ML20128B400
| ML20128B400 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 01/28/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9302030040 | |
| Download: ML20128B400 (15) | |
Text
F f
GE Nuclear Energy
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. :. n wu,s January 28,1993 Docket No. STN 52 001 Chet Posiusny, Senior Project Manager Standardization Project Directorate Associate Dhectorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated AllWR Review Schedule
Dear Chet:
. Enclosed are markups of ABWR SSAR Sections 3.6 and 3.9 for OBE elimination and elimination of AP & SSE load combination. Markups for the remaining SSAR sections dealing with OBE elimination will be provided next week. The OBE chmination issue is DFSER open item 3.1 1.
Please provide a copy of this transmittal to Dave Terao.
Sincerely, NMky9 ack Fox Advanced Reactor Programs cc: Maryann 11erzog (GE)
Norman Fletcher (DOE) d.hluh 0!!G 0.1.^
c nun zz 9302030040 930128 PDR ADOCK 05200001 i!jf A
1 M
DA6tmAE Standard Plant pfv s
' 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE Subsection 3.6.3 and Appendix 3E describe the POSTULATED RUPTURE OF PIPING implementation of the leak.before. break (LBB) evaluation procedures as permitted by the broad l scope amendment to General Design Criterion 4 This Section deals with the structures, sys.
tems, components and equipment in the ABWR (GDC.4) published in Reference 1. It is antici.
Standard Plant.
pated, as mentioned in Subsection 3.6.4.3, that a COL applicant will apply to the NRC for Subsections 3.6.1 and 3.6.2 describe the approval of LBB qualification of selected piping design bases and pro'ective measures which ensure by submitting a technical justification report.
that the containment; essential systems, compo.
Tbc approved piping, referred to in this SSAR as nents and equipment; and other essential strue.
the LBB piping, will be excluded from pipe tures are adequately protected from the conse.
breaks, which are required to be postulated by quences associated with a postulated rupture of Subsection 3.6.1 and 3.6.2, for design against higb. energy piping or crack of moderate. energy their potential dynamic effects. However such piping both inside and outside the containment.
piping are included in postulation of pipe cracks for their effects as described in Before delineating the criteria and assump.
Subsections 3.6.1. 3.1, 3.6 M.1. 5 a n d
.4-tions used to evaluate the consequences of pip.
3.6.2.1.6.2.
It is emphasized that an LBB ing failures inside and outside of containment, qualification submittal is not a mandatory it is necessary to define a pipe break event and requirement; a COL applicant has an option to a postulated piping failure:
select from none to all technically feasible piping systems for the benefits of the LBB Pipe break event: Any single postulated approach. The decision may be made based upon a piping failure occurring during normal plant cost. benefit evaluation (Reference 6).
operation and any subsequent piping failure and/or equipment failure that occurs as a direct 3.6.1 Postulated Piping Failures consequence of the postulated piping failure.
In Fluid Systems inside and Outside of Containment Postulated Piping Failure: Longitudinal or circumferential break or rupture postulated in This subsection sets forth the der.ign bases, high energy fluid system piping or throughwall description, and safety evaluatior. for determm.
leakage crack postulated in moderate.cnergy fluid ing the effects of postulated piping failures in system piping. The terms used in this definition fluid systems both inside and outside the con.
are explained in Subsection 3.6.2.
tainment, and for including neceuary protective measures.
Structures, systems, components and equipment that are required to shut.down the reactor and 3.6.1.1 Design Bases mitigate the consequences of a postulated piping f ailure, without offsite power, e defined as 3.6.1.1.1 Criteria essential and are designed to Sein ic Category i Pipe break event protection conforms to
'"9 " * * *"I'*
10CFR56 Appendix A. General.01pgn Cdteda 4n r amen al and WuHe Mgn Basu.
The dynamic effects that m.y result from a The design bases for this protection is la postulated rupture of high. energy piping include compliance with NRC Branch Technical p
missile generation; pipe whipping; pipe break osidons A E 31 and MEB 31 locluded reaction forces; jet impingement forcest compart.
s and "ap c s[ctlon o
ment, subcompartment and cavity pressurizationst g
,g g,,d im P decompression waves within the ruptured for the following:
pipes and loads identitled with loss of coolant accident (LOCA) on Table 3.9.2.
- 3. b # l Amendment U f
i j
j
1
)
l
- '.rv e IM Standard Plant R
4 F
(al MEB 31. B.I.b.(1) (a) footnote 2 should read. 'For those loads and conditions in which Leiel A and Lesel H stress limits have been speelfled in I
the De:Ign Specification (excluding ear 1hquake loads).
1 (b) MEH 31, H.I b.(1).(d) should read, il A
'The maximum stress as calculated by
'i the sum of Eqs. (9) and (10) In Paragraph NC 3652, ASME Code, Section Ill, considering those loads and I '
conditions thereof for which Level A and Level H stress limits have been
-l l
specified in the system's Design Speelfication (i.e., sustained loads, occasional loads, and thermal expansion) excluding earthquake loads should not exceed 0.8(1.8 S h*
S I' A
e i46B 3-l B.l.G.d).I,b) 5bodM If j
j (c) A A ";'.... w m m a in y g,,,.s g,,f;,u,je,e ye, ww:= u MEB 31 describes an acceptable basis for g gum p f ff13 (
C *d s Cd /CM /4I selecting the design locations and orientations b[ GT bo) excec/$ 7,, 4 S m / a n d f $ 6 l of postulated breaks and cracks in fluid systems
( j /c g /A / f / d v G if b e r"
.{
piping. Standard Review Plan Sections 3.6.1 and gyggy3 (, J,,
/
l g
3.6.2 describe acceptable measures that could be f$. LIN o Y" 6. D I) 8" Idfdjff N6-taken for protection against the breaks and h
cracks and for restraint against pipe whip that y
g,ggy, may result from breaks.
The design of the containment structure, com.
ponent arrangement, pipe runs, pipe whip re.
l straints and compartmentalization are done in l
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t
- 3. b-",\\. k
'l._
--,)
Amendment !!
Standard Plant arv A l
l not result in whipping of the cracked pipe, are generally not identified with particular
. High. energy fluid systems are also postulated to break points. Breaks are postulated 61 all have cracks for conservative environmental possible points in such high.cnergy piping conditions in a confined area where high. and systems. However,la some systems break points moderate.cnergy fluid systems are located, are particularly specified per the following subsections if special protection devices such The fwlowing hich. energy piping systems (or as barriers or restraints are provided.
portions of systems) are considered as potential candidates for a postulated pipe break during 34.2.1.4.2 Piping in Containment Penetration normal plant conditions and are analyzed for Artas potential damage resulting from dynamic effects:
No pipe breaks or cracks are postulated in (1) All piping which is part of the reactor those portions of piping from containment wall coolant pressure boundary and subject to to and including the inboard or outboard reactor pressure continuously during station isolation valves which meet the following operation:
requirement in addition to the requirement of the ASME Code, Section m, Subarticle NE.1120:
(2) All piping which is beyond the second isolation valve but subject to reactor (1) The design stress and fatigue limits of pressure continuously during station (a) through (e) are nut exceeded. When operation; and meeting the limits of (a), (b) and P'
(d),
earthquake loads are excluded.
(3) All other piping systems or portions of (See Submtion 3.6.1.1.1) pioing systems considered high.cnergy For AShm Code, seeilen m. Chtt 1 Pielu i sy5 tem 5.
o Portions of piping systems that are isolated (a) The maximum stress range betwee any two from the source of the higb. energy fluid during loads sets (including the zero load set) normal plant conditions are exempted from does not exceed 2.4 Sm. and is consideration of postulated pipe breaks.This calculated' by Eq. (10) in NB.3653, ASME includes portions of piping systems beyond a Code Section W.
normally closed valve. Pump and valve bodies are also exempted from consideration of pipe break If the calculated maximum stress range because of their greater wall thickness, of Eq. (10) exceeds 2.4 Sm, the stress ranges calculated by both Eq. (12) and 3.6.2.1.4 Locations of Postulated Pipe Breaks Eq. (13)in Paragraph NB 3653 meet the limit of 2.4 Sm.
Postulated pipe break lof ations are selected as follows:
(b) The cumulative usage factor is less than 0.1 34.2.1.4.1 Piping Meeting Separation (c) 'ine maximum stress, as calculated by Eq.
Requirtments (9) in NB.3652 under the loadings Based on the HEl.SA evaluation described in resulting from a postulated piping Subsection 3.6.1.3.2.2, the high.cnergy lines failure beyond these portions of piping does not exceed the lesser of 2.25 Sm which meet the spatial separation requirements a n d 1.8 S except that following a y
failure outside containment, the pipe For those loads and conditions in which between the outbonrd isolation snlve and Level A and Level B stress limits have been specified in the Design Specification.
l Amendmtm t 3M
ABWR u-e Staridard Plant nry n the airst restraint may be permitted analyses, or tests, are performed to higher stresses provided a plastic hinge demonstrate compliance with the limits of is not formed and operability of the item (1).
(
valves with such stresses is assured in accordance with the requirement (3) The number of circumferential and loogi.
l specified in Section 3.9.3.
Primary tudinal piping welds and branch connections loads include those which are deflection are minimized. Where penetration sleeves limited by whip restraints, are used, the enclosed portion of fluid j
system piping is seamless construction and For ASME Code. Section llt. Clau 2 Picimt without circumferential welds unless g
specific access provisions are made to 9
4 (d)
The maximum stress as calculated by the permit inservice volumetric examination of T
sum of Eqs. (9) and (10) in Paragraph longitudinal and circumferential welds.
c NC 3652, ASME Code, Section Ill, D
considering those loads and conditions (4) The length of these portions of piping are thereof for which level A and level B reduced to the minimum length practical.
g 4
stress limits are specified in the q
system's Design Specification (l.c.,
(5) The design of pipe anchors or restraints i
sustained loads. occat onal loads, and (e.g., connections to containment i
}
iermal expansion);Wde -ae-GRE-penetrations and pipe whip restraints) do s
event does not exceed 0.8(1.8 Sh+
not require welding directly to the outer k
S,).
The S and S are allowable surface of the piping (e.g., flued integ-h
$ Cresses at maximum (3h'ot) temperature rally forged pipe fittings may be used)
W and allowable stress range for thermal except where such welds are 100 percent expansion, respectively, as defined in volumetrically examinable in service and a Article NC 3600 of the ASME Code, detailed stress analysis is performed to Section 111.
demonstrate compliance with the limits of item (1),
(c)
The maximum stress, as calculated by Eq.
(9) in NC 3653 under the loadings (6) Sleeves provided for those portions of resulting from a postulated piping piping in the containment penetration areas failure of fluid system piping beyond are constructed in accordance with the rules these portions of piping does not exceed of Class MC, Subsection NE of the ASME Code, the lesser of 2.25 S and 1.8 S.
Section III, where the sleeve is part of the h
Y containment boundary. In addition, the Priraary loads include those which are entire sleeve assembly is designed to meet deflection limited by whip restraints. The the following requirements and tests:
exceptions permitted in (c) above may also be applied provided that when the piping (a) The design pressure and temperature are between the outboard isolation valve and the not less than the maximum operating restraint is constructed in accordance with pressure and temperature of the the Power Piping Code ANSI B31.1, the piping enclosed pipe under normal plant is either of seamless construction with full conditions, radiography of all circumferential welds, or all longitudinal and circumferential welds (b) The Level C stress limits in NE 3220, are fully radiographed.
ASME Code, Section ill, are not l
exceeded under the loadings associated (2) Welded attachments, for pipe supports or with containment design pressure and l
other purposes, to these portions of piping temperature in combination with the are avoided except where detailed stress safe shutdown earthquake.
M Amendment 21
mm ABWR I
Standard Plant asy n
- +
(c)
The assemblies are subjected to a single As a result of piping re analysis due to 6
pressure test at a pressure not less differences between the design configuration than its design pressure.
and the as. built configuration, the highest stress or cumulative usage factor locations j
(d)
The assemblies do not prevent the access may be shifted; however, the initially required to conduct ihe inservice determined intermediate break locations need examination spec. fled in item (7),
not be changed unless one of the following conditions exists:
(7) A 100% volumetric inservice examination of all pipe welds would be conducted during (i) The dynamic effects from the new each inspection interval as defined in (as built) intermediate break locations IWA.2400, ASME Code,Section XI.
are not mitigated by the original pipe whip restraints and jet shields.
3.6.2.1.4.3 ASME Code Section Class 1 Piping in Areas Other Than Containment (ii) A change is required in pipe parameters such as major differences in pipe size, g gj (c) wall thickness, and routing.
Penetration With the exception of those portions of piping identified in Subsection 3.6.2.1.4.2, breaks in 3.6.2.1.4.4 ASME Code Section 111 Class 2 and ASME Code, Section 111, Class 1 pippin 3 Piping in Arena Other Than Containment er postulated at the ftrthrwntg locationsfin each Penetration piping and branch run:, Ea<yde, loads ose enladed.fw N)ad (c).
With the exception of those portions of (a)
At terminal ends' piping indentified in Subsection 3.6.2.1.4.2, breaks in ASME Codes, Section 111, Class 2 and 3 (b)
At intermediate locations where the piping are postulated at the following locations maximum stress range as calcylated by in those portions of each piping and branch run:
Eq. (10) exceeds 2.4 Sm, aev (a) At terminal ends (see Subsection A!!6::Med;d...- -m
.. = : r ;p -
3.6.2.1.4.3, Paragraph (a))
l M4( ^) cae;;E 2/ 0% the stress f
range calculated byg Eq.(12)
(b) At intermediate locations selected by one of
) W. En e%
M8 Egg ~
Eq.(13) in Paragraph N8 3653 drM ::'
the fe!!d.;; criterlar'l fom ude ic4i),
load 5 M e e nku
- 2 e: E.; k
.4 Sm.
e.neec (i) At each pipe fitting (e.g., elbow, tee, (c)
At intermediate locations where the cross, flange, and nonstandard cumulative usage factor exceeds 0.1.
fitting), welded attachment, and valve. Where the piping contains no fittings, welded attachments, or
- Extremities af piping runs that connect to valves, at one location at each extreme structures, components (e.g., vessels, pumps, of the piping run adjacent to the valves), or pipe anchors that act as rigid protective structure.
constraints to piping motion and therrnal expansion. A branch connection to a main (ii) At each location where stresses calcu.
piping run is a terminal end of the branch lated (see Subsection 3.6.2.1.4.2, run, except where the branch run is classified Paragraph (1)(d)) by the sum of Eqs.
as part of a main run in the stress analysis (9) and (10) in NC/ND.3653, ASME Code, and is shown to have a significant effect on Section 111, exceed 0.8 times the sum the main run behavior. In piping runs which of the stress limits given in NC/ND.
3653.
are maintained pressurised during nonna! plant conditions for only a portion of the run (i.e., up to the first normally closed valve)
As a result of piping re analysis due a terminal end of such runs is the piping to differences between the design configuration and the as built connection to this closed valve, configuration, the highest stress w
Amendment 23
T ABWR uomu Standard Plant Wptes ide2tified la subsection '3.6,2.1.4.2.
I le:ktge cr cks are p:stti.ted f:r the most locatio:s may be used unless a redesign of severe envir=me2t effects in ccccrd :ce with items (1), (2) and (3) below, b
' the piping resulting in a change in the pipe parameters (diameter, wall Earthquake loads are excluded from criteria (1) and (2).
thickness, routing) is required, or the dynamic effects from the new (es. built)
(1) For ASME Code, Section til Class 1 piping, at intermediate break location are not axial locations where the calculated stress mitigated by the original pipe whip range (see Subsection 3.6.2.1.4.2, Paragraph restraints and jet shields.
(1)(a)) by Eq. (10) and either Eq. (12) or Eq. (13) in NB 3653 exceeds 1.2 5.
3.6.2.1.4.5 Non ASME Class Piping (2) For ASME Code, Section til Class 2 and 3 or Breaks in seismically analyzed non ASME Class non ASME class piping, at axial locations (not ASME Class 1,2 or 3) piping are postulated where the calculated stress (see Subsection according to the same requirements for ASME Class 3.6.2.1.4.4, Paragraph (b)(ii)) by the sum of 2 and 3 piping above. Separation and interaction Eqs. (9) und (10) in NC/ND.3653 exceeds 0.4 requirements between Seismically analyzed and times the sum of the stress limits given in non seismically analyzed piping are met as NC/ND.3653.
described in Subsection 3.7.3.13.
(3) Non.ASME class piping which has not been 3.6.2.1.4.6 Separating Structure With liigh-evaluated to obtain stress information have Enerp Lines leakage cracks postulated at axial locations that produce the most severe environmental if a structure separates a high energy line effects.
from an essential component, the separating structure is designed to withstand the consequen.
3.6.2.13J Moderate Energy Piping ces of the pipe break in the high.cnergy line at locations that the aforementioned criteria 3.6.2.133.1 Piping in Containment Penetration require to be postulated. However, as noted in Areas Subsection 3.6.1.3.2.3, some structures that are identified as necessary by the HELSA evaluation Leakage cracks are not postulated in those (i.e., based on no specific break locations), are portions of piping from containment wall to and designed for worst case loads.
including the inboard or outboard isolation vahes provided they meet the requirements of the ASME 3.6.2.1.5 locations of Postulated Pipe Cracks Code, Section 111, NE.1120, and the stresses calculated (See Subsection 3.6.2.1.4.4, Paragraph Postulated pipe crack locations are selected (b)(li)) by the sum of Eqs. (9) and (10) in ASME Code, Section Ill, NC 3653 do not exceed 0.4 times as follows:
the sum of the stress limits given in NC.3653.
3.6.2.1J.1 Piping Meeting Separation 3.6.2.143.2 Piping in Areas Other Than Requirements Containment Penetration Based on the HELSA evaluation described in Subsection 3.6.1.3.2.2, the high or moderkte-(1) Leakage cracks are postulated in piping energy lines which meet the separation require-located adjacent to essential structures, ments are not identified with particular crack systems or components, except for (a), (b) locations. Cracks are postulated at all possible and (c) below. Earthquake loads are points that are necessary to demonstrate adequacy excluded from the stress criteria of (a),
of separ tion or other means of protections pro-W and (c).
vided for essential structures, systems and Where exempted by subsections (a) components.
3.6.2.1. 5.3.1 a n d 3.6.2.1. 5. 4, 3.6.2.1.5.2 liigh. Energy Piping For ASME Code, Section 111, Class 1 ptp,
()
ing tbe stress eange ea1euIated '
With the exception of those portions of piping i
3610 Amendman 13 1
1
MM mim-Standard Plant ney,
November 1977. Also NEDO 24057 P, Amendment' 1, December 1978, and NEDE 2 P 24057-(
Amendment 2, June 1979.
4.
General Elects.'s Company, Analytical Model for Loss of Coolant Analysis in Accordance with 20CFR50, Appendix X, NEDE 20566P, Proprietary Document, November 1975.
5.
BWR Feedwater Noule and Control Rod Dnve
.c Return Line Noule Cracking, NUREG.0619.
6.
General Electric Environmental Qualification Program, NEDE 243261 P, Proprietary Document, January 1983.
Functional Capability C,-!::.-!: != of Pipi>A Syst&Mbu.s.*d'"l"4*"1 7.
- *.tuon E:;...,l-l L'.-t !! "!;' ;. NetH>tt999; Nuggc, ;Q 3 gNOMgV /
{
September 1978, prepared by Battelle J
Columbus Laboratories for General Electric Company.
8.
Generic Criteria for High Frequency Cutoff of BWR Equipment, NEDO 25250, Proprietary Document, January 1980.
t g
l' t
194$1
. Amendmcat 16 -
M nMIMAE Standard Plant m,
Table 3.91 PLANT EVENTS I*
B. Dynamic Loading Events )
ASME Code No. o.'
SenMO)
Cycles /g)
Litall Events
- 12. Safe Shutdown Earthquake (SSE) at Rated B6 2 Eve 0
y Power Operating Conditions 10 Cycles / Event
~%,
- 13. Safe Shutdown Earthquake (SSE) (5 at Rated D(')
1(3) Cycle Power Operating Conditions 14 Turbine Stop Valve Full Closure (13VC)(')
B 330 Events During Event 7a and Testing 3 Cycles / Event
- 15. Safety Relief Valve (SRV) Actuation (One, B
4596 Two Adjacent, Allor Automatic Depreuuri-Events (f) zation System) During Event 7a and 7b
- 16. Lou of Coolant Accident (LOCA)
Small Break LOCA (SBL)
D(8) 1(3)
Intermediate Break LOCA (IllL)
D(s) g(s)
Large Break LOCA (LBL)
D(8) 1(3)
DO 16 a
NOTES.
(1)
Some events apply to reactor preuure veuct (RPV) only. The number of events / cycles applies to RPV as an example.
(2)
Bulk average vessel coolant temperature change in any one hour period.
(3)
The,ynnual encounter probability of a single event is <10'* for a Level C event and
< 10 for a Level D event. See Subsection 3.93.1.1.5.
l (4) Use 20 peak SSE cycles for evaluation of ASME Class 1 Components and Cost Support Structures for Service Level B Limits. Alternatively, an equivalent number of fractional SSE cycles may be used 0,, ' /.
r ; " : _ l..
-.... v. m....,,,' 1,... _. _. 002
..r.:..M
'l i !....,.. ooc.
,,L.. - mc.._..L.
'" S did in accordance with ? r;"' " ' ""'". C.-..A.J M ~
49645ese e. H on 3. '"). 3. 2..
4 (5) The effects of displacement. limited, seismic anchor motions (SAMguy to SSE shall be evaluated for safety related ASME Code Class 1, 2, and 3 components r e....,..,..
,,:1' to ensure their functionality during and following an SSE. The SAM effects shall include relative displacM c iping between buddmes, at equiprnent nozzles, at piping penetrations and at connections of small-diameter piping to large-diameter piping. See Table 3.9 2 and Notefor Table 3.9-2 for stress limits to be used to evaluate the SAM effects.
(2 wag ns t w
--a,
\\.'
.ABWR uuimt uv n Standud_ Plani Table 3.9 2 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA FOR SAFETY.RELATED, ASME CODE CLASS 1,2 AND 3 COMPONENTS, COMPONENT SUPPORTS, AND CLASS CS STRUCTURES Service leading ASME Plant Escal Cgebination(1).f ).(8)
Service feel (!)
3 1.
Normal Operation (NO)
N A
2.
Plant / System Operating (a) N + TSVC B
Transients (SOT)
(b) N + SRV(s) g SS 5 556 g S,17. )
3.
NO + et!E' N + etHi-D
-t COT-+ettii
(.) N "' ' n M "
L C,
be\\e}ed (b) "
S!"/(*)
0"L LF 5.
Infrequent Operating N(l') + SRV(s)
C(18)
SBL N + SRV (8) + SBL(11)
C 7.
SBlor IBL + SSE (c0 N + SB 10L)(' ') + 5R 4556 D(7)
(Q n SSC - SRif)
MVLW'" + SS6 8.
LBL + SSE N + LDL(11) + SSE D(7)
M 9.
Ptf - A P N + sRv ta) TSvc()
D NOTES (1) See Legend on the following pages for definition of terms. See Table 3.91 for plant events and cycles information.
The service loading combination also applies to Seismic Category I instrumentation and electrical equipment (See Section 3.10).
(2) The senice levels are as defined in appropriate subsection of ASME Section Ill, Division 1.
(3) For vessels and pumps, loads induced by the attached piping are included as identified in their design specification.
For piping sys: ems, water (steam) hammer loads are included as identified in their design specification.
(4) The melbod of combination of the loads is in accordance with NUREG 0484, Revision 1.
b N MGL e.@hab D v\\ of ASM b MyhR$
on (5) Guuui G4e Cku l coqOsts ud Core. Spot + Strudwes.
j @d hMk ND. lZ,j %)g, 3e h 4 M5 C.
bom I 39ag Amendmem 23 note UO to Ta6)e.
3.*H for rmder of cycles.
i
ABWR umm nrv n Si&D_ ard Plant d
(
Table 3.9 2 LOAD COMillNATIONS AND ACCEPTANCE CRITERIA FOR SAFETY.RELATED, ASME CODE CLASS 1,2 AND 3 COMPONENTS, COMPONENT SUPPORTS, AND CLASS CS STRUCTURES (Continued)
NO1rs
~ i n s Wl*
M%J h 0)t f
(6) Deleter'
[
54.f.
"a/bC[n161f bMC
[ p-g
(7) For active Class 2 and 3 pumps, the stresses are limited by criteria: Om 11.2S, and (Om or OL) + ob 1 8S, where the notations are as defined in the ASME Code,Section III, 1
subsections NC or ND, respectively.
The most limiting load combination case among SRV(1), SRV(2) and SRV (ALL) For main steam (8) and branch piping evaluation, additional loads associated with relief line clearing and blowdown into the suppression pool are included.
(9) The most limiting load combination case among SRV(1), SRV(2) and SRV (ADS). See Note (8) for main steam and bransh piping.
(10) The reactor coolant pressure boundary is evaluated using in the load combination the maximum pressure expected to occur during ATWS.
(11) The piping systems that are qualified to the leak before break criteria of Subsection 3.6.3 are excluded from the pipe break events to be postulated for design against LOCA dynamic bN cffects, vir., SDL, IBL and LBL.
"... mom usam iinu oud eu.. im..;.1
- d ;; ' TE: '-- p;5 M!!"jt-gb(12) TM;,;-Er u.!y s
t in' ' h a N' H SRV-lead; an u.x. ius
.m im.c.c;i ' C;,umbiu.n.v; BAT t c ' ' ' - ' '- ' c " A ~ '- n! D.
q Y,W LOAD DEFINITION LEGEND:
Normal (N)
Normal and/or abnormal loads associated with the system operating conditions, including thermalloads, depending on acceptance criteria.
SOT System Operational Transient (see Subsection 3.93.1).
IOT Infrequent OperationalTransient (see Subsection 3.93.1).
ATWS Anticipated Transient Without Scram.
Turbine stop valve closure induced loads in the main steam piping and components TSVC integral to or roounted thereon.
RBV1. cads - Dynamic loads in structures, systems and components because of reactor building vibration (RBV) induced by a dynamic event.
pgg onu wa,k w,abyn y.L 1ba....kn,,,,1 4 1
Nun LOCA Fetr
-Nif 3W Amendment U 1
i
. 5 i
NOTES 6 & 12 FOR TABLE 3 9 2 (6) All ASME Code Class 1,2 and 3 Piping systems which are essential for safe shutdown under the postulated events are designed to meet the requirements of NUREG-1367 (Reference 7). Piping system dynamic moments can be calculated using an clastic response spectrum or time history analysis.
(12) For ASME Code 1,2 and 3 piping the following changes and additions to ASME Code Section III Subsections NB-3600, NC-3600 and ND-3600 are necessary and shall be evaluated to meet the following stress limits (a) ASME Code Class 1 Piping:
se c M u os-where: S is the nominal value of seismic anchor-motion stress ug M
is the combined moment range equal to the greater of c
(1) the resultant range of thermal and thermal anchor movements plus one-half the range of the SSE anchor motion, or (2)_the resultant range of moment due to the full range of the SSE anchor motions alone.
C g, Doand I are defined in ASME Code Subsection ND-3600 SSE inertia and seismic anchor motion loads shall be included in the calculation of ASME Code Subsection NB-3600 equations (10) and (11).
(b) ASME Code Class 2 and 3 Piping:
/dc
$s e A 6.3.05h z
whore S34y and Mc are as defined in (a) above, and i and Z are defined in ASME Code Subsections-NC/ND-3600 SSE inertia and scimic anchor motion loads shall not be included-in the calculation of ASME Code Subsections NC/ND-3600 Equations (9),.pd"(10) an/ (//).
l L
t
+
j ABWR msim Simpdard Plant urv a l
.o Table 3.9 2 LOAD COMBINATIONS AND ACCEPTANCE CRITERIA FOR SAFETY.RELATED, ASME CODE CLASS 1,2 AND 3 COMPONENTS, COMPONENT SUPPORTS, AND CLASS CS STRUCTURES l
(Continued)
LOAD DEFINITION LEGEND:
RBV loads induced by safe shutdown earthquake.
SSE RBV loads induced by safety / relief valve (SRV) discharge of one or SRV(1),
SRV(2) two adjacent valves, respectively.
SRV(ALL). RBV loads induced by actuation of all safety / relief valves which activate within milliseconds of each other (e.g., turbine trip operational transient).
SRV (ADS). RBV loads induced by the actuation of safety / relief valves associated with automatic l
depressurization system which actuate within milliseconds of each other during the postulated small or intermediate break LOCA, or SSE.
The loss of coolant accident associated with the postulated pipe failure of a high.
LOCA energy reactor coolant line. The load effects are defined by LOCA1 through
. LOCA events are grouped in three categories, SBL,IBL or LBL, as defined LOCA)6 l
here.
--+
Pool swell (PS) drag / fallback loads on essential piping and components located LOCA3 between the main vent discharge outlet and the suppression pool water upper surface.
Pool swell (PS) impact loads acting on essential piping and components located above LOCA2 the suppression pool water upper surface.
(a) Oscillating pressure induced loads on submerged essential piping and componen'.s LOCA3 during main vent clearing (VLC), condensation oscillations (CO), or chugging (CHUG),
or (b) Jet impingement (JI) load on essential piping and components as a result of a postulated IBL or LBL event.
Piping and components are defined essential,if they are required for shutdown of the I
reactor or to mitigste consequences of the postulated pipe failure without offsite l
power (see introduction to Subsection 3.6).
L RBV load from main vent clearing (VLC).
LOCA.$
RBV loads from condensation oscillations (CO).
LOCAS LOCA6 RBV loads from chugging (CHUG).
l 3.7."*6I:
Amtndment 2.)
=-
ABWR umme nty n Standardflant I,.
Table 3.9 2 LOAD COh1111 NATIONS AND ACCEPTANCE CRITERIA FOR SAITTY.RELATED, ash 1E CODE CIASS 1,2 AND 3 COh1PONENTS, COh1PONENT SUPPORTS, AND CLASS CS STRUCTURES (Continued)
LOAD DfflNITION LEGEND:
Annulus pressurization ads due to a postulated line break in the annulus l
region between the RPV and sbicidwall. Vessel depresst.ization loads on reactor i
bb internals (see Subsection 3.9.2.5) and other loads due to reactor blowdown reaction and jet impingement and pipe whip restraint reaction from the broken pipe are included with the AP loads.
Loads induced by small break LOCA (see Subsections 3.9.3.1.1.3 and 3.9.3.1.1.4); the Sill loads are: LOCA (a), LOCA and LOCA
- b**
I"(")*
3 4
6 Loads induced by intermediate break LOCA (see Subsection 3.9.3.1.1.4); the loads are:
lill and LOCA ' b** N I" (III' LOCA (a) or LOCA (b), LOCA, LOCA3 6
3 3
4 Loads induced by large break LOCA (sae Subsection 3.9.3.1.1.4); the loads are:
LBL LOCA through LOCA. See Note (11).
3 6
Amendment 21
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