ML20236R981
| 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: |
| References | |
| PROC-860828, NUDOCS 8711240147 | |
| Download: ML20236R981 (23) | |
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roR inE' I', jb EVALUATION Of THE, PRESSURIZER f' ,
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_! SAFETY.AND REllEF VALVE.
- , DISCHARGE PIPING SUBSYSTEM
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COMMONWEALTH EDIS0N' COMPANY
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O'DONNELL & ASSOCIATES, INC.
ENGINEERING DDIGN Cf ANAL.YllS JER VKU 248 CUHHY tlOLLOW HOAD
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s EVALUATION:0FLTHE PRESSURIZER'
-SAFETY AND RELIEF' VALVE; -
DISCHARGE-PIPING SUBSYSTEM !
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? 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).
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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.
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.c ' EVALUATION OF THE PRESSURIZER -
4 4 RAFFTY ann DFf Trr Val Vr
, DISCHARGE PIPING SUBSYSTEM Paces Chanced
' Description of Chance i-2iand 3; Correcte'd page numbers for Sections 3.4, 3.5, 3.6,
~3.8,13.9, - 3.11, 3.12, 3.13, 3.14, 3.15, 3.17, 3.18, aa 3.19, 1.22, '3.25, 3.26, 3.27,. 3.28, 3.29
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- EVALUATION:0F THE PRESSURIZER' W,y
< 'y 9. SAFETY AND' RELIEF VALVE
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, " DISCHARGE PIPING SUBSYSTEM-
! Zion Station Units 1 and'21
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- TABLE OFJCONTENTS' eg 9: , g,f m .
Page 4
- , - '.~ 100L.PROJECTIDESCRIPTION. =
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
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' ;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, 4
' , ". J3.20 Failure Effects ~ i '
- 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
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- 19. * ~ . -E3.29- Industry Experience: Requirements" 14- ]' .
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I. ' l ARCHITECT: ENGINEER'S PROJECT PLAN-FOR.THE. h- ;' . EVALUATION OF~THE PRESSURIZER w g. : , l SAFETY:AND RELIEF YALVE-u l DISCHARGE PIPING' SUBSYSTEM-9 . u 9 s , Zion Station Units 1 and 2 3-1 g , .: , l110: 'PROJECTL D'ESCRIPTION
, lThe? pressurizer safety ..and relief valve discharge piping system l
~
~foktheJp'ressurizedlwaterreactors(PWRs)providesl overpressure j ; protection for the reactor. coolant system. 7A water-loop seal- is .
w' .
> imaintained upstream of; each pressurizer-safety: valve to prevent a steam. I
- 79h (interface at.the valve Lseat.. . This wateK seal essentially eliminates k L n the; possibility of. safety valve" leakage.
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;i ; -j Jhe original pressurizer t safety and relief valve discharge piping 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 u Relief Land. Safety: Valves." This(required that all operating plant
~
, , : licensees 1and' a.pplicants: conduct' testing to qualify the reactor coolant y
'. relief and. safety' valves; under expected. operating' conditions for design 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 c'o actuated simultaneously, the water seal dr.iven by high-pressure steam 4
- forces aLslug of water through the discharge piping subsystem. This o
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,,' L17191 400-003-02' Page 4 of 18 4 sic Li xr_L__ __ _ __ _- -_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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U N , slug'of water can generate substantial thennal hydraulic forces on the
. 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 o - Bu11etin 79-14 effort. Their conclusions were that several components . 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.
- t The purpose. of this_ project, to be conducted by 0'Donnell a i, Associates, is to review and the Sargent & Lundy analysis and determirje
' 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 j, c of .the discharge piping system from the pressurizer to the
~ 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 I
- 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 g. pressurizer safety and relief valve discharge piping subsystem will be
; divided into two phases. Two phases are required since statisf actory I
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compistibn ofi Ph'ase.1' has the potential of eliminating the need:for h l 0,w' [Phasel2.i The' following tasks are to be. completed as part' of the. Phase . y_ ;e '
"l#activities: '
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@. 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
<4 f areas where'ove'r conservative assumptions- and/or techniques were used..
l
- , w' l.(b)/ :0nce the; review h)Jis complete, the thermal. hydraulic analysis t
j
, 3. .
. willibe redoneL using the'RELAP5/M001 [ Reference 7] and ~REPIPE
[ 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
~ q- Commonwealth Edison Company in preparing a position to be
, 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
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b-J , , x L per' formed l.byf Sargenti a nLu' dy ' and the ' analysis ' carried out- as part 97 i ' ofShiswo'rk; scope.. Ug + , x, a ' p , yg ' c(f)' ;Ifi the"results of"the Phas'e 1: work effort findicate that the piping
~
4 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 . . .
' -f..
y,+~ f 'After completion of Phase 1,11f the 'resulting stresses: meet.the
' applicablelCode!11mits, a; safety-related report will be issued,. and '
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.q W {t'hereis~nofreasonitoproceedfurther. .However, our preliminary
%'[
'. 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
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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 - ~
~, ut f thbresultsTofs Phase?1' and will .be: safety-related for the appropriate ; n 4
; portion offthe piping :syst'em as . delineated;in Section 1.0.- The major FA , 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 ,y , 1 purposes 'and: regulatory (NRC) purpos'est The following tasks, as 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
[ o >
.to represent-the piping.and: supports. All data generated during -
J- ,; r : Phase 1~which will'be used as inputs'for the Phase 2 effort will a . L be.' verified'in accordance with safety-related. requirements. { o ,
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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 g 4
- high stress.
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.,..3 M ", . < l y p.jg f(j)? ilssueLa safety-related report to CECO ont the Phat>e 2 work. s 1
p
- -(k) Laid: Commonwealth Edison Company in' preparing a report _to the~ NRC i
?, ' based upon' the..'results of Phase 2.- l J Yf , , , , . ,e, , ,
,' 9 93.0LDESIGN INPUT REQUIREMENTS-h f, 7 o
[The following, requirements. define the major technical objectives, (%*i ., l restraints,l and regulatory requirements for. the scope of work .j
- associated with.the analysis of'the. pressurizer nafety and relief valve ;
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; di scharge' p'ip'i ng . subsy stem.'
# 1 L
y $3.1 QBasic' Functions"to be Performed '
; .A . b. Analyzel the Messurizer ' safety and relief valve discharge ' piping
,, , , m
. subsystem- forjZion. Station,. Units l' and 2' under the case of. all three
- J ,
~% ; 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 2
gjstructuraliintegrity of the as-built' discharge piping in the event that Lallf t'hree: safety: valves should actuate simultaneously per NUREG-0737,
- 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
<4 "are' as given; by the following: ',
- 4..
.1719-400-003-02 Page 8 of 18
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.(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) ' .
The pressurizer safety and relief valve discharge piping subsystem i
- 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.,
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gg , w , p"a h , e , x y9 msw63kJFinaNSAfetyiAnalysis w Report and Technical Specifications p%q - - . . . . . . M DFor. the analysistof thel events 1 described in Section 3.1, certain s?q*s 4
. unrelated \conditionsi(for.. example, the seismic. loads)' given in the po , (Final Safetyj Analysiy Report are n'ot' applicable. The . appropriate
)
p [] ' ' W', % (conditionsfusedfir[the analysis:willibejcompatible with FSAR , ~,
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ibe more severe lthan the FSAR: requirement, the mor'e: severe' con'dition MM . , E [;y: F ' % S M llbe.used.
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43.5LDesigiConditionsi gl 3yp ' ,ii ; '. & , y, ;The csetpointipressure (2499.7: psia)f ofithe safety valve will. be - , . . o. <. Wm - Mused;forf the pressurizer with- the steam 'in the pressurizer at
.f q ~w, w.
;Msaturation? temperatursj(668*F) [Page 15 'of Reference 23. The
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v . .. . (temperature' distribution .of. the11oop-seal . water 'is as measured by CECO -
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font 10-06-82l[ Reference 117].. . , gm f.e < s e .,..t
, M 3.6 7 Design lLeadsD y
gg < j :.g c 1Thel analyses'will include theideadweight of'the piping [Refere'nces-Pr
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' t3 andMand insulations [ Reference;11]. Time history thermal hydraulic m.
+
s _b - $1oads. derived from' RELAP5/REPIPEWill .be applied to the. ANSYS piping
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imodeu c 3.72 Environmental ~ Conditions
'3 3 iThe? volume of-the reliefitank is 1800 f t and it contains 1440 ft 5 ^
T sof water:at'-ambient teinperature, . assumed to be 80*F [Page 6 of
. . SReferencef2]h LThe' piping, water' vapor inside the piping and ambient I koutsideoffthecontainmentwillbeassumedtobe80*F[Page6of
[R ferenceL 6].gThe piping, water vapor .inside the piping ambient and l e $h/ I ' Lairfinsideithe containment and downstream of the safety / relief valves
'f , . 41sfat'110*F'[ Reference 17]. ]
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0'DONNELL:& ASSOCIATES, INC6 j %e , \~l ^^ J , (
, g 13.8 i Interface System Requirements 1
~
- Because of. the type.of event analyzed, no interface systems need
- to ; beiconsii1ered.- l l
- . 19
- 3.9. : Material Requirements -
~
The material: requirements- [ References' 3 and 4] are as foilows:
- (1) : Seamless austentic steel pipe per ASTM A312
.o .
SIZE- GRADE: SCHEDULE STANDARD Qpu
-1/2 through.6" . TP304. . 40S USAS B36.19 w
4!
'(2) 1 Seamless austentic isteel pipe per ASTM A376 3";. and smaller- .TP304 or 316 160 USAS B36.10
- 4 ' 6": :TP316 .160 USAS'B36.10 ,
.j
-(3). L Fusion welded austentic steel- pipes per ASTM A358, Class 1 i 12"' 316 40 USAS B36.10 .,
c ! Yalues for the modulus of elasticity and the thermal expansion for
;the piping material will be as specified in the ASME Code for Pressure e Piping, B31.'1, 1983 Edition for Phase l 'and as specified in the ASME
[ Code for Pressure Piping, B31.1,1967 Edition for Phase 2. 3.10.' Mechanical Requirements The analysis will. include the mechanical' requirements for all of the piping : components, i.e. straight pipe, elbows, tees, reducers, valves, supports, hangers, anchors, and snubbers. Because of the short duration of.the slug flow event (1.25 seconds) [ Exhibit 19 of Reference 2],. the. heat transfer from -the slug of water to the pipe walls is insignificant and hence will be neglected. i l
.1719-400-003-02 Page 11 of 18 l
h!h '[ R:n ',D h ' [o ' 0'DONNELL & ASSOCIATES, INC. Q$ (, a 1 , .V.lb , ' .
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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
,g , .'second1and 0.014isecond for the simmer and pop periods for the safety a n; . . y u- ' < Dvalves:.[Pager15.of Reference' 2] and .a steady state; steam flow rate of 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 t a
, 3.14. Electrical : Requirements j i ~1
[, LBecauseLof f the.. type of event analyzed, electrical requirements are
~ .?E o-notiapp11 cable. .
i ri # 3.15 Layout I and A' arrangements R' requirements
- 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 s
(Sargent*& Lundy Reactor Coolant System Support drawings [ Reference 12]
# y .and[the Kellogg' drawings [ Reference 10] take precedence over the
;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
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' 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 ! a ,.
'(
Because of the type of event analyzed, security and security 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
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- 0'DONNELL.& ASSOCIATES, INC. ; ,- 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
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ppfD<l .. t ihe' following~.isithe' schedule for the pe'rtinent activities i 4, . / [ g- .b, s6 Cia'ted with the ar.alpsis' bf .the' pressurizer sa fety and relieve
. , , t. valve" discharge piping subsystem: '
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PHA$E ii l/6 ' 1/13'
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' '. RESPOND'70 NAC OUEsilons -
, $o' :AND PHASE I AfPORT'.
j mM i f.jj; ' ' ON ' r - T w.4
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% jf! PHASE;2 i ?/21; 7/26 8/4 8/11i 8/18 8/25 '9/2 9/8 '9/15 9/22 9/29 10/6 10/13
, i (. DETAILED'3-Di i . ANALYSES' . , .
,','M 1
, ~
1 '. COMPARE'aESULT$-
* ,F T0' CODE'
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. + flNAL' REPORT-
- Mk,a, 'AND NRC-licQ t -"
PRE $ENTATION-
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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; s ,
' however,:alif of the analysis effort associated with this project will 7 m.:= - bel controlled by the' requirements' of 10CFR50, Appendix B and ANSI 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
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- -. a .
1719-400-003-02 Page 16 of 18 4
',.s
1719-400-003-01 0'DONNELL & ASSOCIATES, INC. y', m,, m PREFERENCES w
;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 February 15, 1969, revised December 30, Steel," five pakes 1970, numbered dated
-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
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