ML20134G292
| ML20134G292 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/20/1985 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20134G295 | List: |
| References | |
| GL-83-08, GL-83-8, JPN-85-64, NUDOCS 8508230213 | |
| Download: ML20134G292 (4) | |
Text
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0 123 Main street White Plains, New York 10601 914 681.6240
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~ <'ee, ce"e t'ee Aanst 20, 1985 JR4-85-64 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Wachington, D.C.
20555 Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Mark I Containment Long Term Program Wetwell to Drywell Vacuum Breaker Response
Reference:
- 1. NRC Generic Letter 83-08, " Modification of Vacuum Breakers on Mark I Containments,"
dated February 2, 1983.
- 2. NRC letter, D. B. Vassallo to H. C. Pfefferlen (GE),
dated December 24, 1984.
Dear Sir:
Enclosed is a copy of the Mark I Wetwell to Drywell Differential Pressure Load and Vacuum Breaker Response Report for the James A.
FitzPatrick Nuclear Power Plant (JAFNPP).
This report predicts no vacuum breaker actuation during the chugging phase of a postulated loss of coolant accident (LOCA).
This transmittal completes the information required in Reference 1.
The Mark I containment long term program included the construction of a full scale test facility (FSTF) modeling a 1/16 sector of a Mark I torus and ring header, with eight downcomers.
A series of tests simulating a LOCA demonstrated a chugging phenomenon occurring at the end of the downcomers.
A vent acoustic model was developed to predict the differential pressure across wetwell to drywell vacuum breakers during the chugging phenomenon.
Concurrently, a valve dynamic model was developed to predict actuation velocities.
Application of the above methodology to the JAFNPP results in a negative (opening) differential pressure peak of 0.28 psid, applied across installed 30-inch Atwood Morrill vacuum breakers, with no predicted valve actuation.
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The methodology used has been reviewed and accepted by the Nuclear Regulatory Commission in Reference 2.
If you have any questions, please contact Mr. J. A. Gray, Jr. of
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my staff.
Very truly yours, oh'n C. Brons Senior Vice President cc:
Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, New York 13093 l
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r-ATTACHMENT 1 JPN-85 64 dated New York Power Authority James A. FitzPatrick Nuclear Power Plant Docket No. 50-333
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REFERENCES I
1.
Safety Evaluation by the Office of Nuclear Reactor Regulation on the 1
Acceptability of the Analytical Hodel for Predicting Valve Dynamics, issued by F. Eltavila, NRC, December 24, 1984.
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2.
" Hark 1 Containment Program; Hark I Wetwell to Drywell Vacuum Breaker Functional Requirements," Ceneral Electric Company Report No. NEDE 24802,
),
April 1980.
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3.
" Hark 1 Wetwell to Drywell Vacuum ' Breaker Load Hethodology, Revision 0,"
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Continuum Dynamics, Inc. Report No. 84-3, February 1984.
5 4.
" Hark I Experimental Determination of External Line Losses for Definition of External Vacuum Breaker Loads, Revision 2," Continuum Dynamics, Inc.
a 3
Report No. 81-2, September 1984.
a 5.
" Responses to NRC Request for Additional Information on Mark I Containment
[y Program Wetwell to Drywell Vacuum Breaker Load Methodology, Revision 0,"
Continuum Dynamics, Inc. Technical Note No. 84-11, October 1984.
6.
" Hark 1 Vacuus Breaker Improved Valve Dynamic Model, Revision 0,"
l Continuum Dynamics, Inc. Technical Note No. 82-31, August 1982.
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