ML19316A085
| ML19316A085 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/22/1970 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Thies A DUKE POWER CO. |
| References | |
| NUDOCS 7911210810 | |
| Download: ML19316A085 (4) | |
Text
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ATOMIC ENERGY COMMISSION DR ' wading D. Flang 1
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C. K. Beck April 22, 1970 l
Docket Nos. 50-26 M. M. Mann 50-270 T. R. '.?ilson and 50-287 F. Schroeder R. C. DeYoung R. W. Klecker R. S. Boyd D. Skovholt E. G. Case Duke Pow'er Company R. R. Maccaqr Power Building DRS/DRL Branch Chiefs 422 South Church Street.
F. W. Karas (2)
Charlotte, North Carolina 28201 Atterney, OGC ACRS (18)
Attention: Mr. Austin C. Thies W. Nyer (2)
Vice President J hn A. Blume & Assoc.
Production & Operation A. Schwencer entlemen:
F. P er As discussed with you in a meeting at Lynchburg, Virginia on March 31 and April 1,1970, we require additional information to complete our evaluation of your ce=bined loading stress and deflection analyses for fuel assemblies and reactor internals. The information needed is described in the attached enclosure. The requests are in groups which correspond directly to sections in your Final Safety Analysis Report.
You will note that request 313.4 forwarded to you by our letter of March 3, 1970 has been revised.
This revision is based on the above
=entioned discussions.
Please contact us if you desire any discussion or clarification of the information requested by this letter.
Sincerely,
/5/
Peter A. Morris, Director Division of Reactor Liesnsing
Enclosure:
As stated above P
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REQUEST FOR ADDITIONAL INFORMATION
.l 3.8 Reactor Internals (The following requests apply to 3&W Report 4
BAW-10008, Part 1)
(1) 3. 8. 4 With respect to the response spectrum / modal analysis method discussed in Section 3.1.6 provide:
An engineering sketch of the structural configuration represented a.
by the model, b.
A tabulation of masses and flexibility / stiffness factors, preferably in matrix form.
A brief discussion of the program used to compute frequencies, mode c.
shapes, etc.
d.
The mode shapes, frequencies, and participation factors developed by the analysis.
1 e.
The criteria used to codbine the modal contributions in order to arrive at deformations and/or forces on the reactor internals.
- 3.8.13 Provide the following information related to the stress analysis:
a.
The mathematical models used, the assumed boundary conditions and representative free body diagrams.
Identify the co=ponent loads, loading sources and resulting stresses for primary load paths, i.e., bolted joints, plenum cylinder, core grids.
b.
Sketches or drawings, to supplement Figure 23, showing all critical areas (such as discontinuites, areas of clearance and bolted connections).
3.8.14 We understand that with codbined accident loads some of the bolts joining the core barrel and core support shield will be stressed beyond yield strength.
Describe the methods of analysis used for these bolts and justify the bases for exceeding yield strength.
- Also, discuss how you will be assured that these bolts will retain their preload and strength properties throughout the life of the plant.
(1) This is a revision of request 3.8.4 made by letter of March 3, 1970 These are in addition to requests 3.8.1 through 3.8.12 made by the March 3, 1970 letter.
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i 3.8.15 Docu=ent typical results from either an experiment er a analysis that considers the shell bell modes (n=0 theoretical the core support shield and core barrel during LOCA co di i
, n=2, n=4, etc) for results should include the effect of shell bell mode deform n t ons. These bolted joints.
on 3.8.16 Document typical results of a stress analysis that c support shield and core barrel during a LOCA.
ss the core 3.9 (The following requests apply to 3&W Report BAW-10008
, Part 2.)
3.9.14* With respect 3.3, provide: to the time history / modal analysis discussed in Secti on The thrust vs time function used as the applied force a.
assumed model.
on the b.
A brief description of the analytical program used The modal damping coefficients used.
c.
d.
phasevise) with other LOCA and seismic loads.The ma magnitude or 3.9.15 With respect to the fuel assembly horizontal seismic analysis
, provide:
The mathematical models for the Phase 1 and Phase 2 a.
analyses.
b.
between the Phase 1 and Phase 2 models.The engineerin p ng assumed The analog diagrams for the two phases with accompanying c.
tions of symbols used on the diagrams.
explana-d.
A discussion of damping coefficients to include the b tion in the computational method used and an exam asis for their serva-they have been determined.
p e showing how l
Requests 3.9.~1 through '.9.13 were made by letter of Ma rch 3, 1970.-
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3 A description establishing the basis for the gap and stiffness e.
coefficient values selected.
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A copy of one analog run giving necessary data for force balance calculations.
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A discussion of the criteria for the acceptability of the output results of the seismic analyses, and the bases for these criteria.-
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