ML20090M629
| ML20090M629 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/30/1975 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9105070383 | |
| Download: ML20090M629 (3) | |
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NRC 31 RIP.tlT ION FOM P AitT 50 Dr C '
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FILE:
jiRO.3. N rthern States Power.Co.
DATE OF DOC DATE REC'D LTR TWX RPT OTHER Minneapolis, Minn.
55401 6-2-75 XX
.L.O. Mayer 5-30-75 TO:
ORIG CC OTHER SEN1 AEC POR XX Mr. D.L. Ziemann f 1 signed 39 SENT l.OCAL PDR rr-
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CLASS UNCLASS PROPINFO INPUT NO CYS T;EC'D DOCKET NO:
40 50-263 xxx DESCRIPilON:
Ltr re our 4-17-75 Itr... furn ENCLOSURES; addl info re containment design int'o & furg schedule o f response to info re containment...,
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Monti$cilo FOR ACT!ON/INFOR /'ATIUN DHL 6-3-75
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Dear Mr Zietnenn:
MONTICELLO NUC15.AR GENERATING PLANT I
Docket No. 50-263 License No. DPR-22 Additional Containment Desir.n Infomation 4
as requested by your April 17, 1975, letter, an evaluation of the Monticello contain-rnent configuration details will be inade and documented, together with a plant 4
evaluation similar to that performed by CE and discussed with the NRC in a meeting in Bethesda on April 10, 1975.
It is expected that this will be submitted by August 4, 1975.
This evaluation will address the short tem concerns on the effect of poo' swell on the Drywell-To-Torus vent system.
It will fnelude large size plan and section drawings of the suppresrion chamber which illustrate the structures, equipment, and piping in the suppression pool which could be subjected to hydrodynamic loads.
Your letter identified several other specific items of infomation that will require an expansion of the above evaluation. A tentative program and schedule of response to these questiens are outlined below Document S/R Valve Vent Clearing Model July 31, 1975 Impact Tests for Torus Internal Structure Shapes July 31, 1975 Qualify Impact Model September 30, 1975 Calculate Mark I Pool Swell Impact Load for the September 30, 1975 4
Reference Plant Detemine Need for Plant Torus Stress Test for September 30, 1975 S/R Valve Discharge Calculate other Significant Mark I LOCA Dynamic December 31, 1975 Loads Co.nplete Currently Planned Mark I Pool Swell Tests December 31, 1975 l
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NORTHERN OTATEO POWER COMPANY Mr D L Zienann Page ?
M.iy 30, 1975 Confim Calculated Loads March 31, 1976 Perfom Stress Analysis / Test of Torus, Torus September 30, 1976 Internals and Supports Combine St resses and Compare to Plant Licensing Dec eir.be r 31, 1976 Bases In accordance with your Tebruary 14, 1975, Safety / Relief Valve letter requesting a program identification, we should be able to submit details on the above tentative ps ogram by July 7,1975. Our program will be designed to respond to both your February 14, 1975, letter and your recent April 17, 1975, letter and will consider both the S/R valve and LOCA conditions for a titre history of potential loads including assymetric loads and a justification of these loads.
Subsequent to the submittal of wr program identification, we will meet with you as part of the IMR cuners grcup that has been fomed to address this comon problem.
Yours very truly, h.
L 0 Mayer, PE Manager of Nuclear Support Services IDM/LLT/ak cc:
J G Keppler G Charnof f Minnesota Follution Control Agency Attn:
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