ML20044F862
| ML20044F862 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 05/21/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9306010134 | |
| Download: ML20044F862 (6) | |
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May 21,1993 Docket No. STN 52-001 Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated AB'VR Review Schedule - Chapter 3 Clarifications
Dear Chet:
Enclosed are SSAR markups providing the clarifications requested in our May 19,1993 conference call pertaining to feedwater piping classification and the use of special engineered pipe supports. The clarifications pertaining to duct work will be provided by May 26,1993.
Please provide copies of this submittal to Jim Brammer and Dave Terao.
Sincerely, e9 Jack Fox Advanced Reactor Programs ec: Gary Ehlert GE)
Norman Fletcher (DOE) 970037 h hN
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TABLE 3.21 CLASSIFICATION
SUMMARY
(Continued) s i
Quality Group Quality l
Safetg Loca-Classi-Assurance Seismic I
Princinal Comnone'nt*
Class lign*
fication Reauirement' Catenorv Notes i
B2 Nuclear Boiler System (Continued) 4.
Pipingincluding supports 1
C,SC A
B I
main steamline (MSL) and feed-water (FW)line up to and in-ciuding the outermost isolation valve f
5.
Piping including supports-2 SC B
B I
MSL from outermost isolation valve up to andincluding r
seismic interface restraint and j
FW from outermost isolation valve e shutoff valvp to p & inc, lean,ny 5'
6.
Piping including supports-MSL N
SC,T B
B (r) from the seismic interface i
restraint up to the turbine stop valve and turbine bypass valve
.D 6
i
[
[
[.-- -
[
7.
Piping from FW shutoff valve
/N SC to seismic interface restraint
^
'i 8.
Deleted 9.
Deleted
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- 10. Pipe whip restraint - MSL/FW 3
SC,C B
(dd) if needed f
1 r
- 11. Pipingincluding supports-other
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within outermost isolation valves 5
a.
RPV bead vent 1
C A
B I
(g) l b.
Main steam drains 1
C.SC A
B-1 (g) l
- 12. Piping including supports-other beyond outermost isolation or shutoff valves I
a.
RPV head vent beyond N C
C E
shutoffvalves
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b.
Main steam drains N
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I-Standard Plant Rev c (2) The feedwater lines are designed to conduct Group A from the reactor pressure vessel out to water to the reactor vessel over the full and including the outboard isolation valve, range of reactor power operation.
Quality Group B from the outboard isolation valve to and including the ee!=l: 4.:::f;a &ff 5.4.9.3 Description tesna+e4, and Quality Group D beyond the ube, shutoff valve. The feedwatergipijn and all The main steam piping is described in Section connected piping of 2-1/2 inchelarg,er nominal 10.3. The main steam and feedwater piping from size is Seismic Category I only from the reactor the reactor through the containment isolation pressure vessel out to, and including, the interfaces is diagrammed in Figure 5.1-3.
s+imic 4::: face rc;::aM. sMaff whG-As discussed in Table 3.2-1 and shown in The materials used in the piping are in Figure 5.1-3, the main steamlines are Quality accordance with the applicable design code and Group A from the reactor vessel out to and includ-supplementary requirements described in Section ing the outboard MSIV and Quality Group B frorn 3.2. The valve between the outboard isolation the outboard MSIVs to the turbine stop valve. valve and the shutoff valve upstream of the RHR They are also Seismic Category I only from the entry to the feedwater line is to effect a reactor pressure vessel out to the seismic inter-closed loop outside containment (CLOC) for face restraint.
containment bypass leakage control (Subsections 6.2.6 and 6.5.3).
The feedwater piping consists of two 22 inch diameter lines from the feedwater supply header The general requirements of the feedwater to the reactor. On each of the feedwater lines system are described in Subsections 7.1.1.7, from the common feedwater supply header, there 7.7.1.4, 7.7.2.4, and 10.4.7.
shall be a seismic interface restraint.psAa// />e /ocrk/C/ose lo seismic interf ace restraint see:; ::,- the 5.4.9.4 Safety Evaluation boundary between the Seismic Category I piping jdch exiSh dihe Opsifh ed and the non-seismic pipingCD:rumm of t Differential pressure on reactor internals gie@ kgntee*%herE'geet8 under the assumed accident condition of a rup-manual, motor-operated valve powered by a tured steamline is limited by the use of flow non-safety-grade bus. These motor-operated restrictors and by the use of four main steam-valves serve as the shutoff valves for the lines. All main steam and feedwater piping will feedwater lines. Isolation of each line is be designed in accordance with the requirements accomplished by two containment isolation valves defined in Section 3.2. Design of the piping in consisting of one check valve inside the drywell accordance with these requirements ensures and one positive closing check valve outside the meeting the safety design bases, containment (Figure 5.1-3). The closing check valve outside the containment is a spring-closing 5.4.9.5 Inspection and Testing check valve that is held open by air. These check valves will be qualified to withstand the Testing is carried out in accordance with dynamic effects of a feedwater line break outside Subsection 3.9.6 and Chapter 14 Inservice containment. Inside the containment, downstream inspection is considered in the design of the of the inboard FW line check valve, there is a main steam and feedwater piping. This consider-manual maintenance valve (B21-F005) ation assures adequate working space and access for the inspection of selected components.
The design temperature and pressure of the feedwater line is the same as that of the reactor 5.4.10 Pressurizer inlet nozzle (i.e.,1250 psig and 575 F)for turbine driven feedwater pumps.
Not Applicable to BWR 5.4.11 Pressurizer Relief Discharge System As discussed in Table 3.2-1 and shown in Not Applicable to BWR Figure 5.1-3 the feedwater piping is Quality Amendment 25
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branch line connection to the pipe run and the 3.733.1.6 Modeling of Piping Supports elevation of the branch line anchors and restraints.
Snubbers are modeled with an equivalent stiffness which is based on dynamic tests (2) The response spectra will no' be less than performed on prototype snubber assemblies or on the envelope of the response spectra used in data provided by the vendor. Struts are modeled the dynamic analysis of the run pipe.
with a stiffness calculated based on their length and cross-sectional properties. The (3) Amplification by the run pipe must be stiffness of the supporting structure for accounted for. However, if the location of snubbers and struts in included in the piping branch connection to the run pipe is more analysis model, unless the supporting structure than three run pipe diameters from the can be considered rigid relative to the piping.
nearest run pipe seismic restraint, The supporting structure can be considered as amplification by the run pipe will be rigid relative to the piping as long as the accounted for, criteria specified in Subsection 3.7.3.3.4 are met.
When the equivalent static analysis method is used, the horizontal and vertical load Anchors at equipment such as tanks, pumps and coefficients C and C applied to the heat exchangers are modeled with calculated h
y response spectra accelerations will conform with stiffness properties. Frame type pipe supports Subsection 3.73.8.1.5.
are modeled as described in Subsection 3.7.3.3.4.
The relative anchor motions to be used in either static or dynamic analysis of the 3.733.1.7 Modeling of Special Engineered decoupled branch pipe shall be as follows:
Pipc Supports (1) The internal displacements only, as Modifications to the normal linear-clastic determined from analysis of the run pipe, piping analysis methodology used with may be applied to the branch pipe if the conventional pipe supports are required to relative differential building movements of calculate the loads acting on the supports and the large pipe supports and the branch pipe on the piping components whea the special supports are less than 1/16 inch.
engineered supports, described in Subsection 3.73.4.1(6), are used. These modifications are (2) If the relative differential building needed to account for greater damping of the movements of the large pipe supports and the energy absorbers and the non linear behavior of branch pipe supports are more than 1/16 the limit stops. If these special devices are inch, motion of the restraints and anchors used, the modeling and analytical methodology of the branch pipe must be considered in will be in accordance with methodology accepted addition to the inertial displacement of the by the regulatory agency at the time of run pipe, certification or at t time of application, per the discretion of the applicant.
3.733.1.5 Selection of input Time-Histories 3.733.2 Modeling of Equipment in selecting the acceleration time-history to be used for dynamie analysis of a piping system, For dynamic analysis, Seismic Category I the time-history chosen is one which most closely equipment is represented by lumped-mass systems describes the accelerations existing at the which consist of discrete masses connected by piping support attachment points. For a piping weightless springs. The criteria used to lump system supported at more than two points located masses are:
at different elevations in the building, the time-history analysis is performed using the (1) The number of modes of a dynamic system is independent support motion method where controlled by the number of masses used; acceleration time histories are input at all of therefore, the number of masses is chosen so the piping structural attachment points.
that all significant modes are included.
3.7-16.1 Arnendmer.t 23
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QFrame Type (Linear) Pipe Supports: Frame type frame-type supports cannot be applied.
supports are linear supports as defined as ASME Examples of special engineered supports are Section III, Subsection NF, Component Standard Energy Absorbers, and Limit Stops.
Supports. They consist of frames constructed of structural steel elements that are not attached Enercy Absorbers: are linear energy to the pipes. They act as guides to allow axial absorbing support pa.<s designed to and rotational movement of the pipe but act as dissipate energy associated with dynamic rigid restraints to lateral movement in either pipe movements by yielding. When energy one or two directions. Frame type pipe supports absorbers are used they will be designed are designed in accordance with ASME Code Section to meet the requirements of ASME Section III, Subsection NF-3000.
III, Code Class N-420, Linear Energy Supports for Subsection NF, Classes 1,2, Frame type pipe supports are passive supports, and 3 Construction,Section III, Division requiring little maintenance and in-service 1.
The restrictions on location and inspection, and will normally be used instead of application of struts and frame-type struts when they are more economical or where supports, discussed in (4) and (5) above, environmental conditions are not suitable for the are also applicable to energy absorbers ball bushings at the pinned connections of since energy absorbers allow thermal struts. Similar to struts, frame type supports movement of the pipe only in its design will not be used at locations where restraint of directions.
pipe movement to thermal expansion will significantly increase the secondary piping Limit Stons: are passive seismic pipe stress ranges or equipment nozzle loads.
support devices consisting of limit stops increases of thermal expansion loads in the pipe with gaps sized to allow for ther nal and nozzles will normally be restricted to less expansion while preventing large seismic than 20%.
displacements. Limit stops are linear supports as defined as ASME Section III, The design loads on frame type pipe supports Subsection NF, and are designed in include those loads caused by thermal expansion, accordance with ASME Code Section III, dead weight, and the inertia and anchor rnotion Subsection NF-3000. They consist of box effects of all dynamic loads. As in the case of frames constructed of structural steel other supports, the forces on frame type supports elements that are not attached to the are obtained from an analysis, which are assured pipe. The box frames allow free movement not to exceed the design loads for various in the axial direction but limit large operating conditions.
displacement in the lateral direction.
M A pecial Engineered Pipe Supports: In an effort to 3.9.3.4.2 Reactor Pressure Vessel Support S
minimize the use and application of snubbers Skirt there may be instances where special engineered pipe supports can be used where either struts or The ABWR RPV support skirt is designed as an ASME Code Class 1 component per the requirements of ASME Code Section III, Subsection NF*. The loading conditions and
- Augmented by the following: (1) application of stress criteria are given in Tables 3.9-1 and Code Case N-476, Supplement 89.1 which governs 3.9-2, and the calculated stresses meet the the design of single angle members of ASME Class Code allowable stresses in the critical 1,2,3 and MC linear component supports; and (2) support areas for various plant operating when eccentric loads or other torsionalloads are conditions. The stress level margins assure not accommodated by designing the load to act the adequacy of the RPV support skirt. An through the shear center or meet
- Standard for analysis for buckling shows that the support Steel Support Design *, analyses will be performed skirt complies with Subparagraph F-1332.5 of in accordance with torsional analysis methods ASME III, Appendix F, and the loads do not such as:
- Torsional Analysis of Steel Members, exceed two thirds of the critical buckling USS Steel Manual", Publication T111-2/83.
strencth of the skirt. The permissibL skirt Mf'tfiese special devices are 3
[used, the modeling and analytical methodology )
3.9.x Amendmen: 23 l will be in accordance with methodology accepted by the regulatory agency at the time of certification or at gli:ne of application, per f
j the discretion of theAapplicant.
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