ML20198F782
| ML20198F782 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 06/06/1974 |
| From: | Cox T US ATOMIC ENERGY COMMISSION (AEC) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0979, CON-WNP-979 NUDOCS 8605290088 | |
| Download: ML20198F782 (21) | |
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2 JUN 6 274 DOCKET NO.: 50-460 APPLICANT : WASHINGTON PUBLIC POWER SUPPLY SYSTE:t (WPPSS)
FACILITY : WASHINGTON NUCLEAR ONE (WNP-1)
SU19fARY OF MEETING HELD ON MAY 24, 1974 TO DISCUSS DESIGN CRITERIA FOR HIGH ENERGY FLUID LINES On May 24, 1974, representatives of WPPSS, Babcock & Wilcox, United Engineers and Constructors (UE&C), and the Regulatory staff met in Bethesda, Maryland to discuss the subject design criteria. Enclosure 1 is an attendance List for this meeting. The meeting was conducted in accordance with a previously prepared agenda, included as Enclosure 2.
At the conclusion of the meeting, the applicant agreed that their response to all issues raised at the meeting would be documented in
'a future PSAR amendment scheduled for submittal on July 8,1974.- In addition, a letter submittal by June 24, 1974 will transmit the same material. The earlier tubmittal (approximately two weeks prior to July 8) is intended to maintain adherence to the currently established staff review schedule.
The taeeting discussion centered on criteria for the postulated rupture of piping, for piping located both inside and outside of the containment barrier. The special requirements for piping through the primary containment penetrations and the reactor coolant loop piping were also considered.
R. R. Maccary, Directorate of Licensing, made several introductory remarks concerning the history of the staff development of criteria for protection against postulated piping failures. Regulatory Guide 1.46,
" Protection Against Pipe Whip Inside Containment", was published in May 1973. Criteria for lines outside contain:nent were provided to the industry in special consnunications in December 1973 and July 1973.
More recent studies by the staff are expected to result in a new Regulatory Guide, Protection Against Postulated Piping Failures in Fluid Systems outside Containment". This Guide is not yet issued, but a preliminary draf t has been available to the public since approximately March 15, 1974.
In. addition, Appendix A to this Guide, titled, " Postulated Break and Leakage Locations in Fluid System Piping Outside Containment",
has been revised as of April 19, 1974, and copies of this revised Appendix A (Enclosure 3 to this su= mary) were given to the applicant at this meeting.
The following paragraphs summarize staff and applicant discussion of specific acenda items:
8605290088 740606 PDR ADOCK 05000460 A
. la. WPPSS representatives agreed to follow Regulatory Guide 1.46 in detail for postulating break locations and orientations in high energy fluid lines inside containment, with the possible exception of the reactor coolant piping. The exception arose from staff commments that modifications to the positions stated in 1.46 might be acceptable for reactor coolant piping if sufficient detailed bases are provided to show that an equiv-alent degree of protection is provided. WPPSS elected to consider this aspect of the application of Regulatory Guide 1.46 further before replying.
Ib.
WPPSS will delete their reference to a 50% strain limit in a broken, whipping pipe, eliminating confusion over the claimed load capacity of and load transmitted by the broken pipe. In
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Section 3.6.3.1(b) of the PSAR, the applicant will modify the last two statements to clarify the intent of the material regarding applied moments.
ic. The applicant will modify the written material on page 3.6-7, Section 3.6.4.1.1 to more clearly indicate the intent to comply with the requirement that the Operating Easis Earthquake be included in the conditions used to postulate break locations.
Id.
WPPSS will modify their presentation of the postulated break location criteria.to agree with those specified in Enclosure 3.
le. UPPSS will include in the PSAR their intention to use flued integral forged pipe fittings on containment penetration piping, which design approach obviates staff concerns about welding directly to the piping surface.
2.
WPPSS plans to use the 10 CFR 50 definition of isolation valves, and will clarify the definition of the boundaries between which no breaks in piping are postulated.
3.
WPPSS will modify Figure 3.6-1 to clarify the postulated break location.
4.
In conjunction with this agenda item, the staff supplied to the applicant at this meeting. The applicant will, af ter consideration of this enclosure, reply in a future Iceter and amendment, as stated earlier in this summary.
d.
3-5.
The applicant will modify the PSAR Section 3.6.6 to specifi-cally discuss or reference all those design considerations intended to be applicable to postulated piping breaks outside containment.
6.
The technical substance of this item will be addressed by the applicant in response to agenda Item 1, and PSAR Section 3.12 will be modified as appropriate.
05(ser sige.g my Thomas H. Cox, Project Manager Light Water Reactors Branch 2-3 Directorate of Licensing
Enclosures:
1.
List of Attendees 2.
Meeting Agenda 3.
Appendix A. " Postulated Break...
Outside Containment", 4/19/74 DISTRIBUTION:
LPDR LWR 2-3 Rd& ding L Reading RP ads RP BCs SVarga DEisenhut l
JHendrie TR Es TR BCs RLoose TCox DKartalia EGoulbourne AMiller RMaccary JKnight ACRS (16) x7886/ LWR 2-3 oP PtC.,
TH.Cox h su mm a ns. >
. 615 /74 Focus AEC 318 (Rev. 9 53) AECM O240
- u. s. oovgmqMEnf PmtM7tMe oPPtCEt 5974 92616e
ENCLOSURE 1 MEETING WITH WASHINGTON PUBLIC POWER SUPPLY SYSTEM i
WASHII;GTON NUCLEAR ONE MAY 24, 1974 LIST OF ATTENDEES Atomic Energy Commission R. R. Maccary J. P. Knight T. H. Cox A. B. Miller Babcock & Wilcox S. K. Brown J. W. Minarick K. E. Suhrke W. R. Rhyne R. C. Luken Washington Public Power Supply System A. G. hosler C. L. Fies United Engineers & Constructors W. Moritz-A. J. Friedman J. R. Schmieder J. Dainora R. W. Barton r
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ENCLOSURE 2 Froposed Meeting 4,enda C P Fostulated Pipe Breaks 3.0 Desien of Structures, Cv.:3cnents, L3ui,.- ent an.1 Sys:tems 3.6 Protectic1 '..:a t.wt Dvr.2 tic Ef fects Acaat tated with tha Postulcted Ruoturc of Piping 1.
The d:: sign criteria presented in PS.ut 5.6 do not specifically
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confers to criteria acceptable to the ataf f'in a number of detalls.
It is required that the applicant either =odify the criteria
. appropriately or provida technical justification for tha apparent differecces. The principla areas of dif ference are tha following:
(a) Criteria for postulating break locations and oriantations in high energy fluid lines inside containment.
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- (b) Procedures for determining load capacity of pipe following a i
postulated break and the load which can be trans=itted to an anchor point.
(c) 1ssumption of operating condition prior to a postulated break in design of restraints.
(d) Criteria for postulating break locations in high energy lines outside containment but within an enclosing structure or compartment as con,rered with auch critaria fo-lines routed alon:sida. above, o.c below such structures ac.d comparteants.
(c) The avoi-lance of dent:;n feature, capecially at potats of pipa fi::i ty, that would require waldi ; dirc:fti'; to J:a outer surfaca of tiu piping.
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4.
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ENCLOSURE 3 APPENDIX A-POSTULATED BREAK AND LEAKAGE LOCATIONS IN FLUID SYSTEM PI?ING OUTSIDE CONTAINNENT T.
High-Energy Fluid Sustem Piping A.
F1.uid Systems Separated from Essential Structures, Systems d Components For the p u rp os e of satisfying the separation provisions of C.1.a, a review of the piping layout and plan t arrangement drawings should clearly show that the effects o f postulated piping breaks at any location are isolated or physically remo te from essential structures, sys tems, and components.
Optionally, breaks locations as determined by I.C.,
I.D.,
and I.E.,
may be selected for this purpose.
B.
Fluid Systems Piping Between Containment Isolation Valves Tho s e portions of piping of C.6.a and C.6.b are acceptable without postulation of breaks and should be designed to meet the following requirements:
1.
The following design stress and fatigue limits should not be exceeded; For ASME Code,Section III - Class 1 Piping (a)
Maximum stress range should not exceed the following li=its:
Ferritic steel 1 2.0S Austenitic steel 1 2.4S,
(b)
Cumulative usage factor < 0.1, where required by I.B.l(c)
(c)
The maximum stress range between any two' load-sets (including the =ero load set) should be calculated by Eq. (10) in Par. 5B-3653, f o r all upce t p lant conditions, and an OBE event transient.
If the calculated caximum stress range of Eq. (10) exceeds the limits of I.B.l(a) but is not greater than 3SA, the cumulative usage factor limit of I. B.1(b) should be met.
If the calculated maximum stress range of Eq. (10) exceeds 35 the stress ranges calculated by both Eq. (12) and Eq.
(13) should meet the limits o f I. B.1 (a), and the cumulative usage. factor limit of I. B. l(b) should also be 4
met.
For ASME Code Section III Class 2, Piping Maximum stress range as calculated by Eq. (9) and (10) in Par. NC-3652 considering upset plant conditions (i.e.,
I sustained loads, occasional loads, and thermal expansion) and an OBE event should not exceed (5
+S) p, 2.
Welded at tachmen ts for pipe support, or other purposes to these portions of piping should be avoided except where detailed stress analyses, or tests, are performe.d to demonstrate compliance with the limits of I.3.1.
_ 1_/The limit of 0.S(1.2 Sh*3a) ay be used in lieu of (S, + Sp, J.
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3.
the number of piping circusferential and lo231cudinal welds and branch connections should be minimized; 4.
the extent of piping 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 containnent penetrations) should not require "elding 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.l.
i 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.
?!uid Systems Enclosed Within Protective Structures 1.
Breaks in %SME Code,Section III Class 2 and 3 piping, should be postulated at the following locations in each piping and branch run (with the exception of those portions of fluid system piping identified in I.B.) within the boundary of each enclosing essential structure or compartment designed to satisfy the provisions of C.l.b.
or C.1.c:
a.
at terminal ends if located within the enclosing essential straeburs or compartment; wher'e piping is pressuri=ed for only a portion of run, at the tornincZ ands o f the p re ss uiized se c tion,
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b.
at intermediate locations sdlected by either one of the following:
(1) 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 e'xtreme of the run within the enclosing essential structure or compartment, (a terminal end, if located within the e'nclosing essential structure or compartment may substitute for one intermediate break), or,
! exceed (Sh * # )l (ii) at each location where the stresses c
but not less than two separated in termediate locations chosen on the basis of highest stress 3/, within the boundary of each enclosing esse'ntial s tructure or
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compartment.
In the case of a straight pipe run, without any pipe fittings, or welded atta'chments, a
minimum of one intermediate location, at the highest stress point.
2.
Breaks in non-nuclear class piping should be postulated at the following locations in each piping or branch run within the boundary of each enclosing essential structure or compartment a.
at terminal ends of the pressurized portions of the run, b.
at each intermediate pipe fitting, and welded attachment.
2/ Stresses associated with normal and upset plant conditiona, and an CBE event as calculated by Eq. (9) and (10), Par. NC-3652 of A S!!E Code,Section III, for Class 2 and 3 piping.
3/Two' highest str-ss points; select second point at least 10% below the highest stress.
D.
F'uf d Sys tems No t Enclosed within Protective Structures 1.
Break's in ASME Code,Section III Class 2 and 3 piping, should be postulated at the following locations in each piping and branch run (excep t those portions of fluid system piping identified in I.B) not enclosed in protective structures but routed alongside, above, or below escential structures or components designed to satisfy the provisions of C.l.b, or C.l.c:
a.
at terminal ends of pressurized portions of the run if located adj acent to the essential structure and comp ar tmen t; b.
at intermediate locations selected by either one of the following:
6 (i) each pipe fitting (e.g.,
elbow, tee, cross, and non-standard fitting), or (ii) where the stresses 2/ e::c ee d (S. + S 11/
but not n
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loss than two widely sepa rated locations adj acen t to e 1ch essenti:L structure or compartment chosen on the basis o f highes t stress 3/.
In the case of a j
straight run, without any pipe fitting and welded
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attachments and stresses below (S. + S Ji,
1:
c a minimum of one location chosen en the basis of highest stress.
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T 2.
Breaks in non-nucle _ar class piping sheid be. postulated at 1
the following locations in each piping or tranch run:
I a.
at terminal ends of pressurized portions of t' e run if h
adj oining or located adj acept to an aesential 5
structure cycten or component, b.
at each pipe fitting and welded attachment, if adj oining or located adj acent to an essential structure or component.
t II.
Modersta-Enercu Fluid Gyate= Picinc A.
Fluid Systems Separated f rom Escential Structures, Sys tems &
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Components For the purpose of usuring that fluid system piping or portions thereof meet the provisions of C.1.a.,
a reviev cf piping
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layout and plant arrangement drawings should clearly demonstra:e i
that the effects of through-wall leakage cracks are isolatad or physically remote from essential structuras, ay a tems, and components.
B.'
Fluid Systems Piping 3etween Containment Isolation Valves.
l Those portions of fluid system piping identified in C.6.a. and 1
C.6.b.
are acceptable without postulation of leakage cracks and should be designed such that the stresses 4/ do not exceed 4/ f r ASME Class 2 piping.
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C.
Fluid Systems Outsida of or Enclosed within Protective Structures.
Through-wall leakage cracks should be p os tula ted in fluid
- aystem piping located within or outside of s tructures and conpartments containing essentici cyacema c>:d componenta
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a designed to satisfy the provisions of C.l.b.
or C.l.c.,
except where exempted by II.B. II.D, and in'those portions of ASME Code Class 2,
3 and non-nuclear piping where the strcases are j
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less than 0.5(S The cracks should be postulated to c
occur individually at locations appropriate to form the bases for providing maximum protection required from fluid spraying and flooding, and the consequent hazard or environmental conditions developed.
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D.
Hoderate-Energy Fluid Systems in Proximity to High-Energy Fluid Systems Naderate-energy fluid syscem piping, or portions thereof, that f
is located within an area containing a postulated break in high-energy fluid system piping is acceptable without postulation of through-wall leakage cracks.
Where a postulated leakage crack in the nodarcte-energy fluid system piping results in more limiting environmental conditions than the b reak in proximate high-energy fluid system piping, the provisions of II.C should be applied.
E.
Fluid Sya ams Qualifying as High-Energy and Mcdcrabe-Energy Systems Through-wall laaktge cracks instead of breaks may be postulated i
i in the piping of those fluid systems that qualify as high energy 1/ in pe rf o rming f;uid sys ams for only short operational periods 5/An operational period is considered "short" if the fraction of ti=e that the systen operates within the p res s ure-tc=p e ra ture conditions specified for high-energy fluid systems is less than 2 percent of the time that the system operates as a moderate ene rgy fl' tid sys ten, for the period required to accomplish its. system design f unc t ion '(e. g.
-Stets such as the rea::er deca;. h., e t renoval sys t ans qualif;- :
naderate-energy fluid systems; however, systems such as auxiliary' feedeater systems operated during Pl!R reactor startup, hot standoy, or uhutdown qualify as high-energy fluid sfstens).
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III.
Type of Breaks and Leakage Cracks in Fluid S?! stem Piping A.
Circumferential Pipe Breaks The following circumferential breaks should be postulatad in high-energy fluid system piping at the locations specified in Section I of Appendix A with the exceptions identified in III.A.l.
1.
Circumferential breaks should be postulated in fluid system piping and branch runs exceeding a nominal pipe size of 1 inch, except if the maximum stress range in circumferential directions is, at least, twice that in the axial direction, considering upset plant conditions, then only a longitudinal break need be postulated.
(Instrument lines, one inch and less nominal pipe size (or tubing) should meet the provisions of Regulatory Guide 1.11.)
2.
Where break locations are selected at pipe fittings with-out the benefit of stress calculations, b re aka should be t
postulated at each pipe-to-fitting weld.
If detailed stress analyses (e.g.,
finite element analyses) or tests are performed, the maximum stressed location in the fitting may be selected instead of the pipe-to-fitting weld.
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3.
Circumferential breaks should be assumed to result in pipe
,everance and separation accompadied by a one-diameter lateral displacement of the ruptured piping sections unicss physically limited by piping restraints, structural members, or piping stiffness as may be demonstrated by inelastic limi t analysis (e.g.,
a plastic hinge in the piping is not developed under loading).
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4.
The dynamic force of the jet discharge at the break location 4
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should be based on the effective cross-sectional flow area of the pipe and on a calculated fluid pressure as modified by an analytically o r experimentally determined thrust coefficient.
Limited pipe displacement at break location, line re'strictions, flow limiters, positiva pump-controlled f
4 flow, and the absence of energy reservoirs may be taken into account, as applicable, in the reduction of j et discharge.
[
5 Pipe whipping should be assumed to occur in the plane defined by piping geometry.and configuration, and to cause pipe movement in the direction of the jet reaction.
3 B.
Longitudinal Pipe Breaks The following longitudinal breaks should be pos tulated in high-cnergy fluid sys ten piping at the locations of each circumfarential f
break specified in III.A. with the exception of III.S.3.:
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1.
Longitudinal breaks in fluid system piping and branch runs should be postulated in nominal pipe sizes 4-inches and larger except where the ma'ximum stress range /
2 in the axial direction is at least twice that in circumferential direction ecnoidering upset plant conditions," then", only a circumf erential break need be postulated.
2.
Longitudinal breaks should be postulated in addition to, but not concurrent with, circumferential breaks, except as execpted by III.A.1, III.B.1, and III.B.3.
3.
Longitudinal breaks need not be postulated at terminal ends if (a) the fluid system piping at the terminal ends contains no longitudinal pipe wel'ds, and (b) maj or geometric discontinuttles at the circumferential weld j oint of the terminc! ends are designed to minimize discontinuity
- stresses, 4.
Longitudinal breaks should be assuced te result in an axig3 pipe split without pipe severance.
The splits should be oriented at two diame trically opposed points in the pipe or fitting cifcumference (but not postulated concurrently) that results in a j et recction causing cut-of-plane bending of the piping c on fig u r a t i o tt.
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The dyna =ic force of the fluid j et discharge should be based on a circular (or elliptical, 2D x 1/2D) break area equal to the cross-sectional flow aren of the pipe at the break location and on a calculated fluid pressure modified by an analytically or experimentally determined thrust coefficient as determined for a circumferential break at the same location.
L'ine re s t ri'c tio n s, 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.
6.
Piping movement at the break should be assumed to occur in the direction of the jet reaction unless limited by structural members, piping restrainte, or piping stiffness as demonstrated by inelastic limit analysis.
C.
Through-Wall Leakage Cracks The following through-wall leakage cracks should be postulated in codercta-energy fluid sys cam piping at the locations specified in Section II of Appendix A:
1.
Cracks should be postulated in moderate-energy fluid system piping and branch runs exceeding a nominal pipe size of 1 inch.
2.
Crack openings should be assumed as a circular orifice of cross-sectional piping flow area equal to that of a rectangle one-hal'f pipe-diameter in length and whose dimensions are
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The orifice should be assumed to be oriented at any pbint about the circumference of the pipe.
i 3.
The flow from the crack opening should be ' assumed to result l
in an environment that wees all unprotected components within the essential structure or compartment, uith consequent flooding in the compartment and communicating compartments
-based on a conservatively estimated ^ time period to effect i
corrective actions.
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DEFINITIONS Dual Barrier Containment Structures.
Primary containmants that are surrounded by limited leakage, annular shield buildings (usually of concrete construction).
Fluid Sustems or Fluid System Piping.
Identifies those high and moderate energy systems that are subj ect to the postulation of piping failures against which protection of essential structures, (or compartments) systems, and components is needed.
.High-Eneroy Fluid Sustems.
Those systems that, during normal plant condi tions, 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.
Noderate-Enerou Fluid Sustems.
Those systems that, during normal plant conditions, are either in operation or maintained pres,surized (above atmospheric p ressure) under conditions where both of the -
following are met:
a.
maximum operating temperature is 200*F or less, and b.
maximum operating pressure is 275 psig or less.
.7ormcl Plant Conditions.
Includes reactor startup, operation at power, hot standby, reactor cooldown to cold shutdown condition.
e
m Upse t Plcnt Condition.
Includes system transients of moderate frequency during the plant service life which are anticipated operational occurrences, but er.cludes system testing.
Pirina Runs.
Piping that interconnects terminal ends.
Branch Runs. Piping that branches f rom a st i c piping run of greater nominal pipe size, and interconnects terminal ends.
(Free-ended piping nozzles and pipe. stubs o1 main runs are part of piping runs).
Postulched Picine Failures.
Postulated longitudinal and circumf erential b reaks in high-energy fluid system piping and through-wall leakage cracks in moderate-energy fluid system piping.
Recctor Shu:doun.
Involves all system functions required to shut down the reactor safely and maintain the reactor in a safe cold shutdown condition.
Essential Structures, (or Compartment), Systems and Components are those structures, systems, and components required for reactor shutdown and/or to mitigate the consequences of a postulated failure in fluid syste.7 piping that results in trip of either the turbine generator, or the reactor p rotection system.
9 9
S' S'
S The allowable stresses at maximuu (hot) temperature h
c a
and at minimum (cold) temperature, respectively, as defined in Article NC-3600 of the ASME Code,Section III.
S.
The design stress intensity as defined in Article NB-3600 JE -
of the ASME Code,Section III.
Available.
Structures (or compartmen ts), systems, and components those structures, systems, and components that may be needed to mitigate the consequences of a postulated failure in fluid system piping that does not result in a trip of e'ither the turbine-g e n e r a t o'r, or the reactor pro tection sys tem.
Single-Barrier Containment Structures.
Primary containments that a.r e not surrounded by limited leakage, annular shield buildings (usually of concrete construction).
Terminal Ends.
The extremeties of piping or branch runs, (o r portions thereof) that connect to structures, components (e.g.,
vessels, pumps, valves) or pipe anchors that act as rigid constraints to the piping thermal expansion.
The branch connection to a main piping run is a terminal end of the branch run.
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