ML19206A621
| ML19206A621 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/01/1977 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7904200296 | |
| Download: ML19206A621 (4) | |
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George F. Trewbridge, Eso.
Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 Chauncey R. Kepford, Esq.
Chai rman York Committee for a Safe Environment 2586 Broad Street York, Pennsylvania 17404 Mr. Richard W. Heward Project Manager GPU Service Corporation 250 Cherry Hill Road Parsippany, New Jersey 07054 Mr. Thomas M. Crimmins, Jr.
Safety and Licensing Manager GPU Service Corporation 260 Cherry Hill Road Parsippany, New Jersey 07054 b8 r81
222.0 Systems Analysis Section. Analysis Branch Mass and energy release to the containment for the postulated main steam line break accident is determined using a ccmbination of 3 computer codes.
These computer codes are FLASH-P, RELAP 4 and EWHAM.
These codes have not been previously reviewed by the NRC for steam line break analysis.
222.1 Discuss in detail all modifications to the FLASH-2 code which were (15.B.1) made to produce FLASH-P.
Provide and justify all equations and assumptions in the modification to the code.
222.2 Provide a diagram showing the primary loop and steam generator (15.B.1 )
simulation in the FLASH-P code.
222.3 In the FLASH-P code, a slip velocity of 500 ft/sec was utilized to (15.B.1 )
produce zero liquid entrainment at the break.
We believe that a smaller and more realistic value of slip velocity might also produce zero liquid entrainment.
The smaller value of slip velocity would increase the two phase level in the steam generator, the rate of heat flow from the primary system and the rate of steam flow from the break.
Accordingly, justify that the slip velocity assumed in FLASH-2 is conservative by performing a sensitivity analysis on this parameter.
222.4 Provide the heat transfer coefficients used in the FLASH-P code (15.3.1) for heat flow between the two steam generators and the primary system, and also between the core and the primary coolant.
Discuss how these values were made conservative for containment analysis.
222.5 The RELAP-4 computer program was utilized to calculate feedwater (15.3.1 )
flow into the ruptured and intact steam generators.
Provide or reference the version of RELAP-4 used in these analyses.
222.6 Provide the values of bubble rise velocity used in the RELAP-4 (15.B.1 )
model and discuss the conservation of the values for perfoming containment analyses.
222.7 Provide a comparison of the pressure in the ruptured steam generator (15.3.1 )
calculated by the RELAP-4 code with that calculated by FLASH-P The RELAP J pressure should be lower than that calculated by FLASH-P to provide a conservative calculation of.madwater flow rate.
222.8 Provide and justify the flow model used in the RELAP 4 code at the (15.B.1 )
broken steam line pipe and at the feedwater nozzle for critical and subsonic flow.
222.9 The BlHAM ccde was used to calculate the feedwater pump suction (15.B.1 )
pressure for use by the RELAP-4 code.
Provide documentation for the EWHAM code giving all equations and assumptions.
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222-2 222.10 Provide the results of a sensitivity study showing the effect on (15. 3.1 )
feedwater flow calculated by RELAP-4 for various values of the feedwater pump suction pressure calculated by EWHAM.
222.11 Discuss the capability of the EWHAM code to calculate pressures in (15.B.1) saturated fluids.
Discuss the accuracy of the code pressure calcu-lation at locations in the feedwater an' condensate system in the event the fluid becomes saturated during the course of the MSLB.
Provide the pressure history calculated by the EWHAM code at the feedwater pump suction.
38 e83