ML17037C200
| ML17037C200 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/05/1975 |
| From: | Rhode G Niagara Mohawk Power Corp |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037C200 (8) | |
Text
NRC DISTRIBUTION FOR PART 50 DOCKF MATERIAL 0
(TEMPORARY FORM)
CONTROL NO:
FILE' RQM: Niagara Mohawk Power Cor
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~ DATE OF DOC DATE REC'D 5-10-75
" 5-5-75 ORIG 1 signed TO:
Mr. George Lear SENT AEC PDR SENT I.OCAL PDR CC OTHER XX PROP INFO CLASS UNCLASS NO CYS REC'D 1
DOCKET NQ:
INPUT 50>>220 Ltr re our ltrs of 2-15-75 4-17-75.2...furnishing info re relief valve blowdown phenomena 6l'ontainment hydrodynami loads 6 trans the following:
Nine Mile Pt. Unit 1 Contain-ment.Design & Operational Effects.>>..
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Nine Mile Pt. Unit,l FOR ACTION/INFORf'/IATION DHL 5 75 BUTLER (L)
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P~,.gy rP>i Igp dIC Ol Mr. George Lear, Chief Operating Reactors Branch
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Nine Mile Point Unit 1 Docket No. 50-220
Dear Mr. Lear:
Your letters of February 15, 1975 and April 17, 1975 requested information regarding relief valve blowdown phenomena and containment hydrodynamic loads.
A preliminary evaluation, based on recent testing by General Electric Company, indicates that containment design parameters will not be exceeded during discharge of the relief valves.
Operating experience, in addition to analytical work performed by General Electric for other facilities, do not suggest any operational safety problems with the Nine Mile Point Unit 1 containment.
The attached report discusses the program and schedule for a more detailed evaluation of the effects described in your letters.
Be-cause of the scope of this effort, the schedule suggested in your letters cannot be accommodated.
Further details of this tentative program will be submitted by July 5, 1975.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION erald K. Rhe~
Vice President-Engineering
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NINE HILE POINT UNIT 1 Containment Design and Operational Effects This report is a preliminary response to Nuclear Regulatory Commission concerns
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The following program and schedule for Nine Hile Point Unit 1 was devised at a recent meeting with General Electric and other utilities with boiling water reactors.
Initially an evaluation will be made of the hydrodynamic loads on the containment during accident conditions.
This analysis will be similar to that performed by General Electric and discussed with the Nuclear Regulatory Commission in an April 10, 1975 meeting.
This will be submitted by August 4, 1975.
This evaluation will address the effect of pool swell on the drywell suppression chamber vent system.
The submittal will include plan and section drawings of the containment.
These will illustrate the structures, equipment and piping which could be subjected to hydrodynamic loads.
The tentative program and schedule as outlined below is" proposed as a response to meet the remainder of the concerns ad-dressed in the letters
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A.
Relief Valve Blowdown 1.
Document relief valve vent clearing model June 30, 1975 2.
Perform impact tests for internal structure shapes 3.
Qualify impact model 4.
Determine need for plant stress test for relief valve discharge June 30, 1975 Septemb'er. 30, 1975 September 30, 1975
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4 II B.
Pool Swell 1.
Calculate pool swell impact loads for Nine Mile Point Unit 1 September 30, 1975 2.
Calculate other significant dynamic loads December 31, 1975 3.
Complete currently planned Nark I pool swell tests December 31, 1975 4.
Confirm calculated loads 5.
Perform stress analyses tests of suppression
- chamber, internals and supports March 31, 1976 September 30, 1976 6.
Combine stresses and compare to plant licensing basis.
December 31, 1976 (1)Letter dated Pebruary 15, 1975 to Mr. Gerald K. Rhode from George Lear.
'Letter dated April 17, 1975 to Mr. Gerald K. Rhode from George Lear.
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