ML20198F230
| ML20198F230 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 12/26/1973 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0935, CON-WNP-935 NUDOCS 8605280444 | |
| Download: ML20198F230 (4) | |
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Docket File No. 50-460 L-Rdg Docket No. 50-460 SEB RF V. A. Moore, Assistant Director for Light Water Reactors Group 2-3 Directorate of Licensing WASHINGTON PUBLIC POWER SUPPLY SYSTEM - WPPSS NUCLEAR PROJECT NO. 1 FIRST REQUEST FOR INFORMATION, PSAR REVIEW Plant Nane: WPPSS Nuclear Project No. 1 Licensing State: PSAR-CPReview(Ql)
Docket Number: 50-460 Responsible Branch and Project Manager: LWR 2-3, T. Cox Requested Completion Date: December 28, 1973 Applicant's Response Date Nacessary for Completion of Next Action Planned on Project: March 4,1974 Description of Response: First Request for Information Review Status: Conplete The first round review of the PSAR has been completed by the Structural Engineering Branch and we find that additional information is required before we can complete our review. The additional information re-quested, which concerns the structural aspects, is contained in the enclosure. The caterial reviewed to date consisted of infomation provided in the docketed version of the PSAR which incorporated the applicant's reply to the preliminary review completed in August of 1973 which indicated there was insufficient information to initiate Regulatory's detailed review.
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R. R. Maccary, Assistant Director for Engineering Directorate of Licensing
Enclosure:
First Request for Information cc w/o encl:
cc w/ encl:
A. Giambusso, L S. Hanauer, DRTA L. Shao, L W. Mcdonald, L J. Hendric, L T. Cox, L A. Schwencer, L C. P. Tan, L
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'FIRST REQUWT WiR,I,NFORMATIN
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Section 3.3.1.4 1.
In view of the fact bFat shielding by other structures does riot always have a beneficial effect and in scne cases suction co-efficients should be incrGaspd because of the proximity of a neighboring building, justification should be provided for the statement that the effect of shlalding by other structures is neglected.
Section 3.5 (Also Section 3.8.3.4) 1.
Assurance of sufficient margin of safety should be provided if yield line theory is used as design method especially for loading ch"hi',mtinn usina 1 es 1 cad fact:r: fcr :11 thc 1cc 1.
Section 3.7.2.8 1.
The answer provided to Question 3.8 (August 20,1973) is fiot i
adequate or complete.
The Structural Engineet f pg Dranch currently uses a value of 110% variation on the computed peak f)oor response frequencies to broaden the peaks.
The broadening of those peaks is to account for soil property variations, variations in struc-tural materials as well as damping.
Indicate your intent to use this ! 10% value or provide justification for your stated frequency variations which you are to provide.
Section 3.7.2.13 1.
Question 3.9(August 20.1973) remains unanswered.
Section 3.7.3.4 1.
Question 3.10 (August 20,1973) remains unanswered.
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. Section 3.8.1.4 1.
On page 3.8-10 under b. analysis procedure, it is indicated that the containment is idealized as an axisemetric structure under axisymmetric and non-axisymetric loading with consideration of concrete cracking for the axisymetric case. The method and pro-cedure in which the stresses from the axisyrretric and non-axisymmetric cases are combined should be indicated, since in the non-axisymmetric case, cracking is not considered.
2.
A layered representation for the dome apex area used in the ana-lytical model should be provided.
The actual stresses in the reinforcing bars in these areas cannot be obtained from the overall analysis of the containment and a separate analysis should be pro-vided and described.
3-On fiace 1 8-12. under entlysi: cf met:llic lir.cr. it is indicated that the analysis of the anchors considers the effects as indicated in CC-3810 of the ASME Code Section III Division 2.
The Code does not indicate the method of analysis.
Detailed description of the effects considered and the method of analysis used should be pro-vided.
Section 3.8.1.7 Structural integrity test has the added function of confirming the degree of accuracy of analysis, A description of the acceptable degree of correlation between testing and analysis results should be provided.
Section 3.8.3.4 i
1.
On page 3.8-45 under analysis procedures, it is stated that concrete is assumed to be uncracked in the analysis.
Indicate if this same assumption is used in the analysis for thermal gradient across the
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. primary shield wall, noting that the bending moment due to thermal gradient is related to the moment of inertia of the wall section, which in turn is related to cracking.
2.
Since the fuel transfer canal passes through the containment and the general service building, details of the fuel transfer canal to accommodate differential movement of the two structures especially under seismic loading should be provided.
' 3.
The secondary shield wall is a ring wall with open top and cannot prevent the jet force and missile generated as a result of the break of pipe connecting the reactor and the steam generator from hitting the polar crane girder.
The polar crane girder together with the trolley may be displaced and fall down. The treasures to avoid such an occurrence should be indicated.
4.
The d ei.ch proviaco in Figure 5.5-14 wnicn illustretes tne reactor vessel support detail is not adequate in its scope. The manner in which the loads are transmitted beyong this steel support assembly J
should be provided so that an evaluation of its adequacy can be made.
Section 3.8.4.1 1.
On page 3.8-58, tfic main staan and feedwater isolation area enclosure and condensate domineralization building are described.
There are no drawings showing the elevations of these structures and'these drawings should be provided so that an adequate evalua-tion of these structures and effect of these structures on other Category I structures can be made.
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