ML20236F615

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Safety Evaluation Re Analytical Method Used by Licensee to Evaluate Critical Stresses Re Mark I Containment Program Vacuum Breakers Adequate.Max Stress in Breakers Less than 30% of Code Allowable.Existing Design Structually Adequate
ML20236F615
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/01/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20204G396 List:
References
GL-83-08, GL-83-8, NUDOCS 8711020236
Download: ML20236F615 (2)


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'o . t/NITED STATES.

n- NUCLEAR REGULATORY COMMISSION

'5 e$ ' WASHINGTON, D. C. 20555 '

i. . u SAFETY EVALUATION BY THE OFFIC'E OF NUCLEAR REACTOR-REGULATION' RELATING TO MARK I CONTAINMENT PROGRAM - VACUUM BREAKER-INTEGRITY-EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 DOCKETS NOS. 50-321 AND 50-366

1.0 INTRODUCTION

In' addition to the evaluation of the suppression _cb '1ber, torus attached piping, pressure relieving lines.: etc. . under the; ne, y defined loadings, the Mark I containment program required the assurance' of the structural integrity of vacuum breakers during operation in all Mark I plants. This~

additional requirement was categorized as a separate effort, as the' adequacy of other' components was already discussed in a separate Safety Evaluation.

The Franklin Research Center (FRC) has performed an evaluat' ion of the structural integrity of vacuum breakers in the Edwin I _ Hatch. Nuclear Plant, Units 1 and 2 (Hatch) for the NRC staff. Results'of the review ware reported.in the enclosed document TER-C5506-329, " Structural Evaluation of the Vacuum Breakers:(Mark I Containment Program), Georgia Power Company, Edwin I.- Hatch Nuclear Plant, Units 1 and 2." FRC has concluded that actions taken' by the licensee are adequate to . restore the original design margin of safety. for its vacuum breakers under the revised loadings in the Mark I containment. NRC staff reviewed the enclosed document and concurred with the FRC findings.

2.0 DISCUSSION In the Hatch Mark I Containment, there are' twelve 18"Iinternal' type vacuum breakers made by the General Precision Engineering. (Vacuum breakers are located at six of the eight intersections of the' ring header and vent lines in the suppression chamber. There are two vacuum breakers at each location.) Loadings on Mark I structures and vacuum breakers are based on the General Electric Company Report, NED0-21888, " Mark I Containment Program Load Definition Report," Revision 2, dated November 1 1981. For vacuum breakers, the loadings included are gravity, seismic, and hydrodynamic loads. The hydrodynamic ~ forcing functions were developed by Continuum Dynamics, Inc., by.using a dynamic model of a Mark

.I pressure suppression system and the full scale test facility data. The-system model was capable of predicting pressure transients _at specified locations in the vent system. Loading across the vacuum breaker disc caused by pressure differentials based on test. data was thus quantified' 1 as a function of time. This issue'was. reviewed and approved by NRC'on December 24, 1984. Loadings were combined according to:the FSAR l l

commitments.- '

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.To' determine;the structural integrity of the vacuum breakers, result's 2 .

. from a: finite element model and ANSYS. program analyses were:compa_ red ~with -.

' design : limits .specified in' the ASME Boiler:and Pressure Vessel" Code,- '

Section III, Division '1,' Subsection: NC;- 1977 Edition andL addenda .up. to... ,

Summer 1977. -It 'was.found that. critical 1 stresses:in 'all. parts? of;thel "'

Hatch vacuum breakers'are below the Code allowables for every service:

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t level. None'of the maximum stress values exceeded:30%'of'the'. Code allowables values. The licensee therefore concluded that 1 Hatch;. vacuum:

, breakers require no niodifications. .

3.0 CONCLUSION

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' The . analytical' method.'used .byj the. licensee to evaluate critical stressesj" # >

has been reviewed and found to be adequate.i:The maximum ~' stress.inLthe~- t Hatch vecuum breakers is. less- than130% 'of the Code allowable.. :The -

existing design.is structurally adequatefand r_equires no; modification. ,

Therefore, the staff agrees with the.FRC finding and recommends- that?th.is issue be closed.

Enclosure:

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As stated l Principal Contributor: H. Shaw Dated: April 1, 1987 g

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FRANKLIN RESEARCH CENTER.

DIVISION OF ARVIN/CALSPAN I'

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L TECHNICAL REPORT.

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1 NRC DOCKET NO. 50-321; 50-366 FRC PROJECT C5506? ,

i FRC ASSIGNMENT; 12  ;

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- FRC TASK l 329 i NRC CONTRACT NO. NRC-03-81130:

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STRUCTURAL' EVALUATION'OF THE VACUUM BREAKERS t 0
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- GEORGIA. POWER' COMPANY EDWIN 'I. HATCH NUCLEAR PIANT UNITS'1 AND 2-

. TER-C5506-329 '

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4 Prepared for

  • m Nuclear Regulatory Comrnission .

-FRCGroup Leader: V. N. Con : 4

'f NRC Lead Engineer: . LH.; Shaw;

. Washington, D.C. 20555 )

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j August 1, 1986 a

9 This report was prepared as an account of work sponsored by an agency of the United States i Government. Neither the United States Government nor any agency thereof, or any of their employees, rnakes any warranly, expressed or Implied, or assumes any legal liability or 1 responsibility for any third party's use, of the results of such use, of any information, appa- 'i ratus, product or process disclosed la this report, or represents that its use by such third - J party would not inf ringe privately owned rights. q Reviewed by: - Approved by:

Prepared by:

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. ' Department D_ir/eto V, 1 .

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Date: $ ,b Mn -Date: N, I, D$te: N I~ b '

' FRANKLIN RESEARCH CENTIER ' o J DIVISION OF ARVIN/CALSPAN 3 ,

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FOREWORD  !. l 1

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This Technical Evaluation Report was' prepared by,FrankliniResearch/ Center.

p r: under,a' con dact with:the'U.S.'; Nuclear Regulatory Comtnission (Office!of; c d

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Nuclear Reactor R,egulation,; Division,of10perating Reactors) for:technica1L- , n_ . .

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$ .'a ssistance in support of .NRC' operating ' reactor / licensing actions.; DThe : 7 E technica1' evaluation was' conducted"in'accordancelwith-critieria: established.y' b i-the NRC.

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?- 1. INTRODUCTION ~

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In a latter state of the generic. resolution of the suppression pool -

7 dynamic load' definition'of the Mark I Containment Long-Term Program,~a

( i) potential failure mode of the vacuum breakers was identified.during the-

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clugging and condensation phases of. hydrodynamic' loadings. To resolvefthis?

g issue, two vacuum breaker owner groups were formed,:one for those with General-  :)q

( 2 Precision Engineering (GPE) vacuum breakers,;the other for those with Atwood-- <

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-'i Morrill (AM) vacuum. breakers. l T

The issue was not part'of the1 original-scope of the Mark I Containment ?j Long-Term Program as described'in NUREG-0661'[1]. However, vacuum breakers-have the function of maintaining containment integrity and, therefore,:are subject to Nuclear Regulatory Commission (NRC)' review. In a. generic letter.

dated February 3, 1923 (2),. the NRC requested all affected plants either to ,

submit the results of the plant-unique calculations which formed the.basesEfor-7 modifications to the vacuum breakers or to provide the justification for the' j

as-built acceptability of the vacuum breakers.

e Franklin Research Center (FRC) has been retained by the NRCyto evaluate.

the acceptability of,the structural analysis techniques.and design. criteria.

4 used in the plant-unique analysis (PUA) reports of 16 plants. As a part of

) this review, the structural analysis of the. vacuum breakersihas been reviewed and documented in this report.

,. The first part of this report (Sections 1 through 4) consists of generic f

, information that is applicable to all affected plants. The second part of the. -;

report (Sections 5 and 6) provides a plant-specific review, which pertains to. j Hatch Units 1 and 2.  !

a.

l 1.1 GENERIC BACKGROUND In 1980, the Mark I owners and the NRC became aware of the vacuum breaker.-

damage during full-scale test facility testing and of.the potential for damage; y during actual LOCAs .Two~ vacuum breaker owner groups,. General Precision ~' d ll . Engineering'(GPE) and.Atwood-Morrill-(AM),4were_ formed to. develop. action plan; for resolving this issue. In February 1983, the NRC issued Generic Letter =

.83-08 [2),. requesting commitments from"affected util'ities to provide g

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loadingc the NRCLha's' reviewed"andEiss.ued. a staff (positi,n o asTindicateMin i

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LATERAL,' DISC. k ' --

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c '. Figure.4. Atwcod-Morrill' Vacuum' Breaker a , ,, ,t 1

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=

L

$ 3 F. S Chugging Drywell' '!

e Condensation Depressurization 5'

.' Oscillations- Q 4 h,p O '

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Tiame

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. . . , .2 Figure'.5. Typical DW/WW Vacuum Breaker Pressute_ Differential Due.to LOCA

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1 1

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,TER 45506-32.9b r

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% Table 1. sVacuumBreakerTypes.'andAffe$..t'ed' PIShts:-

u,

{ , ..

y:

k' i

G.; >

r, _

p. ,e #

t .

&- . Vacuum Breaker " '

' Plant' ,

a . .

.x -:

4. GPE.18'In'(Internal) _ ' Brown Ferry Unitsll,s23. Land 13 ePilgrim Unit'1" . ' "

. Brunswick UnitsJ1.and 2; -

m; Cooper. . .

, ' ,j Hatch Unitscl?and 2'. .

Peach Bottom Units'.223ando3

Duane Arnold:
Fermi: Unit;2 GPE 24 in.(Internal) a ' Hope Creek!. t I

3

],

AM 18 in (Internal) l Monticello-7- .

Quad Cities Unit'sil:a'nd-2i c e-e AM 18 in (External) .Dresden: Units'2;and'3:

Millstone UnitL1:

Oyster Creek l Vermont Yankee m ..

AM 18 in (External) FitzPatrick ..

3 Nine: Mile-Point' Unit'.1- 4 1

a "f!

- , ' i f .}

' ,j o

., , M.:t I

). '

r - ,

, s Ml

,e '

.g,q  ; e; . f.;- ,

t , I li ' " '

[

&~

s
. ,b j / ,

[h0)

_ . p. . . , , ,

.. -= ,x , c- . . :o; .

>g

, . ;.. - - . c -

y li

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1

i. , ',

.TER-C5506-329 1

n ,

q

~2.. EVALUATION' CRITERIA iTo evaluate the design of the. vacuum, breakers, the affected licensees, S) l

- follow the genera 1 ' requirements of NUREG-0661r['1] and those' of ." Mark If 1 Containment Program Structural' Acceptance Criteria Plant Unique. Analysis. 1 P

(. Application Guide"~[3). Specifically, the' requirements of the.ASME Boiler and p

Pressure Vessel' Code,Section III, Subsection NC.for Class 2' Components, 1977: .

~j I Edition,: including the, summer 1977. addenda (4),.have Laen used l to evaluate the'

l I '

structural integrity of'the vacuum breakers. j

+o f

~

1 7 )

1 L-

~ jl i

l L

.s '

i I

r.

l4 b

r l} 1

?

1 P

G? g j

n  !

b,

>=. .i

.d

- , j

.i_i_ _

Egn 6[

, 3. ._.

"; *1. <- > C.4 L Y' ,

s@  ;, .T ,

,s

.{i 8 :, .

. .i

, 'TER-C5506s' 3291 9: W p

a

.. . . ,. i e n

3. ~ DESIGN LOADSi , I 7

f .

- . e  :].

The.Ioads-acting.on'the-Mark-I structures ~and on the vacuum. breaker are n

h6 -  :

based'upon'the Mark I Program" Load-Definition Report:(5) and the NRC Acceptances '

e' "

' Criteria (1) . . . The: loads acting on the vacuum breaker cinclude gravity,; seismici j

b and hydrodynamic loads. The' hydrodynamic-forcingcfunctions.were developed by; l

Continuum Dynamics, Inc, (CDI).
CDILused-a.. dynamic model of a MarkiI press'u're I

F - suppression. system,',which was' capable of. predicting pressure transients,at. L.1 H

E specified: locations in'the' vent' system..:.--With this dynamic-model and theifull-lt

  • q r .scal e test facility' data,fload definition;resulting in pressure differentia 1'. 1',] ,

j acrossithe vacuum breaker disc wasi quant 1Nied asLa function'of stime. iThis t , j

,- . issue has been reviewed and addressed by the NRO (6).= .

,a

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L- ', . TER-C5506-32 y

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4. STRESS EVALUATION. 'd

{.. .

j To determine structural integrity. of the . vacuum breaker, .the licensees:

~

'have employed standard analytical l techniques,'the; including finiteLelement'-

. i. i s i 7 method,-to calculate stresses of c'ritical componentsfof the vacuum breaker'

[ under various design loadings. . Loads resulting from the hydrodynamic. l phenomenon were compared with' those : values specified in the ASME Codes [4).

W For illustration purposes, a, schematic' drawing.ofLthe moving parts.cf,all' Q components other than-the actual disc of the Atwood-Morrill. valve and.ofsthe~ i corresponding. finite element model'are shown in Figuresi 6.and 7,.respectively.

?

The model in Figure 7 was used'to investigate the dynamic response following. :j 2mpact.

A typical model for stress analysis of the vacuum' breaker disc is shown in Figure 8. Loading inputs to this model are the displacement time histories a

n that were obtained from the impact model analysis.

s v

e

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e 9

2 4.

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INSIDE DISC' SURFACE 1

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,(

5. - PLANT-SPECIFIC REVIEW: HATCH UNITS [1 AND 2;-- '

p t

l,:..

5.1 BACKGROUND

INFORMATION

p. '

p o . Vacuum breaker type: 318-in GPE'(internal)- '

e

p. . >

o ' t Vacuum breaker characteristics: Table;2 o

a. n

.)

o! Vacuum breakers.are located'on'.six of theleight-vent header / vent ,

,j p- line intersections.within the,wetwell. There areitwo' vacuum breakers: 3f-!h
at each. location.

. ,j) .

b 5.2 STRESS ANALYSIS'RESULTS . ,

A finite element model.of theLvacuum; breaker.was. developed using;the

q ANSYS computer program. The stress..' levels'for. vacuum breaker critiSal? d 1

components were calculated for various pallet: impact.velocitiesf(Table.'3). 1

.The plant-unique impact' velocitles for Hatch Units-1 and :2: were predicted-.

}]

ic using an analytical model of the vacuum breaker / vent system fluid dynamics- .

j

[7]. The design impact velocity for. Hatch Unit 1;was' calculated thl bel 1'.26

[i .

[ rad /sec, and the design impact velocity.for Unit 2 was~0.12 ra'd/seeL[8).

O.I d

'Since vacuum breaker stresses are directly, proportional to'the pallet. impact:

velocity, the' design impact velocities for Hatch Units:1 and 2 were 'used: to - h g - <

scale the, stresses in Table 3 to determine vacuum breaker component stresses'. 4 N

[ for this plant. - It can be seen from Table 3 that none of: the components will . '

exceed the ASME allowable stresses for the de' sign impact-~ velocities at' the h)r Hatch plant. Therefore, no modification of the vacuum breakers as:necessary.- .j q

q l

i d

y 11 1

I9 l

f ', '

?

1. ,,

cw ,

. . . . . ,m ,

Y' 'f ' Y .h*-'"

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L? f ' * **

' , . . . ,, . s h .

  • l f . 3.I h -

4/'0 " gg:.e

, i 3 o . .n > ,

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\ ?-

~ ,

1

._t

':c. ,  : ,. ;

p -

, ;n '>

g '

..d n T. " '

y, ;y R 1 TER-C550'6-329L'

, y; 4

'o .; ' .

o "

  • q y

q P '

'TableL2. .: Vacuum Breaker Characteristics for Hatch Units?1 and -2.:. , fj s

5 '

t -

.4, a

p ,

p . ,

g)

.y d

,, , . .. , . , . , ,1

. Vacuum breaker type ,18 inzGPE. Internal: ,

jb V,:

~

O lc ' O .. System moment of.intertia (1b-in2s2 ) 20.08i < Xf F . System moment . arm '(in)-

-- 10.86' ' <

. s. y; L

Dise moment arm (in): 11.468' < > a- 1 r
. i

,1

.-System weight (Ib) - 49.84- F' :9 j H

g Disc' area (in2 ) ^ 3 7 5. 8 3.. ..

System rest angle (rad)' +

'O.06109' 1

  • Seat angle (rad) -0.05236;
  • q

- y n Body angle (rad) 1.391',

> , 1

,' Seat coefficient restitution- 0.6 n

m.

Body coefficient . restitution 10.6 ,

, u i Magnetic . latch set pressure-(psi) :0.25:

,J s.

3 t

l

'(.

'-i'. l sJ

> 5-

=

i o , 7; :I
i' p i .l

, 1 i

{. I(,.

,. e:

, p, O.h -

,, '; i: -

?l 3 -)'l

) .0 : p: ,

~

-i- i .o m 3; .- 4

'm

  • s ..

'!,$N ,

'~

b j.l..  ! ~ fy

. , -, , , , , n , w ... .,.

. . .f I , 4 'j l f ,' y'};. -fT 1, -.j'?! ' _.jjl>

ll ' * ' ~t < l )5

,'4 1 t >

%- m.

w;_]' ml l,. %,,a , .. .- - , w.. t.g , , . ..m

,.+_...

m:.

=-

  • 's "E e i , 4;' ' ',

' i s q,. , g j l* c

. g.; f , f ..' < vL 9

-v ,

,9 e A 3 y,

~e'. '.,,

f .y. w'~ , w _,;;.

r lp} -

e i

i.F' 1

'.i'~.t

.. W i 5 4 .y . . ,g

~ ^

[,1 g. . . . ,

o. ,

,- . m, ,,  ;;7ER- C5506-329 T 4 j_' * '. 4 l) .c.l,' , L .; f 1 QQ.: '

I.). I.7 _' i:

)f

' ^

s

,. r ,

' p:i: 3 d fj. . ,

'r 1i' 1 2

l * '

f Q. s r < 8

[

\ n

-[ .), [f,);O .i. >

.y . . >, . -

.. . .. ... '-e 3 1 Table 13. ! Stress! Lev'els ;>by Component

+

<fori18-Inch GPE Vacudm Break'er' , , ,

', a. ~

t i 77

+ ,

4) ,.

,. < s 'i

+

.n < ' '

p, , .,-,. ,

,. 9 I

, i . Stresst i. ks' ilifor ' ...

m -4 f

r . .V.ar. ious Pall. et: . ,

p '

> ' 'Impactt VelocitieC . <

o

Existing' ASME A.Oowabis*1 - 13.0x . s4,5 <,19;3- >% --

P - Componenti #'

~

Material'

~St ressl(ks'i) i .

"( rad /see b N,"' N m

<-' 7[, .

g . - ..

- i

,: Pal' l' et' i 'SA-516 Gr170' , ,,

'A s35.'1O i ', ,

'21.'60 ~ 32.' 41 ;67.01 ,

w .

n -- -

-( . , .w. ,

,.r'

< 1 ,-

' y' E

Hinge sArm .SA-516'GrJ70 35[0' '

11'.' B i 117.7.i36.6 4 -

-s m' ow

.]

Hinge: Shaft 1  ? W 320 BF 30.0i 19.'1L 128.6L'59.2' "'

n 1

s>

-1

- Hinge Arm Stud ?SA-320 B8. 430'0: . '12;5 2 :18.8'138.8:'Ni; -

go 4 ; , . o- ,

)

q 't!'

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q

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( ' '!'

  • ASME Section III NC3520

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4 .

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k ,' '

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r 6', l ,'

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y

.)

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5 N. ,g *

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/' 2

, s s

'L,

" .. < s g

,,t ,

i y c,,4 e a ,N . 6 t

g p{ g, 3 !. , p.

m,,s ., f v " . ' ' ,

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3,. .

4 , m .c .

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TER-C5506 -329 1 .

n i6. CONCLUSIONS s

g; A' review has been conducted to determine the structural integrity of thel vacuum breakers at:the Hatch Units'I and 2. The' design-loads' associated with' the hydrodynamic phenomena hhve been reviewed and addressed by the NRC in.

5 Reference' 6. This review covered only the stEuctural analysis of:the. vacuum

-i breaker, and the following conclusion is idrawn from the review:-

r- .

f o' The analytical methods'.used;to evaluate-stresses of critica1L-k-

cor:ponents. have been reiiewed and judged to be ' adequate;; the! stress . ' 4 results indicate that all vacuum breaker' components are within ASME l'; allowable limits. :Therefore,'the existing vacuum breaker design'at. y.

P Hatch Units 1 and 2 is structurally adequate. ,

y )a

.J a

p< 4

.1 L.]

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a . ]

i e.. 1 L .

3 it - .,

N .j 1

g_ '!

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3 ,

4  !

5 .

s. ,

4

z 218-e- <

, p 3 'r , ;

l_i_.___ ____ -

r w.

u

, y, ,. mA.3 sw

.,m a <w s m aw .,- m%-

y % ., m aw.rh -m'"

9+.'", > W +6F ,* WM

-yy ,' WhQ

...e p4' R;f . -

l\ 73 1 .

m o

.) k? lq[Q. r &,l. ~2 Q & f

e n..,

p s

wN v

.$% '7e j.y

&m m~'n '

w e cpsw w ,y m ' ' b[j '

% g; L a w m g Q- i W_ ;y y',<&

,p p g f U; p / a: '

hi 4 _.

L

% ' f.,g,' &p g f y,y i y pyg}y W -

Jg 98 - ,,

,w

- 2

%c ry a s w w< .m

y

'p. . . . .., ,.

A~ *

< .w . .. . . . . . ,.

2 1 <

^ /s ,Y 3, , { , #g; , h,.

Y fTER-C5506-329L T.

u 14 s

W,t

+ --

1  %

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! 7,.' REFERENCES' M

t "i g

c 4

se v -

Ji g

L ': t if r i 1

- w} , , , .y(r ' r ) j ':

k4 ,. ,, ,' 3: ' ~

r

, l }.f A i

,, 1 M [,6M/l[je g.

g,,

I 6 t,

t I,,

~l',"NUREG-06'6fl Safety Evaluation j _.

y ' Report / Mark'I: Containment'Long m

Y l .~

k[f.,/,,QW-y Nh Term ,~*5 m

[

R, i, . Resolution of Generfs Technica1JActivity A-7,".OfficeLof; Nuclear akwactorT

,4 4 i, ,' <

'Reguin% ion lDSNRC ' ' '

'W

'g($JulyTi910 \ .

hI ' ON ?

g[ j ,

< 7 Y g'

'['I. M 7 D./ G. dnbutL ~

h 7.

i

.w ..

  1. USNRC Ge.neric. Letter l83-80', Modificat b of Vacuta Br.eakers'on,Mai,*kTI/,s

~

.T lda

-Containgnt" 1: , hL . .

k2';f .Febru g2,1983= ,,j%C' 4%

f.

q , w g &1(

Y ,

'* 37 .. ..

]'6 7

]p . {9 Y.

b s 3. IEDO-7.458$1

~ . ;

? >

L #Y,~- . e '

s

, h.

s "

Mark :I' Cont'ainment ' Program Structural? Acceptance Criteriti Plant! Unique l ' , .

- - e t .j"

-Analysis Application Guide' (GeneralLElectric Co.,1 San Jose, CAJ

~

f

?

~ October 1979, 1 s' O+r

-n eg<W' -g% ,

, " ' @M w r f '

4; a

.4.

4

, . Ame rican l SoNi ety ' of f Mechanica1 l Engihee'rs

'Bo'ller.and: Pressure Vessel Code, SectionlIII,LDivisiontl',$" %Nud h ear,PowE/ $hM $

O d 2

a Plant Componer.ts,".New York, 1977 Edition'and Addenda up to Su%aerLi9777yA &

a

5. q <- "e 2 % j[ Load..g

? NEDO-21888

" Mark LI Containment Progran 1 Revision .

Definitior Report "'Gans ,

q s , . , . .

Co., San Jose, CA  :

';yj,7

' ' " ~

w g November 1981- y -

, s:w e A tb dS' 1 . 6. J.,B.'.Vassallo,.NRC , i m

LetterwithAttachmenttoH.'C.Pfejle)&rien, BWR., Lic..

4 1 .- M. ~M. .p , i!

ensing;Programsi GEE v

i nd j v-

" Evaluation of Model for' Predicting Trywell?to jetwell Vacuum Breaker] , j A.

Valve Dynamics"-

~

'y 3

.7 December:24, 1984(

<+

< 4 7;[; g3 '

V # '

,/  :

,i .

a; =

Y~<

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