ML17194B618

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Rev 0 to Dresden Nuclear Power Station,Units 2 & 3,Plant- Unique Analysis Rept,Vol 4,Internal Structures Analysis
ML17194B618
Person / Time
Site: 05000000, Dresden
Issue date: 05/31/1983
From: Russell Adams, Mcinnes I, Talbott D
NUTECH ENGINEERS, INC.
To:
Shared Package
ML17194B616 List:
References
64.305.1103, COM-02-041-4, COM-02-041-4-R00, COM-2-41-4, COM-2-41-4-R, NUDOCS 8307070218
Download: ML17194B618 (35)
v • d • e


Text

Approved by:

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 PLANT UNIQUE ANALYSIS REPORT VOLUME 4 INTERNAL STRUCTURES ANALYSIS Prepared for:

Commonwealth Edison Company Prepared by:

NUTECH Engineers, Inc.

San Jose, California COM-02-041-4 Revision 0 May 1983 64.305.1103 D. c. Talbott f~~/

I. Do Mcinnes, P.E.

Engineering Manager R. H. Adams, P.E.

Engineering Director Issued by:

i.

8307070218 830627 PDR ADOCK 05000237 P

PDR

\\

I Project Director nutech ENGINEERS

TITLE EFFEC-TIVE PAGE(S) 4-iii-4-viii 4-1.1-4-1.5 4-2.1-4-2.15 4-2.16 4-2.17 4-2.18 4-2.19

'1-? ?n REVISION CONTROL SHEET Dresden Nuclear Power Station, Units 2 and 3 Plant Unique Analysis Report Volume 4 REPORT NUMBER: COM-02-041-4 Revision O I. D. Mcinnes/Engineering Manager INITIALS

!2vt:

INirtIALS D. C. Talbott/Consultant I M. D. Pratt/Engineering Analyst

~s R. Fernandez/Consultant II' f2cvf INITIALS C. T. Shyy/Senior Engineer INITIALS INITIALS INITIALS PRE-ACCURACY CRITERIA EFFEC-PRE-ACCURA.CY CRITERIA REV PARED CHECK CHECK TIVE REV PARED CHECK CHECK PAGE(S) 0 /kt' ~

N/A 4-3.1

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ABSTRACT The primary containments for the Dresden Nuclear Power Station Units 2

and 3

were designed, erected, pressure-tested, and N-stamped in accordance with the ASME Boiler and Pressure Vessel Code,Section III, 1965 Edition with addenda up to and including Winter 1965 for the Commonwealth Edison Company (CECo) by the Chicago Bridge and Iron Company.

Since then, new requirements have been established.

These requirements affect the design and operation of the primary containment system and are defined in the Nuclear Regulatory Commission's (NRC)

Safety Evaluation

Report, NUREG-0661.

This report provides an assessment of containment design loads postulated to occur during a

loss-of-coolant accident or a safety relief valve discharge event.

In addition, it provides an assessment of the effects that the postulated events have on containment systems operation

  • This plant unique analysis report ( PUAR) documents the efforts undertaken to address and resolve each of the applicable NUREG-0661 requirements.-

It demonstrates that the design of the primary containment system is adequate and that original design safety margins have been restored, in accordance *with NUREG-0661 acceptance criteria.

The Dresden Units 2 and 3 PUAR is composed of the following seven volumes:

0 0

0 0

0 COM-02-041-4 Revision 0 Volume Volume Volume Volume Volume 1 -

GENERAL CRITERIA AND LOADS METHODOLOGY 2 -

SUPPRESSION CHAMBER ANALYSIS 3 -

VENT SYSTEM ANALYSIS 4 -

INTERNAL STRUCTURES ANALYSIS 5 -

SAFETY RELIEF VALVE DISCHARGE LINE PIPING ANALYSIS 4-iii nutech ENGINEERS

0 Volume 6 -

TORUS ATTACHED PIPING AND SUPPRESSION CHAMBER PENETRATION ANALYSES (DRESDEN UNIT 2) o Volume 7 -

TORUS ATTACHED PIPING ANALYSIS AND SUPPRESSION CHAMBER PENETRATION ANALYSES (DRESDEN UNIT 3)

This volume documents the evaluation of the suppression chamber internal structures.

Volumes 1 through 4 and 6 and 7 have been prepared by NUTECH Engineers, Incorporated ( NUTECH), acting as an agent to the Commonwealth Edison Company.

Volume 5 has been prepared by Sargent and Lundy, who performed the safety relief valve discharge line (SRVDL) piping analysis.

Volume 5

describes the methodology and procedures used in the SRVDL piping analysis

  • COM-02-041-4 Revision 0 4-iv nutech ENGINEERS

TABLE OF CONTENTS ABSTRACT LIST OF ACRONYMS LIST OF TABLES LIST OF FIGURES 4-

1.0 INTRODUCTION

4-1.l 4-1. 2 4-2.0 INTERNAL 4-2.l 4-2.2 4-2.3 4-2.4 4-2.5 4-3.0 LIST OF COM-02-041-4 Revision 0 Scope of Analysis Summary and Conclusions STRUCTURES ANALYSIS Component Description 4-2. L l Catwalk 4-2.1.2 Electrical Conduits Loads and Load Combinations 4-2.2.l Loads 4-2.2.2 Load Combinations Acceptance Criteria Methods of Analysis Analysis Results 4-2.5.l Closure REFERENCES 4-v Page 4-iii 4-vi 4-vii 4-viii 4-1.l 4-1.2 4-1.4 4-2.1 4-2.2 4-2.3 4-2.8 4-2.9 4-2.10 4-2.13 4-2.15 4-2.16 4-2.17 4-2.20 4-3.l nutech ENGINEERS

ASME co DBA ECCS IBA IR LDR LOCA NRC NVB OBE PUAAG PUAR PULD SRV SSE VB LIST OF ACRONYMS American Society of Mechanical Engineers Condensation Oscillation Design Basis Accident Emergency Core Cooling System Intermediate Break Accident Inside Radius Load Definition Report Loss-of-Coolant Accident Nuclear Regulatory Commission Non-Vent Line Bay Operating Basis Earthquake Plant Unique Analysis Applications Guide Plant Unique Analysis Report Plant Unique Load Definition Safety Relief Valve Safe Shutdown Earthquake Vent Line Bay COM-02-041-4 Revision 0 4-vi nutech ENGINEERS

Number 4-205-1 4-2.5-2 COM-02-041-4 Revision 0 LIST OF TABLES Title Internal Structures Component Loading Identification Internal Structures Controlling Load Combinations Catwalk Stresses for Controlling Load Combinations Maximum Suppression Chamber Shell Stresses at Catwalk Reinforcement Beam Location 4-vii Page 4-2.12 4-2ol4 4-2.18 4-2.19 nutech ENGINEERS

Number 4-2.1-1 4-2.1-2 4-2el-3 COM-02-041-4 Revision 0 LIST OF FIGURES Title Plan View of Suppression Chamber Internal Catwalk Suppression Chamber Internal Catwalk-Typical Support at Miter Joint Suppression Chamber Internal Catwalk-Typical Support Between Miter Joints 4-viii Page 4-2.5 4-206 4-2.7 nutech ENGINEERS

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4-

1.0 INTRODUCTION

In conjunction with Volume 1 of the Plant Unique Analysis Report (PUAR),

this volume documents the efforts undertaken to address the requirements defined in NUREG-0661 (Reference 1) which affect the Dresden Units 2

and 3

internal structureso The. internal structures PUAR is organized as follows:

0 INTRODUCTION Scope of Analysis Summary and Conclusions 0

INTERNAL STRUCTURES ANALYSIS (Catwalk and Electrical Conduits)

Component Description Loads and Load Combinations Acceptance Criteria Methods of Analysis Analysis Results The INTRODUCTION section contains a general overview discussion of the internal structures evaluation.

The INTERNAL STRUCTURES ANALYSIS section discusses the specific components,

loads, criteria,
methods, and results associated with the evaluation.

COM-02-041-4 Revision 0 4-1.1 nutech ENGINEERS

4..1.1~1;.

i *,scope*-'of--Analysis1* "*

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-~:* -~The:.triteria presented in Volume 1 are used as the

    • .*'basis-.* for a1*1 *of *the ' Dresden Uni ts 2 and 3 internal

': 1 *~'"structures *1 evaluations described in this volume.

The E.. : l::_::.'.

~'internal. structures* evaluated are the catwalk and

':electrica-1 conduits.

These structures are not required

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-:*"' for_'~ the'* safe operation of the primary containment

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  • "system:*.during accident conditions.

These internal structures are evaluated for the effects

";* ~- -

1

'.. :of -'-Ioss...l'of-coolant *ace ident ( LOCA) and safety relief 1 *valve: ( SRVl '*,discharge-related loads, as defined by the

.?*:~.* ::;>::Nu'c*lear' Regulatory Commission 1 s (NRC) Safety Evaluation

... y.is* ;,.. * :._R'eportv= NUREG-0661 and the "Mark I Containment Program Load Definition Report" (LDR) (Reference 2).

The LOCA and SRV discharge loads used in this evalua-tion are formulated using the procedures discussed in Volume 1 of this reporte The evaluation includes a structural analysis of the internal structures to ensure that these structures do not fail and result in damage to safety-related components.

COM-02-041-4 Revision 0

~' 4-1. 2 nutech ENGINEERS

, r The results of the structu~-~~-- ~":a~~a~ion1 tQ.r eac:t;t -: l<;>ad are used to evaluate load combinations for the internal structures in accordance with the*, "Ma.rk. I *:-*Containment Program Plant Unique:;. Analysis

.Appl ~-cation Guide 11

( PUAAG)

(Reference

3) c,
  • -The. eva.iuatiqn. :-results are conservatively compared.:with..* the accep1t.;ince limits specified by the applicable.. sections ~o~_-,..t:he PUAAG and the American Society of.. Mechanicall'.Engif1eers (ASME)

Code (Reference

4) to ensure
.tha:~,;_*:S~:fety-related components are not adversely affected.

Other internal structure~-evaluat~d~were ~he vent line

drain, thermowells, and. the.: emei;:genc,y

~c.ore cooling system ( ECCS) suction strainers.*, *,_~:hey ::P!P;~.~.described in Sections 2-2.1, 3-2.1, *6-2.:1;* andt7-2,.-:1,~:iz~spectively.

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";'fhe I! evaluation*' dO"CUffiente"d in this Volume is performed c..:.* r:r; _*,

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,.. -for**. the. Dre*sden. *Units.. ' 2 *and 3

internal structures L::'cl :o*

.:::: idei'ltifiedc Hv*section :'l-1.l and described in Section

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..,.. -,,_,1i;;.,2*. L* ~.-* c.rfhese :'structures. are the catwalk and electrical l [ ;,

-~ :. :*. conduits.>

t ::- ** "= ',_:,.,. The -.LOCA**"'and. SRV discharge-related events defined in NUREG-0661 result in hydrodynamic loadings on the internal structures.

The major loadings which affect the catwalk and electrical conduits above the suppres-sion pool include pool swell impact and drag. loads, froth impingement loads, and pool fallback loads.

The major loadings which affect submerged portions of the catwalk include submerged structure loadings.

Con-servative values for these loadings are developed using the methodology discussed in Section 1-4.0.

Other loads such as dead weight and seismic loads have a lesser effect on the internal structures, but are also considered in the evaluation.

COM-02-041-4 Revision 0

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The a na ly sis re su 1 ts.. :* if_(?:_~ Jj" th~

ey~.~:.;~<2_~-~H p,g*S*., :.:are u ¥3ed~ to formulate the controlling event combinations which affect the internal structures,\\ a.s..discussed in Sect ion 1-3.2.

The results :~are., compared, to ".l :accep~tance limits which ensure that.. the.. internal. structures. do not fail and result in damage.. **t.o* :safety~relate_q corn,ponents. The evaluation results show that the stresses for all of the internal structures are within acceptable limits.

The NUREG-0661 requirements are theref.ore GOnsidered to be met.

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4-2.0 INTERNAL STRUCTURES ANALYSIS An evaluation of each of the NUREG-0661 requirements which affect the design adequacy of the Dresden Units 2 and 3 internal structures is presented in the following sections.

The criteria used in the evaluation are con-tained in Volume 1 of this report.

The internal structures components which* are examined are described in Section 4-2.1.

The loads and load combinations which are evaluated are described and presented in Section 4-2.2.

The acceptance limits to which the analysis results are compared are discussed and presented in Section 4-2. 3

  • The analysis method-ology used to evaluate the effects of these loads and load combinations is discussed in Section 4-2. 4.

The analysis results and the corresponding design margins are presented in Section 4-2.5

  • COM-02-041-4 Revision 0 4-2.1 nutech ENGINEERS

4-2.l Component.Description

  • Theu.frtternal0;*strut:tt.i':r:Eis*.which are evaluated include the r: catvralk *' anE!.
  • electric'al c,ondui ts, which are described in r....

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4-2.1.1 Catwalk three feet

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Jwhd::ch'.:>e.extends.:,a;rOl:l:nd*

the f'Jll circumference of tJ:ler ~uppr~~,si9n. ail!iP.er::.*'.*:

The catw'a'.fk is located in the l.lpper outside quadrant of *e1a*ch suppression chamber mitered cylinder~

The catwalk frame consists of two C9 x 13.4 string*l:{r~s*,

which extend from ring girder to ring girder.

    • The catwalk frame is supported at two locations between ring girders in the non-vent ffri:e bays (NVB) and at one intermediate location in the v~ht line bays (VB) (Figure 4-2.1-1).

The supports at '.ti"fe ring girders consist of a. W12 x 136 horizontal suppo'rtt:

beam attached to a 6 11 xxs vertical pipe column (Fi'gu're 4-2.1-2).

The intermediate supports consist of 'a Wl6 X: 36 horizontal support beam attached to a 4 i1,.,

Schedule 120, vertical pipe strut.

The pipe strut connects to a reinforcement beam which distributes the pipe strut forces to the suppression chamber sheil (Figure 4-2.1-3).

The catwalk platform consists of grating that spans th~

stringers.

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intermittent welds.

Additional hold-down support is provi,q~_Q.:;... <RY:. L3 x

2...--~~*--3/S,. *hold-down angles that bolted

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COM-02-041-4 Revision 0 4-2o4 L3 x 3 x 3/8 angles L3 x

3 x 1/4 angles the ring girder, and at the ring girders

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x 3/8 BRACIUG INTERMEDIATE SUPPORTS

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1.

2o 54'-6" TO it_.

OF CONTAINMENT SEE FIGURE 4-2.1-2 FOR SECTION A-A.

SEE FIGURE 4-2.1-3 FOR SECTION B-Bo Figure 4-2. l.-1 PLAN VIEW OF SUPPRESSION CHAMBER INTERNAL CATWALK 4-2o5 nutech ENGINEERS

<t_ CATWALK I

't_ SUPPRESSION I CHAMBER 3 x 2 x 3/8 GRATING HOLD-DOWN ANGLES

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C9 x 13.4 STRINGERS Wl2 x 136

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SECTION A-A (FROM FIGURE* 4~2.1-1)

SP~?-~~-~JP.~*~ Cf.I~~R;:J:N'~;ERNAL CATWALK TYPICAL SUPPORT AT MITER JOINT

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<t_ SUPPRESSION 1 CHAMBER 54'-6" TO <t,

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COM-02-041-4 Revision 0 NON-VENT LINE BA~

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SUPPRESSION CHAM~R INTgRNAL CATWALK -

- TYPICAL SUPPO.RT.. iBETWEEN!:.MLTER:.:J..0-!'NTS;

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4-2.1o2 Electrical ConduI.&i.. :::.. ~~: ___ ::_;!:* :'~: *-.L:..

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! Electr'ica11 6btlet'S* are: pTad~d along **the catwalk for use Wiring for y::Y01:'-Ctnfrl3*:,*:. efiJ e*l~-tftrlfcal Ofttl~t@ is routed through 3/ 4 18 and

  • .?.*::J;i'i ~;~i;;,_;;~*:,".l'..:;i/4* 11.;fi'~xi-bleueori:'d'uit:S'.** -~The conduits are attached to short it vertibal* 'members'/ that are welded to the web of boxes at the

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4-2.2 Loads and Load Combinations,_,,;_,r,:*,-,

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  • The loads fo_r whic,h the. D.re,sden Uni.ts.:2. and 3 internal

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'l structures are eyalu~~e,q i~~e ~d.q.;fcin,~f'b l,,I};,, NO.fiEG-066J, on a generic basis for q;!,1 _M?.rk ;r,.plfil'l,:b-~:**:.

'fh~ methodq],og¥ used to develop** pl_an;t;: 1._.1;u;iique5 ~199,q~ *for*- ~g.ch applic9pl,.@

load defined ip*. NQ~EG..,,0,~6]::;:J-_s;:.,_gisc,us~:ed_ in S~gt:,i.o~

1-4.0.

The resu;L ts.;;_O,f *.,_9-pplying. ::~.?e

.. :I,ll~jthodol9gy tq develop specific yalues, _-,~Ol:'. ;!3ac;q. ?:f:;,_ -.~lJ.~

cont:i;-olJ,in9 loads are discussed. ~nd p:rese,nted: i,n,_;Sect~pn 4-2. 2.* +..

The controlling load combinations which affect th@

internal structures are formulated by using the evel'.lt::.

combinations and event sequencing defined in NUREG~0661 and discussed in Sections 1-3.2 and 1-4.3.

The controlling load combinations are discussed

@-OG presented in Section 4-2.2.2
  • COM-02-041-4 Revision 0
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~oads J.,

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The loads acting on the internal structures are

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categorized as f:ollows:

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L Dead Weight Loads

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2.

Seismic Loads

4.

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a.

Operating Basis Earthquake (OBE)

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b.

Safe Shutdown Earthquake (SSE)

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Pool Swell Loads l~

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.. Pool

a.

Swell Impact and be Froth Impingement and

c.

Pool Fallback

d.

LOCA Bubble-Induced Struct:ures Condensation oscillation

~

Drag Fallback Drag on (CO) Loads Submerged

a.

Design Basis Accident (DBA)

CO Drag on Submerged Structures

b.

Intermediate Break Accident (IBA) CO Drag o~ Submerged Structures

5.

Chugging Loads

a.. Pre-~.hug Drag on Submerged Structures
b.

Post-Chug Drag on Submerged Structures j

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6.

Safety Relief Valve Discharge Lo~ds

a.

SRV Discharge Bubble-Induced Submerged Structures

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7e Containment Interaction Loads

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Suppression Chamber Motions

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.. J Drag-**. ** 'on Table 4-2.2-1 shows the specific loads that affect the

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catwalk and conduit.

The methodology used to develop

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values for each of the~e loadings is. discussed in i:;.

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The resulting magnitudes arid Section 1-4.0.

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characteristics of each loading are similar to those

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described in Volumes 2 and 3 of thrs report.

COM-02-041-4 Revision 0

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Table *4-2. 2.:i '

INTERNAL STRUCTURES

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x x

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PUAR VOLUME SECTION REFERENCE 1-3.l 1~3.1 1-3.l 1-4.1. 4. 2

.* 1-4 0 l. 4. 3 1~4.1. 4. 4 1~4.1.6 i.,..4 0 1. 7. 3

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.SRV DIS-CHARGE CONTAINMENT IN.TERACTI ON Sb 6a

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    • 1:-

x (1)

. *x 1-4. L 8. 3 1-4.2.4 VOLUME 2 (1)

APPLIES TO SUPPORT COLUMN AT THE RING GIRDER ONLY.

C:OM-02.:041-4 Revision O 4-2.12 nutech ENGINEERS

4-2.2.2 i

  • ~.

i....:.

Load Combina tion.i:;.,..

  • .,".':" ~.... * ~~-*M"'-:*~*
  • ~-::-~~(:.:~*:*::~~.::J~>'::~:--*z;.*i*J.~~*

-.... -~... -~

....-~---*--~--*-

tures are presented in Section 4-2.2.* 1.

The gene*ral

  • ~
      • -*"-"~

~..,;...-~"-"--.*~'C'"':.0.:.-/UC'...... ~=~*:'~~'"**::t.;>Q'!i:i;...~asn:ti~~E.(,.'!%;':~

NUREG-0661 criteria for grouping these loads into; event

~

'~

~C-:*~ C~~*: : -~. :~*.,,,-~~~,J~f.C.ft/

~

combinations.are.. p~scussed Jn Sect10fr1r1;,;;.:a~:2.-~

sl.n:ce the electrical con cf~~ ~1~~*~-:~~r~:~j-rii~~rT~y-*of.. ~tne~*=t*~ternal

~.............., *..* _...

,I
    • ~-*
  • "':fYii~) ~ *.~r:;::1~*t.;.::

catwalk components< are locat~-ci*

0

  • ifiJ0'1b or below th~ *P0t>1

:- --****"~----. '**--,,...*.** *"°-. ________,, __ ~,.......,,~******-.-~._,,,{

. surface, the eyenbr c6mbi.9;9tio~s-:tli'::*~~a:~...!/:: p~roduc*e

,........,,,,..,.,.,,~-**:~**l"""****

~.-.......,,_

~,,,._.. _,,.,. _ _i_,..,_._,.,,.,.....,.,,,._,. '""?-*'"~.. ~~j controlling ~tress~s ar;,~ those )'1,hic~ contain pool~ swe.11 r

and SRV disch:arge***.¥erifds-~----"*-~.... *-**,,, _____ _.... -;

.-:;~

. ~

i
  • *:r--
    • _*---*~r *--*~*-~:--n*--****---- **~-~~-;,1 The submerged p*ortions of*

tffe' caitwalk suppor:e.s a:re

***~~.,.... _........_ ___.._.,..,,,_.J.**** *.* -,... -........ -.. ~...:

...,{

~

. \\

', l subjected to LOCA **.\\ air

  • c.leat;ing, condeli1sat ion
  • -~,'<.ft***~---*............. _*~~-*-
    • . -;.,_.. _ _........ -.****-****~:

~-~~-J:~3:*;1!.

-.~~(~*\\;::~:~ } ~

osctllation,. chugging':!~ an¢!

~~v qi'schar'§:e:;

su~merged

't structure * ** 1oads * -ifder'f~1f1e"d""'"'"trr-*-"'Se'"ction 1-4.* O.1 i

  • Th'e
  • ~
  • ./...

1 ;

J

.1 !

f catwalk is. ev a 1 ua tf d ";~-or~...t.1;:1.0..-c.on.t.r-6r1 lin.9--kQJRP-iA;~ti b rfs *
  • .. ~

q These are the IBA'. 15 ahd the*"bBA (,4.5,,,,-<:::9-J,!1.b--~,P.a,t_~phs :as

,_ >~*"'*-~:~*.. c-~** *~*~**---1 *.1>.:*:-:;~,~:;~=~*;2:~:* ; t described in the PlJAAG '(.Table 4~2.2'"f2).

The *eTeGtric,a1

.. -- *-~---*-.. ---:-.;__**--~~-:L~**-*-------~i c_onduits and junctiq_n>: bofes *:.~c:re : evaluated fAr 'the

  • i cbn tr611 ii:'ig.... os1c*TS-*-sc5i'.fi151"i'fc!ft~on;-"S"1)nce~:;i~n~-~::l;)Ool~ swe11

,;~-

i

'--~'.-)~

i.;_

~~

load is.... the~.dam inant_.J...oad_on_.t.h.e.s..e.~C..O.mtlQ.ll..~11...t.§..&-.~'5

  • J

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  • ~-.. *'~-~:~~-~*:...... :.~~--- ~:.r. _....,~L--~~~<*~~~~~-~0~::::~:1
  • ~fi2i.. : ~::f.t. *~ 1. /;,, *:;*.. ;.. ;0.

'*~o.=* *w"~~~:_~,-.=r~~~J.*=-* *"~~~-~~' ::.~:-.:~'.:::'._]

. '\\

COM-02-041-4

-Revision 0 4-2.*13 nutech ENGINEERS

INTERNAL STRUCTURES CONTROLLING LOAD COMBINATIONS

  • -E.Hi(f 0 ~.,;*.~:-.;.',~:;.. J.:;*

i::llJf':;:t:i.t',,_.

  • c.... * '.1*'::1.

f:LOAD.:coMBINATION

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(**.*.* L':*.:fu0~P~ o;;~f.G~,~1:~~-fs~.

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  • n;;>.!::e,-i. > SEISM-TC :r * * ~"' "-*,~,"

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. SAFE SH~1DOWN EARTHQUAKE

~.edl.""D".. :r:::.~.'£1.B

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    • 1

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TORUS

    • .1* :i.

SHELL SERVICE LEVEL AT WHICH

=e:.:'5);;;:.i: *:**'.'.ST~Ss:E:s~:- ARE,.rEV.A3:i.UATF;O: >. -CATWJ>.LK**)'AND ELECTRICAL er.\\;<

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SEE PUAR ~?E:CTl9~ Jl:.-2::.,*~:"':.ho **'::' __ '/.i, (2)

SEE NUREG-0661.

1 2b 4b Sa-Sb 6

" 7

. "'" (5).

E

*5 -.
. :,. \\/ ~*

l 2b 6

7 c

( 5)

E (3)

SUBMERGED STRUCTURE LOADINGS ONLY AFFECT SUBMERGED PORTIONS OF CATWALK COLUMN SUPPORTS.

(4)

THE CONTROLLING LOAD COMBINATION FOR THE TORUS SHELL AT CATWALK ATTACHMENT LOCATIONS IS THE OBA 18 COMBINATION AS DESCRIBED IN REFERENCE 3.

(5)

THE CATWALK IS CONSERVATIVELY ANALYZED TO.

SERVICE LEVEL D LIMITS.

COM-02-041-4 Revision o

-' * ~. 4:.,... 2 0 14 r

nutech ENGINEERS

    • -~*

4-2.3

t. *-**

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.j Acceptance Critefia_-~ 9 ~~sT

.. ;)r.-f; *v *;?::)_~r*.:~?~ (\\).:; ~:~:17.7T~ US: r E.

.;,.~ :**~.'-~ 2 *.:~,-~

. *-.... --.. '.. _...._,..,, __.. -.--*-~----~....._-._,.. _. -*-... -----*-*

Table 4-2. 2-2 shows the service level assignments *f'or the internal structures and the suppression cham:ber

"""'""'f'l"::.."Zl***-1.*.~~~~.,.Krut-.,*r.:r.">",(IO.o,.* ~

... ~li'U.~

... ~~-i:ir1.i~1~?1 shell ta\\t ::attachment poii:ts to internal structure*soH :'fhe

\\

It tabl~*** sj1o~sl that the \\*~ctf~~¥k'~;)§riac es_c:~b~rical con;4u;fts

    • ** -£~,,.,-.,..,.! -*.* -~.---.... ~~._..._,_.\\.. ~v.-o---**.,.w.r#.fo'W'.ao~~: _.......,,., *.,..-..ni.*--'llW".,..,~.....;~'~

are de:signated as Service Level E c~TB?~~J1~

.. ~J-.::aijd.'as

~

il such,

a re*** -q0t-*""t"E:H:IU1'YER'l--to-nre*et.. - A~de--aee'ep*an c e

-.. f!rrt*;:. *,***:.;,:

  • ~*, t*.:r

);1, r-;**A* :*****~J" l

~...... *".r,.. -

. 'l :i....l !

limits.-

    • .,Ini or-0-e£--EG*... emp-l.Qy.......a-CGi:i.s.iste!t *~~k,;:g:f****q~'siign

';..1.r-,:~*C<r..

~!..~
~~ *,.; r

..::~.r.. ~-~~~,:* ;?."7iP*.2 *

~-~

criteria which~~enaur..e.$.tPa:t.....f.a..il.JJX:5L~rd1.l..,,;,!J.Q..t;._P££.Y.~) :tihe catwalk is i conservatively evaluated 'fOP;,:;tii>e<::::;:*sJ.l.v'i.ce

.*... t--.--. -----*-****.,._.,_*~.. ---** --*--- -~~-~-~-.,~-.,---~-.,...4.;j J

'~ \\

tf Level D acc:eptance 1 inii tr& JCdn¥aT'ried 11.*q;1r::~ihe~iQ.\\s.r./fE it:oa:e,,.

The supp*~~~lio~ *-::-m~~; sh:*ll near ~~~~~~~-rJ;:~~'S to internal st~u~~u;;;--*i'~* ~-v-~ii:;:;t-~d ~in,;~:i9:ir.~.-~ii"~*~,~i;i'~ the

  • -...---.-.--.. n**--- *... _, *- ~---*~---~~ '--'*._:.~~.*.~~~,:_~~~*:;~~*~r.*,~:~~-*~

requirements for Class MC,._..~'3~!?Jf2~~ys7,fp~!-1J:~~i.~~-d-' -~~ the i

ASME code ;--**""1the'C'orresponaihg~'a"I'!<'5W'al5t~rns-s!'H~'!!r*'-&f 'the

............,:.,,,.. ~""""

~-.-.........-~"~-**-~~~-~-~~~~>\\*"";-.~*

._:,L:rr(:'.-

~f catwalkc:. componen~.~'.;._Jpr the controlling combinatidp are

    • *--*-*--*-** *--~
~'."'.*.
i:*j'.r.

T -~ 3 'f. :£...;

f *.~.! *;;:r,:;:*:;t::;:;

~;

presented in sec'tionL *4*-2. 5* oiT/;,:_The..';'ele.ctr!ca:l,L'O:od<luits

..i.;.: -. *x. _, :,:

~I I

~

c;u;.~L.. ~V.-~~+JJ.aJ:_~d.,~t..9:,,e~tj'~~-~L-~~hey will not impa~,r t 1he

-~~.ltolOOr~~.r.;

  • . ~~:*.*

function of safety-rel-kt~d~ **dontpdn;e*n¥S 0~1-~.;(:

=-~* :,

  • .2 *.

... ~..... I"'

8;~. i.1 I :1!-. :-_-:.,.;

'l~:!T 1'*2:;:J ~ "!' p, C:'.3~~;-s :~t ;t 8. L; ~~

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COM-02-041-4 Revision 0 nutech ENGINEERS

4-2.4 Methods of Analysis F* j..' :.-:: :.: *... t

. :~

,. /

.. ii

      • ~--~......, --

,,,,;:~;~:. ~;* -~, _: ::::*;*:. '*

':{'he :--,,_lQ4~i.A-Q:%

fo~

wh~c;::,~>:<the.intern,_p.;L structures are i'O(*:, '* j :~ :: ~<.. '.'. :* ::

0

"-:e,iv;alµa t~¢e r{lr@..,~~¢~'3t i:l~)!e.:ci( ;il'} SeC;-t ion.. 4~ 2. 2. L l '* ;*. '

'"i'Fh~,,,g.n:§!.lys ~9::.o.4:

~t_h~,* *1Ca tw-9.lk; is.. ~,perforr.ned. using manual

~. (J

~* ::; i. r *..:.-:i. : * -~

~

'r *-

  • ~ * * -~ * *

() r..* {:'

_.:_ in:teraetion. **apd,ypP,O;l

~w~J,:iJ:, loads, fol'.' which transient catwalk components.

The reaction loads from the cat-

,,.;=:..; \\?:r:'~i ;.:":wallvpipe s;t.rJ.J,t-..* jto* ~e

)?U,pp:;-e,ssion~ cl}?-mber: are obtained

);,

.. /.. 'fr.om:ci-t.he.:.;13,oundi;11g

i.-<<)_a:P,~ _::Q.pmq)~!l:ation for.the attachment

-~-

element model composed of plate

elements,

-which represents a 90° section of the suppression chamber shell and the reinforcement beam, are factored by the reaction loads from the catwalk.

The resulting stresses in the suppression chamber shell are combined with the stresses obtained from the suppression chamber analysis to evaluate local stresses in the suppression chamber shell.

Volume 2 of this PUAR describes the suppression chamber analysis and the general state of stress in the suppression chamber shell.

COM-02-041-4 Revision O

\\-

(<

-~.

F 4-2.16

-~......

~

~~:-*" *..,.;_;*

    • J.C;: JB-T; nutech ENGINEERS

4-2.5 j*

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f,

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.1.....

.; 1_ '

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Analysis Results 11 The

~ - ~

~

(

i'.

  • ~.:
  • acceptance.

of the internal structures are presented in the

- preceding se?dti6rrl5~ *i;:,.:Tab'i.e '4~2~S~I f snt>ws*,.;,Ehe res~l ~ing maximum sYr'esses~

  • 0£0.r.rr:the1.1:,catwa1J~ir :f.o..b: ltih~ contr?lli~g load combina*tidn~""" fThif'S."t}ablei ;sho'v--1s:! thartnnb.e cal~ulated stres'ses

'~for than the correspond1n'i;f a'l!lowa0tei;;:9tf-~s~es.' <-'i'creyle-'n4-2.5-2. sh~ws the state *6f stress' fn '*t:he~..:s\\Jw.re:sisi.G>nc.\\Chamber shell at The resuits;:; 8 cf'~*.:;t.he,,.*E3.'lec"t.riea12 cQnqui~t~:.. Asupports and junction':" bO:xels"'.~lcon~*ei~rin

~t:na'tJ:'.:the.:ifii!:oniilufts wi 11, not impair the function c'ef c:ariy2safe*t:.)f-re,:la1tre.d:..'..compone_nts.

(:'.. '.~.'..

~*:: -

, r;.

!"'ft*

b'r... *. ;_;.. J -:.i*.*_,.

... *--=* ~':; ~ ~ -::.~

.~.-.*.

~- - ~

    • \\ __.. f..'... ~.::*.

r.

1:~ :.:;2:~ r

~~

. (

-J ~::(: **;',J:..* -:':..*

COM-02-041-4 Revision 0 4-2.17 i- "- ~' l;-:;;._, ~-. ::*<i?

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nutech ENGINEERS

1

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~:..*_

-~::~~~*~.. ~~;-",t.. :,.~:

./:*;:.. ~~~~~'.r**;.~\\.. -.*.,.

_-:~:,

... cA'i'Wltl:"IC-s-~ru:s*S'ES'""'FOR C'O"N*rRor;:r.TNG **LOAD cbMBINATIONs

-E~- ~;..~i:.~.. }~:~.~~2t.8.. ~ ~~.;~:;:~~'.~~...,~~~1':~1~~~:.':~.~:~i..~ ~~:.=*-~~~~*. '*~-< ;_.~~:..

LOAD COMBINATION STRESSES (ksi)

I°TEM INTERMEDIATE PIPE STRUT

ANCLE BRACING

$TERIAL MAT~RIAL PROPERTIES (ksi)

ASTM s

26.7 A-333 y

CRADE 6 Su.. 55.0 ASTM s = 36.0<2>

y.

A-36 Su 58.o BEAM STRESS TYPE COMPRESSIVE BEN.DINd COM~RES~I.VE BENDING 9.89 8,l!Q 1.4.91, 13.31 (1)

VALUES SHOWN ARE OBTAINED FROM BEAM INT£.RACTION EQUATION,

(*2)

. VALUES CONSIDERED ARE FOR *ACTUAL TEMl?J:;.RATURE;.

DBA 25 27.52 35.24

~8.00< 2 >

4~.20< 2 (3)

'TIME PHASING OF THE RESPONSE IS NOT CONSIDERED. THE PEAK-TO-PEAK VALUES ARE CONSERVATIVELY USED, COM-02-041-4 Revision O CALCULATE~(l)

ALLQWAB.LE

().99 0.04 0.07 0.49 0.6~

0.86 nutech ENGINEERS

.i.-

i_... *--*-*. *--*..

CoM-.02--041-4 Revision o PRIM1\\RY ME.MB RANE

',;.'
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.... U

... -.......... oM-<":'1*~.)lty~~J i:.;~. ~**.

.... ~*.-;.-:1;-& *. ?.f"" =:tr ;.}J*

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4-2.5.1

  • s::<< ".*.'::;.*

f'!C'.i:.:} : r~

Closure

-~*:.. *~,~:.~) *:... _.:

.. '. C;

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.. c._, :;-!.

    • , i***:*:,*,,f<:::'.~*::;.: ~.::*:i'.Tc-:.<'"3f.::'l'..,: :*,.'{

'I'd c:-.~*/<<::: ::.~:

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The s*~~l-tie-S"'"o*fi°*r.th'e *.loads f'U'S'~d

  • t:-6..:.. evailuate the interp.a.1.1

!ud~**.

't.l

°J:"TSi!,o::~t

  • 1.(~.. :-~~: t :3,:*.: ***.. J. :.":., J :---~~l""';_. * ':-;(.~~~:;:

1 st*5~.~~~f~r~~*~ t~~~1 ~,,~~~~.;~~~~!:~

e:~timat~.s

postu 1l~t~'d*:* t"01 :':¢'<f9(i:t*:i!'.'dfirttj.g.:;*.. an: iactu~l

. -1.* _.:_,.. **:

/

"'JE"._J.f.F**f*"...:'J.:~y... : :

.~.

..... :~:;

of the loads

  • J...

LOCA or

SRV,

-*:* **!\\.'

1 2:::'j'_*. _

a:t.~~1\\afgs ev~nt.:.:rh~:<ev~t*;(combinatio.ns for which tre,,.

~~~' '~; ~;.~~;;w~~:iti~;¥;~y,~;;;:.. ~~E~ted tve iol? the actuat:

'~; "'-'even ts. e~pt=h=ted "*to :::62du:e.'cfutrj_fp.g: a~ LOQ,f\\*i.or SRY di sc,p. ar

.. ~~,

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~~$ ';:.

~

T.,

.~.....A

' ~.'1;.

D:!F.*

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  • ~. *:~ *:.,..f.t;*. *; ~.!, ! (..

~;/~';

I :.r..

  • .* '-. ~r*... J.'

J.

\\

~... \\

"fE*.G"'-: 'f'ti.t:.::'

~ ;_.... ;~ ~.

The acceptance 1 im its are compared. are more restrictive*. than those requir~q _,

(

~-:,:.;

by NUREG-06610 use of these acceptance limits ensures

,: :::1 that the internal structures will not fail and cause

  • ~.

. ~*.. :; ~*-=* ~:.

damage to safety-related,c~~.~o_nentso The analysis the internal conservative results presented show structure

~* :.-\\ !. i.

acceptance component~

~,:":.

limits.

that stresses in are within th~se NUREG-0661 The

  • J>~

... *1 -

criteria are therefore considered to b~ meto COM-02-041-4 Rev*ision O*

/.i.~

I'

<~

/

nutech ENGINEERS I

I I

I I I l

4-3.0

.:.. ~...:-,

~.i_.-

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t

~* x

. f.

LIST O~ REFERENCES.

  • ~ '"*I,,;.: **.

~ l. * *'

1.

"Mark I

Containment Long-Term. *Program,"

Safety

., Eva.).uat~:.on,,R~p_ort '*

.~uq);e,ar-.,.~e,gpJ~:*t.pr~c Commission,

  • ' 'NU_REG-06-*61.,. July~,1960;,;Suppfemei::it,::1,,_August 1982.
2. _L'

.,.;,M~~k * :~ +/-,,;*. c'~:nt~~rii'~~*t:,::)

J;>*~ggrJ~~:-~

1*;~pa~*-

1 ':Definition RE::!port, *~.

G~Fl~:t::'a:l

  • E1_~p_trr l,SJ CpJ.!lPc".1-flJ.r.< 1,Ii'JED0-218 88,

'*Revision 2;.nNovember J.~81~..J

>*~ *<'*J'J..,:. -*-

  • r. *,

. :-.::; \\;.

=~ 11 *.

~*.***~ :.::.{;.....

...,... p ~.;.,.,.*~.,) *
  • r*
3.

"Mark 1-.* -e.On.t~inmen:f: ~Progr;~iji 'Strq~t\\iia1 *-* A.cceptance n

Criteria,.. -Plq.nt.;:..,.Uni_qu.e.,-... ~naly:si,!?... Applications

r.

Gu:ide, II-,, :Task~ -~Nui:nber ~- 3 ~ L :L. 'M'ark~'.'.:X~e;'_o~ners Group,

.,: -:: G~!\\eral EJ... ~~.i;;~ic _ C<?mpaqy!*s-~.EP,9;~*45_~2-~~-_,,Revision 1, October.;l.9179i..

~... : ~-*,,

~.

' r~~,..
4.

. - ),: :

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