ML19316A673
| ML19316A673 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/08/1972 |
| From: | Peltier I US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19316A672 | List: |
| References | |
| NUDOCS 8001130223 | |
| Download: ML19316A673 (2) | |
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.O-DEC 8 1972 i
h -l'iO.LQ R. C. DeYoung, Assistent Director for Preocurized Water Reactors, L THEU:
A. Schwencer, Chief PWR Eranch No. 4. L 1EETING WITH DUKE POWER CO:!PAirt, EABCOCK AND WIILOX - OCO:EE 2/3 CORE PLOODLINE EREAK ANALYSIS - DECEMBER 1.,1972 Enclosed is a omry of the nocting held with Duke Power Co::pany t
and Enbeock and Wilcox on Dece:acr 1,1972. An attendance list is also enclosed.
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I. A. Peltier Project Manager PWR-4 Enclosure
- 1. S a ry of Hecting_
- 2. Attendance List cc: v/ enclosures j
R. S. Boyd i
D. Skovbolt D. Knuth J
R. Haecary p
R. Tedesco
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H. Denton r
PWR Branch Chiefs R. W. Kleciar M. Rosen RO (3) i H. Schierling D. Knuth Each major AEC participant i
i DISTRIBUTION gDo ket i.
l RP Reading t
PWR-4 Reading
_ Project Manager-Licensing Asst.
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. ATTACHMENT I 5
Meeting With Duke Power Comapny and Babcock and Wilcox - Oconce 2/3 Core Floodline Break Analysis-December 1, 1972 Summary - The purpose of the meeting was to provide B&W with an opportunity
. to discuss with the staff the analysis and possible solution to.the core floodline break issue based upon work performed by B&W since the November 17, 1972 meeting on this subject.
The significant point that B&W tried to make at the meeting is that B&W did not impose the by-pass assumption because there are good hydraulic reasons why it is not necessary to do so and not because analysis shows that the "end of blowdown" is not reached. The remaining technical. discussion centered around the assumptions used to arrive at those hydraulic reasons.
One of the important hydraulic phenomena in this analysis is the bubble rise phenomenon. The correct way to model bubble rise in view of its possible I
sensitivity to system geometry is still an open question.
B&W did some comparison of large break models with small break models for the floodline break and claims reasonably good agreement in results regarding water remaining in the vessel.
B&W also cla ims that its non-equilibrium model shows more water left in the vessel than the equilibrium model used in BAW 10034 Supplement 1.
Dif ficulty with physical interpretation results when multinoding of the core is employed for small breaks because of phase separation. Some of the staff expressed the thought that the intent of the interim criteria could still be met with a single node in the core.
B&W stated that.50 pounds of water per_second is required to cool the core and the injection rate (for this accident) ~is 65 pounds per sec.
Therefore,_although the core may be being cooled, it will take a long time-to fill-the vessel.
B&W discussed the use of a flow restrictor in the floodline nozzle which would reduce the effective break size from 0.722 f t.2 to 0.442 f,t.2, According to B&W -this approach results in a significant savings of water j
in the primary vessel for the 'floodline break without serious penalty to the larger break analysis. -The reflood rate stays within 10_ pounds
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per second of equilibrium.
Duke and B&W l' ave concluded that the Oconce electrical system will not permit adding on another high head pump to increase the flood rate and cross connections between the two injection points would take 10 months _ to a year in a plant like Oconee.-
It is planned to hold another meeting on this subject the week of December 18,-1972 when Technical Review has completed;its own independent analysis..
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t ATTACHHENT II e
ATTENDANCE LIST j
Atomic-Energy Commission I. A. Peltier j
- H. J. Faulkner H. Schierling D. Davis B. Buckley D. Knuth J. Hendrie V. Stello D. Poss H. Sullivan t
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j Duke Power Company
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R. J. Ansell
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C. L. Sansbury Babcock and Wilcox i
i C. E. Parks k
J. E. Mecca B. M. Dunn L. R. Pletke i -
R. V. Straub D. W. Montgomery i
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