ML19206B288
| ML19206B288 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/24/1975 |
| From: | Kniel K Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7905080334 | |
| Download: ML19206B288 (32) | |
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Metropolitan Edison Ccepany ATT'l:
Mr. R. C. Arnold Vice President P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
To cocplete the review of your application wita regard to coculiance with 10 CFR 50.46, certain material is needed which may be in addition to that subnitted in the B5W topical reports covering the ECCS syste'"s.
Attachment I to this letter is an overall requirements statement dolineating all information necessary for the staff to complete its review of ECCS capability on each and every application docket. Each NSSS vendor (including B5W) has already been provided with all the attached information except the first two pages.
We urge you to evaluate these requirements and be assured that your submittals on the Bree Mile Island, Unit 2 docket include all the required information outlined in Attachment 1.
Please advise this office within 10 days of your schedule fr e submitting additional information as required.
Sincerely,
%nal sl~1bI Earl Kriel Karl Kniel, Chief Light Wat ir Reactors Branch 2-2
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Division ' Reactor Licensing Required Information
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Metropolitan Edison Ccmpany DISTRIBUTICS:
ces:
NRC PDR George F. Trowbridge, Esquire Local PCR Shaw, Pittman, Potts 6 Trowbridge
. Docket File 910 17th Street, N.W.
LWR 2-2 File Washington, D. C.
20006 mtoore -
her 2 N4 Mr. Richard W. l{eward W'tcDonald "Willians Project Manager GPU Service Corporation RKlecker 260 Cherry 11111 Road ELD Parsippany, New Jersey 07054 IE (3) liSilver Mr. 'Ihomas M. Cri=nins, Jr.
TR AD's TR BC's Safety and Licensing Mansger LWR n 2 BC's GPU Service Corporatien 260 Cherry Hill Road
!.CRS (14)
Parsippany, New Jersey J70S4 MSc rvice Chauncey R. Kepford, E.guire Cha12 man bcc:
York Committee for a JRBuchanan Safe tinvironment TBAbernathy General Delivery York, Pennsylvania 17401 l
Para AI.C.)1 s i Re'. 9 5 3).6 0240 W u.s.oovs==essme,=invine oppics:,es4.sas.ies
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UNITED STATES NUCLEAR REGULATORY COMMISSIOF W ASHIN G ton. D.
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20555 Docket No. 50-320 July 24, 1975 Metropolitan Edison Ccepany ATIN:
Mr. R. C. Arnold Vice President P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
To complete the review of your application with regard to comuliance with 10 CFR 50.46, certain material is needed which may be in addition to that submitted in the BS',. topical reports covering the ECCS systems. to this letter is an overall requirements statement delineating all infonatica necessary for the staff to complete its review of ECCS capability on each anc every application docket.
Each NSSS vendor (including SSW) has already been provided with all the attached infomation except the first cwo pages.
We urge you to evaluate these requirements and be assured that ycur submittals on the Three Mile Island, Unit 2 docket include all the required infomation outlined in Attachment 1.
Please advise this office within 10 days of your schedule for submitting additional information as required.
Sincerely, f4/ piJ Karl Kniel, Cnief Light Water Reactors Branch 2-2 Division of Reactor Licensing :
Required Info m ation ec: See next page c' UTIC4
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i Metropolitan Edison Company ces:
George F. Trowbridge, Esquire Shaw, Pittman, Potts 5 Trowbridge 910 17th Street, N.W.
Washington, D. C.
20006 Mr. Richard W. Heward Project Manager GPU Service Corporation 260 Cherrv Hill Road Parsippany, New Jersey 07054 Mr. Thomas M. Crimins, Jr.
Safety and Licensin; Manager GPU Service Corporation 260 Cherry Hill Road Parsippany, New Jersey 07054 Chauncey R. Kepford, Esquire Chairman York Committee for a Safe Environment General Delivery York, Pennsylvania 17401 L u.
r REQUIRED INFCF".ATION 1.
Break Socc:run and Partial Loop C eration The informatica p:cvided for each plant sha'll ec= ply with the provisions of the attacned =ccorandu entitled, ""inimum Requirements for ECCS 5:eak Spectru: Submittals."
2.
Potential Baron Precioitation (?'iR's Cniv)
The ECCS systen in each plant should be evaluated by the applican:
(or licensee) to show that significant changes in chcaical concentrations will not occur during the long ter= after a loss-of-coolant accident (LCCA) and these potential changes have been specifically addressed by appropriate operating procedures. Accordingly, the applicant should review the system capabilities and operating procedures to assure that boron precipita:ica would not cceprc=ise long-term core cooling capabilit:.
folicwing a LCCA.
This review should censider all aspects ci the specific plant design, including cctpenent qualification in the ;CCA envircreen: in additica to a detailed review of operatin; procedures.
The app 11: ant should examine :he vulnerability of t'.ie specific plant design to single failures that would result in any significant boren precipitation.
3.
Single Failure Analvsis A sinole f ailure evaluatica of Fe ECCS should be provided b:. the o
applicant (or licensee) for his specific plant design, as recuired b:-
Appendix K to 10 CFT 30, Sec: ice 1.D.1.
In pericraing :nis evaluatica, the effects of a single failure or operator error that causes anv man u a l l,.
- ontrolled, electrically-onara:ed valve to move :o a positica that enuld adversely affect the ECC3 mus: be considered.
Therefera, 2f :his censid-eration bas not been specifically repor:ec in the past, the applicants upccming submittal cust adcress this consideration.
Include a list of all of the ECCS valves that are curren:ly required by the plant -echnical Specifications to have power disconnec cd, and any procosed plant modifications and changes to the Technical 5cecificacicna that mi;l be required in or,er to protect against anv.oss c:_ sarety tunctica caused by this type of failure. A ccpy of 3 ranch Technical ?osition CICi3 13 frca the
.S. Nuclear Regula:orv Cc==ission's S tandarc Reviev Plan is attached to provide you with guidance.
The single f ailure evalurticu should include the potential for passive f ailures of fluid g stems during long term cooling follcuing a LCCA as well as single failures of active components.
For P'AR plan:s, the single failure analysis is to censider the potential boren concentra-problem as an integral part of long ter: coolin;.
4 Submer;ed Valves The applicant should review the specific equipment arrance=cnt wi:5-in his plant to determine 12 any valve actors within c.ntaintant will beccme submer;cd folicwing a LCCA.
The review should inc.ude all valve cotors that may become submer;cd, no: caly those tu the safe:f injection system..
Valves in other sys: ems may be needed :o limi: boric acid con-centration in the reactor vessel during long tern cociing cr me-be required,for containment isolatica.
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The applicant (or licensee) is to provide the following information, for each plant:
(1) Whether or not any valve notors will be submerged following a LCCA in.
the plant being reviewed.
(2)
If any valve =otors will be flooded in their plant, the applican: (or licensee) is to:
(a)
Identify the valves that will be submerged.
(b)
Evaluate the potential cenacquences of flooding of the valves for both the shor: ters and icng tern ECCS functions and containment isola:icn.
The long ter= should consider the potential problen 0; ex:essive concentrations of boric acid in PWR's.
(c)
Propose a interia colution while necessary modifications are being designed and implemented.
(currently operating plants only).
(d)
Propose design changes to solve the potential flooding, proble -
5.
Containment Pressure ( PWR ' s__on 1 v )
The containment pressure used to evaluate the performance capabilit', of the ECCS shall be calculated in accordance with the provisions of Branch Technical ?asition CS3 6-1, whici. is enclosed.
6.
Low ECC3 Reflood Rate (L'estinghouse NSSS Cnly)
Plants that have a ',.'estin;houre nuclear steam supply shall perform their ECC3 analyses utilizing the proper version of the evaluation acdel, as defined below:
(1)
Ine December 23, 1974 version of the Westinghouse evaluati:n
- model, i.e.,
the version withou: the modificaticas descriaed in WCAP-8471 is acceptable for previously an.civ:ed plants for.hich the peak clad temperature turnarcund was identi::ed prier :o :he reflood rate decreasing below 1.1 inches per second or fer which the reflood rate was iden:ified :o remain above 1.0 inch :er second; conJi:icns for which the December 23, 197' and. arch 13, 1975 versions woulu be equivalent.
(2)
The March ?5, 1975 version of the c.estinghouse evaluatien --del
. an acce: tau.- rudel to be used for all previously analy ec plants for.;hich tnm c2k clad te=perature turnaround was identi-fiad to c cur after the reflood rate decreased below 1.1 fncnes per.econc, a-i cor which 3:ca cooling conditions (reficed rate less than ] inc ser second) exist prior to the time of peak clad temperature tu rna round.
The March 13, 1975 versien vill be used for all future plant analyses.
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4 nrK 2 5 375 MINIMUM RFCUIREE';TS FOR ECCS SREAK SpECTRLH SUSMI-~".1LS I.
INTRODUCTION The followin; outline shall be used as a guideline 1-n.the evaluatien of LCCA break spectru: submit t als. These guideline 3 have been formulated for contemporary reactor designs only and cust be re-assessed when new reactor concepts are sub=itted.
The current ECCS Acceptance Criteria requires that ECCS cooling perferrance be calculated in accordance with an acceptable evaluation codel and for a number of postulated loss-of-coolant accidents of dif f erent sizes, 1cca:icas and other properties sufficient to orovide assurance that the entire scectrc:
of oostulated loss-of-ecolan: accicents is covered.
In acdition, the calculation is c be conductec with at leas:.three values of a discharge (C ) applied to the postulated break area, these values spanning coefficient D
the range frc: 0.6 to 1.0.
Sections IIA and IIIA define the acceptable break spectrun f or ros operatin; plants which have received Safety Crders.
Sections II3 and III3 define the break spectru require ents for cos: C? and OL :sse work (exceptions n::cd later)
Sections IIC and IIIC provide an outline of the
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equire:ents for an acceptsole corolete break spectru=.
Such a ec=plete areak spectrue could b e appropriately re:erenced by sete plants.
Sections IIID and IIIE provide the excep; ions to certain plant types noted above.
due to reload a portica of its core will have prevtously sub itted all A plant or part af a break spectru= analysis (either by reference or 6y specific calcula:Lons).
If it is the inten:ica cf the Licensee to replace expended fuel wit.. new fuel of the same design-(no techanical design differences wnich could affect thermal and hydraulic performance), and if the Licensce intends to operate the reloaded core in cc pliance with previously approved Technical If the reload core Specifications, no additional calculations are required.
design has changed, the Licensee shall adop: either of Iecticns IIA or IIC, or of Sections IIIA or IIIC of this document, as appropriate to the plant (BWR or PWR).
The criterien for establishing whether paragraph A cr C type shall be satisfied will be determined on the basis of whether the Licensee can demonstrate that the shape of the FCT versus break sice curve has ac:
When been codified as a censequence of changes to the reload core design.
the break the reload is supplied by a source other than the SSSS supplier, analyses specificd by Sections IIC or IIIC shall be submitted as a spectru
=ini=u: (as appropriate to the plant type, SWR or ?WR).
Addi:icnal sensitivity s'udies may be required to assess the sensitivity of fuel changes in such areas tas single failures and reactor coolant pu=p.perfor:ance.
II.
PRESSURIZED WATER REACTORS A.
0 eratin2 Reactor Reanalvses (?lants for which Fafety Crders were issued)
If calculational changes
- were made to the LSM** co make it wholly in Calculational changes /Medel changes--those revisions made :o calculational techniques or fixed paraceters used for :he referenced complete spectrum.
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' conform.ince with 10CF350, Appendix K, the following m.inimum number of break sizes should he reanalyzed.
Each sensitivity study performed during :he e
development of the CCCS evaluatlan model shall be individu 11y verified as remaining applicable, or shall be repeated.
A plant may ref erence a break spectrum analysis condacted on another plant if it is the same configura: ion and core design.
l.
If the lar?es: break si:e results in the hirhest PCT-a.
Reanalyze he li=iting break.
b.
Reanalyze two smaller breaks in the large break region.
2.
If the largest break size does not result in the hizhest PCT-a.
Reanalyze the li=iting break.
b.
Reanalyze a break larger and a break smaller than :he liciting break.
If the limiting break is outside the range of Mood;.
multipliers of 0.6 to 1.0 (i.e.,
less than 0.6), then the iiriting break plus two larger bceaks must be analyzed.
If calculational changes have oeen made_to the S3M to make it who ll:. in ccnformance with 10CFR30, Appendix K, the analysis of the
'rs: sn'. ! b reak (S3M) as previously cetermined f rom paragraph C belcw should be repeated.
B.
New CP and CL Case b'ork A complete break spectrum snould be provided in accordance with paragraph C below, except for the following:
1.
If a new plant is of the same general design as the plan: used as a basis for a referenced complete spectrum analysis, but operating parameters have changed which would increase PCT or cetal-water reaction, or approved calculational changes resulting in cere :har 20 F change in PCT have been cade to the ECCS codel used for the referenced complete spectrum, the analyses cf paragraph A above snculd be provided plus a minimum of three small b eaks (SEM), one of which is the transition break.*
The shape of the break spectru: in the referenced analysis should be justified as remaining applicao le, includin; the sensitivity studies used as a basis for the F.CCS evaluation model.
2.
If a new plan: (configuratien and core design) is applicable to all generic studies because it is the same with respect to the generic plant design and ; rateters used as a basis for a referenced complete spectrum defined 2.;
paragraph 7., and no calculational changes resultin; in core than 20 F chan,e in PCT were made :o the ECCS model used for the referenced complete spec:run, then no new spectrum analyse > are required. The new plant may instead reference :nc app 11:able saalysis.
- Transition Break (T3)--that break size which is analyzed wi:5 both the L3M and S3M.
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C.
Minimum Recuirener:s for a Conclete Break Soectrum Since it is expected that applicants will prefer to reference an applicable
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cocplete break spectrum previously conducted on another plant, this paragraph defines the -int um number of breaks required for an accep:able
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complete break spectrum analysis, assuming the cold leg pump discharge is established as the worst break location.
The wors single failure and worst-case reactor coolant pump status (running or tripped) sha'1 be established utilising appropr: ate sensitivity studies. These studies should show that the worst single f ailure has been justified as a fun::icn of break size.
Each sensi:ivity study published during the developmen:
of the ECCS evaluation model shall be individually justified as re: 'ning applicable, or shall be repe
- ,ed.
Also, a proposal f or partial loop operation shall be supported by identifying and analyzing the worst bress size and location (i.e.,
idle loop versus opera:Ing loop).
In adcitica, sufficient j ustification shall be provided :o conclude that the shape of the PCT versus 3reak Si:e curve would not be significantly altered by the partial loop configuration. Unless this information is provided, plan:
Technical Specifications shall not permit operation with one or core idle reactor coolant pumps.
It must be demonstrated that the centainment design used f or the break spectru analysis is appropriate for the specific plant analy:cd.
!t should be noted that this analysis is to be performed with an approved evaluation model wholly in conformance with the current ECCS Acceptance Criteria.
1.
LBM--Cold Leg-Reactor Coolant Pump Discharge a.
Three guillotine type breaks spanning at least the range of Moody multipliers between 0.6 and 1.0.
b.
One split type break equivalent in size to twice the pipe cross-sectional area.
c.
Two intermediate split type breaks.
d.
The large-break /small-break transition split.
2.
L3M--Cold Leg-Reactor Coolant Pump Suction Analy:c the largest break size fro par: 1 above.
If the analyses in part 1 above should indicate that the worst cold leg break is an intermediate break size, then the larges break in the pu=p suc tier should be cnalyzed with an explanation of why the same trend would not apply.
3.
L3M--Hot Leg Piping Analyze ::e largest rupture in the ho: le; piping.
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SBM--Splits Analyze five different small break si:es. One of these breaks must include the transitica split break. The CFT line break must be analy:ed for 35% plants. This break may also be one of the five small breaks.
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v s The generic model developed by General Electric f or 3WRs proposed that split and guillotine :ype breaks are equivalen in de:creining blowdown phcncrena.
The staff concluded this was acceptable and tha: the break area cay be O' e vessel no::2e with a zero. css coefficient using a two n
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A consiveree at phase critical ficw model.
Changes in the break area are equivalen:
c changes in the Moody cultiplier.
The minimun number of breaks required for a cerclete bre:k spectrum analysis, assuning a suctica side recircu'.a:ica line break s the design basis a::iden:
(33A) and the wars: sin le failure has been established utilizing appropriate sensitivity studiec, are shewn in paragraph C belcw.
Also, a prepcsal for partial loco. c;eration shall be cupacr:cd b"/ identi:/ int > anc analyzing the wors:
F break size and location (i.e., idle loop versus operating loop).
In additien, suffici:n: justification shall be prov.ded ta conclude that the shape of the PCT versus 3reak Size curve would nct be significantly altered by the partial loop configuratica. L'aless this inf ormatica is provided, plant Tc:nnical Specifications shall ne: permit opera:.cn witn one or =cre idle reac:cr coolant pumps.
A.
3WR2.
223. and EWE' Rean21vsis (Plants fcr whimh Saiety orders were issuec)
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If the larces break does not result in the hiches: ?CT:
a.
Reanalyze the limiting break, the largest break, and a smaller break.
If calculational changes have been made to the SSM to make it wholly in conformance with 10CFR30, Appendix K, reanaly e the small break (S3M) in accordance with Section IIIC.
3.
New CP and CL Case Jork A complete break spectrum should be provided in accordance with Section III, paragraph C below, except f or the f cilcwing:
1.
If a new plant is of the same general design as the plant used as a basis fer the lead plant analysis, but operating paraceters have changed which would increase ?CT or setal-water reaction, or approved calculational changes have been made to the ECCS =cdel resulting in more than 200F change in PCT, the analyses of Sec:icn !!!, paragraph A above shoulc be provided plus a minimum of three small breaks (SEM),
one of which is the transition break.
The shape of the break spectrum in the lead plant analysis should be justified as recaining applicable, including the sensitivity stud;es used as a basis for the ECCS evaluation model.
2.
If a new plant (configuration or core design) is applicable to all generic 7:udies because it is the sare with respect to the generic plant design and parameters used as a basis for a referenced cceplete spectrun defined in paragraph C, and no calculational changes resultin; in more than 2007 chan;c in PCT were made to the ECCS =cdel used for the referenced cc=plete spectrum, then no new spectrc= analyses are required.
The new plant may instead reference the applicable analysis.
C.
Minimum Repuirements for a Cc=nlete Break Srectrum This paragraph defines the mininun r"mber of breaks required for an acceptable complete spectrum analysts.
.ars complete spec: rum analysis is required for each of the lead plants of a given class ( 3'JR:, a-ra 2 -:,
BWRS, and SWR 6).
Each sensitivity study published during the develo; tent of the ECCS evaluation ecdel shall be individually justified as r -cain.n; applicable, c: shall be repeated.
1.
Four recirculation line breaks at the worst location (pump suctit discharge), using the L3M, covering the range from the transition break (T3) to the D3A, including C3 coefficients of frc: 0.6 to 1. t times the DEA.
2.
Five recirculation line braaks, using the S3M. cavering the range from the smalles line break to the T3.
3.
The following break loca: ions assuming the worst single failure:
a.
largest s canline break b.
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D.
SWR 4 wi:S " Modi ~ied" ECCS Same as Section IIIC.
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5W25 Same as Section IIIC.
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On each plant and for each break analyzed, the folleving paraceters (versus time unless otherwise no:cd) should be provided en engineerin; graph paper of a quality to facilitate calculations.
--Peak clad temperature (ruptured and unruptured node)
--Reactor vessel pressure
--Vessel and dcwnconer water level (PWR only)
--Water level inside the shroud (EMF caly)
--Thermal power
--Containment pressure (?NE caly) 3.
For the wors: break ansi :e:, the folleving add tional p raceters f
(versus time unless ::hcrwise ncted) should be provided on engineering graph paper cf a cuality :: facilita:e calculati:ns.
The worst single failure and w:rst-case rea:::: :: clan: pump status will have been established utilizing apprcpriate sensitivity studies.
--F1 ceding rate (PWR only)
--Core flew (inle: and outle )
--Core inle: en-halpy (EWE nl:
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--Hot spot pellet avera;e temperature
--Fluid :ceperature (hottest assembly) (PWR caly)
A tabulation of peak clad tcaperature and metal-water reactica (local C.
and core-wide) shall be provided across the break spectrum.
D.
Safety Analysis ?eperts (SARs) filed with the iRC shall idenriff ca each plot the run da:c, version number, and version date of the cenputer in
=odel utilized for the LCCA analysis.
Shculd differences exis.
version nunber or eersion date frcn the ecs: current code listings made available to the ' RC staf:, the. each mod _ fica:ica shall be identified with an assesscen: of i: pact upon PCT and metal-water reaction (iccal and cere-wide).
E.
A tabulation of times at which significan: events occur shall be provided on e.?ch plant and f or cach break analyzed. The following events shall be included as a mininum:
--End-of-bypass (?%" Only)
--Beginning of core recovery (?%R cnly)
--Time of rupture
--Jet pumps uncovered (5%R cnly)
-MCpR (3%R caly)
--Time of rated spray (SWR only)
--Can quench (323 only)
--End-o f-b icwd e vn
--Plane Of interes: uncovery (3%R caly) 23 002
'~~'
.pWomem
=
4 e
3 Possible groucir.g of clants for the purpose of perfor?.ir.g generic as well as individual plan ::reak spectra analyses.
CURREiT COCKETED A PPL IC AT IO:;5 003 f
S.
BABCCCK ANC WILCCX CATEG0ci I:
177 FA w/Lcwered Locos Arrance. ment Re-analysis (Safety Order Plants):
Oconee 1, 2, 3
-- IIA >
.hese
_1,,..s _,e,s.
,,s.. _3.
m,.
i 2c 3
.7,'ev e;,,
co i
inas' ":
-as e
s
^
-so cy re ere-ce to a ':
Threa Mile 'sland 1 -- IIA c
te.e 2535 break soectrun rear.aiys s sa:-
nrkansas rowu i
,In, mitted generi a,ity,y :sa.,
2, c,3 IIA Rancho Seco j
2772 New OLs_:
Three Mile Island 2 --IIB (2))
q i r,m,,_..e s e o l a.n...
,,,..,. 3,-
.a 27,'2 design as the aucve clar,
ney Crystal River 3
--IIS(2) v
->7 re#erar-a -ha s~= a r = ' ' >' tsi c of the comolete s;ectrur accve. '
' ""' ~
~' ' ' ' '
l 2 c '
i Midland-1, 2
-- I I o, ( m, )
)
New cps:
None CATEGCRY II 177 FA w/~aised Lcoo Arrar:e ent New CLs:
Davis Besse 1
--IIB Complete spectrum recui-ec.
New cps Davis Besse 2, 3
--IIS Complete s;ectrum recui ec.
CATEGCRY III:
205-FA Plants New OLs:
None 23 004
~-
k
~.
New cps:
Bellefente 1, 2
-- IIB T Comolete scectrum recuirec.
(Plans are for a:. to reference Greenwood,, 3
-- IIB a complete spectrun sucmitted m
probably en 'a?PSS.)
WPPSS 1, *.
-- IIB
)
Pebble Springs 1, 2 -- IIB
_C_ATEGCRY I'!- 145-FA Plants New OLs:
None New cps:
North Anna 3, 4
-- IIB Ccmolete 5: ectr'9 re2;ed (Cne will pr:caciy refarer.ce Surry 3, 4
-- IIB the otner.)
s 23 005 e
e
GENERAL ELECTRIC BWR-2 Oyster Creek
-- LP*
Cecolete scectru recuired.
(IIIA)**
Nine Mi'-
'nt
-- Reference only required.
(I!IA)
BWR-3 Quad Cit e> 2
-- LP*
Cemolete scectrum recuired.
(II!A'**
2511 Millstone
-- IIIA - 3 breaks required 2011 Monticello
-- IIIA - 3 breaks required 1670 Dresden 2, 3
--IIIA 3
2527 h
.May reference LP Quad Cities 1
-- IIIA
)
2511 Pilgrim
-- IIIA - 3 creaks recuired 1998 BWR-4 Without fix H3tch 1
-- LP*
Ccr.olete srectc;-
'm ' rec.
(II!A:
2436 Pea,ch Bottom 2, 3 -- !!IA
}
Ccrolete s ectrum recuired. Cne J203
(
may reference tne Otrer.
Browns Ferry 1, 2, 3 -- IIIn, J 3293
-- IIIA 1
Cooper i
2381 Fitzpatrick
-- IIIA
[
[3 breaks retuired.
2:36 H= -* ' -:v serve Duane Arncid
-- IIIA - 3 breaks recuired as a reference 1653 Hatch 2
-- IIIA
)
'for tne otners.
1 2436 Brunswick 1
-- IIIA 2436 Shcrenam
-- IIIB Fermi
-- IIIB Newbold
-- III3
- Lead Plant
- Original break s ectrum not anolly in conformance witr ICCFR50, Appendix <.
~
23 006 e
BWR-4 With fi 3runswick 2 (Lead Plant)
-- I" ' - (cr:lete s ectrum 2436 recuirec. -
Vermont Yankee -- IIIA - 3 breaks required (Leac Plant can be 1593 referenced, if Browns Ferry
- 1, 2, & 3 S appropriate)
Peach Bottcm* 2, 3
)
See preceding page i
Fitzpatrick*
)
BWR-5 Lead Plant
-- IIIE - Ccmolete s:ectrum recuired.
Nine Mile Point 2 -- IIIB Ccmplete s;ectrum recuired.
LaSalle 1, 2
! IIB
\\ (Lead Plant can be reference:
(
by other 5'aR-5 p'. ants, i f Bailly
-- IIIB appropriate.)
f Zimmer
-- IIIB Susquehanna 1, 2 -- IIIB SWF-6 Lead Piant
-- IIIF - Cc alete sce:trum rer_fre.
Grand Gulf
-- IIIB Black Fox
-- IIIS Earton I, 2, 3, 4 -- IIIB Complete spectrum recaired.
(Lead Perry 1, 2
-- IIIB Plant cer ce referen:ec by ot er BWR-6 piants, if a;;repriate.)
Clinten 1, 2
-- IIIB Douglas Point
-- IIIB Hanford 2
-- IIIB Skagit 1, 2
-- IIIB Hartsville
-- IIIS f
Somerset
-- IIIB River Bend Staticn -- IIIB Allens Creek
-- I!!B
- May or may not have tne ?CI 'ix
- Criginal treak spectrum not wno'ly in confor ance witn ICCF?iO, A;;endix <.
~
c3 00,l 9,
e
PLANT SPECIFIC IIIA Comp'ete spectrum required.
Oyster Creek a
IIIA Nine Mile Point a
IIIB Lirr.erick 1, 2 a
a n
IIIS Hope Creek a
a a
IIIA Humboldt Say a
a n
IIIA Dresden 1 a
a u
IIIA Big Rock 4
23-008 e
CCMBUSTICN ENG!NEEU NG The foilr.;ing list is grouped according to sinilarities in design.
Some of the older, operating plants are fairly un'ique, as indicated, The list is in and don't fall conveniently into any other groups.
approx.chronclogical order.
1.
Palisades (Unique) -- I!A N
2.
Ft. Calhoun (Unique) -- ITA p
3 breaks required
- 3.
Mai ne Ya n'<ee (Unique) -- II A
)
4 2560 MW: Series Calvert Cliffs Units 1 & 2
-- IIA -
3 breaks retuired a.
b.
Millstone Unit 2
-- IIS Comolete scectrum rec; ired.
(One may reference tne otne.)
c.
St. Lucie 1
-- IIS
- d.
St. Lucie 2
-- IIS Ccmplete spectrum required S.
30C0 MW: Series
(
3410 MWt 217 Fuel Assemblies)
- a. Pilgrim 2 (3470 Mw ) --IIS}
l Ccmplete spettrum recuired.
b.
Forked River 1
-- TIS
/
(One may reference tne etner.)
c.
San Gnofre 2 & 3 -- IIS d.
Waterford 3
-- IIS j
6.
Arkansas Class
(
29C0 VW: 177 Fuel Assemblies) a.
Russelville 1
-- IIS Ccmplete spectrum -ecuirem,.
(One may reference tne otnen) b.
Blue Hills 1
-- IIS Maine Yankee is unique in that it has 3 steam generatcrs, 3 not legs and 3 cold legs.
All other CE plants nave 2 steam generatc-s, 2 not legs ar.d 4 cold legs.
All plants shcwn above listed before St. Lucie 2 are of the 1 *xia fuel design-All clants after, ar.d includ ng, St. Lucie 2 are 16x16.
4
') 7 009 uu cj l
7.
Svstem S0 Class-(CESSM)
-- II3 Ccaplete spectrum required These plants have not all been named yet. The utility and approx.
number of plants expected are as folicws:
a.
Duke (6)
)
I b.
WUPPS (1)
May reference ccmplete spectrum, if applicacie.
rri::cna Power and Lignt (,,j c
c.
d.
TVA (2) j c) d.u
Westinchcuse Oceratinc Peactors (Safetv Order Plants)*
I I
3-loco i
4-1c00 2-loco I
Yankee Ecwe Ginna Surry 1/2 g
Kewaunee Turke'v Pt. 2/4 IP2 i
P:
9each 1/2 l
H. s. Robinscn :
1 D. C. Cock I i
I i
Zi c r. 1, Prairie Island 1/2 t
I l
Oceretin: License **
2-iccc I
3-iccc 4-100c l
ceaver,,aiie.s 1
,. - iro;an*
i Farley 1/2
- Salem 1/2' North Arna 1/2 l - Diabic Carycr 1/2",
en m
.r-a i
l l
./. C.
cc< 2 e
McCuire 1/2 l
I Secuc.r '.l:
l
~
- 3 breaks recuired (::C.
Cne s'.an: a;. reference a.c: er
,<4 e
G,y 8www a..
m O
m?'9*
- he PC* neb @*3
- '3@ ****f
.gf 8 W w gw my
-wa
- =8 Eege m
y 99 p o. m*393 m**-9w-e c, ned wena.
wP3 0-**W
- d
w
w
'N*
W W**='
a es, es.w s.
R@Y}^@
i C'&R
< }-
{ *
- f.
A)%
-..a
...e m
e o ') o\\\\
(._
Constructicn Permit **
I d-loco I
3-loco 2-1000 North Coast Sharon Harris 1/4 Byren/Braidwcod 1/2 J
Kosnkcnon; i/2 Catawoa 1/2 Summer i Floating Nuclear i,'5 1
Eeaver Valley 2 i
Jamesport 1/2 i
Wisconsin Utilities l Seatrco< 1/2 t
l ShUPPS 1-5 4
I l
Soutn Texas 1/2 i
l Comancne PeJ<.,/2
}
n'atts Ear 1/2
{
i i
Millstone 3 1
I l
Vogtle 1/2 l
o
- Complete s:ectrum recuired.
Cne olant may reference anntner if applicable (see paragra:n I:3).
LJ k
k r.., - n. s c... a.s
,,. 4 h.. c.,1.....,IL..445ew 1
).sso
... C F.., e.......,. t i r.. -.....,... r.. r u l f......,.,..
et....-...
re...
...s A P PL. Ca.,, r..
ts a.-....
3 ELgr.. ice.,sLf
.s so A.
2*CKT-C _T 2 t: e r f : r-
'nhere a single f 3ilure in an electrical syste can res.!t in isss :f c3:!;ti:
a safety fu--tion. **; effect :- Dic".t safety
.s* te eval. ate:
This is attess!", 'e:t less of onet.ee tne icss of s3fety fantlic, is ceste: :j a ::.."cnt f ailin: I: ': ': - !
requisite e;"3nical -Cti:9 Or t/ a c:. :.cnt ;crfor9ic; J1..;;*:raLie ech..:
';e.
This ;;siti0n estd:lisrcs 19e 20:e:t3:1I 1 ty o f Oi s :- e0*.ng.c.c r
- .0 e' c tri::.- : eats of a flu 1: syst0 ds C"
?
's ;# sc s ' ; * * ; 3 : ' ' 's '. 3 s!".g'e #31: -'e 9*"'.
' se a' wa-desira:le :
- 0aee.t 30!;..).
I*ese ;r:<tsi ns are 03se :n *rc 3ss. :t n !*
- :: ;; c is trcn e vivalent to a st-ii3r g 0 ect ta3t is c:*
- $:gne: 'cr eie: -i: s' :-
e.9.
4 VJI.e
- 31 can b; C*ctC" r cI:se: :a'f 'y etr?:t 39y3I
. erat ' - **.
- 2
>- - nc Ihey arc als: '.a s e :n t*t 3 s s ' t i n *
- d t "O s i r,.,. : fa...re CJ..-- ces1;r-
.. - (. 3
-*-*'#.'."*l-^..*.^.'..'**u*
.-... - e. r. e. r - e. r
- 3. s.
-a e l e C
- r i c 3 '> s"s*.'
3"'
> a.
syst*S-IFC validity of tnese ass:M;t':as sr.: :ld DJ.e r : '; e: s'e-3 :1f : P.:
.s
___.t.,......,tc_._.3,.....
.,.. r. g 3.
- .i i
Failu cs in ::.
t*2
'aii la ' un.-
- n s e-,e :.: te and: iratic.-: :- :e s: '
1.
r C r;;"erts in clC trical 5 ysto s s!' es d^
eta 2-
ui
.s;'
c:--
1..
be c:as'CerCf "Es1;"te: 3 : 3 f ".1 ; 2 S i e '. i c 3...'
t c1 s
- "?!
IIJid sf s!C'.
- T #c9*
3
";t * ? Cli t
.::a
- n ic 3 0'
$3.
'8*
se ve*c?.
2.
Where ' t i s cet?*-iee: th;. #3tigre :
ga c i c :*,-; ; 21 syst.- : - Ore *t 3"
- .3-und
- sired -?cFa":031
- t* n of 3 Si.0 Or et*.ee f'.id sys;- : : e
- 3 :
rotion resolf,$ in less :( **O syste-53fCty f;r:t109, it is 4 :c;t3:I:,?-
.s-*
- ..*..' 4.' '. ' *
- e
. S 5 *. *. " "2
.5 '
- 3 '. I s'..-
w' ".. a - a s *... 31 * '
..n d e s '. '3, 2
~3 Of tne 43Ive r t'er *l.1 sist; : ::nC"!
"O O ' ! 91
- e ' n ' 35 s:2-
!') SP I
inClace 3 lis*
- III ele ~t-t c 3f-::ees te:
I',es, aad t c r?:;i r: r;s'
- 5 J.e S c is 3.:ife:
~
tm :- er !:
valves. *: which t*e re:g:rc cet #:r re vai Sf e!ec*ric ;;wer s3tisfy t*.e sin;If f 3 t !'src criter;cn.
3.
Elec*rical'y-c::-!te: v31ves that are classi'.e: as s ti ve'* v3 he s, i.e., 3 re ec:ai re 3r0..i:'f-to cren r c!:sc in vari:ss s!faty syste- - r-at : 31 sec;; ces. 0.:
centrolle. s e.i: te ::er3te:
r:- the 2, ::-t-:t roa -
ss:- v3.cs
- <
- t e r
a
-er is re : sed in :r: - t eet.. s - :e included < en;
- ese valses ' -,
tes failure criterio, unicss: n) ete:tri:31 ::.er can te rest:re
!= 'he 4 5. e s ' :- the main centrol ::,-(t) velic ::er3t, is -:t ecess3 y 'or at least r -: tes follcwing occar-ence :( t e esent.':u:rtag sa:M ::er3t, r.
se: ;; ; it is ce cnstrate f
\\
- t1 m
,v p-7A-27 r.
.~
fj
~Y a
--~
% s n
that there is reas0na:le assLrance that all necessary c;erater actions will :e per.
.f forned within the time shown to be ace vate by the analysts.
T*e plan
- te.*mical specificati:ns shoald include a list of the re; sires positions Of anaally-centr:lled, electrically-c:erated valses and sheste icentiff these valves ta -n::n t*e ec:.tre-rent for re eval Of electric ?~ er is a;; lies in cr:er to satisfy the single f at!are criterien.
4 When the single failure c-iter 4:n is satisfied :y reteval :f electrica' ::-er '-:-
valves descrite: i a (2) ar.: O' ateve, t esc vahes s.:uid ha.e reca:2 t ::1 - :-
indicat1:n in the rain c:ntr:1 rc:S an: 1.he csit on tacication syst+ sa:v;; t s e ' ',
reet the single 'ailare :ri er::n.
5.
The ;nrase " electrically-crerated valves" inc!.ces :::S val <es ::erate: 0: re :.
i-electrical c:vice (c.)., a ?:ter-operatcc valve :r scleroic-cre-ate:.sice
.ve valves crerated indirectif Of an electrical res-i:c (e.g., an air-:::-a.e: 3 -e
- 10 air sarplj is ::r. trolled by an electr:ca ' solen:i: sai.cl C.
_R_E_T E ? E '. E 5 l.
Pemora-c.- to R. C. ~?f eur; ar.: V.
A.
P:cre fran V.
5 el :, ::t: c i, '272.
4 f
f 7A-23 b
.\\,
~
- "i,.
\\_
23 014
BRANCH TECHNICAL POSIT *01 C33 6-1
.u. g.. y..~...r a... w....m.. : p : r w. c u...e r.
..s FOR P.R r C.5 P r sr-.s..--..;- :.--4...a..
I a
s A.
BACrT ^'30 J-Paragr!;n I.C.2 of 4 ;crdix K to 10 CFR Part 50 (:ef. 1) rew ircs in3: tre c qtat -er:
pressure used to evaluate the ;cr';r.ance 03:30ili f of 3 pressarize: =3 ce rea:.:r - :
3 ;rcssyre 031:J13*.ed c rseria" ::j # r eergerc' C0re 00:*ing sfste- (E C3)
- .3t ext c f
^#
a.
'.'. ' C s' 1 3 *. '..'. '1 '.".*'iL'**
... e #. #. d '. *. *2
- .#."-..'-~-.-
f ***** rF,uire5 gg.a.,A,r,Cge.
{..
all installed ;r:ssure-r::.cir; sjste s and ;r:: esses. Trerefore, " e :'icua; :
- c :-
h 5 teen Oevel;;e3 *.o
- r0 vide ;s
!*Ce ii the ;erre 4.cc :< ir.-
technic 31 ;05)tiCG 4
Cont 3{rrent press.,re Saalysis. *r.e 3;; Q 3
- ) 0:0;r'.00 0010.; 6;;lics Onij ::
'e [. <.
related c:atair U *. press;re evtl.a.
n and :t : :*e c:ntairee-; f r.cu : 3; C3;t:i! :/
ev31ge.t10n f 0r ;rss*sl3tCO desi q !s's 3:01099:5.
3.
-..d
-.3.....
.s, t,
..-3_.
,n
(.,
s.'. e ;. }
j.
- p...
a.
In'*:C:-'--m
- c-,n. C- : *vs
....,,.s., r.',
-'9i4'.- C**.*..**e.*.*.
- r.
4.FC,
....4...,..
.,g T.o. g., g g. i -..
.,.3 s.
.t....
.-.*'.s, 11- * * * ' '. ' ' ' ' *-..'
3 r. s
.As...
idl.j.
..3.
., 3,o
.,,,-.**s..c.*
CO': i ti c r.S e.r.uld h' usc:.
h.
{ni.
3.
.,.. e 4.
- o. "..ne.gi
,..- ;..c..-
".m-..
..,.g 9 ^
..e.
,-.3c.,,..
.2.s A r e.s g.-
3.3*i,f
.s., ; s..
...-.,.s3....,
et.
3 t
..i..
c.
C:a.ts'*
ca*..:' :
4
.s c.-..
_,A.
....,.. 4.,, t3
.....2.......,.... '.. --...'
.t s...s..
.,... -...,". '. r. -
.- -.- t e.
- . *. * - -... -. - m.
=. 5 V
].-,
.s
..... 3g
..3 is
..,5, 5.,.....,,.
- c....,...
. e....c..',....c.,5 t.
,5
- s..,..
,,e
.3
...3.,..
o,.
3l
- v..
s.,....,.
4,.. s
..e.,....e..v'.....
c>.
2.
Act*ve
-81 5 **s e
4.
z.,.,s..
- ,..~.~...
..,-z.
3..
..,.3{
,,c...-.>
- g.g
.,p.3..
... e.
'.i
....,g.,.,...
- c. 3.,....
.... 9 2
i
,4
.c..
1*9 3]*
..r*..'*.'**.5.'"*.
.E;.-
..s *. r a.-...i.
..3.3- *.
.., p,3 *. 4 *...
.a*.
3
- T a i.a s.* '.' * * * * * "
a*. ".'t*..
- ..'a "..'.....*'.'as.***.3'*6
- - ' *. *. " *. < #.8 ", **'
3.".**..
e..
...,2..
.s
_,.4_.
...... s 3
2..
.,e..
4..
>e..
...i.
,3,. 9,.....,.,;
2.
'....z, s.
., 3 5.>......
e. 'a,.,.,3,.
- 4..3..
- 5..*.1. C. T
-e.
- -.g.w
-e.m. g.ey.g e e e.m w,.
- eman.
.g.
g8H'h
) /
tJ
Ccviatier rcm the f:regoing will te at e:ted if can to sn wn that tSc w:rs; 5
conditions regarding a single active fatiure,~s::re:.ater te :cratare, ar:
cooling -ater ter:erature nave been sele :e: fra, the stane:oint Of :nc escrail
\\
ECCS m:cel.
b.
C:ntair ent Stea, "inire x a 5:*lle: E<
=te-The spil-lage of s te:Ote: E:05 water int:
- e c:ntairrent r: vices an at: :::cai heat sir.k as the su:::: led EC ; wa cr et zes,:';n t e 5 ea-in tre ::ntat e -
The ef fect of tne steam-atcr nixin; snesid te ::nsicered
,n e conta:r en; pressure calculati:ns.
-t c.
Cc.tair nt Stea-4 v r - ' t n u a. ce fr:- !:e "- -
The water resul:Tr.; fr:. ice eitir; in an ice : -censer t:n; air.r n :r: :d:s a-additi:nal nea; sirx as ;"e sat;;;iri aater :ses witn tre stea,,a le : : n' from the i:e condenser int:
.e ic-cr c ntair :nt e:1; e.
The effc:: c' ; e s
steam _ water e.ixin; stesid be ::rsidered in tre ::r. a n en Orcssure cal:;iat : s.
3.
Dssive "ea_t5,rks a.
_Identift !:icn The passive hea; sin (s ina: s cui: :: inclated in t e centa:r rnt cvtl.2: /
r.edel should be est:b'.:s.:: :/ id:
'f / r; ; :se s: u:tsrcs an: :: cret:s i
tre centair ent tha: c:vi: inf'ucc:: ; c :res:. e res;:nse. The,
- r. 3
' sirs:
tures and c n;:ncr:s :ta sn:vid :c i.cluded.re listed in Tarit i fN l
Data on ;assive Ec:: sirts nave t:: c:r.:iic? ' : :rcei:.s reva -s ar:
(
been used as a basis for tre si :lified ::e1 0.t.
- e d t a t :.s is ::2
's actc;tatic for
.it r.n ::n: air cn ;ressw c analjses 'Or :::-stes i:.
1; 3
a;plic::i:ns, and until s.:n c c (:.e., at :re :; era:1 :
- e-sc ey c..
- a co. le*e ide-tifica:::.n O' avallatic 22: s:
.s ::
2 cc:3.
Tnis - -'
a;;reacn :s als: :ren f oli:...: :r :::ca: : -'a 2 :
.i:e secs :-
..f-Section 50.06 (a}{. Of 1: FR :r: 50.
fer 3.:- ::ses, a-d ';r :.,- - --
- crm.t rev ews,
- v. e-e a ceta Ic lis:1re :#
i
-33
? ss. : sn *
- := ~ :-
of ten carrot be :r:,*:::.
a f;, :_i-: :r:ce:;re sy Oc.;c: :: :::: : e 3<
neat sinks wit"i. : e ::nta n :n:
(1) Use :.5e sa-face a ea ar: :- : ness :f.ce :riracy ::rta'r en: s : L e '.
-eii :-
steel lirer and asse:: ate: a-: crs ar: ::ncre:c, as a: r: -:2:c.
(2) Estimate t c es:: sed surface ar sa of :
e-steel 9 eat sin ~s ia a:::r:2 :2 with Tigure 1 and ass.re an avera;c : scsress of 3/3 ircn.
(3) M: del the inte-nal ::r ete stre:ja es as a sia: ite a :tici~es s -' i f:::
and ex;;se: surface Of 160,0:: f:'
The heat sick therr:: ysical ;r :crties :ta. uld be acce::2:Ic are s c.n in Tabic 2.
p 5.2.1.5-4 23 016
=
4 S
At the ating license stage, 4:olicants s*0ul
-: vide a detailed list :f passive heat sin (5, with a:pr:;riate dircnsi:ns and ;r:;eeties.
b.
Heat Transfer ::a<ritieats The folleuing c:nservat:<e cercensing reat transfer c:efficients ':r eat transfer to the ex:: sed ; ssive "est sir.ks 0;rt g the Ol:-::..n and :est-t':.':..n ;"ases f the ic55.cf.c:Olant at:: ent sh:uld te used (See ' ;;re 2l-9 (1) During tre Ol:..d:an :tase, assa e a linear ir -case in e c:rd:-s r;
- a 9
=2 B:;/*r.ft' *:, at :
0,
- a : ass
=
transfer c:ef ficie,; fr:n ngn,,,,;
s value fcur ti-:s ;rea:cr taan the ax1r., cal:.la::: ::rce s -
.a.
s-fer coc'ficien at t.*e end of 012.::.n, us1r.; t e Ta;ami tr-
.s.
(Ref. 2),
. n
, u..t-72.5 h
=
eax n iPJ 2.'F rar: ;m heat tr?.sfer : efficie.t. 3:s/=.r 't i
where h
=
m3x pr'-ary :ala-; e c ty, 3:a Q
=
1 net frc ::ntair :-: vc. e,
Y t,
tire it:crval to end of 510.::*n, sc:.
=
(2)
- '.,*>a.
'n,g*.-..'...'..4.'...
- .* s c..'...'.=.-.'..e..,
' e-les turbulence 'n : : ::.ta e :n t 3 ; :s: cre, a s s.. - ;:ms-
,---'a c:cfficients i.2. es grea:e-an :tose Orc:'-':: : - tc..
.:2 :. 2 (P.cf. 3) an: given in Table 3
(,3 )
a,4..,
.c.,.,.,...-,
.a.
,,..,c tne len g-:c r:s t. d c.,d:- n --asc. a ress
-a_
c:-=
.a:
transitien in U.c ::-::nste.: 23: t : sfee ::effici.
<*:si:. u t.- :
( te? F i;;
-2
?;.
The cal:;' a:e c ::r. c-s ' : c.: : arsfe ::'
-::ca: ::2:- :
. a. c. i w.,...
s..s>,. -. -
s.,*
c 3.- 'i. is.
. 2 3s
.s2.
$ r,u l.a s
o for toin.:
- r. c: a.: an:ai-::: s. 'a:es.
Heat transfe-et..ee-a:;;:ni-c a:2-:= s n : ass,e 22: si s.
.c. :. :
- a..., -,,,..,.
c.-
On,.,,.
,.5s.-..
.2 2..
..e..
.m..
--,.n.
. x.,-,, 1.,
s-r..,i..,s...
.. i3
-e..,.
s.
- s:
.2 r...'.,.,
- .-,.-*..se.a.
..n i. e. s. e s..> (.- (
..v a. e. s.. * ;
..ra..'i. ~ *
.a-s 2 t '2. - *>.
).
} n...- Q Nu:iear 2:,c-Rea::r-s,' a
' OF: Da
- . ::: -: s c.
'::: :< a i. a * :- ::'
- e..,,,, :
- .....-
- .....- c.., f.,..
- n..,......
j.. j.,33r f...
L,,...
r.
3..
33r.
7,,
.2
- 3..-. -... -
t;..
2
- a...a.
..3
....3
%,s i
i.v.s' 5...
23 017
3.
H. Uchida. A.
a an: Y. Tc,, "Evaluatio.* af Pcst-
- ent coolir; sjste-s or tigne.
Water Poacr D.enctors," Prec. Thirt, Internaticnal Cor.fercace en tae pea:eral uses of Atomic Ener;y,'lolure 13, Sessien 3.9 Ur.ited Nations, Geneva (1;E:;.
e e
- e e*
D.
5.2.1.5-5 LJ Ulu 5
TAsLE 1 ICCNilFICAT!:1 CF : *iTA!'NENT -EAT SI*.KS,
. r. d Contain ent Building (e.g., liner plate and external c:ncretc. alls, fl r, and samp, 1.
ifner anchors).
Contair ent internal Str; tures
'e.g., internal se:aratten. alls and 'le:rs, rc'.e':c; 2.
pool and fuel transfer ;it. alls, and snielding alis).
I
- ::tt,*.s.
t;e 3.
Su;; rts (e.;.. reactor vessel, steam ge erat:r, ;;
s, tanks, ajor su;;;rts, and stora;e ra:ss}.
4.
Unirsulate: Sistems and C: ;ccents (e.g., cold.ater syste 5,
catirg,,<.n.:14
-:. ar:
air c:nditionin; syste s, :u :s, :::rs, fan ecclers, rec -t.:rers, and tar..s 5.
Miscellanc us E:;i;.ent (e.;.. la::ers, ;ritic;s, cie:trical c.34 e tra,s, 3-: : 2 es:
6.2.1.5-7 4
~-
~ ~ - - - -.. ~..
- ? Zi () 1 S)
-IAELE 2 HE AT SIM THEs" P-YS:"R TPC7RI'E3 Specific i.ver si Centi;y neat Cce.d.:
Paterial lb/ft" Etu/lb *r 3ta/*.e.'.-
C or.c re te 145 0.156 0.92 L
Steel 490 0.12 27.0
- a
(
s 5.2.1.5-8
,3 020 L
TABLE 3 UCM f 0,*. %f AT : *.* If Et 0:[ r :c:t_.;;s
. ass Heat Transf e r Mass Heat Transfee M
Ratio Coefficient htic Coef fic c, *
(15 air / h steam 1 (9tu/tr
't'
' I (15 sie/ b sta*-)
(Staine
't' 50 2
3 29 20 8
2.3 37 18 9
1.3
- 5 e
14 10 1.3 63 10 14 0.3 93 7
17 0.5 140 5
21 0.1 250 4
24
)
23 021 6.2.1.5-9 23 020 6
h, 1
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10(' ft Containment Free Volume, x O
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