ML20236R981

Ae Project Plan for Evaluation of Pressurizer Safety & Relief Valve Discharge Piping Subsystem

ML20236R981
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	08/28/1986
From:	Gazica M, Watson J AEA O'DONNELL, INC. (FORMERLY SMC O'DONNELL, INC.
To:
Shared Package
ML20236R975	List: ML20236R973 ML20236R981 ML20236R999 ML20236S020
References
PROC-860828, NUDOCS 8711240147
Download: ML20236R981 (23)

Text

,

,S

)fff~g/~g((

C 3,

y Tj$

A yng;,g ggg gg,3 3, Rom l'IM y ',

roR inE' I',

jb EVALUATION Of THE, PRESSURIZER f'

+

_! SAFETY.AND REllEF VALVE.

DISCHARGE PIPING SUBSYSTEM

.. =

r

~,

Zion Station Units 1 and 2' u ' +.

n 90 ~ ' '

Prepar'ed for m

, jj; _

COMMONWEALTH EDIS0N' COMPANY

+

rChicago, Illinois 60690

,h

Under P. 0. N0. 805890 o

• A (.e E

August 1986 1'

' j g.....{ /, &

'8-27-86 /

GN b Pf

~

u

' Prepa'redy/Da te Quality Assurance /,Da te i

a.

s

• .f Si e b f// f $ vn rA 2;:

]Yww0 )

. s f/14N w

Ve ri f ied ' By/Da te,-

Approved By/D te' y ;,7 3

,y

-: Project Secretary /DaTe '

proved CECO-SNED

(.*

O'DONNELL & ASSOCIATES, INC.

ENGINEERING DDIGN Cf ANAL.YllS JER VKU 248 CUHHY tlOLLOW HOAD l

- PITTSDUNCF8, PENNSY LV ANI A 13230 (4:23 ess.i2oo 14 :23 ess.e so j

Page 1 of 18

,w.

1. w.7...>

g Rev Ol' 02 / 03

/

l' L

- Date 9-89 /10-8f 0-86 /

hg I719..:00'-003 b'I' N o N

,,9[')

/

9.

i

/ uA,4 n'?,,9{\\G Q

2-e L

r C..

- = - -

7; g.g W

e'S Lpy;b; i

j f

o:,.

': 4 ' '

l SPECIFICATION AND REPORT CHANGE RECORD FORM g:

n

~^ ARCHITECT. ENGINEER'S PLAN FOR THE s

EVALUATION:0FLTHE PRESSURIZER'

~

-SAFETY AND RELIEF' VALVE; DISCHARGE-PIPING SUBSYSTEM i

A 1

Paaes-Chanced Description of Chance

lit

3. 9' DDED LAST PARNGRAPH (ERR 0NEOUSLY SUBMITTED AS 1

I PAGE 10 IN REV. 02)

<.t i

n Es:

m

,3

&b&

/0 WO6 AN L /

ebd, U [ $ w,_ h 4 o h

&LL lo/ x64

.Enginee Date

/

Proj ect).lanager 6at6

. Verifier [

. ' a t'e Qua'Ift'y Assur'ance

'Date D

i

/

W o/J.g/ Rev.

03 Change Record Page

.1 of 1 4

gpprtive~d~CECf-SNED

. Da'te

.j

.I bi l

n -

-h

p

i'

."( : y

.+

t 3

'g.,

? SPECIFICATION AND REPORT CHANGE RECORD FORM ARCHITECT! ENGINEER'S PLAN FOR THE

' EVALUATION-0F THE PRESSURIZER SAFETY AND RELIEF VALVE DISCHARGE PIPING SUBSYSTEM Paoes Chanced Description of Chance 8~

3.3...... (Level D' loading condition per ASME BPV Code

~SectionIII, Division 1).

9-

. Added paragraph. after (4') =and before 3.4

~

_9 :

(1)' Changed :" based on B31.1, (1967 Edition)" to "and" (1)' JAdded "through Winter of 1985" (2f Changed "B31.1'," to "A110wables and methodology based on" (2)( L Added "(1983 Edition through Winter of 1985)"

(3): Changed "B31'.1," to "A110wables based on B31.1

'(1967 Edition), methodology based on B31.1 (1967

-Edition) and" (3) ! Added "(1983 Edition through Winter of 1985)"

(4). Changed "B31.1," to "Allowables based on B31.1 (1967 Edition), methodology based on B31.1 (1967 Editio 1) and" (4). Add'ed "(1983 Edition through Winter of 1985)"

{

110 3.9 added last paragraph 14 Changed page-# to 15 and title, E.J. Kreh, Manager, Quality Assurance.

& /. '& /0 -/0 -9 C

/// /0//c d$ r En ineer f g Date Projec~ (fat 4 ger A Lu folto/M

hIG1, u/niK 1

[ Verifier' dat'e Quality A'ssurance' Date j /=/juIr-Rev. 02 Change Record Page 1 of 2 M ppr6vsd CECO-SNED ' ' ~ L h I L $ino__ _ j

,- - g -s f. m Q4j l I 4 <r-e- q., 1: s SPECIFICATION-AND REPORT CHANGE RECORD FORM _ s ARCHITECT ENGINEER'S PROJECT PLAN FOR THE -f- .c ' EVALUATION OF THE PRESSURIZER RAFFTY ann DFf Trr Val Vr 4 4 DISCHARGE PIPING SUBSYSTEM Paces Chanced ' Description of Chance 2iand 3; Correcte'd page numbers for Sections 3.4, 3.5, 3.6, i- ~3.8,13.9, - 3.11, 3.12, 3.13, 3.14, 3.15, 3.17, 3.18, 3.19, 1.22, '3.25, 3.26, 3.27,. 3.28, 3.29 a a .' ja wk{W; ) 7 . f 2, yg9...j ' h

0'DONNELL &' ASSOCIATES; INC.

Ed.hd, lg. Njw. 'i [b %-g;fe m m. p .5I ~ yy:7 u 7p ~ y v ,i c-4 M j [ARCHITECiNNGINEER'SPROJECTPLAN .. FOR~THE m 'y 9.

• EVALUATION:0F THE PRESSURIZER' W

SAFETY AND' RELIEF VALVE ,y " DISCHARGE PIPING SUBSYSTEM-

.f 3 o

! Zion Station Units 1 and'21

TABLE OFJCONTENTS' eg, g,f

,o 9: m Page

, - '.~

100L.PROJECTIDESCRIPTION. 4 = NI > I- ,i2.0.. SCOPE OF WORK: 5 8

310HDESIGN. INPUT. REQUIREMENTS'.

_s M e };_ 3.1t Basic Functions to be: Performed 8 .f ' ~, ' L3.23 Performance' Requirements:. 8 3.3 D Codes,0 Standards : and LRegul atory l 8 f Requirements'. S J3.4 Final SafetyL AnalysisLReport and 10 P ..TechnicallSpecifications-J3.5;:f Design Conditions' 10

.3.6M Design Loadst 10 A

( 3.7 : Environmental Conditions - 10 M i3.8f Interface' System Requirements: 's 11 %r ' ;3.9 : Materiali Requirements, 11 J,' L3.10 MechanicalTRequirements 11 .13.11^ Structural. Requirements - 12- ,3.12 Hydraulic Requirements.: 12 l. J3.13 Chemistry Requirements i' 12

3.14f Electrical Requirements 12 3_15 Layou.t. and

Arrangements Requirements -

12 13;16 :0perational1 Requirements and Review. 12 Cof, Operation Procedures. e 3'.17 Instrumentation and Central 13 1 w lRequi.rements' ' 3.18~ Security and Security Lighting 13 ~ Requirements ? 13.19 Redundancy' and; Separation Requirements 13 I y, J3.20 Failure Effects ~ i 4

3.21; Test Requirements.

-3.22 Accessibility, Maintenance, Repair, 13 . (andLIn-Service. Inspection -3'.23; Cathodic Protection Requirements 13 M ..L3.24 Transportability Requirements 13 1 "z3125 Fire-Protection Requirements 14 - 3.26 Handling, Storage-and Shipping 14 Requirements.

f1719-400-003-02 Page 2 of 18 L

!*i g .b) 4 L. ...f..,,4 .1____.

~. r,m,: 1:z w n,: -, t _'p. r. j (&,, 9: ' y

r. i *,

1 ,p+ .t,i 2 1], '- 4 ()t d'.x., w a j 3 j

3. :., o

. F' '; 4 .s-r 4 ",4 0'DONNELL&' ASSOCIATES,' INCL-gg{f,pj,, i p%W %. @o,. > i...f I w ] 4

g. o %- > g m :

p4 8 s,s..< : ; 4.., g.n ..p 1-1 ~ 'fN ; ' [').f.,{.f 5 'j .,j..,. u>, ,.../ 4

i.

a ,, o p..,., ...-.......)..:m3n '!m i A 93.27fPersonnel. Protection - ALARA_ '14 J ,i, Requirements? J ? ' ";i.3.28~ Communication (Telephone / Radio)' 14- .... h 3 M ,4 . [ Requirements < ]'

19. * ~

-E3.29-Industry Experience: Requirements" 14-i j= g '15 , ' 4.0f ; PROJECT (ORGANIZATION.-

h. ~ g$

'.g 4 e m ',, ;.. 15.0 ? PROJECT!SCHEDULEL '16 Siu a w-c Mr m, .. SAFETY.-RELATED; EQUIPMENT LIST 16

6'0

.q e, w sREFERENCESi '17 'y v l m. 1, ~ 1 4. .:( 4 ).,, //~- . '.'[ j ./. i 731.'!:ql? D.S i.'k.. p., t e -.tg l

n

..b'. ']

s.

[vf.i ~p, . z. R.'V '* 'l m z JL n# ', g. \\p ?.,m Vt .. g 4 w ' N !q '; ?* z ,o, . '.'1. 2 :. ;i y/ 1' 3 3 1m o (4. 4 g .;pqw.. +..

v y- -,.

~. b4 a' 1 . hc4 1 .)', p.', f ' ' 33v - e 1 t n e t. t-at g b. % ^ 1-- l 1 i \\ i f p . I. i. . ).. 1 ..J u 5 s u. = s , m:w g' 'A it, i S. l +' ' u! f . i i 6 t .s l s + .o g. ~ t .,'5'e; 4.u;. y~'t :. : H ;,.pt -.W ' ~, / 4

g i,,

I-a,mlt ! ! ) \\ u t s -.1.. 9 ~ [3; [G 8 i n. \\ g ta y.! (1719 400-0' 3-02 Page 3 of 18 l 0 a i, -. c:o p l -rW. Ii! l t ; [t y \\. gr j T? -4

E.. A~ '~i W@ a.

f

i. W b

r,10 J0'DONNELL.& ASSOCIATESs INC.- (;o t ... g-y i

• p 2

+< @f 9 j I. l ARCHITECT: ENGINEER'S PROJECT PLAN-FOR.THE. h-EVALUATION OF~THE PRESSURIZER l SAFETY:AND RELIEF YALVE-w

g. :

l DISCHARGE PIPING' SUBSYSTEM-u 9 u Zion Station Units 1 and 2 9 s 3- , l110: 'PROJECTL D'ESCRIPTION 1 g lThe? pressurizer safety..and relief valve discharge piping system l ~foktheJp'ressurizedlwaterreactors(PWRs)providesl overpressure ~

protection for the reactor. coolant system. 7A water-loop seal-is j

I w imaintained upstream of; each pressurizer-safety: valve to prevent a steam.

79h (interface at.the valve Lseat... This wateK seal essentially eliminates k

._y. n the; possibility of. safety valve" leakage. L

i ;

-j t t Jhe original pressurizer safety and relief valve discharge piping t k; { subsystem _ was-designed by, Sargent &. Lundy. Subsequent to the Three W .MileilslandLincident, the Nuclear Regulatory Commission issued NUREG- /0737XSection II.D.1-[ Reference 5],- " Performance Testing of BWR and PWR Relief Land. Safety: Valves." This(required that all operating plant u , : licensees and' a.pplicants: conduct' testing to qualify the reactor coolant 1 ~ '. relief and. safety' valves; under expected. operating' conditions for design y n a - fbasis? transients and accidents..In addition to the qualification of i -valves, the functionability and structural integrity of the as-built

discharge' piping subsystem and supports must be demonstrated on a

plant-specific basis..

..Under the 'new accident conditions. postulated by NUREG-0737, the possibil.ity 'of a slug flow l condition exists in the discharge piping

subsystem.1 -In the,unlikely event that all-three safety valves are g, -

o actuated simultaneously, the water seal dr.iven by high-pressure steam c ' o

forces aLslug of water through the discharge piping subsystem. This 4

o ( i Y L1719 400-003-02' Page 4 of 18 1 4 sic Li xr_L__ __

357T H 1 %id, h4 j W @ O'DONNELL & ASSOCIATES, INC. s a. !$!] U slug'of water can generate substantial thennal hydraulic forces on the N ^ . discharge piping subsystem and its supports. p LStone.& Webster [ Reference 1] -and 'Sargent & Lundy (Reference 2]_ \\ L performed the plant specific analysis of the Zion Units 1 & 2 safety - and~ relief: valve. discharge piping subsystem as part of the NRC IE '- Bu11etin 79-14 effort. Their conclusions were that several components o L of the piping system would be overstressed. Sargent & Lundy [ Reference -2] concluded. that the postulated slug flow accident condition ' overstressed condition.could not be eliminated by additional or

relocated supports, and that-a portion of the piping must be rerouted, ySargent 8' Lundy also proposed that the safety. valves and all of the piping upstream of the safety valves be insulated in order to maintain a _ higher water temperature-in the' l'oop seals.

The purpose. of this_ project, to be conducted by 0'Donnell a

t Associates, is to review and the Sargent & Lundy analysis and determirje i,

' whether, and, if so, where excess conservatism was used with' respect to the: Zion Units 1 and 2 of CECO. As shown by Reference 16, the portion c of.the discharge piping system from the pressurizer to the j, ~ safety / relief valves, including the valves', is safety-related (Class 1 ] piping). The ' remainder of. the piping system is nonsafety-related { _(Clabs'3 piping). O'Donnell & Associates will. reanalyze the discharge piping subsystem using more realistic assumptions and analysis ( techniques..The refined evaluation may result in a satisfactory piping ~ system in its current configuration, thereby avoiding the necessity of rerouting any piping-and adding the proposed insulation. L 2.0 SCOPE' 0F WORK [, .The' 0'Donnell & Associates work scope for the evaluation of the pressurizer safety and relief valve discharge piping subsystem will be g.

divided into two phases. Two phases are required since statisf actory J

n 1 -1719-400-003-02 Page 5 of 18 g

---

_ --_J

pp g:5 ~ g'; 9%@ gi '0'DONNELL a' ASSOCIATES, INC. 7 1 -,a wa j e h;;, s 7i a s e ,,,l A...:.y; n':!y t 'l ,t ' l. h compistibn of Ph'ase.1' has the potential of eliminating the need:for i 3 l 0,w' [Phasel2.i The' following tasks are to be. completed as part' of the. Phase.

e "l activities

y_ y@l%.+f

.m e

@. f ' E ; [(a))( A'n;indApen' dent : detailed study. and: review of the St,one & Webster ~ I ?

anESargent

& Lundyireports. This review will-focus on those L

f areas where'ove' conservative assumptions-and/or techniques were <4 r used.. w' l l.(b)/ :0nce the; review h)Jis complete, the thermal. hydraulic analysis . willibe redoneL using the'RELAP5/M001 [ Reference 7] and ~REPIPE j t

3..

[ Reference 8] programs'. Unduej conservatism identified in Part (a) pa

willLbe removed from; this. reanalysis. lThe result' of this' analysis iwillLbeEthe appropriate dynamic. forces acting on the discharge-piping system as a result:of' the slug flow event.:.

J M ?(c)i The' dynamic forces determined ~in.Part (b) will' be used as input to .the ANSYS: Finite. Element program [ Reference,9). A linear elastic eJ ? finite element l analysis of the discharge piping subsystem will be ~ performed. A_ gain,f undue conservatism will be omitted from this ~ analysis. '(d)' The results;of Part (c) will be compared against the' applicable <sectionL of[the ASME. Boiler and Pressure: Vessel-Code.- If M satisfactory results.are' obtained, O'Donnell-8 Associates will aid Commonwealth Edison Company in preparing a position to be ~ q-presented to the United States Nuclear Regulatory Commission.. 5 (e)- '0' Donne 11' & Associates will also. provide. Commonwealth Edison . Company: with detailed answers to questions 12 and 13 proposed by . the NRC in Reference 014. -These questions pertain to the analysis m I t i U~L1719-400-003-02 Page 6 of 18 ...3 'T f. i (- :

g\\ n' (i) 26 M .; j w m, j.[ hh( 0'DONNELL &LASSOCIATES, INC. g&A _..[',. f*L; f Q, ',gm s Y n a

• L per' formed l.byf Sargenti a Lu' dy ' and the ' analysis ' carried out-as part b-J n

x 97 i ofShiswo'rk; scope.. Ug + x, a ~ p, yg ' 4 c(f)' ;Ifi the"results of"the Phas'e 1: work effort findicate that the piping i s gu m791 l system l.does not. meet'. the ~ applicable - Codes,. 0f Donnell. &. Associates $C, (. a si11 tissue (a nonsafety-related.reportito CECOon the' Phase 1 work. pge L 's 'After completion of Phase 1,11f the 'resulting stresses: meet.the -f.. f y,+~ ' applicablelCode!11mits, a; safety-related report will be issued,. and ' .q {[- % ' [ {t'hereis~nofreasonitoproceedfurther..However, our preliminary W '. Investigation.ofj thet work ldone by;Sargent & Lundy [ Reference,2]' .,s. ' :suggestsithattinsufficient margin' willEbe' realized by the linear ,m' W,.; ' Jelastic analysis with; reduced conservatism..,Therefore, it is' most 7" m 4 ....m pc < 'l 5, slikelyf that theUsecond-phase of.this project will'.be ' required to 3 y'f +: ? l satisfactorily; analyze l the' piping s9 stem. The Phase. 2 effort will use - f thbresultsTofs Phase?1' and will.be: safety-related for the appropriate ~ ~, ut

portion offthe piping

syst'em as. delineated;in Section 1.0.-

The major 4 nFA, 4 . task;ofJ theiPhase' 2, effort will be 'a nonlinear inelastic analysis. m; w jg, ' " H Properly ~. executed,finelastic analyses. are acceptabTe for both ASME Code w 1 purposes 'and: regulatory (NRC) purpos'est The following tasks, as ,y q7 fapplicab1'e,' willLcomprise Phase: 2 of this work'~ scope: m M ja ;. l( g)' Perfonn.a. nonlinear inelastic. piping analysis of the complete w ; ;',

pressurizer safety and relief valve discharge piping subsystem.

[ ' This analysis will use discrete beam and nonlinear finite elements .to represent-the piping.and: supports. All data generated during - o J-

Phase 1~which will'be used as inputs'for the Phase 2 effort will r

a L be.' verified'in accordance with safety-related. requirements. { o,;&; j ? f f ' I ((bli As required:by the results.of Part (g), detailed three-dimensional i ~ finite _ element Linelastic ' analyses will be made of the areas of

high stress.

g 4 We l 9~ 9 l 1719-400-003- 02. Page 7 of 18 ~ g g.g A ~ u

ggp

c ~

Ll,' N v Of ~..

0'00NNELL'&= ASSOC 1ATES; INC. '

j @f a Eg,' o. 31

k' a g,:gtp,

• pf g.

+ gg i ' "f(i)! 1The, resul ts' ofLth'e inelasticianalys'es. willi be compared with the. g ; la,, ' appropriate 'CodeIlimits ~ and NRC. Requirements. @P M ", $W' .,..3 < l y jg f(j)? ilssueLa safety-related report to CECO ont the Phat>e 2 work. 1 s p p.

-(k) Laid: Commonwealth Edison Company in' preparing a report _to the~ NRC i?,

' based upon' the..'results of Phase 2.- Yf l J ,e, ,' 9 93.0LDESIGN INPUT REQUIREMENTS-h f, [The following, requirements. define the major technical objectives, 7 (% i l restraints,l and regulatory requirements for. the scope of work .j o [~,

associated with.the analysis of'the. pressurizer nafety and relief valve

+ .m W

di scharge' p'ip'i ng. subsy stem.'

1 y $3.1 QBasic' Functions"to be Performed L

.A.

b. Analyzel the Messurizer ' safety and relief valve discharge ' piping ,,,, m

J

. subsystem-forjZion. Station,. Units l' and 2' under the case of. all three ~%

Lsafety ; valves being

actuated simultaneously (hereaf ter referred,to as y

- the " event: analyzed"),7 NUREG 0737, Item II.D.1. 1 f j'.' ( '3'2L P'erformance Requirements;

,, Wl,

There are no' performance requirements associated with this work x

w 1 scope. 's

3.3(; Codes, Standards and Regulatory Requirements

'The ' purposeof...the analysessis to assure the functionability and gjstructuraliintegrity of the as-built' discharge piping in the event that 2 Lallf t'hree: safety: valves should actuate simultaneously per NUREG-0737,

1. OI '

JSectionLII.D.1 and thus result in. a faulted condition (Level D loading 9 x 3 condition.per ASME BPV Code Section Ill, Division'1). The allowable stresses and ' design criteria and methodology equations for the piping "are' as given; by the following: <4

4..

.1719-400-003-02 Page 8 of 18

j 0'DONNELL.& ASSOCIATES, INC. y p 'd Q

e-

.(1)L Phase'.1, Class 1 Piping (Allowables :and methodology based on ASME BFV Code Section III, DiviNion 1, Subse.ction NB. (1983 Edition through Winter of 1985). .(2) Phase l',1 Class 3 Piping LAllowables? and methodology based on ASME BPV' Code Section III, Division 1, Subsection ND. (1983 Edition through Winter of 1985).

(3) ' Phase 2,. Class.1 Piping

. A110wables based on B31.1. (1967 Edition), methodology based on B31'.1. (1967 Edition) and ASME BPV Code Section III, Division 1, . Subsection NB and Appendix F- (1983 Edition through Winter of i 1985).. '(4) ' Phase:2',' Class 3 Piping' ~ . A110wablesLbased on' B31.1 (1967 Edition), methodology basted on 831.li(1967 Edition) and ASME BPV Code Section III, Division 1, Subsection' NDiand Appendix F (1983 Edition through Winter.of .'1985) '. i The pressurizer safety and relief valve discharge piping subsystem

contains 'both 's'afety-related. and norsafety-related components (see last

t. paragraph of Section.1.0). For purposes of this scope of work, all analyses

.which require interaction of the entire piping subsystem and/or those which E deal directly with the safety-related portions of the subsystem will be treated as. safety-related analyses. Analyses which deal entirely with the nonsafety-related portion-of the piping subsystem and whose performance does ~

not aff'ect the _overall piping. system will be considered as nonsafety-related tanNyses.,

+, L 41l r; f.. l-L 1719-400-003-02' Page 9 of 18 Lp pw

m~mm;=- ~ *c-l %yM) y b< W j i DM .9 L lo 0'DONNELL&.ASSOCIAT'ES,'INC.- 5 w y.o. N b i i ( / 7 it,,,

c u

p"a h, e gg w , x y9 msw w p%q 63kJFinaNSAfetyiAnalysis Report and Technical Specifications M DFor. the analysistof thel events 1 described in Section 3.1, certain s?q*s . unrelated \\conditionsi(for.. example, the seismic. loads)' given in the 4 po, p [] (Final Safetyj Analysiy Report are n'ot' applicable. The. appropriate ) W', (conditionsfusedfir[the analysis:willibejcompatible with FSAR . ~ ~, w , s Wr'equirementsi. ;Shuldiany con'dition..(e.g'j peak pressure) be found to K o 1 'w + o. os MM. ibe more severe lthan the FSAR: requirement, the mor'e: severe' con'dition E F ' % S M llbe.used. [;y: \\ T* ,, A y

.'. i' _

k; 0,

43.5LDesigiConditionsi gl 3yp ,ii ; '.

The csetpointipressure (2499.7

psia)f ofithe safety valve will. be y,

Mused;forf the pressurizer with-the steam 'in the pressurizer at . o. <. ,. Wm q ~w, w. z'. " W'

Msaturation? temperatursj(668*F) [Page 15 'of Reference 23. The

~ .f ~, v 9 (temperature' distribution.of. the11oop-seal. water 'is as measured by CECO + .o font 10-06-82l[ Reference 117]..

• 6 gm f.e <

s e .,..t , M 3.6 7 Design lLeadsD y 1Thel analyses'will include theideadweight of'the piping [Refere'nces-cgg < j g Pr ' t3 andMand insulations [ Reference;11]. Time history thermal hydraulic ~ s m. + _ b $1oads. derived from' RELAP5/REPIPEWill.be applied to the. ANSYS piping .d . h imodeu y m c 3.72 Environmental ~ Conditions '3 3 iThe? volume of-the reliefitank is 1800 f t and it contains 1440 ft sof water:at'-ambient teinperature,. assumed to be 80*F [Page 6 of 5 T ^ I SReferencef2]h LThe' piping, water' vapor inside the piping and ambient koutsideoffthecontainmentwillbeassumedtobe80*F[Page6of [R ference 6].gThe piping, water vapor.inside the piping ambient and l L e $h/ I ' Lairfinsideithe containment and downstream of the safety / relief valves ] ,. 41sfat'110*F'[ Reference 17]. 'f 1 2 ,m t . f.; w, .,[ 1 . - o... j M n17194400-003-02L Page 10 of 18 p M ),.

~ mrv - }. p j e + 0'DONNELL:& ASSOCIATES, INC6 j %e \\~l J ^^ ( i Interface System Requirements , g 13.8 1 Because of. the type.of event analyzed, no interface systems need ~ l - to ; beiconsii1ered.- l 19

3.9. : Material Requirements -

~ The material: requirements- [ References' 3 and 4] are as foilows:

(1) : Seamless austentic steel pipe per ASTM A312

.o SIZE-GRADE: SCHEDULE STANDARD Qpu -1/2 through.6" . TP304.. 40S USAS B36.19 w 4! '(2) 1 Seamless austentic isteel pipe per ASTM A376 3";. and smaller-.TP304 or 316 160 USAS B36.10 ' 6":

TP316

.160 USAS'B36.10 4 .j -(3). L Fusion welded austentic steel-pipes per ASTM A358, Class 1 i 12"' 316 40 USAS B36.10 c Yalues for the modulus of elasticity and the thermal expansion for

the piping material will be as specified in the ASME Code for Pressure e

Piping, B31.'1, 1983 Edition for Phase l 'and as specified in the ASME [ Code for Pressure Piping, B31.1,1967 Edition for Phase 2. 3.10.' Mechanical Requirements The analysis will. include the mechanical' requirements for all of the piping : components, i.e. straight pipe, elbows, tees, reducers, valves, supports, hangers, anchors, and snubbers. Because of the short duration of.the slug flow event (1.25 seconds) [ Exhibit 19 of Reference 2],. the. heat transfer from -the slug of water to the pipe walls is insignificant and hence will be neglected. i l .1719-400-003-02 Page 11 of 18 l

h!h '[ R:n ',D h [o 0'DONNELL & ASSOCIATES, INC. Q$ (, a 1 ,.V.lb, ' .. e, g 1 g 3.11) Structural:. Requirements - $PY' - Thel analyses will':' demonstrate the structural integrity of the q ) piping sy' stem unddr. consideration. .] /.3112HydraulicRequirements' \\' Thef analyses willfdemonstrate the' functionability of the piping system for the. event ' considered. The. analysis will. use' values of 0.88 j .'second1and 0.014isecond for the simmer and pop periods for the safety ,g a n;. Dvalves:.[Pager15.of Reference' 2] and.a steady state; steam flow rate of y u-S /129.5. Lib /secI[PAge 9.ofl Reference 23. (111%' of rating) through the s ', isafety valves Las required by: the ASME-Code. ..~ 4ff ' j3131 Chemistryi Requirements

Because:of'the function ~ of the system, chemistry requirements are w

C <f not Lapplicable. ' l w a t 3.14. Electrical : Requirements j i ~1 [, LBecauseLof f the.. type of event analyzed, electrical requirements are ~ .?E notiapp11 cable.. o-i ri 3.15 Layout and A' arrangements R' requirements I

The analyses will be' based on the as-built piping system

[ References 10,11,'12,and'133 The Stone & Webster support I

- modification ~ drawings 79-14'[ Reference 13] take precedence over the (Sargent*& Lundy Reactor Coolant System Support drawings [ Reference 12] s .and[the Kellogg' drawings [ Reference 10] take precedence over the y

Sargent 8' Lundy drawing [ Reference 11].

l [3'.160perationalRequirementsandReviewofOperationProcedures

Becausel of

the type of event analyzed, operational requirements

.and operationalTprocedures' are 'not applicable. ~ y. A [1719-400-003-02 Page 12 of 18 t I a

0'DONNELL & ASSOCIATES, INC. '3.17 Instrumentation add Control Requirements Because of the type of event analyzed, instrumentation and' control I . requirements are not applicable.- 3.18 Security and' Security Lighting Requirements Because of the type of event analyzed, security and security a '( y lighting requirements are not applicable. i 3.19 Redundancy and Separation Requirements Because of the type of event analyzed, redundancy and separation N e'ffects are not applicable. - 3.20 Failure Effects. Because of the type of event analyzed, failure effects are not !~ applicable. t3'.21 Test Requirements t Because of the type of event. analyzed, test requirements are not applicable. 3.22 Accessibility, Maintenance, Repair, and in-Service Inspection Requirements Because of the type of event analyzed, accessibility, maintenance, repair and in-service inspection requirements are not applicable. 3.23-Cathodic Protection Requirements Because of the type of event analyzed, cathodic protection . requirements are not applicable. 3.24 Transportability Requirements Because of the type of event analyzed, transportability j requirements are not applicable. f '1719-400-003-02 page 13 of 18 s - -. -_--.._ - ____ O

n -n 0'DONNELL & ASSOCIATES, INC. ~3.25 Fire Protection Requirements Because_- of _ the type of event analyzed, fire protection requ_irements are not applicable. 3.26 Handling, Storage and Shipping Requirements Because of the type' of event analyzed, handling, storage, and ' shipping requirements are not applicable. 3.27 Personnel Protection - ALARA Requirements .Because of the type ~ of event analyzed, personnel protection - ALARA' requirements - are not applicable. 3.28 Communication (Telephone / Radio) Requirements Because of. the type of event analyzed, communication i (telephone / radio)- requirements are not applicable. ~ !' 3.29 Industry Experience Requirements The personnel involved with the project shown in the following Section meet the industry experience requirements. i l 1719-400-003-02 Page 14 of 18 1 = _ - _-

7__,, 0'DONNELL.& ASSOCIATES, INC. 3. s 3 r l /4.0' PROJECT ORGANIZATION The ' organizational structure employed by O'Donnell & Associates { for this project.is as follows: I 1 - CECO - J. REISS l I DR. E. J. HAMPTON PROJECT DIRECTOR E. KREH DR. W. J. O'DONNELL MANAGER OR. RAY G. FASICZKA QUALITY ASSURANCE PROJECT CONSULTANTS l EVAN WESTERMANN j PROJECT MANAGER l 1 1 l RON KICHKO DR. ROLAND RAC0* ED URBANSKY I COMPUTER SPECIALIST PROJECT ENGINEER TECHNICAL SERVICES

• Work 'will be independently verified per ANSI N45.2.ll.

1719-400-003-02 Page 15 of 18 uj

m;,w x.y;'y;p i r g a s,. e s y w.1 " 1:s'1 $1 U R ' 0'DONNELL 1 ASSOCIATES. INC. 3 / ,.y g-]

h ^ s

+ t E y; N. Y^ 0 k{ r-s 8 1., d_ iu-- > + 4 t j ygr g ,s hg['M dj.0L'?PROJECTSCHEDULE j ppfD<l t ihe' following~.isithe' schedule for the pe'rtinent activities . / [ g- .b, s6 Cia'ted with the ar.alpsis' bf.the' pressurizer sa fety and relieve i 4,

t. valve" discharge piping subsystem:

X f: j Gl,J ^ [m . j r ', lk > ~ <ie s s 1 . se

]

PHA$E ii l/6 ' 1/13' I/20 1/27 2/3

r. n,

a: ' '. RESPOND'70 NAC OUEsilons - i E9'., ' ' , $o'

AND PHASE I AfPORT'.

j mM i f.jj; ' ' ON r T w.4 51 .i : i jf! PHASE;2 i ?/21; 7/26 8/4 8/11 8/18 8/25 '9/2 9/8 '9/15 9/22 9/29 10/6 10/13 i (. DETAILED'3-Di i. ANALYSES' 'M ~ 1 '. COMPARE'aESULT$- '. l.. .i' t 1 ,F T0' CODE' flNAL' REPORT-Mk,a, . + K 'AND NRC-licQ PRE $ENTATION-t -" r/ .t L-x ~ p x - _.s v

l. I -

6.0: SAFETY-RELATED EQUIPMENT LIST 'y L As. shown by Reference 16, only the portion of the discharge piping subsystem upstream of the: safety and relief. valves is safety-related; however,:ali of the analysis effort associated with this project will f s, m.:= - bel controlled by the' requirements' of 10CFR50, Appendix B and ANSI 7 T' N4 5. 2.11'. In addition, the requirements of the O'Donnell & Associates . Quality Assurance Manual. [ Reference 15]' and Commonwealth Edison Company ' SupNement will also 'be involved. p y

p a.

1719-400-003-02 Page 16 of 18 4 ',.s

1719-400-003-01 0'DONNELL & ASSOCIATES, INC. y', m,, PREFERENCES mw

1. EBooks 1 through 6, inclusive, of Stone & Webster, " Zion Station Pipe 1 Stress and Support Analysis Report," Number 13430RC - 2, 3, 4, 5, Revision 0, dated January 17, 1983, Commonwealth Edison Job Order 713430.01 for Reactor Coolant (Pressurizer 1RC002 'to Pressurizer Relief Qank1RC003).

2. Sargent & Lundy Report SL 4283 dated May 2; 1984, '" Evaluation of the Pressurizer Safety and Relief Valve Discharge Piping System - Zion Stations l'and 2 3. " Zion Piping Design Table 'L' Stainless Steel " six pages dated February 15, 1969, revised December 30, 1970, numbered X-2242 and X-

2245.

4. " Zion Piping Design Table 'E' Stainless Steel," five pakes dated February 15, 1969, revised December 30, 1970, numbered -2242 and X- '2245. 5. NUREG' 0737 - Item 11 D.1, NRC Docket Numbers 50 - 295 and 50 - 304, '" Performance Testing of BWR and PWR Relief and Safety Valves." 1 6. Sargent & Lundy Report No. 037064, Project No. 6320-00. " Dynamic .' Analysis of Typical Pressurizer Safety and Relief Valve Discharge Piping Due to Valve Actuation." dated August,1982. '7. Ransom, V. H. et al., "RELAP5/ MOD 1 Code Manual," Volumes 1-2, NUREG/CR-1826', EGG-2070, March 1982. 8. Norton,' P. J., " User's Manual for Program REPIPE," Utilities Service t Center, CDC, Rockville, Maryland. i ' 9. ' ANSYS Engineering Analysis System, Revision 4.1, Swanson Analysis Systems, Inc., Houston, Pennsylvania.

10. Kellogg Company Power Piping Division, Job No. N8342, System #34 Reactor Coolant, Drawings:

150. 1-34-15 Rev. 2 .150 1-34-20 Rev. - 150 1-34-21 Rev. 1 150 1-34-22 Rev. 1 150 1-34-23 Rev. 3 150.1-34-24 Rev. 1 .o 1719-400-003-02 Page 17 of 18

O'DONNELL & ASSOCI ATES, INC. 4 11. Sargent & Lundy Drawing M-418, Pressurizer Piping Analytical Data Isometric, Zion Station Unit 1, Sheet No.1, Rev. D, dated July 31, 1979.

12. Eargent & Lundy Reactor Coolant System Support Drawings:

Hanger # Date Hanger # Date IRC146-FR1 8-25-77 RCH-1008 12-18-72 1RC146-SR1 4-21-77 RCH-1009 1-28-74 1RC147-SR1 4-21-77 RCH-1014 10-27-72 1RC147-SR2 4-21-77 RCRS-1112 11-20-72 1RC151-RV1 4-21-77 RCRS-1114 6-2-71 1RC157-RV1 8-25-77 RCRS-1115 11-20-72 1RC157-RV2 4-21-77 RCRS-1119 2-16-73 RCH-1005 10-27-72 RCRV-001 12-21-72 RCH-1007 1-12-73

13. Stone & Webster Bulletin 79-14 Modification Support Drawings:

Hanger # Date RCH1006 2-10-81 RCH1010 1-30-81 RCRS1117 1-30-81 RCRS1118 1-30-81 RCRS1120 2-4-81 RCRS1121 1-30-81 RCRS1122 1-30-81 RCRS1123 2-4-81 RCRS1117A 7-22-81 RCRS1117B 7-22-81 RCRS1118A 7-22-81 RCS1011 RCS1012 RCS1013

14. NRC letter dated February 19, 1985, Docket No. 50-295 and 50-304 to Mr.

D. L. Farrar, CECO from Mr. S. A. Varga, NRC Licensing Division.

15. O'Donnell & Associates, Inc. Quality Assurance Manual, Revision 5, dated January 15, 1985.

16. Sargent & Lundy, Diagram of Reactor Coolant Loops 3 and 4, Zion Station M-53, March 3, 1970.

17. Graesser, K.L., (Zion Station Superintendent) to Butterfield, L.D.,

(CECO), Letter November 9,1982, " Unit 2 Pressurizer Safety Valve Loop Seal Temperature". ~ 1719-400-003-02 Page 18 of 18 ad

ATTACHMENT 2-1 1 f E I f, i ll i il a 4 i i 1 s I - - -- -}}