'in eccentricity from hole of end attachment towards centerline of the 9 inch long weld: L L C6 - - ecc_to_ weld L ecc_to_ weld = 5.5 in RC147SR2.MCD,4

COMMONWEALTH EDISON COMPANY

 - CALCULATION ND. 22S 2-004M 207                            l PROJECT NO. 9432 W7 H4                              i PAGE NO. 49 As o.: f. e mi 6 4
 ' REVISION NO. 0                  l                       l                  l                       l PREPARED BY:

hr s f$ DATE: /7jg.39 7 l REVIEWED BY: / ((g[p) DATE: ; , d 0) Aeve McGuve MATHcAD PLuS 6.0 S&L PROGRAM No 037.54850 A. L. Sabharwal CALCULATION (continued) Therefore: M out : P in't ecc_to_ weld M in : P vert'l ecc_emb

  • P out'l ecc_to_ weld M vert : P in't ecc_emb Or Load at embed plate.

P out = 1.64 kip M out = 2.194 *in kip-P in = 0.4 kip M in = 11.55 *in kip P vert = 0.55 ' kip M vert = 1.86 *in kip Weld properties of a 1/4_ inch fillet 9 inches long, per Reference 8, on two sides of the C6 x 8.2. l 2 w emb 2'( 9'IA) l w_ emb = 1B *in sw In : _ sw n = 27 in 2 2 s w vert : d C6-( 9 in) s _ w vert = 54 *in J w ou, ; 3.d C6 - (9-in)2i 6 ' I w out = 283.5 *in' c in : c in = 4.5 in c vert

  • e vert " 3 *I" 2

P M vert ' P n f _ out M in ( M out c inh 'P vert M out c r emb ~ f s w vert s I * '

  • vertf, ikl w emb

_ _ w in/ ' '\ I w emb _ _ Iw out _ + 'kwl emb } w out i i r_emb = 0.559 in b

 ' RC147SR2.MCD, 5 I
                                                                                                                           .. . _ _ __ _ _ _ _ --__ J
                                             'ComuoNWEALTH EDISON CeMPANY CALCULATION No. 22S 2 004M 207 '                               l PROJECT NO. 9432 Mr r%                         l PAGE No. 50 MtneLnest B REVISION No. 0                      l                      l                      l                  l PREPARED BY: /hjef p                              DATE: /7F20))J              l REVIEWED BY; [ . /M[p[ DATE: ; if b)

Asym McGuire MATHCAD PLUS 5 0 $&L PROGRAM No 03754850 K. L. Sabhafwel CALCULATION (continued) F u_ weld : 70-F F .in '; r_emb_all : u_ weld- F r_emb_all = 3.712 - 32 IC < 1.0 , O. K. w_ emb

  • p IC w emb = 0.15 r_emb_all Weld of item 6 Conclusion. The IC of the weld to the embed is acceptable. SSE loads were used with OBE allowables.

Weld of End Atachment to item 7. PSA-3 end attachment is 2.23 inches wide (in the 'in' direction) by 2.25 inches high (in the ' vert' direction). use 2.23 inches for both.1/4 inch fillet all around. I w ea : 4-(2.23 in)

                       .,                                                                       I , ,, = 8.92 ain s w ea : 2.23 in-(2.23 in) 3+ (2.234n/                                                             2

_ 8w ea = 6.631 in [P out M vert M in 1 iP in i IP ' f - ' vert r_emb

  • j( g I ^!
                                                                                ~

f I emb = 2.208 kip s w ea s l :I

                   -i w _ ea               _          w _ eal       i w_ea:         ' w ea n
               -F                            F r_emb_all :                  u_ weld-      in)                F r_emb_all = 3.712 -

IC - c. w emb _ p IC w emb = 0.595

                                                                                                    < 1.0 , O. K.

r_emb_all (' Weld of End Atachment to item 7 conclusion. Weld is acceptable. Also by comparison the weld of item 7 to item 6 is acceptable. RC147SR2.MCD,6 l

COMM NWEALTH EDis N COMPANY CALCULATION No. 22S 2 004M-207 l PROJECT NO. 9432 DT W4 i PA2E No. St A M ace.e.ent F REVISION NO. 0 l l ( l l PREPARED BY: h p/ g DATE: /77t?$ p / l REVIEWED BY: [, j-%64/ DATE: %*If ' N Aenn McGuire MATHcAD PLUS 5 0 $&L PROGRAM No. 03 7.546 5 0 K L. Sabharwal CALCULATION (continued) Check Item 6. The C6 x 8.2 is"12 inches log with 9 inches welded to the embed plate. Three inches are not welded. Item 7 is a 4 inch by 4 inch plate welded to the end of the C6 with room for a 1/4 inch fillet weld. Also item 8, a 1/2 inch ' stiffener' plate is welded to underside web of the C6. The load of the snubber is tranfered to the embed plate through the C6. Consider the critical section of the C6 located at the beginning of the weld to the embed. f eccentricity from hole of end attachment towards face of wall: L ecc_emb = 4.67 in eccentricity from hole of end attachment towards beginning of the 9 inch long weld: L E ecc_to_begin L C6 - 9 in - p L ecc_to_begin

  • l 'I" Therefore: M out_C6 : P in'l ect 'o_begin M in_C6 = P vert'l ecc_emb + P out'l ecc_to_begin M vert.,,C6 = P in L ecc_emb
                  -Or Load for C6 check.

P out = 1.64

  • kip M out_C6 = 0 99 in kip P

n r 0.4 kip -M in_C6 = 4.19 in. kip P vert = 0.55 kip M vert _C6 = 1.86 in< kip C6 x 8.2 section properties: s y_C6 = 0.492 in 3 s 3 x_C6 : 4.38 in M out C6 kip. M n C6 I b major * ~ I s b major = 0.091 q

                                         -                                     f b minor
                                                                                                  ~

f b_ minor = 8.515 kip x_C6 in s 2 y_C6- in ( RC147SR2.MCD. 7 _- ---_ - . l

coMMUNWEALTH EDISON COMPANY CALCULATIONNO. 22S-2-004M-207 l PROJECT NO. 94321Dr 7% I PAGE NO. S 2 ALLa c k-cd & REVISION NO. 0 l l l l PREPARED BY: h /v/@ DATE: /7(SM 7 l REVIEWED BY: ',, i[fft.<.[ DATE: g , }, og Aevm McGuire MATHCAD PLUS $ 0 S&L PROGRAM No. 03 7 546 5 0 K. L. $sbharwal CALCULATION (continued) Check item,6. (continued) The C6 x 8.2 also resists M_ vert, a torsional load. The load is applied through the end attachment and the item 8 plate. The load transfer mechanism stiffens the C6 and prevents a torsionalload from warping the C6. The length of the C6 welded to the embed can be considered as a boxed section. For these reasons the effect of the ecentric load that causes torsion in the C6 is acceptable as the member cannot deform and the load is being transfered to the embed just when the weld of the C6 to the embed begins. Say the C6 is acceptable. Item 7. Transfers load directly to the C6. Say OK by judgment. Embed Plate. From B-432, Reference 8, the embed plate is either a Detail D, E or F, The details are a embed plate on either side of the 1 foot wide Pressurizer Enclosure wall with four through studs. The minimum plate thickness is 1 inch with the maximum plate width or height between studs of 9 inches. The steel through rods are 1 inch diameter. By judgment due to the low stresses in the weld check of item 6 to the embed and the length of the item 6 weld, 9 inches long, say that the Embed Detail either D, E or F will be acceptable. No further calculations are required.

SUMMARY

AND CONCLUSIONS Support M 2RC147-SR2, Revision B, Node Point 96 - Y skew, is adequate for the SSE/ transient and OBEltransient loads. RC147SR2.MCD, B

on u p/ 3 7/> 7 COhlh10NWEALTil EDISON COMPANY CALCULATION NO. 22S-2-004M-207 PROJECT NO. 9432-1107 Wf PAGE NO. 53 A64a c R red 6 PREPARED BY: fel 44/ DATE: 3-6-97 REVIEWED BY:f4)t.g,r,v.

                    . hirish Patel                                                     n mes e. , _j
                                                                                                  - eDATE a v     3/4// 7 PifRPOSE:                                 ,,

Evaluate Support M-2 RCRS-2205 for a revised load. The support was checked in a detailed calculation that follow. This calculation will be determine if that calculation is stili valid.

REFERENCES:

See the calculation for this support which follows. STETIIODOI.OGY AND ACCEPTANCE CRITERIA: A comparison will be made of a revised support load versus the load used in the following calculation. A judgment will be made as to applicability of the calculation. See the calculation for this support, which follows, for further criteria. ASSifMPTIONS: See the calculation for this support which follows. DESIGN INPIIT: PIPSYS Run Dated 3/5/97 ATTACilMENTS: None CA1.Clfl.ATION: Loads: Revised Checked in Calculation SSE_ loads Frevised :: 1.165-kip Fdesigned = 3 468 kip 1C =

            " S*d F

IC = 0.336 < l.0, load reduction. designed StIMM ARY AND CONCl.liSIONS: This revised load of Support M-2-RCRS-2205 is less than previously checked . Previous calculation, prepared on 1/28/97 is still valid.

                                                                                                    ,/s i r/> ?_--_- f CICMONWEALTH EDISIN COMPANY CALCULATION NO. 225 2-004M-207               l PROJECT NO. 09432 M 794 A H n e(L ~ e n t B lPA0E NO. 54 l   REVislON NO. 0               l             l                 l                   l PREPARED BY:[I M4Y DATE: l- TJ-f 7 l REVIEWED BY:                               Q ,b, f.h)    DATE: o I Oh N7.

FILE: RCRS2205 MCD MATHCAD PLUS 5.0 O&L PR00140. 03.7.546-5.0

Purpose:

61 To evaluate the structural support steel for the following new support in Reactor Building, Zion Station Unit-2. Support No. RCRS-2205 ( New Support ) Node Point: 61 Sub - System: 2RC- 02 Support type: Snubber / Seismic & Nuclear Safety related.

Reference:

1. Supprt Drawing No. RCRS-2205, ( ECN No. 001289M/ Project No. 4794 )
2. Drawing NO. B-432, Rev.V
3. Project Structural Design Criteria for Plant Modifications, Zion Station DC-SE-01-ZN, Rev.7
4. S & L Standards SDS-E11.0, Rev. 3
5. S & L Standards SDS-E37.0, Rev. 5
6. Seismic Design Criteria for Zion Station DC-SE-002 Z1, Rev. 3
7. Pacific Scientific Catalog.
8. Stress Run ( Program No. PIP 037026230), Dated 01.23.97
9. AISC manual ninth edition.
10. Grinnell Catalog PH-92 Methodoloav and acceptance Criteria:

This calculation shall be performed in accordance with ref.3 & 8 Assumptions: See Calculations. Deslan input: Ref.1 & 8. (

                                                                                                                   /

COMMONWEALTH EDISON COMPANY CALCULATION No. 225-2 004M-207 l PR2 JECT N3. 09432 W 794 l PACE No, M Attx Amcai 8 REVISION No. 0 l l l l PREPARED BY: f / M#I DATE: / 7.8* 77 l REVIEWED BY: d,3, faz) DATE: 01 'L 4 'M FILE: RCRS220$ MOD MATHCAD PLUS $ 0 S&L PROG No. 03.7.546 5.0 Calculation: The proposed support consisu of Mech. Shock Arrestor PSA-3 attached to steel frame supported from wall mounted base plate with 4 expansion anchors. Conservatively, OBE allowable are used for SSE condition to qualify the support U.N.O. Desian Loads: F 3.468 kip- SSE load along snubber axis. Displacement in Local Axis: d, : { in (Global Y )

                \-0.000 0.00                                                    0.00 d b*          g  .in        ( Lateral to pipe )         d c=                          .in        (long axis of pipe )

Factors for self weight excitation due to SSE condition: gh : 2.4 ( Page A-40 of Ref. 6 ) gv :1 2 gh 3 ( Ref. 6 ) p_p 17.125 in a : asiniimin((d b )) a = -0.361 *deg

                    . PP

( p : asin i min ((dc ))' p_p p = -0.09 deg L I

COMMONWEALTH EDISON C0MPANY CALCULATION N3 3 226 2-004M-207 l PROJECT NO. 09432 W ~7% AfrAcV. n ed B l PA2E NO. 54 REVISION NO 0 l l l l PREPARED BY: f /kMW Y DATE: /* M"9 7 l REVIEWED BY: N .B. h# DATE: p l '4 6 l'} FILE: RCRS2205 MCD MATHCAD PLUS 5 0 S&L PROG NO 03.7.548 5 0 Weight of support components: wt : 26 lb + 10 lb ( Weight of snubber + approximate weight of accessories like transition tube, end bracket & adapters etc Ref. 7 ) Check item # 9 - 3/4" x 61/2" x 9"lono otate ( Mat'l- A36 k ( Ref.1 ) tp : 0.75 in L = 7.ln b : 6.5 in Py = 36.ksi F . d.gv .b.6 (b : . 2 .4 2 fb = 10.094 kip in 2 < 0.6 Fy = 21.6 kip in.2 b tp 10 : IC = 0.467 < 1 0.6 Fy O.K. Check Weld Bet Rear Bracket & 3/4" Plate ( Item # 9 ) and between R Bkt. & TS 3"x3"x1/4" ( Item # 7 Y The rear bracket of sway strut ( Grinnell Fig. 211) Size C is cosidered to evaluate the weld. Allow +/- 5 deg. tolerance.

            - 3.468 kip                       Wt : U + 11.ft.8.81.$ + 48.85.$ 1.25.ft) 2   \              ft           ft        /

I' y : F + Wt gv F y = 3.696 kip Use max. swing of 60 in either direction ( Conservative ) t F x : Wt gh + F. sin (6 deg) F x = 0.573 kip o tn -. i F z : Wt gh + F sin (6 deg) L p , , Fu w .: 70.ksi

                                                                                                                 ~5

COMMONWEALTH EDISON COMl*ANY CALCULAYlON NO. 225-2-004M-207 l PROJECT NO. 09432-W 7f4 Afto cRmed & l PA3E NO. 57 REVISION No. 0 l l l l PREPARED BY: /,-( hu# DATE: /- 1-d 97 l REVWWED BY: 4.S. fh ' DATE: 01-2.9-91 FtLE: RCRS2205 MCD MATHCAD PLUS 5.0 $4L PROG NO. 03.7.548-5.0 Weld between rear bracket . .id ts 3"x3"x1/4"is critical, e :: 3.25 :n d ta x F2 e M x = 0.155 kip ft M z:Fe x M z = 0.155 kip ft Weld between rear bracket and 1/4" plate: b : 3 in d : 3in Aw y = (b + d) 2 Sw z:bd+ 2 3 SW x:bd+b3 Fr * = (F y

                                            +

Mx

                                                                    +

M z\ /F 9 lF x

                                                                                                            +i 2 T*

(Aw y Sw x Swz jl -(Awyj (Awj y Frw = 0.622 kip in Fr w 0.707 Fuw. 0.3 t w = 0.042 in < t wa : 0.25 in t# IC , IC w = 0,168 < 1 O.K. t wa \

COMMONWEALTH EDISON COMPANY 2 6-2-004M-207 l PROJECT N3. 09432-1R 7M CALCULATION A N3.ffs.c

                                    %ewi 8                                                            l PA?E NO. 6F REVISION NO. O                   l                 l                 l                   l PREPARED BY:d fdbwM DATE: j, gg-f/ l REVIEWED BY: d, g, fg DATE: o f '2.b% 'l .

FlW: RCRS2205 MCD MATHCAD PLUS 5.0 S&L PROG No. 03.7.548-5.0 Weld between ts 3x3x1/4 ( Item # 7 ) and ts 8x8x1/2 ( Item # 3 ) F y = 3.696 kip F x = 0.573* kip F z = 0.573 kip h : e + 12.5 in M xt : Fz h M zt=Fx h IF y M xt M zt /F x 1 2

                                          ^                      '

F z 'I h }Aw y ' Sw x Swz / (Aw yj Awf y Fr wt = 1.814* kip *in Frwt 0.707 Fu w 0.3 1 w = 0.122 *in < t wa = 0.25 in IC t* w:t w, IC w = 0.489 < 1 0. K. Check TS 3x3x1/4"( Item # 7 ) Sy_ts = 46.ksi For A-500 Gr. B Mat'l Ay = 2.59 in* d S 3 = 2.1 in i 3 '= 3.16 in r 3 . = 1.1 in k = 2.1

i. k-(h + 4 in) = 37.705 < C c = 111.6 r3 ( Per table 4 at page 5-120 of Ref. 9 )

_ _ __J

COMMONWEALTH EDISON COMPANY CALCULATION NO. 225-2-004M-207 l PR8 JECT No. 09432 ' Arf 79/( l PAGE NO. Si AtfAcRmewf 8 ! l' REVISION NO. 0 l i l l PREPARED.BY: 4p[MM DATE: I" Si l REVIEWED BY: N.6.PJJ DATE: 01 - 7.B 'i7 FILE: RCRS2205.MCD MATHCAD PLUS 5.0 S&L PROO HO. 03.7.546-5.0 k-(h + 4 in) For '3 C , = 0.527

                                           = 0.338 Ce F , : Sy_ts C       8 F a = 24.242 kip in-2 Fy fy0                                                   F z-(h + 4 in)

IDX : Ay S3 F x-(h + 4 in) S3

                   = 0.059
                                          <    0.15 b-           *
                                +

z

                                                = 0.45             <      1       0.K.

F a 0.6 Sy_ts 0.6 Sy_ts Shear loads are very small, therefore O.K. for shear stress. Check TS 8x8x1/2" ( ltem # 3 ) Ax 8 14 4'IU d S 8 = 32.9 in' I 8 : 131 in I 8 = 3.03 in k = 2.1 S = ( 9 + 3).in O = 8.317 < - r8 C e = 111.6 ( Per table 4 at page 5-120 of Ref. 9 )

                           $8 For              3 - 0.075                                         C , = 0.588 C  e

( F , : Sy_ts C 8 F a = 27.048 kip in-2 b

comu:NWEALTH EDISON COMPANY CALCULATION NO. 225 2 004M-207 l PROJECT NO. 09432.W 714 l PACE NO. 40 AbcRmed 8 ' REVISION NO. 0 l l- 1 I PREPARED BY: f. t[M DATE: /- Il-f y7 l REVIEWED BY: N.6. @ DATE: o 1 - 1,6 M

       - FILE:RCRS2205 MCD MATHCAD PLUS 5.0 S&L PROG NO. 03.7.548-5.0 -

F y = 3.696* kip F x = 0.573 kip p z = 0.573 kip S = 0.75 ft H ': h + 4 in J : 217 in' H = 1.646 ft Mx_8 :Fg H Mz_8 : Fy S + Fx H My_B : Fz'S F N 8o = Y-Ax fby_8 : fbz_8 : - S 8

                         = 0.053
                                                            < 0.15 IX 80 , fby_8 fbz_8
                                           .                     = 0.056            <   1     0.K.

F a 0.6 Sy_ts 0.6 Sy_ts Check Shear Stress: Fv = Y z W8

                                           +                        v     _ 0.5 in 2 8 in 0.5 in            2 8 in 0.5 in .           J g,

Fv = 0.56 kip *in.2 < 0.4 Sy_ts = 18.4 kip in.2 g,g, = r Check Weld Between TS 8x8x1/2" and Base Plate: b = 8 in d = 8 in 7 1 2 Y '

           . Aw = 2-(b + d)                                       Sw:bd.d                                  .Q N 3                          .    <                         1,%

Jw := (b + d)* 9 @ Xl 6 i jL o O f 2 l I Mx 8 I Frw := l i Aw

                                  +

My_8 Sw _W_8 Sw h Mx -8 2 Jw / ,(Aw h - 2 _6,= , 3 \Aw Jw / 1 0 ,aG'

ChMMONWEALTH EDISON CC#"PANY . CALCULATION NO. 225-2-004M-207 l PROJECT NO. 09432-W 794 l PAGE NO, 61 Atta.:Amed & REVISION NO.- 0 l l l l PREPARED BY: f. gM DATE: f. g$ 812 l REVIEWED BY: N . 6. Pot) DATE: 0 /- 2. B24 7. FILE: RCRS2205.MCD MATHCAD PLUS 5.0 S&L PROG NO. 03.7.546-5.0

                                                      .i Frw = 0.634 kip in

Frw 0.707 Fu w 0.3 t w = 0.043 *in < t wa = 0.25 in t* Ic w 2 Ic w = 0.171 < 1 0.K. t wa , Check deflection: E = 29000 ksi 3 FS Y a Y=3E1 8 A y = 2.364 10'd in << 1/16" O.K. Check base plate with 4 - 3/4" Hilti Kwik Bolts: F x = 0.573 kip F 2 = 0.573 kip F y = 3.696 kip Mx_8 = 11.325 kip *in My_8 = 5.161 kip *in Mz_8 = 44.593 kip *in For max. bolt pull out and shear forces: B' = 9 in D' ': 12 in n := 4

                                                                                                                                                   <^

t t dOMZONWEALTH EDIS!N COMPANY CALCULATION NO. 225-2-004M-207 l PROJECT NO. 09432-W 714 AtfAebeat B l PAGE NO. 62 REVISION NO. 0 l l. l l PREPARED BY: (,((./_ auf DATE: /. Q-4 7 l REVIEWED BY: d. 6. f4 DATE: 6/ , 7- 6 'O , i FILE: RCRS2205 MCD MATHCAD PLUS 5.0 S&L PROG NO. 03.7.545 0 I x ': + 4 l x = 225 in' 4 To = Mz_8 My_8

                                         +                                                 To = 2.288 kip D *-      B' "

Fy Mx_8, B.\ IF z y, , Mx_8 D' q(4 1 x 2'j (4 1 x 2j vo = 1.234 kip Ta ': 4090.lb SSE allowables for fc'=4000 psi p : 0.7 ( Table 11.1.2A.1 of Ref. 4 ) -, T = To + Y- T = 4.051 kip p IC = T- IC = 0.99 < 1 O. K. Ta Check for Plate: M pgj = 2J0-(9 + 6 - 8)dn M pgj = 1.335 kip ft M pl2 To-(12 + 2 - 8) in M pl2 = 1.144 kip ft M pg3 6 14 in-(0.75 in)2 Fb1 = 12.203 kip in 2 k M pg6 Fb2 = 12.203 kip in.2 12 in-(0.75 in)2

C MMONWEALTH EDISSN CUMPANY CALCULATION NO. 25-2-004M-207 l PROJECT NO. 09432 R 799 l PAGE NO. 63 l Attac me d B

     . REVISION NO. 0                    l                               l                    l                 l PREPARED BY: f. t[W DATE: /- W 4 7 l REVIEWED BY: d.6.hdd                                                                    DATE: 01 2.6 '91 FILE: RCRS2205.MCD MATHCAD PLUS 5.0 S&L PROG No. 03.7.546-5.0 61 ICp; 0.75.Fy IC pi = 0.452                 < 1              O.K.

Conclusion:

The support as designed is adequate for loads per the latest stress analysis. 1

                                                                                                                                              --~~~      - - - - - ' - - ~ ~ ~ ~ ~ ~   

f CbMMONWEALTH EDIStN COMPANY CALCULATION NO. 225-2-004M-207 l PROJECT NO. 09432 W 774 i PAGE NO. 6ff AMAcR m e nt /3 REVISION NO. 0 l l l l PREPARED BY:l thQ DATE: l a % d

  • 4 ) l REVIEWED BY: Q, g,, P,h) DATE: 0 t - 2 9 'A ')

KL.Sabharwal

Purpose:

61 To evaluate changes to support RCRS-2205 ( ECN # 001289M ) per FCR # 970016. Calculation:

1. Base plate size is revised and Hilti Kwik bolts length shown as 1 ft for item 2.

4 Check base plate with 4 - 3/4" Hitti Kwik Bolts: For max. bolt pull out and shear forces: B' = 8.75 in D' = 13.75 in n :4 i x: + 4 l x = 265.625 *in 2 To + - + - To = 2.06 kip n D* E B' E - 2 2

                                   *8 vo :           +       -
                                                 + b +
  • 8.E .

J(4 ix 2j_ (4 lx 2/ vo = 1.193 kip Ta = 4090 lb SSE allowables for fc'=4000 psi p : 0.7 ( Table 11.1.2A.1 of Ref. 4 ) T : To + $ T = 3.765 kip p ic = T- Ic = 0.92 < 1 0.K Ta {

                                                                                                                                     ,;   1

COMM'NWEALTH EDISON COMPANY 225-2-004M-207 l PROJECT NO. 09432-llWF 7M CALCULATION A& No bed 6 lPAGE NO. 66 REVISION NO. 0 l l l l PREPARED BY: / l[dN DATE: J . & 4 - 4) l REVIEWED BY: g , g, pg DATE: of-24-S7. KLSabharwel it will have no adverse imp $ct on plate stresses since plate was checked for higher bolt pull out force applied on wider & longer plate.

2. The size of item # 3 is revised to TS 8x8x3/8" from TS 8x8x1/2" Check TS 8x8x3/8" ( Item # 3 )

Ax 8 '* 11 i*In S 8 := 26.4 in* I 8 = 106 in" r g = 3.09 in , k = 2.1 S = (9 + 3) in d J = 170 in gS = 8.155 < - I8 C c = 111.6 ( Per table 4 at page 5-120 of Ref. 9 ) ES For 3 = 0.073 .C a = 0.588 C e Fa SY ts C a F a = 27.048 kip - in-2 F y = 3.696 kip F x= 0.573 kip F z = 0.573 Idp S = 0.75 ft H = h + 4 in H = 1.646 ft Mx_8 = F2 H Mz_8 = Fy S + Fx H

          - My_8 ': Fz' S
  • Y8 fx_8o = fby_8.:

A8 S8 fbz 8 =

                        -8 S 8 6   ,

COMMONWEALTH EDISON C".MPANY l PROJECT NO. 09432-Mr T'14 l PAGE NO. 66 / FI#Al. I CALCULATION A6% NO.d8 we ni22f 2-004M-207 REVISION NO. 0 l l l l PREPARED BY: g.f fpp_qp[ DATE: /.3/.9y l REVIEWED BY: N . b k.a C l DATE: O l-31 -M. KLSabharws! fbz_8 S8

                                               = 0.053 a
                                                                     < 0.15 fx_8o , iby_8                              ,     fbz_8
                                                                           = 0.07          <

F a 1 0.K. 0.6 Sy.,,ts 0.6 Sy_ts Check Shear Stress: Fv := Y

                                                               +
                                                                           *       +        0.375 in 2 8 in.0.375 in            2 8 in.0.375 in       J Fv = 0.737+ kip in-2                                      <         0.4 Sy_,ts = 18.4 kip in. 2       0.K.           .

Check deflection: E : 29000 ksi Fy S' a .: Y 3E1 8 ay= 2.92210" in << 1/16" O.K. Check Splice weld for TS 3':3x1/4"( Item 7 ) Per FCR two pieces of TS 3x3x1/4" are joined by providing alaround penetration weld. Effective throat; t , = (.25 .125) in Weld size as calculated on page for TS 3x3x1/4" to TS 8x8x3/8"- t w ': 0.122 in t , : 0.707 t w t e. = 0.086 in < t , = 0.125 in Therefore, the penetration for the splice is O.K. by comparison. The weld for splice is sujected to smaller moments. Rest of changes by this FCR are within the tolerances considered in the ( previous calculation and acceptable.

Conclusion:

The structural modification to the support per FCR 970016 is acceptable. m

  • J

1 Attachment C STANDARD /NON-STANDARD COMPONENTS QUALIFICATION FOR SUPPORTS RCRS-2120, RCRS-2123A, 2RC147-SR2, AND RCRS-2205

ot e :

Calculation documented on pages 2-10 of this Attachment qualifies all support components,' except for 2RC147-SR2 clamp, which is qualified in a separate calculation documented on pages 11 14 of this Attachment. Calc. No. 22S-2-004M-207 Revision No. O Attachment No. C Page 1 of 14

s i COMMONWEALTH EDISON COMPANY CALCULATION TITLE PAGE CALCULATION NO. 225 co4tt - 201 A do.tS.mc d C ( PAGE NO.: 2. i SAFETY REMTED REGULATORY RELATED __ NON-SAFETY RELATED CALCULATION TITLE: PtPE SuPPORTG od THE PRESSdE87ER SM:cTY/ Ret.tEf:

  • kJCP DISCt4AA.C E OPldG STATIONIUNIT:  :::l04 Ll4 t T - 2 SYSTEM ABBREVIATION: Rcgg EQUIPMENT NO.: os am.

PROJECT NO.: ca wu 94 M -794 REV: ---------------------------------------- o STATUS: Approved QA SERIAL NO. OR CHRON NO. --------- DATE: PREPARED BY: [/.[0;j9 {g DATE: 01- C.'-9 7 REVISION

SUMMARY

Original issue.

Add pages:1through 10 ELECTRONIC CALCULATION DATA FILES REVISED: (Name ext / size /datelhour; min /venfication method! remarks) DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIREYES LATER NO VERIFICATION? [ REVIEWED BY: EA.10St40 0 GMM j MO.}> ~ DATE: ^t/lf/97 REVIEW METHOD: DGmM D Mjt50 COMMENTS (C. NC OR Cl): C1 APPROVED BY: ggyg g , p g ps u f 7% , ,) . ,3pps DATE: J / / 9 /c/ j Un??c2

rJ2

Exhibit C NEP 12-02 l Revision 4 COMMONWEALTH EDISON COMPANY CALCULATION REVISION PAGE CALCULATION NO. 22S-2-004M-207, Attachment C PAGE NO.- 3 REV: STATUS: " QA SERIAL NO. OR CHRON NO. DATE:_ PREPAPID BY: DATE: REVISION SUMMTJtY: DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION O YES O NO REVIEWED BY: DATE: REVIEW METHOD: COMMENTS (C OR NC) APPROVED BY: DATE: REV: STATUS: QA SERIAL NO. OR CHRON NO. DATE: PREPARED BY: DATE: REVISION

SUMMARY

DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION O YES O NO REVIEWED BY: DATE: REVIEW METHOD: COMMENTS (C OR NC) APPROVED BY: DATE:

Exhibit D NEP-12-02 Revision 4 COMMONWEALTH EDISON COMPANY CALCULATION TABLE OF CONTENTS PROJECT NO. 9432-794 CALCULATION NO. 22S-2-004M-207 REV. NO. O PAGE NO. 4, Attachment C i DESCRIPTION: PIPE SUPPORT CALCULATION PAGE NO. SUB-PAGE NO. TITLE PAGE 2 REVISION

SUMMARY

3 TABLE OF CONTENTS 4 PURPOSE /OBJECTIVN 5 METHODOLOGY / ACCEPTANCE CRITERIA 5 DESIGN INPUT 5 REFERENCES 6 i ASSUMPTIONS 6 CALCULATIONS 7-9 SUMAARY AND CONCLUSIONS 10 ATTACHMENTS NONE

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               . /                        X l Safety Reistes                               l Non-Safety Related                 Page 7 ll                                                             ef'    -

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6. [ SUPPOR.T rdO. 2-8,Cd47- ,"> R2 / REM 3 I.T E M I TE.M N E.vs LOAD 'f.S S) FIN D I NCJ N O. DESCRIPTiot4 LOAD b EN RATIMG OK FAILED (KMERG) (E M r:.RG.)

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ITEM I TE.M N Evd LoAp(f..%)[**F IN D i r4GS N O. DESCRIPTiot4 LOAD W RA7l,qs OK PA1 LED (fEMERGr) (fE M E.R.G.) 4- - . PSA -3 .. iI65 . ElO . ~ll .. -. muhadcal arm 40r -- llb5

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(y. gal}) 4 / 4W ' 2 0-hoQ G: Eld,x " De;.Ib73) rren @ cfS = l" (i V2") 2 (010X 6 SWFE ) T O K es - ( I A" + 2 %," ) = 48 /v '

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  • Ok G.4 SUPPORT WO. RC/1$ _ 2 /234, Rey, O 1 ress (TsM -

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( 761= G2 "-( i .i..i ' ~~ r , t

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                                 . Ifn=RhsitoM PATIO = f<779/py =0 9g <l                                                     ,

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                                                                                                                                                      .-        ~tWlI'ID                            _     . _

7.6 All danAr6 comeconfr ort supports //.Hel in 6d/hi~ e.2 in4/ evalawe+ & rectionG./ + bra C 5 fcv .. adegvda k Carrt) He increaseci 109cis. __3 _ _ _ _ __ 1

                     ,,                                                                                              Exhibit E NEP-12-02 COMMONWEALTH EDISON COMPANY                                                                 Rnvicion 4 CALC. NO: 22S-2-004M-207        PROJECT 4794 (Comed)

! PAGE NO . It Att a h M ed C 94 32-794 (S&L) Prepared By: [. M Date: 3-$-77 Reviewed By: d h =- - Date: 2'S-37 Review Method: Detailed Design Review Comments: NC Approved By: [M Date: 3 9 '7 Clamp oualification for Support 2RC147-SR2 ~

1. Purpose / Objective The purpose of this calculation is to qualify clamp of Support 2RC147-SR2 for the governing Upset load of 1326 lbs (see page 10 of Attachment A to this stress report).
2. Methodology / Acceptance Criteria As stated in Design Input 4.1 and described in Section 6.
3. Assumptions and Limitations 3.1 Assumptions None 3.2 Limitations None 3.3 Engineering Judgements/ General Notes 3.3.1 This calculation is very conservative, as clamp reinforcement (see page 5 of Design Input 4.2) is not being taken credit for.

3.3.2 This calculation also does not consider a possible five degree clamp swing angle. Although, this is not conservative, any possible swing angle is more than compensated by not taking credit for the clamp reinforcement (see Section 3.3.1).

4. Design Input 4.1 SWEC 79-14 Calculation for Subsystems 2RC-2, 3, 4, & 5, J. O. 13430.01, Rev.0 4.2 NDIT No. ZDE-97-012, dated 02-17-97 (see Attachment H)
5. References 5.1 ADpendix I to ASME B&PV Code, 1977 Edition through Winter 1979 Addendum REVISION NO O 1

l l

Exhibit E NEP-12-02 COMMONWEALTH EDISON COMPANY RGvicion 4 l CALC. NO: 22S-2-004M-207 PROJECT 4794 (Comed) ) 9432-794 (S&L) PAGE NO.12 j A th.cL eag C i

6. Calculations A copy of the sample clamp qualification (from Design Input 4.1) is attached at the end of this calculation.

This calculation follows the same methodology (with one exception as described in Section 3.3.2) and uses the same nomenclature. P = 1326 lbs alpha = 44 deg do (Pipe OD) = 3.5" - From Design Input 4.2: b = 2.5", t= .25", d = .75" Using similar clamp data, see pages 3-4 of Design Input 4.2: E = 8" and 1 2 = 5" 11 = E - d /2 = 6.25" a1 = 1/(bp7 == 1.60 a 2 = 1/ (tb 2) = .64

                     =                                  6.40          a 4 = 1/(b-d)t = 2.29 a3 a3           =               1/(t(b3b)3 b/     -d ) t = .66              a 6 = 1/(b-d)t 2 , g,14 a7           =               .25a 1    =    .40               a g = .0654a 4 = .15 kt           =               .5 sin 44      =    .35          k 2 = 3cos44 = 2.16                                k 3 =0 Section 1          fa                       =    Pa k,      =    743 psi (negligible) r fg = P1 1a 2                            2    =   11457 psi           f by " P1 1a 3k3                     =  0 Section 2-2:

fa = Pa k = 1063 psi (negligible) f 3x = P1,4a k, = 9452 psi f by = P1,a ~ s3 k = 0 f shear = a 7'k3 +a) g = 1345 psi Allowable Stresses: For materials SA-312 TP-304 and SA-376 TP-304 at 680 deg: (see Ref. 5.1) F[" F x == 1778 0.6F yn 0 psi= 10668 psi F by = 0.75F yn = 13335 psi S;ction 1-1: fbx/Fbx +fby/Fby = 11457/10668 = 1.074 (see note below) Section 2-2: f3x/Fb 9452/10668 = .886 Snear :x +f shear fby/Fby = =3 1 4 5 psi < 0.4F yn = 7112 psi Note: 7.4% overstress is concluded to be acceptable based on the conservatism described in Section 3.3.1 and the fact that the clamp temperature is lower than the pipe temperature (e. g. at 500 deg: 0.6Fyn = 11640 psi and IR Decomes less than 1.0)

7. Summary and Conclusions The clamp of Support 2RC147-SR2 is acceptable.

REVISION NO O l

Q s.. N -

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                                                                                                                       +
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                                                             'CNd '  I\/                 s*-in et^at t Y-2 N

g - OUTSIDE FACE f =:$ l DF RUN PIPE

    @ SECTtoN                         g-1           -

a ' s. b* = O 6 *j E '_ = o 2 2_

           =- )R y IC l = l8GSXD'67X0 8 95= IIbD a' =

(N54tE918LE)g,, 6 ,. ,  ;\ h b

   ~ibx k 0 2 Nz lggsx6 31xo 22x2 93 5.P S                                        i
                                                                                                                 ~ 1- a
    $by=.D.2<a3 3k =1BN563 I M3*W 4 0 3 ).P b                       ,   -          6       =a 23 "i     eLs'-d'.)
    @ SECT IotJ                         2 -Z.
   *r                                                                                     6;    ' P          -d) = 2' ' C Ia = PM4 or a,)<o ==/677x leo oes=is e Pe OW=cyECTED)            y r['c.2 5 a , - C I b 7

TbX* YzA 5 k z =l85574 97SWZblXZ93 1  := 6 1 2 l ?Si . o casa ao =o . 0 3 b3 = ?A 2 As k$ a#

                                                      \ 855x 4 275?21 D*LS '5
       .x         - -                            =

n r = o rv

        ' ' ' d C 7 h t + Gd =tB55(q ks75>a 03 +s.cssa) K ' ~., n,-4                        u 2
                                                                                                                        ~

p:: m 2:5.:.=w.:n = lo 5 g 19 u m .: ,. o A *. ! 2 e ~4 . C o q , 5 u, (c , g ;2

         ~
                                                                                                                  .      ,m

STONE & WEBSTER ENOMEERING CORPORATION .ALCULATION SHEET ,, ,,,,f ,,,,,,,te ,t ,,,, ,,, , , , , , - em. .. (34M ol ~gioW OMI'TN & o PatRhase/satt navissta/cutcuta/satt A RAZ.7_.AO, I t - t 5 - 82 p. c.tf a fe _ 2 2 -pz, isotermotor at SUSJECT/ TITLE V 0; ;f*i t PW%s0:2Rc-o2.,.SPRTNo. RcR.S-2115> PTNo: I ?-. C, CaCc. No. : 22s 004/1 20~/ SCVisioN MD,

  • O Attac h est 'C Att_oWAlbLE_ STREs5Efr- e2j e n/nwE 67D l0 FoR. MAT'L_ A Sta.TPS o4- A7 7: 3 40 7444A 9
AZ44%

EL = 2.6 7 >T y s .= 2 1 7d x k'i, C__cs = i s s, i4-I .> 046 Yb y = Q G Fyk .= 0 6 X ? ) J 8 0 = I 5 0 70l'/7

  )Sl*4 8 Y b y = O 7 GFy,= 6 7 57' 2.f 780 = 16.546 fia                                      '
                .SEcTioN 1-1 i_

A1.f c.- bbx 4 bb'/ = '7.5~45' 4 407 1 Dggf / l4/ Fbx Fby 13070 /6340

                 .SE.cT ion a-2.
                 .bs x           dsy             6IZ1 4                               4 A-730                  a 75~g/_ f e

, Fbx Fby /3c 70 /6340 _S HEA R g .::- /43 2. pt/ AIf a 1 5 . l 2 -. Vy = O *4 Fyw =. O-4 / 21780= B 7/LJ s .

                                      /-  i    ,  r. n o
                                                   .      1/     s    - - n ~ .- . < -

s f ( Attachment D NDIT ZDE-96-032, dated 11-26-96 Calc. No. 22S 004M- 207 Revision No. O Attachment No. D

   \                                                                                          Page    1    of        2
                                                                    -- ww       - - - -

to p m - EL-C @ d E32:s 2/ 6 ATTACHMENT B PART 'l COMED NUCLEAR DESIGN INFORMATION TRANSMITTAL sSAFETY.RELATED l ' Originating Organization DNON SAFETY RELATED sComEd NDIT No.JDE-96 032 JREGULATORY RELATED 00ther (specifyl i Station, Zion _ Unit (s) 1&2 Design Change Authonty No.: N/A page_ i of ,- System Designation: RC To L. Kaushansky - S & L Subject Pressurizer SafetviRelief and Discharge Picino and Succort Desian Critena __ K, Panucci

            -                                            DE Zion                               mJ
                                                                                                                 ..// /; 6 / 9 C J. Minlehiello                            M&S DG
            .. _                                   ._                                                               //
                                                                                        ..m                          ./.% /96 Status of Information:                 zApproved for Use D unventied OEngineenng Judgement Mothed and Schedule of Verification for Unverified NDITs:                      N/A Desenption of Information: UFSAR Section 5.4.11.1 provides the piping and piping support criteria for the pressurizer safety / relief and discharge piping. Per this section, the stress limit for the pressunzer safety / relief piping (this is the safety re#ated portion from the pressurizer to the valvo discharge) for the combination of loads described is 1.2S,. This section does not exoticitly state the stress limit for the nnn-safety related discharge piping (the pip:ng from the relief / safety valves to the PRT) otner than it must be capable of preventing the back pressure at the code safety valves from exceeding 20% of the setpoint pressure at full flow. To ensure this function can be                                        e performed th emergency stress limit of 2S,, stated in UFSAR section 3.7.3.2 shall be used.                                        .

Condition Loadings" as defined in sections 4.2.1.2 and 4.2.1.3 in . e ccrresponding weight, thermal. OBE ano relief valve (PORV) load:ngs, For ciping restraints installeo tne discharge piping, the " Normal Condition Loadings" apply for tne corresponding weight a ano therm l leaoings. As discussed in UFSAR sect:on 5.4.11.1, the piping restraints instailed on  ; t the pressu safety / relief and oischarge piping must be 'suffic:ent" to "withstano" tne DBE and transient con This can be accomplished by meeting " Emergency Condition Loacings" as defined in sectio . .. TLD MS 12, Rev. O, for the loadings resulting from weignt, DBE, safety valve discharge trans thermal (thermal caused by the transienti loadings. Use of emergency level *or these loading s t. censistent vvith using the emergency pipe stress limit cf 2S.,. l Purpose of issuance: To provide the piping and pipe support design criteria fur the analysis of the pressunzer safety / relief and discharge piping. Source of information: Zion UFSAR. TID-MS-12. Rev. 0 ' i Distnbution: K. Panucci. E. Massey A. Mikottis, J. Minichiello, Master File r File No.._CZDE 96 597 CHRON No.:_ N/A ( s Cafe.No. 22$,g coqrn.zoq Re viseo.J N. , o A h A,e-L o fage t/ruaC

k Attachment E NDIT ZDE-97-003-1, dated 02-27-97 Calc. No. 22S-2-004M-207 Revision No. O Attachment No. E Page 1 k of 7 i

                                     '.            ATTACHMENT B, PART 1 in s COMED NUCLEAR DESIGN INFORMATION TRANSMITTAL ESAFETY RELATED -                        Originating Organization                _NDIT No. ZDE-97-003 1 DNON SAFETY RELATED               E Comed OREGULATORY RELATED               DOther (specify)_

Station -ZION Unit (s) -1&2 Page 1 of 6 Design Change Authority No.: E22-1(21-97 209 System Designation: RC To Saroent & Lunav Subject. Piping design input for Subsystems RC 2,3,4,5 & 2RC 2,3,4,5 re analysis. Alan F. Mikottis 0,eoerer Desian Enor. Posnen

                                                                   #ff#M" Preparet's 5.gnature
                                                                                                         ~2 - 24 4 7 Oste Ken R. Panucci                 Desion Enor.                                  O"                 .2 -2 7- f 7 a ..                           Po.a.on                       n.... . s.an.iu,e                   o.ie Status of Information:         E Approved for Use             OUnverified OEngineering Judgement Method and Schedule of Verification for Unverified NDITs:

Description of Informaiian: See Pace 2 for information. I NDIT #ZDE 97 0031 supersedes #ZDE 97-003. All the previous information previously transmitted under NDIT #ZDE-97-003 is contained in this NDIT with the addition of 2 Comed calculations which replace Grinnell hydraulic snubbers RCRV 001 & RCRV 2001 with Lisega snubbers. The new Lisega snubbers have lower load allowables, especially RCRV-2001. Only the snubbers were replaced, no other modifications to the supports were done. The design basis calculations are listed below along with the level A D Lisega snubber allowable loads. RCRV-001 Comed Calc. # 22S-1-004M-183, Rev. O,07-02 96. (Lisega Part #3072RM3) RCRV-2001 Comed Calc. # 22S-2 004M-157, Rev. O 02-29-96. (Lisega Part #3062RM5) (#3062 Series Snubber Level A/B = 21,200#, Level C = 28.000#, Level D = 36,400#) @ 302' F (#3072 Series Snubber Level A/B = 39,300#, Level C = 53,500#, Level D = 67,500#) @ 302' F Purpose of issuance: Re analysis of Zion Subsystems RC-2,3,4,5 & 2RC 2,3,4,5 to incorporate revised valve weights and correct pressures & temperatures. Source of Information: See References on Page 2 8 Lisega Catalog, Product Group 3, " Shock Absorbers, Rigid Struts '93". Distribution: A. Mikottis (Design Engr'g) K. Panucci (Design Engr'g) E. Massey. (CFW) Original L. Kaushansky (Sargent & Lundy) File No.: NA CHRON No.: NA Cafe, No.

  • 225 2- oo9N-207 Revisios (Jo. . O Attacb c i E (bg e. 2

ATTACHMENT B, PART 2 COMED NDIT No.2DE 97-003 1 NUCLEAR DESIGN INFORMATION TRANSMITTAL > Page _ 2 of 6 1/J!.!.F3.'t1A 1(2iRC80C0A(B) 180# Valve Body w/o Actuator (Ref. [1]) 260# SB 0015 Limitorque Actuator (Ref. [2])

                                        ,13#_ " Insulation (approx.) (Ref,13])

469# Total (Use same CG that SWEC used in their analysis. Your analyzed weight needs to be within ::: 20% per NCIG 05 tolerances.) Desian Basis Analyses The following calculations are the latest design basis documents: Subsystem RC 2, 3, 4, 5 SWEC 7914 Calc. R/0, Dated 01/17/83 s

  • S&L Calc. EMD-066312 R/1 (incl. Addendum "A"), Dated 06/27/90 (The S&L Calc. is a partial model only)

Subsystem 2RC 2, 3, 4, 5 SWEC 7914 Calc. R/0, Dated 05/06/83 S&L Calc. EMD 066121 R/0 (incl. Addendum " A"), Dated 06/04/90 (The S&L Calc is a partial model only) Q2f i an Pressure & Temperature (Ref. [41) Pressurizer to SRVs and Valves P = 2485 psi. T = 680' F 1(2)PCV 455C. 456. Downstream of SRVs and Valves P= 500 psi. T = 470' F 1(2)PCV 455C,456. References (1) Velan Letter Dated Aug. 29,1996 from Bertil Nilsson to Matt Gooder (Comed), Ref. BN 608 051. [2] Limitorque Corporation Center of Gravity Report #R 3277, Dated 4-16 96 (for Valves 2MOV-RC8000A(B)) for SB 0015. (3) SWEC 79-14 Calculations for Subsystems RC 2,3,4,5 Dated 01/17/93 & 2RC 2,3,4,5 Dated 05/06/83. C adt . Ile . : 2 21 2 - 00Qtf-2o ; (4) Zion DBD Zl-004, Rev. A, Section 5.7.4.3. P evon n., o s (. Attact,we d E Fsje 3 r ___:.

       *~ '
                  .           ~.....       . . _ . . . _ .

WPIT A ?)2-17 Co3-l

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                                                                               $50 McAnhur, Ville Stk.urrnt Quebec, Canada H4T1X8 DATE : Aug. 29,1998                           PAGE:     1OF1 FROM : Berill Nilsson                         FAX :     847-746 18'74 PHONE: (514) 748-7748 ext 241                 TO- :     Comed FAX-      : (514) 342 2311                   ,ATT.:     Matt Gooder
   .            REF       : BN-608-051                        C.C. '                      -

SUBJECT:

Your 2 iaxes date Aug 28,'9G. We have reviewed your requests and are pleased to respond as follows:

1) After verification of drawing 88405 2 we confirm that weight of 352 lbs, which is listed on this drawing is incorrect. Estimated weight of valve is approx.180 lbs and estimated weight of the Limitorque SMB.00 is between 225 -250 lbs. We back in the mid 70's advised Westinghouse of this. Drawings were never revised. ,

i

2) We have reviewed drawing P2-8905-N2 and aro pleased to advise following:
                                                                                                                /j                 .

a) Yoke on this valve will accommodato an SMB-00 actuator as is. Derefore there is no need to change out Yoke. . b) Stem in this valve is 1 1/8" x 1/5 x 115. Stem in valve to drawing 88405 2 is 1 1/8" x 1/3 x 2/3. Additionally stem to dwg 88405-21s UT Tested. As result you shouldiake Stem from valve to drawing 88405-2 in order to be able to used the samo Stem Nut as well as not affecting closing time. c) There is a slight difference in height between the two valves. Valve to drawing P2 8906-N2 is approx %" higher from Centerline to top of Yoke. Based ca past experience you should still be able to taka Stem from valve to drawing B8405-2 and install this Stem in valve to drawing P2-8906-N2. We do request that you verify that you have a minimum of 13/4" Thread engagement between Stem and Limitorque Driva Nut. d) After verification of weight on drawirig P2-89'08-N2 we believe the wefgTt of ~ 270 lbs is too high. According to information this valve should weigh approx 200 lbs without the handwheel. Would appreciate if this could be verified. We trust this meets with your acceptance. Should additionalinformation be required, please do not hesitate to contact us. Cale. Ih. : 225 2 0%t1 2n R evasu Ne. : O i B. Nilsson Attached E pajg q Velan Inc. Velan Valve Corp. 2125 wordavenu, CERTIFIED TO ISO 9001 A v,=, c' macul ou,6,e QUALITY STANDARDS ~ Gala hdustrid Park

                                                                                                ,.~,,.m.  ,.____.

n,r v.. w . ,,. oos.,

r. y ., e LIMITORQUE CORPORATION CENTER OF GRAVITY REPORT REPORT NUMBER: R- 32 7 7 l

CUSTOMER'S NAME: - Co M Mou WEALTAJ E6 /S o d ORDER NUMBER: 234767 Reg. o/a 744658 4 GENERAL DESCRIPTION OF UNIT: SB-oo,15"/#oo RPM uve. MoroR,

      /2." SM H V, stb C.I. L S C , 4TC.,LS, N b P I h                  -

P0 503152XX524 gd

                                  ~

g LIMITORQUE VENDOR CODE L200 VALVE TAG 2MOV-RC8000A M

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                                                     + X'       +Z TOTAL UNIT WEIGHT (APPROX. ):                        150 A LOCATION OF THE CENTER OF GRAVITY WITH RESPECT TG THE- POINT ORIGIN.                   (LOCATED AT INTERSECTION OF DRIVE SLEEVE CENTER LINE AND MOUNTING BASE. )

i AXIS X -Y Z LINEAR DISTANCE- (IN. ) (APPROX. ) -/ 6;4 23/4 CALCULATED BY: Gb CHECKED BY: ___ DATE: NS-94

N91T Nr. 2 QE-97003 l'. S os C ' LIMITORQUE CORPORATION CENTER OF GRAVITY REPORT - REPORT NUMBER: R- 327 7 CUSTOMER'S NAME: -Co M Mou WEALT4 Eb /So d ORDER NUMBER: 244767 Ra , o/a ?R4ss'B B GENERAL DESCRIPTION OF UNIT: $_g.oo, jfrS/Aoo RP M vue. Mo ro R, 12."SM M V, stb e.l. LSC , 4YC,l.S, Mb PI N P0 # 503152XX524

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LIMITOROUE YENDOR CODE L200 VALVE TAG f 2t0V-RCS000B ma , e; , Ca Qc , llo. ; 2kt 2 00!f4 - 20i

       '                                                                                               f M u.a flo.; O Mk%cd              E y +Z                            P"lc 6
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                                                                +X         +5 TOTAL UNIT WEIGHT (APPROX. ):                                ifo A LOCATION TO THE POINT ORIGIN.

OF THE CENTER OF GRAVITY WITH RESPECT (LOCATED AT INTERSECTION OF DRIVE SLEEVE CENTER LINE AND MOUNTING BASE.) ( __ AXIS y x z LINEAR DISTANCE (IN.1 (APPROX.1 -/ 6M 2M

       - CALCULATED BY: GbL                              CHECKED BY:          vE                     b/5-94 DATE:

Woli k Epi. 97.w3 HESTINGHOUSE PROPRIETARY CLASS 2 O' S U 0 Commonwealth Edison Company l Zion Station Units 1 and 2 DBD-Z1-004 Reactor Coolant System Revision A 12/19/91 5.7.4.3 General Design Requirements 5.7.4.3.1 The design pressure and temperature of the pressurizer safety / relief valve inlet piping shall be 2485 psig and 680*F based on pressurizer design conditions. (References 11.3.002, 11.4.001) 5.7.4.3.2 The design pressure and temperature of the relief valve discharge piping shall be 500 psig and 470'F based on safety valve discharge design considerations (see Section 5.7.4.3.8). (P,a f erences 11.3.002, 11.5.039) 5.7.4.3.3 The re'iief line piping materials of construction shall be compatible with the RC vater chemistry, as well as the nitrogen gas used to control the atmosphere in the PRT. Refer to the referenced documents for water chemistry information and recommended materials. (References 11.3.001, 11.4.001, 11.5.001) 5.7.4.3.4 The relief line piping shall be designed and analyzed for the applicable loads and transients defimd in the referenced documents. (References 11.2.010, 11.2.013, 11.6,001) 5.7.4.3.5 The piping design life shall be 40 years consistent with the plant design life. (Reference 11.6,001) l 5.7.4.3.6 The pressurizer safety valve inlet line shall be designed and sized to minimize pressure drop to the safety valves for the steam flow resulting from the maximum calculated insurge of reactor coolant into the pressurizer. (See Section 5.7.2.3.5.) The size is normally the same as the safety valve inlet (6 inches). ( The pressure drop is minimized since this line is part of the (qQt do.: 26 2.oo4h- tel (?t Apod flo. '. O AhtLtd 6 Pa) e T l Wed J

t s Attachment P NDIT ZDE-97-009, dated 02-05-97 Calc. No. 22S-2-004M-207 Revision No. O Attachment No. F Page 1 of 20

vum up.ca

      -                                   s          D NA'HIddN C      N,YdkT1                     e2 n.n isis:    ,,,,

COMED NUCLEAR DESIGN INFORMATION TRANSMITTAL '  ! ESAFETY RELATED I Originating Organization i CNON SAFETY RELATED ! 3 Comed NDIT No. 2DE 97 DO9 CREGULATORY RELATED I COther (specityL  !

                                                                              ~

[ l Station Zien Unitts) 1 & 2 Design Change Authority No.:_ N/A Page 1 et Ii . 1 System Designa: sore RC To L. Kaashantiv S & L i j Subject Pressumer SafetV/ Relief end Discheroe Piorna and Suppert Des on Criterle ' l K. Panucci

          .....                           e.   .

0F Zion W W'

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                                                                       %J.h..                      m2. o94 ~)
                                                                             . sL .CJ_
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w.. i Status of irformation: MApproved for Use CUnverified ' CEngineering Judgement I Method anc Gehedule of Versfication for Unverified NDITs: N/A The following Informati0n is being provided to support your piping analysis of the Urut 2 pressurizer relief piping an:f PORV I f t transient analysis applicab e to both Units 1 and 2: Latest Drawing Revisions (From Ref.11: Drawing i lOE133, dated 02/18/70 - Pressurizer Relief Tank, Units 1 and 2

       , Drawing L 143844, Rev. 2, dated 02/14/95 - PORVs (PCV 4 55C, 456), Units i and 2 I Drsw:ng 884052. Rev. H, dated 09/20/96, including pending changes from ECNs 001050E,00 and FCR 960096 - PORV block valves (RC8000A, B) Urists 1 and 2 i

I PRT Data (Nom.nal values from Ref.

  • 2 and 4. Datasheets attacned):

Pressure: 3 psig mnl.10 psig imex) CaG:.Jh. m s 2 W <oi Temperature: 50 degrees F (min) 125 degrees F (max) g %,,, jt , . p Water Level: Between 80 to 90% of the levelinstrument range A b.t .~ c , . r {' fgu; .2 I Walkdown Data, Ret 3 (NEP-04-04 Forms attachedt Valve 2PCV.456 eccommodate a 1/8 inch has a vertical displacement. clearance of 31/4 trches and an East West clearance s Purcoseosoing. dis::harge of issuance: To provide aesign input to support tr.e analysts ci the pressuri;er safetyirelief and Source of 190 mation- 1, Zion EWCS Equ:pment Data

2. Station Procedure IMD-RC60, Rev. O
3. Walkdown Data. dated 2/4/97 tattached)
4. UFSAR Section 3. 8.1. 2.1. 6
    ,    Distribt. tion: K. Panucci. E. Massey, A. M:kottis, B. Tref 4'

File No. N/A C H R O N N o.: NrA

UR$Mi 'ECH+HO FAN NO.8 PDS 746 2182 #2-05+9" 1S:41 11PCfl0 P.03 CD4TtCLit0 00CUMENI$ !! FDAMATICW -C2/C$/97 69:32 faciltty a 21N Dec Type e 0660V $wb Type = D3C he. 1198133 Status s ACTIVE Security = k $heet Lntt a 00 5 fety Classe _ Wpdate Peteetty= . Total Fre es. _1 tatest title Rt. Date/Rev- 02/18/74 _ pag 5$URI ktLitf Taux issued Osto 02/18tf8 Auth DCP teview Org; Ave Cytit:-. . test Review C*iginatore W120 Originator Dot Org/Dtt: he, e t'ip Sheet: Rev Date: Eev: ,,,,,_ Mod e la tystem e _ ,,,, 4de codea Disetpline - Desc Coce= hos Coc C,hg (gp Pas Att"%ts (ds Reveseesa. ssassas....aanesesseemees Contents' fj fj ;_ cf pl [ 7 *i

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i l Attachment G NDIT ZDE-97-011, dated 02-14-97 Calc. No. 22S-2-004M-207 Revision No. O Attachment No. G Page 1 of 3

ATTACHMENT B, PART 1 j COMED NUCLEAR DESIGN INFORMATION TRANSMITTAL i OSAFETY RELATED Originating Organization NDIT No. 2DE 97 011 DNON SAFETY RELATED E Comed OREGULATORY RELATED DOther (specif y) Station ZION Unit (s) 2 Page 1 of 2 Design Change Authority No.: E22-2 97 209 System Designation: RC To Chervi Boaaess (Westinahouse) Subject, Qualification of Pressurizer Nozzle Loads (PORV Piping) Alan F. Mikottis e...., _ Desian Enar. e.w.on d

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e.u n ay. r. s.on.i o.i. Status of Information: E Approved for Use OUnverified OEngineering Judgement Method and Schedule of Verification for Unverified NDITs: Dsseription of information: See Paae 2 for Pressurizer Norrie loads from PORV Pioina. Note The loads contained in this NDIT are identical to those transmitted oer NDIT

              #ZDE 97 007 except the PORV transient loads are 3X the previous values due to liould discharae, except FA is =6X. (See Note #9 on Paae 2)

Cg&c . /je, '. 22 5 1 co4M- 207 Re m aa tJo.' 0 ha d me c'. 6 Pyt 2 Purpose of issuance: Re-analysis of Zion Subsystem 2RC 2,3,4,5 to incorporate revised valve weights, PORV transient, and correct pressures & temperatures. PORV Pressurizer nozzle loads increased from previously evaluated values and require re qualification. , Final loads will be compared against these qualified loads to determine final acceptability. Source of information: Enveloped loads from several PIPSYS analyses being performed for Calc. #22S 2 004M-0207 (Preliminary). Distribution: A. Mikottis (Design Engr'g) K. Panucci (Design Engr'g) ( E. Massey (CFW) Original W.Trefz (Design Engr'g) L.Kaushansky (Sargent & Lundy) File No,' NA CHRON No.: NA

C - Comed NDIT CZDE-97-011 ZION UNIT 2 PRESSURIZER NOZZLE LOADS (PORV PIPING) LOAD TITLE LOADID FA FB FC MA- MB MC > DEADWEIGHT WGHT 857 766 30 712 -1163 -839 THERMAL MODE 1 THM1 1368 1151 625 992 -2886 3019 THERMAL MODE 2 THM2 1129 1336 470 910 -2342 3274 DYN OBE OBEH 558 859 509 611 322 1110 . DYN SSE SSE1 796 1230 724 1013 512 1528 SRV HYDR. TRN. TRN1 288 528 7.19 1171 703 1002 : PORV HYDR. TRN. TRN2 3000 1764 1260 2265 1596 2718

1. LOADS ARE REACTIONS OF THE NOZZLE TO THE PIPE. 1
2. LOADS ARE LOCAL. "A" IS AXIAL WITH THE PIPE, "B" & "C" ARE PERPENDICULAR.

3 FORCES = #, MOMENTS = FT-#

4. OBE, SSE, & TRANSIENT LOADS ARE +/ .
5. LINE 2RC146-6" IS ATTACHED TO THIS 6 " NOZZLE.
6. REFERENCE WESTINGHOUSE PRESSURIZER OUTLINE DRAWING #1097J51.
7. THERMAL MODE 1 IS NORM AL OPERATING, MODE 2 IS TRANSIENT RELATED.
8. THE ABOVE LOADS ARE ENVELOPED LOADS FROM SEVERAL DIFFERENT ANALYSES AND ARE CONSERVATIVE.
9. NDIT #ZDE-97-011 ONLY REVISED THE PORV TRANSIENT LOADS (3X) EXCEPT i FA (approx. 6X). OTHER LOAD CASES ARE UNCHANGED FROM NDIT #ZDE-97-007. g PP, o  :

w"lo. k h . l C:\AFM\NDIT1ZDE-011.XLS ?g7E =[,N I-L ^ o A.

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Page 2 of 2

                                                                                                                          -s i

AttachmeAt; f NDIT'ZDE-97-012, dated 02-17-97 7 4 F I 1 Calc. No. 22S-2-004M-207 Revision No. O Attachment No. H Page 1 of 6 s

t COMED NOCLEAR DESIGN INFORMATION TRANSMITTAL j GSAFETY-RELATED Originating Organization NDIT No. ZDE-97-012 ONON SAFETY-RELATED EComEd OREGULATORY RELATED OOther (specify) ll Station Zion Unit (s) 2 Page 1 of 5 Design Change Authority No.: E22-2-97-209 System Designation: RC To A. Gershman -S&L Subject Desinn Inout for Pinino nalysis of the Pressurizer Relief Pipina __ K. Panucci DF,- Zion

                                                                          .r. s ...
                                                                                                                 -                                       A//7/97 o.. .

A. Mikottis w .., DE-Zion #N///jd 2-/ 7-f 7

                                       ..m.on                         w    .r.       s mi .                                                             o.i.

Status of information: GApproved for Use DUnverified OEngineering Judgement Method and Schedule of Verification for Unverified NDITs: N/A

                                                                                                                                                                 .=

Description of information: This NDIT provides installed dimensionalinformation for supports M 2RC147-SR1,2. Pages 2 through 5 were prepared in accordance with Comed procedure NEP 04-04. 5 Purpose of issuance: To provide design input to support the analysis of Pressurizer Relief Piping. ( Source of information: 1. As-Built Field Dimensions Distribution: K. Panucci, E. Massey, A. Mikottis File No.. N/A CHRON No.: N/A ( :u b . th . 22 6 oO4h -20 'l i Rov'i m A.: 0 hiladln e d M fayc 2. l c _ - _ _ _

E Exhibit A NEP-04-04 I.. 1 Revision 1 WALKDOWN OBSERVATION RECORD Type of Walkdown: 0 0 N9M O 6 Date of Walkdown: f//M'!9 7 (S:udy, Designer's, Installer's, ther's) Design Change No.: 6 2 7 - J - 7 7 ,2 0 7 i

Participants:

i _-Department Name (Printed) Signature i i bl[- W.NE hdLY/t- hh j)/W R.J.kACzMAREW k. Racfmatelf ., I Significant Observations: [Use additional pages if necessary. Note, if attachments are expected to be used as controlied design input for calculations (i.e., dimensiona' data, etc.), then the attachments must be pror .'.y prepared and reviewed / verified.] No or  ? OL - 9 ] - 0 / 2 P'Y Co.&c. flo . . 225 -2 00tf h -20 l

g. Rc v'se on . J o . ', O Att ce4.m c wt'. 4 Feyc 2.

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t i Attachment I NDIT ZDE-97-021, dated 03-03-97 Calc. No. 22S-2-004M-207 Revision No. O Attachment No. I Page 1 of 2 7____.,...., -

                                                                                                                                                 - -     ' ' ~ '
                                                                                                                                                                           ~- - - - ' - ' ' - - - ~ ~ -
 'AUM UbM-0W                                      rox ho. ree r.s at:2                     es.e3.,7    1:ses             P.aa l                            COMED NUCLEAR DESICN INFORM ATION TRANSMITTAL NSAFETY RELATED                          Originating Organization           NDIT No. ZDE 97-021 l   l ' :NON SAFETY-RELATED aComEd                                 i i

ZREGULATORY RELATED COther (specify) i i Station Zion Unittsi 1&2  ! Page 1 of 1 Design Change Authority No.: E22 2 97 209 l System Designation: RC To A Petr>rson -S&L 1 l l Subject Desion incut for Picino Analysts of the P'essur ter Relief Pip'no

                                                                               .                                                  1 K Panucci
       ~...

e w, OE - Zion

                                                                    ,..w.,,.

h 3-I-77 w.. B Treft

       ~...

DE4en w Lb 010 L- 9 1

                                                                      .. . . .. a      o         ....

Status of Information; mApprovec for Use ~' Unverified

                              ] Engineering Judgement Method and Senedule of Verification for Unventied NDiTs:_ _N/A Descript!on of Information:                                                                                                .

CcmEd has determined that the fellowing cases should be evaluated for the PORV lift transient. 1. Satureed steam disenerging from the two FORVs at the ncminal set pressure of 2335 psig tnat coulo occur at power.

2. Saturated steam dischstging from the two PO AVs at tt>i nominal set pressure of 2335 psig that could occur at power followed by a transition to saturateo liquia at 2335 psig w.th:n the pressunzer (i.e. pressurizer becomes water-sclic) after tne PORVs are openea. This case would cover an inadvertent safety injectior at power with two charging pumps capable of filling the pressunzer water solid.
3. Water discharging from tne two PORVs 0, e. pressurizer is water solid) curing the LTOP j

concition. For analysis purposes and to al>ow for design margin use a set pressure of 519 psig l and subcooled liouio temperatu es betwoon 100 degrees F a-e 457 degress F. 6 Purcose of issuance: To provita dmgn input to support the analysis of Pressunzer Relief Piping. Source of info mation: 1. DBD-Zi 004, Rev. A {

2. Comed lener to the NRC datec 9/25/95 from 1.W. Simpkin to Document l Control Desk. "NUREG 0737 Item ll.D.1 ** l
3. Operating procedures GOP 1. Rev.12 end GOP 4, Rev.13 j

Distrioution K. Panucci, E. Massev, B. Trefz, B. Mammoser  ! File No.' N!A CHRON No., N/A l CaQe. ne,: 225-2 0o46-207 revossaa tio.: 0 A6tucbCnt I fy :. 2/ Fa 6

i l Attachment J NDIT ZI-EXT-1229, dated 03-07-97 Calc. No. 22S-2-004M-207 Revision No. O Attachment No. J ( Page 1 of 4

NEP 12 03 Nuct :r D: ign inform:.tian Transmittal " * " E Safety Related Originating Organization: O Non Safety Related O Comed O Regulatory Related NDIT No. Zl-EXT-1229 E Other (specify) Saraent & Lundy Station: Zip.n Unit (s):.2 Design Change Authonty No.; E22-2-97-209 Pm1da System Designation: RC To: V. Volot (Comed)- Zion

Subject:

Evaluation of Subsystem 2RC-02 for Revised Pressure. Temoerature. and Weicht of Valves 2RC8000A/B L Kaushansky Project Enoineer

  • Preparer Position Q3-07-97 Preparers Signature Date A 1 Gershman Reywwer Project Enoineer Posttion

_ 64 Sd_ Reviewers signature 03-07 97 Date Status of Information: @ Approved for Use O unverified O Engineering Judgment Method and Schedule of Verification for Unverified NDITs: N!B Description of Information: Based on the revised pressure, temperature, and weight of Valves 2RC8000NB provided in Ref.1, Subsystem 2RC-02 was reanalyzed (as documented in Ref. 2) and found acceptable and within the design basis requirements as explained below: The PIPSYS computer model was created using the latest (as confirmed in Ref.1) 2RC-02 design basis information documented in Ref. 3,4,21 and was updated to include the above mentioned revised pressure, temperature, and valve weight. Then this subsystem was analyzed for the following loading conditions: (a) Weight (b) Thermal modes with pressurizer hot / discharge piping cold and with pressurizer & discharge piping hot (c) OBE 1/2% and SSE-1% Seismic (1/2% and 1% indicate damping values) (d) SRV opening transient. The transient force time history was obtained from Ref. 3. Note that the generation of a force time history according to NUREG-0737 requirements is not in the scope of this evaluation and will be perfonned later as part of a commitment to the NRC (see Ref 5). (e) PORV opening transient. The transient force time history was based on RELAP analysis (see Ref. 6). Note that per Ref.19, in addition to the steam discharge, the liquid discharge due to the extended high pressure injection and low temperature overpressure protection (LTOP) events was also evaluated. Purpose of issuance To provide Comed with the results of the evaluation of Subsystem 2RC-02 for revised pressure, temperature, and valve weight. Source of Information: See References on page 3 of 3. Distribution: W.C Cleff Zion M. S. Zar - Zion F. G. Gogliotti Zion i W. Mammoser - Zion D. N. Diotallevi- 23 K. R. Panucci - Zion File No.: 9432-794 P. H. Kirsch / File 3.2 -23 Central File West - Zion CHRON No.: Ud E=umc coraroned Form Page 1 of 3 J.aC: ,/4,:225 2-004h -2e ; Fde: 12038-o doc See NEP Table of Contents cevui w No.. O lasuee 12/1m h tt a c$.rs t d ~) Pape 2

Nucizr Design Informatian Tran mittal NDIT No. gl EXT-1229 Page 1 of 3 The results of these individual analyses were then combined and compared to the correponding allowables provided in Ref. 7. The summary of the results appears below. Note that for these results to remain valid, the following changes to Subsystem 2RC-02 must be implemented: (a) Snubber RCRS 2205 must be added as shown in FCR 970016 (b) Main Steel for Support RCRS 2120 must be re!nforced as shown in FCR 970014 (c) Struts RCRS-2114 and RCRS-2115 must be amoved (note that rear end brackets and clamps can remain abandoned in place). These slotted supports are being rmmovad, since they cannot be readily ' qualifted for higher thermal loads that resulted from the revised subsystem temperature. Sargent 8 Lundy recommends that since piping shear lugs are welded to the clamp of Support RCRS 2114, the welds between these shear lugs and the pipe as well as the pipe in the vicinity of the shear lugs should be inspected. (d) Snubber RCRS 2121 must be removed (note that rear end bracket and clamp can remain abandoned in place). Summary of Results: (a) Piping stresses (including welded attachments) have been determined to remain within the corresponding allowables. (b) Supports RCRS-2120,2123A; 2RC147-SR2; and new support RCRS-2205 have been evaluated for the increased loads and found acceptable subject to the reinforcement of RCRS-2120 main steel. The evaluation (see Ref. 2,8, and 9) included the qualification of standard and non-standard components, aux. steel, and 1. P. structural elements (containment structural steel and pressurizer coffin C walls). Loads on all other supports have either decreased or increased within the allowable criteria defined in Ref.10. Note that qualification of support 2RC147-SR2 is based on the as-built information documenud in Ref. 20. (c) Pressure Relief Tank 2RC003 has been evaluated and found acceptable (see Ref.11). (d)criteria Loadsdefined on Pressurizer in Ref.10. 2RC002 SRV nozzles have either decreased or increased within the allowable (e) Loads on Pressurizer 2RC002 PORV nozzle have remained below the vendor qualified loads (see Ref.12 and Ref.13). (f) Displacements in Subsystem 2RC-02 have remained within the criteria specified in Ref.10, with the exception of displacements at the operator of Valve 2PCV456. However, based on the as-built walkdown (see Ref.14), it has been concluded that enough clearance exists around the valve operator to avoid any potential interferences with surrounding piping, steel, etc.. (g) Valve accelerations for Valves 2RC8000NB. 2PCV456 and 2RC8010NB have remained within the corresponding allowables (see Ref.15,16,17). Valve accelerations for Valves 2RC8010C and 2PCV455C have exceeded those allowables. These valves have been evaluated in Ref.18 and found acceptable. Valve accelerations in global coordinates for MOV Valves 2RC8000NB are provided below for your information and possible future use in 89-10 valve qualifications (see Ref.15): Combined Seismic and Transient Accelerations at CG Location (g values) Valve Upset Condition Emergency Condition X Y Z X Y Z 2RC8000A 1.128 2.407 1.240 1.184 2.415 1.285 2RC8000B 1.157 1.436 1.233 1.399 1.463 1.281

Conclusion:

The subject Subsystem 2RC-02 has been evaluated for revised pressure, temperature, and valve weight and ( has been found acceptable, subject to the implementation of the changes described above .

   ~

Electronic Controhed Form Page 2 of 3 See NEP Table of Contents Mc . N o ,

  • 2 2 5 00 4 r1 - 2 0 ~1 Revepeu no. . O ht.welved .~)

ht 3 - - - - - - '

Nucl:ar D: sign infsrmatinn Trcnsmittal NDIT N Zl-EXT-1229 Page 1 of 1

References:

u

1. NDIT ZDE 974031, dated 02-27 97
2. Calculation 225-2404M 207. Rev 0
3. SWEC 79-14 Calculation for Subsystems 2RC-2,3,4, & 5. J. O.134 80.01, Rev. 0
4. S&L Calculation for Subsystem 2RC42. EMD 066121, Rev 0, including Addendum A
5. Letter from J. H. Mueller (Comed) to U. S. NRC, dated 09-13-96,

Subject:

"NUREG 0737, item _II.D 1; Performance Testing of Relief and Safety Valves; Zion Nuclear Station Units 1 and 2; NRC Docket Nos.

50-295 and 50-304"

6. Calculation 225-B 004M-215, Rev. 0
7. N91T ZDE 96432, dated 1126-96
8. Calculation 22S-2-202S-017 Rev 0
9. Calculation 225 2-2018-006, Rev. 0 -
10. ZEP 5.10, Rev. U
11. Calculation 22S-2-004M-212, Rev. 0
12. NDIT ZDE-97-011, dated 02-14-97
13. Letter from B. S. Humphries (Westinghouse Electric Corporation) to A. F. Mikottis (Comed), Letter No.

CWE 97-116, dated 02-18-97,

Subject:

" Zion Unit 2 Revised Pressurizer Nozzle Load Evaluation"
    .14. NDIT ZDE 97-009,' dated 02-05-97
15. Calculation 22S-B-300S-030, Rev.1 MOV Seismic Thrust Limit of Zion Station Motor Operated Valves
16. Westinghouse E-Spec. 676279 for Pressurizer Safety Valves
    - 17. Westinghouse E Spec. 676270 for Control Valves 18, Calculation 22S 2-004M 214, Rev. 0
19. NDIT ZDE 97 021, dated 03-03 97
20. NDIT ZDE 97-012, dated 02-17-97 21._ Calculation 22S-2-004M-157, Rev. O I

C a f e . N o.'. 22 5 -2 ~00li tt - 20'1 ACUt slot) flo . '. O AttacAmed 7 Fay e 4/ rwak Electrone Controped Form Page 3 of 3 See NEP TatWe of Conter.ts

4 l (g l. Attachinant K LETTER FROtt J. H. MUELLER (COBSD) TO U.S. NRC, dated 09-13-96 Calc No. 22S-2-004M-207 Revision'No. O Attachment No. K Page 1 of 4 3 i :-

[ FROMs EeN-NO , m ko.: 708 Tot 2112 02 } 14:2? F.02 2'.on Genecahng Stauan 101 ShJoh Blvd. Zion, Illinois oco99 Telephone los t 746-2084 th '~ O , t S % U.S. Nuclea: Regulatory Commission Washington, DC. 20555 ATTENTION: Document Control Desk ' SUBJECT; NUREG 0737, item II.D 1 Performance Testing of Relief and Safety Valves 7, ion Nuclear Station Units 1 and 2 NRC Do ket Not 50.795 nr_d 50-304

REFERENCES:

1) T. Simpkin letter to USNRC, dated Septemeer 25,1995
2) April 24,1996 Teleconference between USNRC, EASI, and CemEd In reference 1, Comed provided additional inictmation regarding the analysis that was performed in response to NUREG 0737, Item II.D.l. During a conference call (reference 2) the NRC expressed contems regarding the analysis methodology employed. Suesecuent to this conference call, Comed has decided to pursue the installation of a modification rather than continuing with the development of an acceptable analytical app:cach.

The purpose of this letter is to document Zion Station's in:ent to install a modification to address NUREG 0737, Item II.D.1 and to provide a proposed schedule for modification installation. The modification will address the discharge loading associated v.ith the operation of the pressurizm safety valves. Several modification options are being considered. The options include elimination of the loop seals, modification of piping, and/or modification of supports. The proposed schedule associated with the installation of the modification is included in attachment A. s Ca ec , No. . 225 oo4tf - 2 o 1 Revasou no., o ( , A6t.aeb. cwt k Pyc 2 _ _ _ _ _ - - --- I

  "0 N '- EcN-N0                     ,,      rax No,s  reg 746 2112                          22-84 97  uip   p,g3 l-Picase direct any questions to Joe Benucci of our System Engineerin;; Depart:nent at (847) 746-2084, extension 3010.

61 Sincerely,

                                                                                               . w J. H. Mueller Site Vice President Zion Station Attachmen:: Proposed mqdification schedule ec:     A. B. Beach, Regional A6ninistrator, Region !!I C. Y. Shiraki, Zion Project Manager, h1R s

Acting Senior Resident inspector, Zion Station J. Yesinowski, IDNS Resident inspector, Zion Station t ca.L: th, 221 2 004 n Lo n Revium No.: o-hitacRnsul K Pnp e t

F A 0M s -' ttN-H0: .rax ho.: fas 746 211:

                                             .f ._                                                    82-04-97 14:27    P.04 c.
                                                               . Attachment A Proposed Modification Schedule initial Scoping an'dOption Iden:iCeation            9/30/96 Perform Detailed Walkd$wn ofI? nit 2                10/31/95 (Z2R14 Refueling Outage)

Perform Detailed Walkdown ef Unit 1 4/30/97 (ZlRIS Refueling Outate) Install Modification on Unit 2 Z2RI S (Scheduled for 3/23/98 - 6/1/98) . Install Modification on Unit 1 Zl R16 (Scheduled for 9/3/98 - 11/14/95) 4 t I Cage No. : 2 2 s -a - oo9tr.2o r ' Revisioou No.t O

                    * ==*mmena AL1!ac Mmer.i K Pje 4/ wak

T Attachment L LETTER FROM B. S. BUMPERIES (WESTINGHOUSE ELECTRIC CORP.) TO A. - F. MIKOTTIS _ (C00MD) , LETTER No. CNE-97-118, dated 02-18-97 4-Calc. No. 22S-2-004M-207 Revision No. O Attachment No. L Page 1 of 2

N ' VD0 F46 2112 e2-19-97 13:51 P.e2 W8stingh0Uls Eftergy Systems n= ses

                                                                                     ******m8*s** 152nm Electric Corporation CWE-97-11 g February 18,1997 Mr. A. F. Mikottis ComBd                                                                    Cod:.No.: 225-2 M h- m Zion Nucisar Station                                                     gcy,3,g g,                   o 101 Shiloh Boulevard Zion, IL 60099                                                           ADC$ twC ^I                    ^

f%?c 2 /fW L Comed Zion Unit 2 Zion Unit 2 Revised Pressurizer PORV Nozzle load Evaluation

References:

1. Zion Unit 2 NDIT No. ZDE 97-007, dated 1/31/97
2. CWE 97111. " Comed Zion Unit 2 Pressurizer Nozzle Load Evaluation,"

dated 2/5/97

3. Zion Unit 2 NDIT No. ZDE.97 01), dsted 2/14/97

Dear Mr. Mikottis:

We have cocipleted our evalus.non of the pressurizer piping nozzle loads tranunitted by NDIT No. ZDE.97 007 (reference 1) and revised PORV nozzle leads as transtnitted by NDIT No. DE.97 011 (reference 3). The loads were shown to be acceptable. The evaluation of the loads confonns to the design requirements detailed in UFSAR Section 5.4.10.2. This _ evaluation is also applicable to Zion Unit I loads. Documentation supporting this conclusion can be found in the Westinghouse ID_S document storage system under calculation number W.SMT 96151 Revision 1. If you have any questions or require further information on this matter, please contact Cheryl Boggess (412) 374-6273. Very truly yours, WESTIN0 HOUSE ELECTRIC CORPORATION M i B. S. Humphries, Manager ( Comed Project Operating Plant Programs cc: 3. A. Johnson c:ct m :rnI Junt gnq Njl):2[ [661 '${ 'pi _ _ - _ - . _ _ )

ZRA97018 ' ATTACllMENT A Sketch Showing Changes Made to Unit 2 Power Operated Relief Valve Piping Supports During Z2R14

                                                                                          )

T ATTACHMENT SCHEMATIC OF MODEL FOR REllEF VALVE PIPING SYSTEM Reduction Reducer toe

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vatve Block Block vahe valve q p 64nch _ 00 pipe N Relief valve-f h 34nch Pressurtzer C D pipe 34"Ch CD pipe 64rw.h Lately [ Reducer tem

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I " Salety Recuction _ valve 4g-system W VerbemI 3 _ S e w w' lo cP bo W a l Sb w fi IE**VO d

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Eneher i E"

12. Inch CD pdp9 1

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        . ZRA97018 t

6: ATTACIIMENT B Commitments identified in ZRA97018

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AlTACHMENT B Page1of1 List of Commitments Identified in ZRA97018

The following table identifies those actions committed to by Comed in this document.

Any other actions disedised is this submittal represent intended or planned actions by Comed. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify Mr. Robert Godley, Zion Station Regulatory

   -Assurance Manager, of any questions regarding this document or any associated                  o regulatory commitments.

t Commitment Committed Date or Outage Comed will perform calculations for the Unit 1 PORVs similar to those Prior to entering a performed for Unit 2 and install any necessary. modifications. The Mode when the Unit I calculations will be performed using the same methodologies as PORVs are required the Unit 2 calculations. The Unit I stress calculation will evaluate the to be operable bending- moment applied to the Unit 1 PORVs against the limits during ZlR15 (Unit identified in the EPRI test program. 1) The PSV modifications and associated analyses will include evaluation Z2R15 (Unit 2) of the PSV discharge loads in combination with SSE loads. ZlR16 (Unit 1) , In accordance with the NRC Staff request (Reference 3), Comed will 12/1/97 provide a description of the PSV modifications for staff review and , approval prior to installation. The PSV modifications committed to in Reference 2 will be designed Z2R15 (Unit 2) such that the expected inlet; piping frictional and-dynamic pressure ZlR16 (Unit l) losses for full flow steam conditions will result in stable performance of the PSVs. As a part of the PSV modification committed to in Reference 2, the maximum applied bending . moments will be determined and evaluated. ki\11cgroupimisc-sub\porv\porvtran1. doc _ u}}