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REACTOR C00LA?iT PIPI!:G TYPICAL ELEVATIONS | REACTOR C00LA?iT PIPI!:G TYPICAL ELEVATIONS | ||
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ends in a clevis, through which loads are transmitted to the owners structure. Each clevis is drilled to accept anchor bolts. | ends in a clevis, through which loads are transmitted to the owners structure. Each clevis is drilled to accept anchor bolts. | ||
The pump stop matesd 'irectly with the pump casing. The clearance between the mating surface and the stop must be shirred to a specified size and verified during hot functional testing. | The pump stop matesd 'irectly with the pump casing. The clearance between the mating surface and the stop must be shirred to a specified size and verified during hot functional testing. | ||
. 4.3.4 Pressurizer Supports The pressurizer succorts are shown in Figure 8. The cressurizer is supported by a cylindrical skirt welded to the bottcm head ' | . 4.3.4 Pressurizer Supports The pressurizer succorts are shown in Figure 8. The cressurizer is supported by a cylindrical skirt welded to the bottcm head ' | ||
of the pressurizer. The skirt er.ds in a flange drilled to accept anchor bolts. Althcugh most thermal growth will be in the vertical direction, the cressurizer skirt design will accomodate racial growth without bolt slippage. ; | of the pressurizer. The skirt er.ds in a flange drilled to accept anchor bolts. Althcugh most thermal growth will be in the vertical direction, the cressurizer skirt design will accomodate racial growth without bolt slippage. ; | ||
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Latest revision as of 05:26, 27 February 2020
| ML20003C687 | |
| Person / Time | |
|---|---|
| Site: | 05000470 |
| Issue date: | 03/03/1981 |
| From: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, EMVC-EPS |
| To: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| References | |
| LD-81-012, LD-81-12, NUDOCS 8103090621 | |
| Download: ML20003C687 (26) | |
Text
C-E Power Systems Tel 203/6881911 Combustion Engineenng. Inc Telex 99297 1000 Prospect Hill Road Windsor. Connecticut 06095 H POWERSYSTEMS 60 ' gr7D March 3, 1981 LD-81-012 f.\'9-s Mr. C. I. Grimes ($ 9 %
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t Office of Nuclear Reactor Regulation y h r h <. b U. S. Nuclear Regulatory Commission y\'c5,y[ #' f-Washington, D. C. 20555 4-M
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Subject:
Confirmatory Piping Analysis Information jg'h
Dear Mr. Grimes:
In a telephone conversation with Messrs. G. A. Davis and T. E. Natan on February 20, 1981, you requested information on the System 80 Reactor Coolant System (RCS) cold leg piping, for use by Pacific Northwest Laboratory in performing a confirmatory piping analysis of the PVNGS Safety Injection System (SIS) piping. The requested information is provided in the enclosures.
As we stated earlier, we have serious reservations as to whether the simplified analysis you are planning will yield sufficiently accurate results. Combustion Engineering performs a very lengthy and complex analysis of Reactor Coolant System (RCS) piping, which includes the interactions of the major components and their supports.
If we can be of any additional assistance, please feel free to contact either myself or Mr. T. J. Price of my staff at (203)688-1911,, Ext. 2803.
Very truly yours, COMBUSTION ENGINEERING, INC.
A. E. Senerer Director Nuclear Licensing M V 'r \
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, 1.0 PURPOSE i The p'urpose of this document is to describe the purpose and function of ,. the reactor coolant system supports and restraints.
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2.0 SCOPE i i Supports and restraints for the components and piping of the reactor I coolant system are covered by this document. [ 3.0 REFERENCES - t c 3.2 ( ASME B&PV Code Section III (applicable addenda)
4.0 DESCRIPTION
4.1 Definitions The following definitions apply to this document and its ' references. Support - a device which pr'ovides support to a component - or pipe curing normal and abnormal plant operations and con-ditions. Restraints - a device which is inactive during all plant normal aperations and conditions but acts to restrain a pipe for ex-cessive motion following a postulated pipe rupture. , Stop - a device which is inactive during all plant normal opera-
, tions and conditions but acts to stop a conpanent from excessive motion following a postulated pipe rupture.
4.2 General Description ! 4.2.1 Reactor Coolant System Suppcrts The purpose of reactor coolant system su;; orts is to provide support to the reacter c:clant system durina all normal and abnerral clant coerations an: conditions. Their function is to limit the stresses im:osed on components and su: ports by the pressure, thermal and ' mechanical loadings to those allowed by Reference 3.2.
. This functicn is accomplished by minimi:ing the resistance :
to ther-al eyrtas#29 Erd centractie- '?.ile cre ridin, s.:"ic ei . su;c:.. Os ::. - :: e t 2 . - n d ic s . :< : . . f . . c a.::::r ccol E r. :ys:_, at:ta ne reca,ar.: fez;asn;y a' the c;ntaircent f Page 5 of la i
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b interior structures which interface with the component r supports . This is accomplished by judicious use of ; low friction bearings, spherical bearings, hydraulic ! snubbers, and stops which limit the deflection of , ( components following postulated pipe breaks. 4.2.2 Reactor Coolant System Restraints f t
- l The purpose of the reactor coolant system restraints i is to restrain the pipes of the reactor coolant system (
following a postulated pipa ructure. Their function is j to limit the flow of reactor coolant frem the ruptured ; I pipe and/or to prevent the ruptured pipe frem damaging components or struc'tures required for the orderly shut- i down of the plar.t. f 4.2.3 Reactor Coolant System Stops l t The purpose of the reactor coolant system stops is to : limit the motion of components following a postulated l . pipe rupture. Their function is to maintain the stresses ! l in the components, pipes and supports resulting frem ( l forces generated by the pipe rupture within the limits 1 prescribed by Reference 3.2 4.3 Detailed Description l ] , ! 4.3.1 Reactor Vessel Supports The reactor vessel supports are shown in Figure 1. The ! reactor vessel is succorted by four vertical columns located ; 1 under the vessel inlet no:zles. A pad welded to each noz:le ' provides a surface to which the column is bolted. This pad t also acts as a horizental key to positively locate the : . vertical centerline of the vessel. It is designed to mate . with the owner's structure and allows free radial growth l
- of the vessel during tFermal excansion while succorting the t vessel horizontally during earthquakes and following a postulated pipe rupture.
Figure 2 shows the interface at the upper horizontal reactor .
. vessel supperts. Low friction bearings are used to minimize i resistance to thermal exoansion. The clearance between the [
nozzle pad and the upper horizontal supporting structure must be shimed to a spec.rled size and verified during hot functional testing. The vertical colu ns are designed to supocrt the vessel and resist vertical motion during earthquakes and following a pipe rupture. , Page 6 of 1C
At the bottom of each column is a baseplate which is drilled to accept anchor bolts. Shear bars attached to this plate and preloaded anchor bolts are the mechanism by which column loads are transmitted to the foundation. The baseplate also acts as a keyway for a horizontal key welded to the lower vessel head. An energy absorbing material is used between the key and keyway to provide horizontal seismic support, while limiting the load on the vessel head during a pipe rupture. . Low friction bearings are used at each sliding surface on the lower keyways -to minimize friction loads to the supporting structure. Figure 3 shows the interface at the reactor vessel lower supports. , 4.3.2 Steam Generator Supports and Stops The steam generators supports are shown on Figure 4. The steam generator is supported by a conical skirt welded to the steam generator lower head. The skirt provides a bolting surface for a heavy steel sliding base. Four low friction spherical head bearings under the plate are the sliding interface which allows horizontal motion parallel to the hot leg due to thermal expansion. Machined cutouts in the sliding base act as keyways for embedded keys which support the generater horizontally. In addition, the cutouts provide a mating surface for a stop that limits motion parallel to the hot leg following a postulated reactor coolant pipe rupture. Slotted holes are previded in the sliding base to accept anchor bolts. Figure 5 shows the interface at the lower steam generator supports. In the keyways, low friction bearings are used to minimize resistance to thermal motion. The clearance j
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between the step mating surface ar.d the key must be shirmed to a specified si:e ar.d verified during hot functional testing. Also the gao between the too of the sliding base and the anchor bolt nuts must be set to a specified size during hot functional testing. Horizontal support at the top of the steam generator is cro-vided by two keys and t'..o interecnnacted hydraulic snubber assemblies. They act as hori::ntal su: ports for the steam generator during earthquake and following a ecstulated pipe rupture, while allcwing motion parallei to the hot icg due to thermal expansion. Page 7,cf la -
Figure C shows the upper steam generator supports. Low ! friction bearines are bolted to the sides of the owner's keyway. Each snubber assembly consists of a lug welded t to the steam generator, a lever, two links, two snubbers, j one clevis pinned to the lever and two clevises pinned to i snubbers. Each clevis, through which loads are transnitted 1 to the owner's structure, is drilled to accept anchor : bol ts. , i 4.3.3 Reactor Coolant Pump Supports and Stops ! t The supports and stop control movement of the reactor coolant . pump in the horizontal and vertical planes during accidents l but accomodates thermal growth during plant heat up. ! f The reactor coolant pump supports and stop are shown in Figure i
- 7. The reactor coolant pump ar,' motor assembly is supported by four vertical columns pinned to the pump counting ring. It is supported for seismic and loss of coolant accident loads by two ,
horizontal columns pinned to the top of the motor mount, two I horizontal columns pinned to the pump counting ring, and a l horizontal snubber system attached to the top of the motor mount. In addition horizontal restraint is provided, following
. a postulated pipe rupture, by a stop located at the pump casing at the elevation of the discharge nozzle.
Each column, horizontal and vertical, and the snubber assembly - ends in a clevis, through which loads are transmitted to the owners structure. Each clevis is drilled to accept anchor bolts. The pump stop matesd 'irectly with the pump casing. The clearance between the mating surface and the stop must be shirred to a specified size and verified during hot functional testing. . 4.3.4 Pressurizer Supports The pressurizer succorts are shown in Figure 8. The cressurizer is supported by a cylindrical skirt welded to the bottcm head ' of the pressurizer. The skirt er.ds in a flange drilled to accept anchor bolts. Althcugh most thermal growth will be in the vertical direction, the cressurizer skirt design will accomodate racial growth without bolt slippage. ; Four keys welded to the upoer pnetion of the pressurizer i shell give additional succor: to the pressurizer during seismic a-d folle.:irg ' tos ulated cira ru;tura l Page C of 18
t 4.3.5 Reactor Coolant Piping (liain Leop) Restraints Pipe restraints are located to prevent excessive move-ment of reactor coolant pipes as a consequence of postu-lated guillotine pipe ruptures. Restraint for slot type ruptures is provided by the normal component support system. The restraints also limit the mechanical loads transmitted to the components and limit the size of postulated guillo- l tine rupture flow areas in order to minimize the magnitude ' of the subcompartment pressures. O'ne horizontal restraint is located on each discharge leg elbow for a postulated discharge leg '.erminal cnd guillotine at the r'eactor vessel inlet no.:zle terminal end. A vertical restraint is located beneath each hot leg elbow to protect against a postulated guillotine rupture at the steam generator inlet nozzle terminal end. Two ; vertical restraints and one horizontal restraint are located on the suction leg. The vertical restraint under the pumps is provided for a cuillotine rupture of the ' suction leg at the pump suction nozzle terminal end. The other vertical and the horizontal restraint, together, restrain the pipe folicwing a costulated circumferential pipe break ' at the steam generator outlet nozzle terminal end. Pipe stop locations are shown in Figure 9. - In order to allow unrestrained thermal movenents of the oice, a specified gap will exist between the pipe and the restraint at all restraint locations. This clearance must be shimmed to a specified size and verified during hot functional testing. Two lugs welded to each discharge leg elbow provide a mating surface for each discharge leg restraint. At all other restraint locations restraints mate with the. pipe itself. .. Fage 9 of 13 i
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