ML20210T059
| ML20210T059 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 09/13/1974 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-1791 NUDOCS 8605290676 | |
| Download: ML20210T059 (52) | |
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q 11-1 11.0 MECHANICAI. ENGINEERING 110.1 Under 3.6.2.1.4(a) piping systees having an internal pressure of (3. 6. 2.1) up to 275 psia and fluid tenperatures not in excess of 200*F are excluded from pipe break griteria, This is not censistent with Regulatory Guide 1.46 nor the present MEB position. The present MEB position is that through wall leakage cracks should be postulated for such piping as delineated in Attachment A which I
is generally applicable for piping outside the containment.
l 110.2 PSAR states that criteria for postulating pipe breaks for (3.6.2.2) piping outside the containnent will be per AEC letter from J. O' Leary of 7/12/73.
This is acceptable, however, imple-mentation of this criteria should be as contained in Attachment
.A.
110.3 (1) Provide loading-combinations and. stress criteria for (3.6.3.1) normal, upset, and energency conditiens for Class 1, 2 and 3 piping in the A/E - BOP scope.
(2) Provide more specific criteria than "per code" for faulted condition stress criteria for Class 1 piping.
For example, ASME Section III permits the use of Appendix F of the code for faulted conditions; but, does not require it.
State specifically what is to,be used.
(3) Provide specific design details for the three types of piping penetration guard pipes. Also discuss the access provisions to carry out inservice inspection of the flued head to process pipe welds for the Type I and III penetrations.
110.4 (1) Identify the computer program to be used for the calculation (3.6.4.1) of postulated pipe break and if the program is not videly used in the nuclear industry, provide justification for its applicability and validity for this type of analysis.
(2) In the conputation of the thrust force using the simplified forcing function, justify the use of P in lieu of P sat o
for compressed (flashing) or saturated water.
110.5 (1) For unchoked flow, the Regulatory staff will accept use of (3.6.4.2) a nodel with a uniform half angle of dispersion not exceeding
'10'.
(2) In calculating jet impingement force as described in Eq. (1),
the definition of the velocity ratio Um is not clear.
Current MEB position requires that the steady state forcing function for jet impingement should have a magnitude (T) not less than i
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11-2 110.5 T = KPA (3.6.4.2)
Where P = system pressure prior to pipe break A = pipe break area, and K = thrust coefficient.
(3) For choked flow, provide justification for the following l
assumed angles of dispersion for the jets:
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Flashing water - 45' i
Steam
- 22' Non-Flashing Water - 25' and clarify the pressure that is going to be used for calculating jet force.
(4) Define the symb'ols for calculating the jet impingement forces as given in cases A, B, C and D.
In those formulas, explain the missi,ng pressure, force component.
(5) For the calculation of the Drag Force (Case C) expand the discussion to include a broader range of Reynolds numbers other than the range of R, = 10 to 105 3
given.
110.6 (1) The information presented in this section'of the PSAR does (3.9.1.1) not satisfy the requirements concerning " Seismic Category I Mechanical Equipment Testing and Analysis - C.E. Scope of Supply" for plants currently undergoing review.
Provide the appropriate commitments from CESSAR.
l (2) Clarify type of operating expertence to be used to verify that equipnent will operate under SSE conditions.
(3) Provide commitment that all Category I bachanical equipment and supports will be qualified to requirements Of specifi cations 7-74 in Appendix 3.9.A.
(4) In paragraph 3.02 d of Appendix 3.9.A. when using the Response Spectrum Modal Analysis methods provide criteria for determining closely space modes, (5) In Appendix 3.9.A, paragraph 3.02.e permits an allowable stress of 0.9 of the material yield stress for faulted conditions.
This is not consistent with limits stated per Table 3.9.3 of the PSAR. Revise the Appendix to conform with Table 3.9.3.
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110.7 The seismic qualification program described in this section is (3.9.1.2) not to' tally acceptable. Revise the program to be in accordance (3.10) with criteria provided in Attachment B " Electrical and Seismic Qualification Pro;: ram."
110.8 (1) In the last sentence of Part I of Appendix 3.9.B change
'I (3.9.2.4)
"will" to "may".
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(2) In Section II of Appendix 3.9.B expand the valve operability testing criteria to include Lhe valve design pressure.
(3) In Section II of Appendix 3.9.B under criterion d state the Qualification Standards to be employed.
t (4) In Appendix 3.9.B define the horizontal and vertical accelerations to be used for static valve qualification.
(5) In Appendix 3.9.B.Section II, your position that for valves with natural frequencies less than 33 Hz operability can be verified without performing valve exercising per step C requires justification.
110.9 Provide more specific, equations of motion and discuss methods (3.9.2.5) of solution for the dynamic analysis for open and closed systens.
110.10 The information provided in this se< : ion is not adequate.
In (3.9.2.7) addition to the nominal pipe ~ size which determine whether AStiE (5.2.19)
Class 2 and 3 piping will be field run, identify in the PSAR those Category I piping systems which will be field run.
Include any special or simplified procedures which will be used for designing and installing this piping.
110.11 Provide the, specific criteria that will be used to guarantee t
(3.10.2) operability of instrumentation and electrical equipment, not furnished by C.E., under faulted conditions when a dynamic analysis without performance testing is employed in the design of this equipment.
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_m 7/1/74 Attachment A BRA 2;CH TECIC;ICAL POSITIO!!-:423 : 0.1 MECFX;ICAL E::GI::EER!::G CE.'.: CR DIRECTO.uTE OF LICE::Si:;0 t
CRITERIA FOR POSTL* LATED 7AIUJ2I x;3 LIX.: AGE I.CCrtIO :S I:1
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FLUID SYSTE:I PIFI::G O!.;T5IDE CO::T.O.;:!E'.T The follow'ng criteria are within the review responsibility of the
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i Mechanical Engineering Sranch with the er.ception of I.A., II.A., II.D.,
1 II.E and 1.a.,1.b.,1.c., 2.a and 2,c. (3) of Appendix A 1,
Rich-EnercuFluidS.stehPtoinc
- A.
Fluid Synte.no Separated fron E.caencial Structuus, Systats &
Ccmponents For the purpose of satisfying the separation provisicas of 1.a.
of Appendix a, a revicu cf the piping layout and plant arrangement drawings should clearly show that the effccts of postulated piping
' breaks at any locctisn are isolated c; physically remote from essential structtwes, :ystc.=s, and comanents.
At the designer's option, breck locations as determined fron I.C.,
I.D., a.d I.E below may be selected for chis purpose.
B.
Fluid $ystem Piping Between Con::.1 tinman: Isolation Valves Breaks need not be postulated in chose portions of piping identified in 2.C. (1) and 2.C.(2) of Appendix A provided thay meet the requirenents of AS !E Code,Section III + Subarticle NE-1110 and are designed to neet the following additional requirements:
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- See Glossary for definitions of italicized phrases.
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The following design stress and fatigue limits should not be exceeded; For ASME Code,Section III. Class 1 Piping (a) Maximum stress ranges should not exceed the following limits:
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Ferritic steel 1 2.0S Austenitic steel < 2.4S.
f (b) The maximum stress range between any two load sets (including the zero load set) should be calculated by Eq. (10) in Par. NB-3653, ASME Code,Section III, for upset pZcnt conditions and an OBE event transient.
If the calculated maximum stress range, of Eq. (10) exceeds the limits of I.B.l(a) but is not greater than 3S the limit of I.B.i(c) should be met.
g If the calculated =aximum stress range of Eq.q(10) exceeds 3S," the stress ranges calculated by both
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Eq. (12) and Eq. (13) should meet the limits of I.B.1(a) and tha limit of I.B.l(c).
(c) Cumulative usage factor 10.1, as required by I.B.1(b).
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For ASME Code,Section III, Class 2 Piping l
Maximum stress ra tge as calculated by Eq. (9) and (10) in Par. NC-3652, ASME Code,Section III, considering upset pZcnt
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conditions (i.e., sustained loads, occasional loads, and thermal l
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2.
Welded attachments, for pipe supports or other purposes, to these portions of piping should be avoided except where detailed 1
' stress analyses, or tests, are performed to demonstrate compliance i
with the limits of I.3.1.
3.
The nucber of piping circumferential and longitudinal welds and branch connections should be minimized.
4.
The length of the piping run.should be reduced to the minimum 16ngth practical, 5.
The design,at points of pipe fixity (e.g.,- pipe anchors or welded connections at containment penetrations) should not require welding directly to the outer surfaco of the piping (e.g., fluid integral forged pipe fittings may be used) except where. detailed stress analyses are perfor=ed to denonstrate compliance with the 11=its of I.B.1.
6.
Geometric discontinuities, such as at pipe-to-valve section transitions, at branch connections, and at changes in pipe wall thickness should be designed to minimize the discontinuity stresses.
C.
Fluid Systems Enclosed Within Protective Structures 1.
Breaks in ASME Code,Section III, Class 2 and 3 piping should 2/The limit of 0.S(1.2 Sf + S ) may be used in itcu of (S, + S }'
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be postulated at the following locations in each piping and branch run (except those portions of fluid system piping
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identified in 1.3.) within a proccetive structure containing essential systems cnd c:mponents and designed to satt_sfy the l
provisions of 1.b. or 1.c. of Appendix A:
i a.
At tenninal ends of the.pressuriced portions of the run 4
if located within the protective structure.
i b.
At intermediate locations selected by either of the following criteria:
(1)
At each pipe fitting (e.g., elbow, tee, cross, and 5
non-standard fitting) or, if the run contains no i
fittings, at one location ai canh extreme of the run (a terminal end, if located within the protective structure may substitute for one intermediate break).
(ii) At each location where the stresses 3/ exceed (Sh but at not less than two separated locations chosen en the basis of highest stress /
In the case of a straight 4
pipe run without t.ny pipe fittings or welded attach-J ments and stresses below (S. + S ), a ninimum of one n
c location chosen on the basis of highest sttess.
3/
-- Stresses associaL d with normal and upsc# plant conditions, and an GBE 9
avant as calculated by Eq. (9) and (10), Par. NC-3652 of the ASME Code,Section III, for Class 2 and 3 piping,
-- Twc highest stress points; select second point at least 10% below the higbest stress.
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Breaks in non-nu, clear class piping should be postulated at the following locations in each piping or branch run:
At terminct enda of the pressurized portions of the run if a.
located within the protective structure.
b.
At each intermediate' pipe fitting and welded attach =ent.
D.
Flu.id Systers Not Enclosed Within Protective Structures 1.
Breaks in ASME Code,Section III, Class 2 and 3 piping, should be postulated at the following locations in each piping r.nd branch run (except those portions of f7 aid system piping iden'tified in I.B) outside but routed alongside, above, or below a protective structure containing essential systems cnd componsnts and de9 guad to satisfy the provisions of 1.b, or 1
1.c cf Appendix A.
At terminci ends of' pressurized portions of the run if a.
located adjacent to the protective structure.
b.
At internediate locations selected by either of the following criteria:
(i)
At each pipe fitting (e.g.', elbow, tee, cross, and non-standard fitting).
Ateachlocationwherethestresses! exceed (Sf+S,)/
2 (11) but at not less than two separated locations chosen on the basis of hig' hest seress /
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straight pipe run without any pipe fittings or welded attachments and stresses below (Sh
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c minimum of one location chosen on the basis of highest stress..
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2.
Breaks in non-nuclear class piping should be postulated at the following locations in each piping or branch run:
a.
At te =inal ends of pressurized portions of the run if located adjacent to the protective structure.
b.
'At,each intermediate pipe fitting and welded attachment.
- 11. Moderate-Enercy Flu *d System Pintng A.
Fluid Systens separated from Essential Structures, Systems &
Components For the purpose of satisfying the separation provisions of 1.a. of Appendix A, a review of the. piping layout and plant arrangement drawings should clearly shew that the effects of through-wall leakage cracks at any location are isolated or physically renate from essentici structures, syste.T:s, c"d cornponents.
B.
Fluid System Piping Between Containment Isolation Valves Breaks need not be postulated in those portions of piping identified in 2.c. of Appendix A provided they meet the requirements of ASME Code,Section III - Subarticle NE-1110, and are designed such that the stresses do not exceed 0.5(S + S )5/ for ASME Code,Section III, n
e Class 2 piping.
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,3 C.
Fluid Systems Within or Outside and Adjacent to Protective Structures Through-wall leakage cracks should be postulated in fluid syst5n piping located within or outside and adjacent to protective structures containing essential systems and comoonents and designed to satisfy the provisions of 1.b.
or 1.c..of Appendix A, except where exempted by II.B, II.D.
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or in those portions of ASME Code,Section III, Class 2 or 3 piping or non-nuclear piping where the stresses are less than h + S ) E. The cracks.should be postulated to occur 0.5 (S a
individually at locations that result in the maximum effects i
from fluid sp aying and flooding, and the consequent hazards or environmental conditions developed.
D.
Moderate-Energy Fluid Systems in Proximity to nigh-Energy Fluid Systems Cracks need not be postulat;ed in moderate-energy fluid system piping located in an area in which a break in high-energy f! aid system piping is postulated, provided such cracks would not result in more limiting environmental conditions than the high-energy piping break. Where a postulated leakage crack in the moderate-energy fluid system piping results in more limiting environmental conditions than the break in proximate high-energy fluid systen piping, the provisions of II.C should be applied.
E.
Fluid Systems Qualifying as High-Energy or Moderate-Energy Systems Through-wall leakage cracks instead of breaks may be postulated
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in the piping of those f!uid systems that qualify as high energy f2uid systems for only short operational periode / but qualify 6
as moderate-energy fluid systems for the =ajor operational period.
III. Type of 3reaks and Leakare Cracks in ?! aid Susten Pining A.
Circumferential Pipe Breaks The following circumferential breaks should be postulated in high-energy fluid system piping at the locations specified in 1
Section I above:
1.
Circumferential breaks should be postulated in f7 aid systen 4
piping and branch runs exceeding a nominal pipe size of 1 inch, except that, if the maximum stress range in the circumferential direction is at least twice that in the axial direction, only a'
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longitudinal break need be postulated.
Instrument lines, one
+
inch and less nominal pipe si'ze for tubing should meet the provisions of Regulatory, Guide 1.11.
2.
Where break locations are selected at pipe fittings without the benefit of stress calculations, breaks should-be postulated at each pipe-to-fitting weld.
If detailed stress analyses 2
6/
-- An operational period is considered "short" if the fraction of time that the system operates vithin the pressure-temperature conditions specified for high-energy f! aid systems is less than 2 percent of the time that the system operates as a moders:a energy fluid system (e.g., systems such as the reactor decay heat removal systems qualify as moderare-energy f7 aid syssens; however, systems such as auxiliary feedwater systems operated during Pi'R reactor sta'rtup, hot standby, or shutdown qualify as high-energy fluid systems).
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,(e.g., finita ele =ent analyses) or tests are performed, the maxd:pd2 stiessed location in the fitting may be selected l
instead of the pipe-confitting weld.
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Circumferential breaks should be assumed to result in pipe severance and separation amounting to a one-diameter lateral displacement of the ruptured piping sections unless physically limited by piping restraints, structural members, or piping stiffness as may be demonstrated by inelastic limit analysis (e.g., a plastic hinge in the piping is not developed under loading).
[.
The dynamic force of the jet discharge at the break location should be based on the effective cross-sectional flow area of the pipe and on a calculated fluid pressure as modified by an analytically or experimentally determined thrust coefficient. Limited pipe displacement at the break location, line restrictions, flow limiters, positive pump-controlled flow, and the absence of energy reservoirs may be taken inco account, as applicable, in the -reduction of jet discharge.
5.
Pipe whipping should be assumed to occur in the plane defined by the piping geometry and configuration, and to cause pipe movement in the direction of.the jet reaction.
6 B. ' Longitudinal Pipe Dreaks 2
The following longitudinal breaks should be postulated in high-snargy f7 aid cystem piping at the locations of each circunferential break specified in,III.A.:
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1.
Longitudinal break in fTuid systen piping and branch runs should be postulated in nominal pipe sizes 4-inch and larger,
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except that, if the maximum stress range in the axial direction
, is at least twice that in the circumferential direction, only a circumferential break need be postulated.
2.
Longitudinal breaks need not be postulated at tennin2l ends if the piping at the terminal ends contains.no longitudinal pipe i
welds and major geometric discontinuities at the circumferential weld joints of the terminal ends are designed to minimize dis-continuity stresses.
3.
Longitudinal breaks should be assumed to result in an axial split without pipe severance.
Splits should be located (but not concurrently) at two diametrically-opposed poines on the piping circumference such that a jet reaction causing out-of-f plane bending of the piping configuration results.
4.
The dyr.ani'c force of the fluid jet discharge shoul'd be based f
on a circular or elliptical (20 x 1/2D) break area equal to the effective cross-sectional flow area of the pipe at the 8
break location and on a calculated fluid pressure modified by an analytidally or experimentally determined thrust coefficient as determined for a circumferential break at the same location.
Line restrictions, flow limiters, positive pump-controlled flow, and the absence of energy reservoirs may be taken into account, as applicable, in the reduction of jet discharge.
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5.
Piping covement should be assuned to occur in the direction of the jet reaction unless limited by structural members, piping restraints, or piping stiffness as demonstrated by inelastic limit analysis.
C.
Through-Wall Leakage Cracks The following through-wall leakage cracks should be postulated in moderate-energy fluid system piping at the locations specified in Section II above:
1.
Cracks should be postulated in mderate-energy fluid system piping.and branch runs exceeding a nominal pipe size of 1 inch.
2.
Fluid flow from a crack should be based on a circular opening of atea equal to that of a rectangle one-half pipe-diameter in length and one-half pipe wall thickness in width.
3.
The flow fron the crack should be assumed to resu'l! in an environment that wets all unprotected components within the 6
compartment, with consequent flooding in the compartment and communicating compartments.
Flooding effects may be determined on the basis of a conservatively-estimated time period required to effect corrective actions.
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d APPE'iDIX A PLANT ARRANGDIENT CRITERIA AND SELECTED PIPING DESIGN FEATURES i
1.
Plant Arranzement i
i Protection of essencial structures, systems, and components against i
postulated piping failures in high or moderate energy fluid systems that operate during normal plant conditions and that are located out-side of containment should be provided by one of the following plant arrangement considerations:
Plant arrangements should separate fluid system piping from a.
essential structures, systems, and components.
Separation should I
be achieved by plant physical layouts that provide sufficient distances betueen essencial structures, systems, and components and fluid system piping such that the effects of any postulated t
piping failure therein (i.e., pipe whip, jet impingement, and the I
environmental conditions resulting from the escape of contained fluids as appropriate to high or moderate-energy fluid system j
piping) cannot impair the integrity or operability of essential structures, systems, and components.
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b.
Fluid system piping or portions thereof not satisfying the pr'ovisions of 1.a. above should be enclosed within. structures or compartments designed to protect nearby essential structures, systems, and components.. A1cernatively, essential systems and 4
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1 componen:s may be enclosed within structures or compart=ents designed to withstand the effects of postulated piping failures i
t tu nearby fluid systems.
I Li Plant arrangements or system features that do not satisfy the c.
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'i provisions of either 1.a. or 1.b.'above should be limited to i
those for which the above provisions are impractical.
Such cases may arise, for example, (1) at interconnections between fluid systens and essentici systems and components, or (2) in
- flu *d systems having dual functions (i.e., required to operate during,norrnal plant conditions as well as to shut down the reactor).
In'such cases, redundant design features, separated or otherwise protected from effects of postulated' piping failures, or additional protection should be provided so that reactor shutdown is assured in the event of a failure in the ' interconnecting piping of (1),
or in clie dual function piping of (2). Additional protection may.he provided by restraints and barriers or by designing or L'
s testing essential systems and cocponents to withstand the effects s.
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' associated with postulated piping failures.
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.6 2.
Design' Features i
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a.
Essential systems cnd components should be designed to meet the
_a seismic design requirements of Regulatory Guide 1.29.
q c.
'b.
Protective structures or compartments, fluid system piping
< restraints, and other protective teasures should be designed in
.,7 accordanc'e with th'e following:
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(1) Protective structures or compart=ents needed to i=placent
.i 1.b. or 1.c. above should be designed to Seis=ic Category I i
requirements.
The effects of a postulated piping failure t
I (i.e., pipe whip, j et i=pingement, pressurization of compart-l ment, water spray, and flooding, as appropriate) in combination i
i
~
with loadings associated with the Safe Shutdown Earthquake and normal operation should be used for the design of required protective structures.
Piping restraints, if used, may be taken into account to limit effects of the postulated piping failure.
(2) High-energy fluid system piping restraints and protective measures should be designed such that the effects of a postulated break 1/ in one pipe cannot, in turn, rupture
~
other nearby pipes or components which could result in unacceptable offsite consequences or in loss of capability of essential systems and' components to initiate, actuate, and complete actions required for reactor shutdown.
c.
Fluid systen piping between containment isolation valves should meet the following design provisions:
1/ In the design of piping restraint, an un' restrained whipping pipe should be considered capable of (a) rupturing i=pacted pipes of staller nominal pipe sizes and (b) developing a through-wall leakage crack in larger nominal pipe sizes with thinner wall thicknesses except where experimental or analytical data for specific i= pact energies demonstrate the capability to withstand the impact without failure.
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(1) Portions of fTuid systen piping between isolation valves of single barrier containment structures (including any rigid connection to the contain=ent penetration) that connect, l
on a continuous or intermittent basis to the reactor coolant j
pressure boundary or the steam and feed ~ water systems of PWR plants should be designed to the stress limits specified in I.B. or II.B. of this document.
These portions of high-~ energy fluid. system piping shoulk be provided with pipe whip restraints (i.e., capable of resisting bending and torsional moments') located reasonably close to the containment isolation valves.
The rcitraints should be designed to withstand the loadings resulting from a postulated piping failure beyond these portions of piping so that neither isolation valve operability nor the leaktight integrity of the containment will be impaired.
~
Tenninal ends of.the pipfng runs outside containment should bc-considered to originate at the pipe whip restraint locations outside containment.
Where contain=ent isolation valves are not required inside containment, those portions of the fluid system piping extending from the outside isolation valve to either the rigid pipe connection to the containment penetration or the first pipe G
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whip restraint inside containment should be considered as
. the boundary of'the system piping required to meet the above design limits and restraint provisions.
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(2) Portions of fTaid system piping between isolation valves of i
dual barrier containment structures should not exceed the stress limits in I.B. or II.B. of this document. These portions of ;high-energy fluid system piping that pass through the annulus, and whose failure could affect the leaktight integrity of the containment structure or re,sult in pressur-ization of the annulus beyond design limits, should be provided with pipe whip restraints (i.e., capable of resisting
~
bending and torsional moments) located reasonably close to the containment isolation valves and should be provided with'an enclosing structure or guard pipe. Restraints should be designed to withstand the loadings resulting from a postulcted piping failure beyond these portions of piping so that neither isolation valve operability nor the leaktight integrity of the associated containment penatration will be impaired.
TermincI ends of the piping runs outside containment should be considered to originate at the pipe whip restraint locations outside containment.
For the purpose of establishing the design parameters (e.g.,
pressure, temperature, axial loads) only of the enclosing 4
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4 structure or guard pipe, a full flow area break should.be assumed in that portion of piping within the enclosing structure or guard pipe.
4 I
(3) For those portions of f7 aid system piping identified in 2.c. (1) and 2.c. (2) above, the extent of inservice examination conducted as specified in Division 1 of Section XI of the ASME Code during each inspection interval should be increased to provide volumetric exanination of 100 percent of the circum-ferential and longitudinal weld joints in piping identified in Section III.A.l. and Section.III.B.l. of this docu=ent.
The areas subject to examination should comply with the require-ments of the following categories as specified in Section XI of the ASME Code:
(a) ASME Class 1 piping welds, Examination Category B-J in Table IIIB-2500.
(b) ASME Class 2 piping welds, Examination Category C-F and C-G in Table II,'C-2500.
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GLOSSARY Essential Structures. Systems. ad C:= enents.
Structures, cystems, and conponents required for reactor shutdown without off-site power or
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to mitigate the consequences of a postulated piping failure in fluid i
system piping that results in trip of the turbine-generator or the reactor protection system.
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Fluid Systems.
High and moderate energy fluid systems that are subject to the postulation of piping failures against which protectiot. of essenticI structures, systems, and components is needed.
Righ-Enercy Fluid Systems.
Fluid syste=s that, during normal plant conditions, are either in operation or maintained pressurized under conditions where either or both of the following are met:
a.
maximum operating te=perature exceeds 200*F, or
- b. ' maximum operating pressure exceeds 275 psig.
Moderate-Ener:p Fluid Sustens.
Fluid. syste=s that, during normal plant conditions, are either in operation or maintained pressurized (above atmospheric pressure) under conditions where.both of the following are met:
3 a.
maximum operating temperature is 200*F or less, and b.
maximum operating pressure is 275 psig or less.
i
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Norma! ?? nt Canistions.
Plant operating conditions during reactor startup, operation at power,' hot standby, or reactor cooldown to cold
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shutdown condition.
' Upset P!cnt Conditions.
Plant operating conditions during system transients that may occur with =oderate frequency during plant service life and are anticipated operational occurrences, but not during system testing.
Postulated Picin Fdi! ares.
Longitudinal and circumferential breaks in high-energy fluid system piping and through-wall leak' ge cracks in a
moderate-energy f2 aid system piping postulated according to the provisions
~
of this document.
S S,,. cnf S.
Allowable stresses at maximum (hot) temperature, at p
g minimum,(cold) temperature, and allowable stress range for thermal expr.nsion respectively, as defined in Article NC-3600 of the ASME Code,Section III.
S.
Design stress intensity as defined in Article NB-3600 of the ASME Code,Section III.
Sincle Active Ccirenant Editure.
Malfunction or loss c! function of a component of electrical or fluid systems.
The failure of an active component of a fluid system is considered-to be a loss of component function as a result of mechanical, hydraulic, pneumatic, or electrical malfunction, but not the loss of component structural integrity.
The direct consequences of a single cative component failure are considered to be part of the single failure.
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Temin ! Ends.
Extremeties of piping runs that connect to structures, components (e.g., vessels, pumps, valves), or pipe anchors that act as t
rigid constraints to piping thermal expansion. A branch ccanection to I
a main piping run is a terminal end of the branch run.
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's Attachment B
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ELECTRICAL AND MECH.*.'!!C.*.I. EQUIPMENT SEIS"IC QUALIFICATION PROGRAM I.
Seismic Test for Eouipcent Ooerability j
1.
A test program is required to cenfirm the functional operability of all Seismic Category I electrical'and mechanical equipment j
and instrucentation during and after an earthquake of magnitude i
up to and including the SSE.
Analysis without testing cay be j
acceptable only if s:ructural integrity alone can assure the
~
design intended function. When a complete seismic testing is 4
impracticable, a combination of test and analysis may be accept-able.
2.
The characteristics-of the required input motion should be specified by one of the following:
(a) response spectrum i
(b) power spectral density function (c) time history 4
Such characteristics, as derived from the structures or systems seismic analysis, should be representative of the input motion at the equipment mounting locations.
3.
Equipment should be tested in the operational condition. Oper-ability should be verified during and after the testing.
4.
The actual input motion should be characterized in the same manner as the required input motion, and the conservatism in amplitude and frequency content should be demonstrated.
5.
Seismic excitation generally have a broad frequency content.
Random vibration input motion should be used. However, single frequency input, such as ' sine beats, may be applicable provided one of'the following conditions are met:
(a) The characteristics of the required input motion indicate i
l
.that the motion is dominated by one frequency (i.e., by structural filtering effects).
i l
(b) The ant'icipated response of the equipment is adequately I
representdd by one mode.
(c) The input has sufficient intensity and duration to excite all modes to the required magnitude, such that the testing response spectra will envelope the corresponding response spectra of the ded'vidual modes.
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6.
The input motion should be applied to one vertical and one principal (or two orthogonal) horizontal axes simultaneously i
unless it can be demonstrated that the equipment response along the vertical direction is not sensitive to the vibratory
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motion along the horizontal direction, and vice versa. The time phasing of the inputs in the vertical and horizontal direc-tions must be such that a purely rectilinear resultant input is avoided. The acceptable alternative is to have vertical and horizontal inputs in-phase, and then repeated with inputs 180 degrees out-of-phase.
In addition, the test must be repeated with the equipment rotated 90 degrees horizontally.
7.
The fixture design should meet the following requirements:
(a) Simulate the actual service mounting (b) Cause no dynamic coupling to the test item.
I 8.
The in-situ application of vibratory devices to superimpose the seismic vibratory loadings on the complex active device for operability testing is acceptable when application is justifiabic.
9.
The test program may be based upon selectively testing a repre-sentative number of mechanical components according to type, load 1evel, size, etc. on a prototype basis, f
II.
Seismic Design Adequacy of Supports 1.
Analyses or tests should be. performed for all supports of electrical and mechanical equipment and instrumentation to ensure their structural capability to withstand seismic excitation.
~
2.
The analytical results must include the following:
f (a) The required input motions to the mounted equipment should be obtained and characterized in the manner as stated in Section I.2.
(b) The combined stresses of the support structures should be within the limits of ASME Section III, Subsection NF -
" Component Support Structures" (draf t version) or other comparable stress limits.
3.
Supports should be tested with equipment installed.
If the equipment is inoperative during the support test, the response at the equipment mounting locations should be monitored and characterized in the manner as stated in Section I.2.
In such a case, equipment should be tested separately and the actual input to the equipment should be more conservative in amplitude and frequency content than the monitored response.
4.
The requirements of Sections I.2, I.4, I.5, I.6 and I.7 are applicable when tests are conducted on the equipment supports.
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Responsible TR Branch and Technical Reviewer: MEB, F. Cherny, P. Chen d4 l
Requested Completion Date 9/13/74 i'f :
Description of Responses. Draf t Q-1 Review of FSAR h
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'f of the Senadmed Format (Ragalatory Guide 1.70) dated October
, 1972.. Staae the WRF - 3 and 5 PSAR references CESSAR, only.
,O non-CESSAR portions of these sections have been reviewed.
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Positions and areas in which additional information is required 1
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.l-11.0 MECHANICAL ENGINEERING 110.1 Under 3.6.2.1.4(a) piping systems having an internal pressure of f
(3.6.2.1) up to 275 psia and fluid tenperatures not in excess of 200*F are j
excluded from pipe break criteria. This is not consistent with l
Regulatory Guide 1.46 nor the present MEB position. The present j
MEB position is that through wall leakage cracks should be i
postulated for such piping as delineated in Attachment A which is generally applicable for piping outside the containment.
i 110.2 PSAR states that criteria for postulating pipe breaks for (3.6.2.2) piping outside the containnent will be per AEC letter from
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J. O' Leary of 7/12/73.
This is acceptable, however, imple-mentation of this criteria should be as contained in Attachment I
A.
110.3 (1) Provide loading combinations and stress criteria for (3.6.3.1) normal, upset, and emergency conditions for Class 1, 2 and 3 piping in the A/E - BOP scope.
i (2) Provide more specific criteria than "per code" for faulted condition stress criteria for Class 1 piping.
For example, i
ASME Section III permits the use of Appendix F of the code for faulted conditions; but, does not require it.
State specifically what is to be used.
(3) Provide specific design details for the three types of piping penetration guard pipes. Also discuss the access provisions to carry out inservice inspection of the flued head to process pipe welds for the Type I and III penetrations.
110.4 (1) Identify the computer p'rogran to be used for the calculation (3.6.4.1) of postulated pipe break and if the program is not widely used in the nuclear industry, provide justification for its applicability and validity for this type of analysis.
(2) In the conputation of the thrust force using the simplified i
forcing function, justify the use of P in lieu of P i
sat o
[
for compressed (flashing) or saturated water.
110.5 (1) For unchoked flow, the Regulatory staff will accept use of (3.6.4.2) a model with a uniform half angle of dispersion not exceeding 10'.
(2) In calculating jet impingement force as described in Eq. (1),
the definition of the velocity ratio Um is not clear.
Current MEB position requires that the steady state forcing function for jet impingement should have a magnitude (T) not less than swu 7
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<3 11-2 110.5 T = C'A (3.6.4.2) l Where P = system pressure prior to pipe break A = pipe break area, and K = thrust coefficient.
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- f (3) For choked flow, provide justification for the following assumed angles of dispersion for the jets:
,l Flashing water - 45' Steam
- 22' Non-Flashing Water - 25*
,i and clarify the pressure that is going to be used for calculating jet force.
(4) Define the symbols for calculating the jet impingement forces as given in cases A, B, C and D.
In those formulas, explain the missing pressure force component.
i (5) For the calculation of the Drag Force (Case C) expand the discussion to include a broader range gf Reynolds numbers 3 to 10 given.
j other than the range of R,= 10 l
110.6 (1) The information presented in this section of the PSAR does (3.9.1.1) not satisfy the requirements concerning "Seismih Category I Mechanical Equipment Testing and Analysis - C.E. Scope of Supply" for plants currently undergoing review, Provide the appropriate commitments from CESSAR.
(2) Clarify type of operating experience to be used to verify that equipment will operate under SSE conditions.
(3) Provide commitment that all Category I mechanical equipment and supports will be qualified to requirements of specifi-l c,ations 7-74 in Appendix 3.9.A.
(4) In paragraph 3.02 d of Appendix 3.9.A, when using the Response Spectrum Modal Analysis method, provide criteria for determining closely space modes.
(5) In Appendix 3.9.A, paragraph 3.02.e permits an allowable stress of 0.9 of the material yield stress for faulted conditions.
This is not consistent with limits stated per Table 3.9.3 of the PSAR. Revise the Appendix to conform with Table 3.9.3.
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4 11-3 j
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110.7 The seismic qualification program described.in this section is (3.9.1.2) not totally acceptable.
Revise the program to be in accordance (3.10) with criteria provided in Attachnent B " Electrical and Seismic Qu'lification Program."
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110.8 (1) In the last sentence of Part I of Appendix 3.9.B change (3.9.2.4)
"will" to "may".
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(2) In Section II of Appendix 3.9.B expand the valve operability t
testing criteria to includ2 the valve design pressure.
(3) In Section II of Appendix 3.9.B under criterion d state the Qualification Standards to be employed.
(4) In Appendix 3.9.B define the horizontal and vertical accelerations to be used for static valve qualification.
(5) In Appendix 3.9.B Section II, your position that for valves with natural frequencies less than 33 Hz operability can be verified without performing valve exercising per step C requires justifiestion.
110.0 Provide more specific equa.t19ns of motion and discuss methods (3.9.2.5) of solution for the dynamic analysis for open and closed systens.
110.10 The information provided in this section is not adequate.
In (3.9.2.7) addition to the nominal pipe size which determine whether ASME (5.2.19)
Class 2 and 3 piping will be field run, identify in the PSAR those Category I piping systems which will be field run.
Include any special or simplified procedures which will be used for designing.and installing this piping.
110.11 Provide the specific criteria that will be used to guarantee (3.10.2) operability of instrumentation.and electrical equipment, not 1
furnished by C.E., under faulted conditions when a dynamic analy' sis without performance testing is employea in the design of this equipment.
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Attact.sent A i
BRANCH TECE:ICAL POSITION-ME3 NO. 1 MECHANICAL E::GINEERI::G SEl.NCH DIRECT 0MTE OF LICE::SI: 0 CRITERIA FOR j
POSTL' LATED FAILURE AND LEAKAGE LCCNrIONS IN FLUID SYSTCi ?I?I: r; OUTSIDE C0::Tal:::!E'E
'l The following criteria are within the review responsibility of the
?-
l Mechanical Engineering Branch with the exception of I.A., II.A., II.D.,
II.E and 1.a.,1.b.,1.c., 2.a and 2.c. (3) of Appendix A.
1.
Righ-Energy Fluid Susta IPtninc
- A.
Fluid Systems Separated fran Eaaential Structures, Systemt 4 Components
+
For the purpose of satisfying the separation provisions of 1.a.
{
of Appendix A, a review of the piping layout and plant arrangement drawings should clearly show that the effect:s of postulated piping
- breaks at any location are isolated or pbysically remote froci taaeniial atr$tatures, syste.:3, 2:!coqootents.
At the designer's option, break locations as. determined from I.C.,
I.D,, and I.E 4
below may be selected for this purp.se.
B.
Fluid System Piping Between Containment Isolation Valves
[
Breaks need not be postulated in those portions of piping i
identified in 2.C.(1) and 2.C.(2) of Appendix A provided they meet the requirements of AS:!E Code,Section III - Subarticle NE-1110 and are designed to meet the following additional requirements:
1/-SeeClossaryfordefinitionsofitakicizedphrases.
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The following design stress and f atigue limits should not be
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exceeded; For ASME Code,Section III. Class 1 Piping ej j
(a) Maximum stress ranges should not exceed the following limitst Ferritic steel
< 2.0S m
Austenitic steel < 2.4S.
l l
(b) The maximum stress range between any two load sets (including the zero load set) should be calculated by Eq. (10) in Par. NB-3653, ASME Code,Section III, for upset plant conditions and an OBE event transiant.
If the calculated maximum stress range of Eq, (10) exceeds the limits of I.B.1(a) but is not greater than 3S,, the limit of I.B.l(c) should be met.
If the calculated maximum stress range of Eq. g(10) l exceeds 3S, the stress, ranges calcula:ed by both m
Eq. (12) and Eq. (13) should meet the limits of I,3.1(a) and the limit of I.B.1(c).
(c) Cumulative usage factor < 0.1, as required by I.B.l(b).
i For ASME Code.Section III, Class 2 Piping Maximum stress range as calculated by Eq. (9) and (10) in Par. NC-3652, ASME Code,Section III, considering upsst plant conditions (i.e., sustained loads, occasional loads, and thermal 6
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2.
Welded attachments, for pipe supports or other purposes, to j
these portions of piping should be avoided except where detailed
,j stress.snalyses, or tests, are performed to demonstrate complianc.e with the limits of I.3.1 3.
The number of piping circumferential and longitudinal welds i
and branch connections should be minimized.
4.
The length of,the pipin'g run should be reduced to the minimum length practical.
5.
The design at points of pipe fixity (e.g., pipe anchors or welded connections at containment penetrations) should not require welding directly to the outer surface of the piping (e.g., fluid integral forged pipe fittings may be used) except where detailed stress analyses are performed to demonstrate compliance with the limits of I.B.1.
6.
Geometrie discontinuities, such as at pipe-to-valve section transitions, at branch connections, and at changes in pipe wall thickness should be designed to minimize the discontinuity i
stresses.
C.
Fluid syste.ms Enclosed Within Protective Structures 1.
Breaks in ASME Code,Section III, Class 2 and 3 piping should L
1/rne limit of o.sct.2 s; + s,) may de used in lieu of (s; + s ).
3
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be postulated at the following locations in each piping and branchrun(exceptthoseportionsoffluidsystempiping identified in I.B.) within a prot'ective structure containing
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essentict systems and components and designed to satisfy the i
i provisions of 1.b. or 1.c. of Appendix A:
a.
At tennincI ends of the. pressurized portions of the run if located within the protective structure.
t b.
At intermediate locations selected by either of the following criteria:
(i)
At each pipe. fitting (e.g., elbow, tee, cross, and non-standard fitting) or, if the run contains no fittings, at one location at each extreme of the run (a ten: inst end, if located within the protective structure may substitute for one intermediate break).
(ii) At each location where the stresses / exceed (Sh 3
c but at not less than two separated locations chosen on the basis of highest stress /
In the case of a straight 4
pipe run without any pipe fittings or welded attach-4 ments and stresses below (Sh + S )' " i"i "* f ""
c location chosen on the basis of highest stress.
3/
-- Stresses associated.with normcl and upset plant conditions, and an OBE event as calculated by Eq. (9) and (10), Par. NC-3652 of the ASME Code,Section III, for Class 2 and 3 piping 4/
-- Two highest stress points; select second point at least 10% below the highest stress.
4
2.
Breaks in non-nuclear class piping should be postulated at the following locations in each piping or branch run:
i' At ter7inal ends of the pressurized portions of the run if a.
located within the protective structure.
I b.
At each intermediate' pipe' fitting and welded attach =ent.
D.
Fluid Systens Not Enclosed Within Protective Structures 1.
Breaks in ASME Code,Section III, Class 2 and 3 piping, should be postulated at the following locations in each piping and branch run (except those portions of fluid system piping identified in I.B) outside but routed alongside, above, or below a protective structure containing essenticI systems qnd components and designed to satisfy the provisions of 1.b, or 1.c of Appendix A.
At terminal ends of pressurized portions of the run if a.
located adjacent to the protective structure.
b.
At intermediate locations selected by either of the following criteria:
(i)
At each pipe fitting (e.g., elbow, tee, cross, and non-standard fitting).
(ii) At each location where the stresses 2! exceed (Sh c
but at not less than two separated locations chosen on the basis of hi'g' est stress /
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straight pipe run without any pipe fittings og l'
welded attachr.ents and stresses below (Sh*#)'*
c ginimum of one location chosan on the basis of q
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highest stress.-
l 2.
Breaks in non-nuclear class piping should be postulated at the following locations in each piping or branch run:
l At e.erminal ends of pressurized portions of the run 'if a.
located adjace.nt to the protective structure.
b.
At,each intermediate pipe fitting and welded attachment,
- 11. Moderate-Ener:p Fluid Suorem Picing A.
Fluid Systems Separated froa Esaential Structures, fyctems &
Componenta For the purpose of satisfying the separatibn provisions of 1.a. of Appendix A, a review ot the pipfng laycut and plant arkengement drawings should clearly shov that the affects of through-wall leakage cracks at any location are isolated or physically remote 4
from essentiai atructures, ayatems, and components.
B.
Fluid System Piping Between Containnent Isolation Valves Breaks need not be postulated in those po tions of piping identified in 2.c. of Appendix A provided they meet tile requirements of AS:1E Code,Section III - Subarticle NE-1110, and are designed such that the stresses do not exceed 0.5(Sh * # )5/
f r AS!!E code,Section III, c
Class 2 piping.
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C.
Fluid Syste s tiithin cr Vutsid$ and Adjacent to Protective Structures Through-wall leakaga cracks shonid be postulated in fZuid tystdn piping located nthir. or outside end adjacent to protectiva structures enntaining essential systene 2nd corr.ponente and deaigned t.o satisfy the pro risions of 1.b.
or 1.c. of Apper.lix A, except whste exempted by II.B. II.D, or in those portions of A9fE Code, Sectio 6 III, C1 css 2 or 3 pipin,g or non-nacicar piping where the stresses ar6 less than 0.3(Jh*#)
The r.rsckg should te postulated to occur c
individually at. 3petticos that Iasult in che :naximum eff er.ts from fluid sp sying and flooding, and the conscquent basards I
or eAvirc u::ent al ;ond,itisac deve'.oped.
D.
Modcrate<Enagy Thid S,ustama in l'roxist?.y to High-incrgy fluid Syste:s Cracks need not be p6st.ulated in f.ederste-energy fluid syctan piping locace.d in an area in which a break in high-energy f*uid system p.iping is postulated, provided such cracks would not result in more limiting environmental conditiene than the high-energy piping break.
tihere a postulated leakage crack in the moderate-endtgy fIaid systcm piping results in core limiting environcental conditions than the break in proximate high-energy fluid systen piping, tha previsions of II.C should be applied.
E.
Fluid Systems qualifying as High-Energy or Mcderate-Energy Systems Through-wall leakage cracks instead of breaks may be postulated
.m s
inthepipingofthosef!uidsyst:msthatqualifyashighEnergy f7uid systcis for only short operational periodsb but qualify as moderate-energy fluid systems for the major operational period.
III.
Type of Breaks and Leskage Cracks in Fluid Systre Piping A.
Circunferential Pipe Breaks 3%e following circumferential breaks should be postulated in high-energy fluid system piping at the locations specified in Section I above:
1.
Circumferential bfeaks should be postulated in f7uid systen piping and branch runs. exceeding a nominal pipe size of 1 inch, except that, if the maximum stress range in the circumferential direction is at least twice that in the axial direction, only a longitudinal break need be postulated.
Instrument lines, one inch and less nominal pipe size for tubing should meet the provisions of Regulatory, Gdide 1.11.
2.
Where break locations are selected at pipe fittings without the benefit of stress calculations, breaks should ~ be postulated at each pipe-to-fitting weld.
If detailed stress analyses i
a 6/
-- An operational period is considered "short" if the fraction of time that the system operates within the pressure-temperature conditions specified for high-energy fluid systems is less than 2 percent of the time that the system operates as a moderate energy f7 aid system (e.g., systems such as LSe reactor decay heat removal systems qualify as ecderate-energy fluid systcas; however, systems'such as auxiliary feedwater systems operated during P'4R reactor startup, hot standby, or shutdown qualify as high-energy fluid systems).
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s (e.g., finite eleaent analyses) er tests are perfor=ed, the maximum stressed location in the fitting may be selected instead of the pipe-to-fitting weld.
.f 3., Circumferential breaks should be assumed to result in pipe severance and separation amounting to a.one-diameter lateral displacement of the ruptured piping sections unless physically limited by piping restraints, structural members, or piping stiffness as may be demonstrated by inelastic limit analysis (e.g., a plastic hinge in the piping is not developed under loading).
4.
The dynamic force of the jet discharge at the break location should be based on the effective cross-sectional flow area of the pipe and on a calculated fluid pressure as modified by an analytically or experimentally determined thrust coefficient. Limited pipe displacenent at the break location, line restrictions, flow limiters, pcsitive punp-controlled
~
flow, and the absence of energy reservoirs may be taken into
'I account, as applicable, in the reduction of jet discharge.
5.
Pipe whipping should be assumed to occur in the plane defined by the piping geometry and configuration, and,to cause pipe movement in the direction of the jet reaction.
B. " Longitudinal Pipe Breaks The following longitudinal breaks should be postulated in high-anargy fluid system piping at the locations of each circusferential break specified in, III.A. :
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Longitudinal break in fluid sys:cm piping and branch runs should be postulated in nemical pipe sizes 4-inch and larger, except that, if the max 1;um stress range in the axial direction is at least twice that in the circumferential direction, only a circumferential break need be postulated.
.2. Longitu:linal breaks need not be postulated at terminal ends if the piping at the terminct onds contains no longitudinal pipe i
welds and major geometric discontinuities at the circumferential weld joints of the terminal ends are designed to minimize dis-continuity stresses.
3.
Longitudinal breaks should be assumed to result in an axial split without pipe severance.
Splica should be located (but not concurrently) at two diametrically-opposed points on the piping circumference such that a jet reaction causing out-of-I plane bending of the piping' configuration results.
4.
The dynamic forca of the fluid jet discharge should be based on a circular or elliptical (2D x 1/2D) break area equal to the effective cross-sectional flow area of the pipe at the 4
break location and on a calculated fluid pressure modified by an analytidally or experi=entally determined thcust coefficient as determined for a circumferential break at the same location.
Line restrie.tions, flow limiters, positive pump-controlled flow.
and the absence of energy reservoirs may be taken into account, as applicable, in the reduction of jet discharge.
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5, Piping covement should be assumed to occur in the direction of the jet reaction unless limited by structural members, piping restraints, or piping stiffness as demonstrated by inelastic limit analysis.
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Through-Wall Leakage Cracks i
The following through-wall leakage cracks should be postulated in moderate-energy fluid syscem piping at the locations specified in Section II above:
1.
Cracks' should be postulated in moderate-energy fluid systen piping.and branch runs exceeding a nominal pipe size of 1 inch.
2.
Fluid flow from a crack should be based on a circular opening of area equal to that of a rectangle one-half pipe-dia=eter,in length and one-half pipe wall thickness in width.
3.
The flow from the crack,should be acsuced to resu'1c in an environment that wets all unprotected compenents within the compartment, with consequent flooding in the compartment and communicating compartments.
Flooding effects may be determined on the basis of a conservatively-esti=ated time period required to effect corrective actions.
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APPENDIX A PLANT ARRANGEMENT CRITERIA AND SELECTED PIPINC DESIGN TEATURES 1.
Plant Arrangement j
Protection of essential structures, systema, and components against postulated piping failures in high or moderate energy fluid cystema that operate during normal plant conditions and that are located out-side of containment should be'provided by one of the following plant arrangement coc.siderations:
Plant arrangements should separate fluid system pipin5 from 4.
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. essential structurcs, systems, and components.
Separation sivuld be achieved by plant physical layouts that provide sufficient distan:es between escential structures, systens, and componente and fluid Jystem piping such that the effects of any postulated piping failure therein (i.e., pipe' whip, jet impin:;ement, and the environmental conditions resultin3 from the escape of contained
~
fluids an appropriate to high or madarate-energy fluid system piping) cannot impair the integrity or operabi.'.ity of essential str:ustures, systems, and compcnents.
b.
Fluid syster piping or portions thereof not sat.sfying the provisions of 1.a. above should be enclosed within.1tructures or compartments designed to protect l2earby est;ential structures, systems, and comycnents.
Alternatively, esas.nti:t systans and 9
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components may be enclosed within structures or compartments designed, to withstand the effects of postulated piping failures in nearby f!uid systems.
Plant arrangements or system features that do not satisfy the c.
4 i
provisions of either 1.a. or 1.b. above should be limited to those for which the above provisions are impractical.
Such
~
cases may arise, for example, (1) at interconnections between fluid systems and essential systems and components, or (2) iit fluid systems having dual functions (i.e., required to operate during normal plant conditions as' well as to shut down the reactor).
/
In such cases, redundant design features, separated or otherwise protected from effects of postulated piping failures, or additional
- protection should be provided so that reactor shutdo m is assured in the event of a failure in the interconnecting piping of (1),
or in the dual function piping of (2). Additional protection may be provided by restraints and barriers or by designing or testing assential systems and components to withstand the effects associated uith postulated piping failures.
I 2.
Design Features Essential systems and components should be designed to meet the a.
seismic design requirements of Regulatory Guide 1.29.
l b.
Protective structures or compartments, fluid system pi;,ing restraints, and other protective measures should be designed in l
accordanc'e with the following:
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(1) Protective structures or compartments needed to implement 4
1.b. or 1.c. above should be designed to Seismic Category I requirements.
The effects of a postulated piping failure
.{i.e., pipe whip, j et i=pingement, pressurization of compart-i ment, water spre.y. and flooding, as appropriate) in combination with loadings associated with the Safe Shutdown Earthquake and normal operation should be used for the design of required protective structures.
Piping restraints, if used, may be taken into account to limit effects of the postulated piping failure.
(2) High-energy fluid system piping restraints and protective measures should be designed such that the effects of a postulated break in one pipe cannot, in turn, rupture other' nearby pipes or components which could result in unacceptable offsite conseque'nces or in loss of capability of essential systems and' components.co initiate, actuate, and complete actions required for reactor shutdown.
c.
Fluid system piping between containment isolation valves should meet the following design provisions:
1/ n the design of piping restraint, an un' restrained whipping pipe I
should be considered capable of (a) rupturing impacted pipes of scaller nominal pipe sizes and (b) developing a through-wall leakage crack in larger nominal pipe sizes with thinner wall thicknesses except where experimental or anal'ytical data for specific impact energies de=onstrate the capability to withstand the impact without failure.
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(1) Pertions of juid sysicm piping between isolation valve's
'f of',singlebcIriercontainmentstructures(includingany t
rigid connectio'n to the contain=en't penetration) that connect, s
on a continuous or intermittent basis to the reactor coolant pressure boundary or the steam and feedwater systems of PWR
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plants should be designed to the stress limits specified in~
I.B. or II.'B. of this document.
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i These portions of high-energy fluid system piping should be V
provided with pipe whip restraints (i.e., capable of resisting bending and torsidnal moments). located reasonably close to the containment isolation valves.
The rcitraints should be designed to withstand the loadings resulting from a postulated piping failure beyond these portions of piping so that neither isola:: ion valve operability nor the leaktight integrity of the containment will be impaired.
Terminct ende of the piping runs,outside containment should be-T considered to originate at the pipe whip restraint locations outside containment.
~
Where containment isolation valves are not required inside containment, those portions of the fluid system piping extending from'the outsidc' isolation valve to either the rigid pipe connection to the containment penetration or the first pipe 4
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.3 whip restraint inside contain=ent should be considered as the, boundary of the system piping required to ceet the above design limits and restraint provisions.
(2) Portions of f?uid system piping between isolation valves of
-1 dual barrier containment structures should not exceed the stress limits in I.B. or II.B. of this document. These portions of high-energy fluid system piping that pass through the annulus, and whose failure could affect the leaktight integrity of the contain=ent structure or re,sult in pressur-ization of the andulus beyond design limits, should be provided with pipe whip restraints (i.e., capable of resisting bending and torsional coments) located reasonably close to the containment isolation valves and should be provided with an.
enclosing structure or guard pipe. Restraints should be designed to withstand the loadings resulting from a postulated piping failure beyond these portions of piping so that neither isolation valve operability nor the leaktight integrity of the -
1.
l associated containment penetration will be impaired.
Tenninal ends of the piping runs outside containment should be considered to originate at the pipe whip restraint locations outside containment.
For the purpose of establishing the design parameters (e.g.,
pressure, temperature, axial loads) only of the enclosing G
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structure or guard pipe.
(3) For those portions of fluid system piping identified in 2.c. (1) and 2.c. (2) above, the extent of inservice examination conducted as specified in Division 1 of Section XI of the ASME Code during each inspection interval should be increased to l
provide volumetric extmination of 100 percent of the circum-farential and longitudinal weld joints in piping identified in Section III.A.l. and Section,III.B.l. of this document.
The areas subject to examination should comply with the require-ments of the following categories as specified in Section XI of the ASME Code:
(a) ASME Class 1 piping welds, Examination Category B-J in 4
Table IWB-2500.
(b) ASME Class 2 piping welds, Examination Category C-F and C-G in Table IWC-2500.
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GLOSSARY Essca. tic! Strat:ecs. Fystc s, ad Cc ronents.
Structures, systems, and components required for reactor shutdown without off-site power or to mitigate the consequences of a postulated piping failure in fluid
{
system piping that results in trip of the turbine-generator or the i
FZuid Suste s.
High and moderate energy fluid systems that are subject to the postulation of piping failures against which protection of essential structures, systems, and components is needed.
High-Energu Fluid Systems.
Fluid systems that, during normal plant conditions, are either in operation or maintained pressurized under conditions where either or both of the following are met:
a.
maximum operating temperature exceeds 200*F, or
- b. ' maximum operating pressure exceeds 275 psig.
Moderate-Fner;p ?!uM Systems.
Fluid. systiems that, during nor al plant O
conditions, are either in operation or maintained pressurized (above atmospheric pressure) under conditions where.both of the following are t
met:
I s.
maximum operating temperature is 200*F or less, and b.
maximum operating pressure is 275 psig or less.
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Norect P!cnt C v.iirirns.
Plant operating conditions during reactor -
startup, operation at power,' hot standby, or reactor cooldown to cold shutdown condition.
Upset Plcnt Canditions.
Plant operating conditions during system transients that may occur with moderate frequency during plant service life and are anticipated operational occurrences, but not during system testing.
Postulated Pir 'nc Fci!:ess.
Longitudinal and circumferential breaks in high-energy f2 aid system piping and through-wall leak' ge cracks in a
moderate-energy fluid system piping postulated according to the provisions of this docu=ent.
S S. cnd S.
Allowable stresses at maximum (hot) temperature, at p
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minimum (cold) temperature, and allowable stress range for thermal expansion respectively, as defined in Article NC-3600 of the ASME Code,Section III.
- i. Design stress intensity as defined in Article NB-3500 of the ASME Code,Section III.
Sincle Active Ccrrenent FciIare.
Malfunction or loss of function of a component of electrical or fluid systems.
The failure of an active component of a fluid cystem is considered to be a loss of component function as a result of mechanical, hydraulic, pneumatic, or electrical malfunction, but not the loss of component structural integrity.
The direct consequences of a single cative component failure are considered to be part of the' single failure.
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Extremeties of piping runs that connect to structures, components (e.g., vessels, pu=ps, valves), or pipe anchors that act as rigid constraints to piping ther=al expansion.
A branch connection to
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l a main piping run is a terminal end of the branch run.
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12/5/73 1
Attachment B
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EI.ECTRICAI..V!D MECE.O!!CAI. EQUIPMEYr SEISMIC QUALIFICATION PROCPJ.M I.
Seismic Test for Eculotant Oserability 1.
A test program is required to confirm the functional operability of all Seismic Cate;ory I electrical'and mechanical equipment and instrumen:ation during and af ter an earthquake of magnitude up to and including the SSE.
Analysis without testing =ay be acceptable only if s:ructural integrity alone can assure the design intended function. When a complete seismic testing is
~
impracticable, a combination of test and analysis may be accept-able.
2.
The characteristics of the required input motion should be specified by one of the following:
(a) response spectrum (b) power spectral density function (c) time history Such characteristics, as derived from the structures or systems seismic analysis, should be representative of the input motion at the equipment mounting locations.
3.
Equipment should be tested in the operational condition. Oper-ability should be verified during and after the testing.
4.
The actual input motion should be characterized in the same manner as the required input motion, and the conservatism in amplitude and frequency content should be demonstrated.
5.
Seismic excitation generally have a broad frequency content.
Random vibration input motion should be used. However, single frequency input, such as sine beats, may be applicable provided one of'the following conditions are met:
I (a) The characteristics of the required input motion indicate that the motion is dominated by one frequency (i.e., by structural filtering effects).
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(b) The anticipated response of the equipment is adequately l'
represented by one mode.
l (c) The input has sufficient intensity and duration to excite l
all modes to the required magnitude, such that the testing response spectra will envelope the corresponding response j
spectra of the individual modes.
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6.
The input =ction should be applied to one vertical and one principal (or two orthogonal) horizontal axes simultaneously unless it can be demonstrated that the equipment response along the vertical direction is not sensitive to the vibratory motion along the horizontal direction, and vice versa. The time phasing of the inputs in the vertical and horizontal direc-tions must be such that a purely rectilinear resultant input is avoided.
The acceptable alternative is to have vertical and horizontal inputs in-phase, and then repeated with inputs 180 degrees out-of-phase.
In addition, the test must be repeatsd with the equipment rotated 90 degrees horizontally.
7.
The fixture design should meet the following requirements:
1 1
(a) Simulate the actual service mounting i
(b) Cause no dynamic coupling to the test item.
i i
8.
The in-situ application of vibratory devices to superimpose the seismic vibratory loadings on the complex active device for operability testing is acceptable when application is justifiable.
9.
The test program may be based upon selectively testing a repre-j sentative number of mechanical components according to type, load level, size, etc. on a prototype basis.
II.
Seismic Design Adecuacy of Supports 1.
Analyses or tests shou'ld be performed for all supports of electrical and mechanical equipment and instrumentation to ensure their structural capability to withstand seismic excitation.
2.
The analytical results must include the following:
(a) The required input motions to the mounted equipment should be obtained and characterized in the manner as stated in Section I.2.
(b) The combined stresses of the support structures should be within the limits of ASME Section III, Subsection NF -
" Component Support Structures" (draf t version) or other comparable stress limits.
3.
Supports chould be tested with equipment installed.
If the equipment is inoperative during the support test, the response at the equipment mounting locations should be monitored and characterized in the manner as stated in Section I.2.
In such a case, equipment should be tested separately and the actual input to the equipment should be more conservative in amplitude and frequency content than the monitored response.
4.
The requirements of Section.s I.2, I.4, I.5, I.6 and I.7 are applicable when tests are conducted on the equipment supports.
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