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OAK RfDGE NATIONAL LABORATORY CEEPATCO SV UNION CARBIDE CORPORATici1 NUCLEAR HV1510N e | OAK RfDGE NATIONAL LABORATORY CEEPATCO SV UNION CARBIDE CORPORATici1 NUCLEAR HV1510N e | ||
Po1T OFFICE sox Y cAE RioGE. TENNE 15EE 3700 Dece=ber 21, 1978 Dr. R. ' Schamberger, Chief Experimental Gas Cotied Reactor Safety Research Branch Division of Reactor Safety Research U.S. Nuclear Regulatory Commission Wasnington, D. C. 20555 | Po1T OFFICE sox Y cAE RioGE. TENNE 15EE 3700 Dece=ber 21, 1978 Dr. R. ' Schamberger, Chief Experimental Gas Cotied Reactor Safety Research Branch Division of Reactor Safety Research U.S. Nuclear Regulatory Commission Wasnington, D. C. 20555 | ||
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: 2. Post DBDA and LOFC energency cooling flows and core helium inlet temperatures and pressures are the same as those given in Ref. 2; and | : 2. Post DBDA and LOFC energency cooling flows and core helium inlet temperatures and pressures are the same as those given in Ref. 2; and | ||
: 3. Af terheat equations used are based on the updated estimates approved by NRC for LETCR safety studies, which include substantial uncertainty factors.3 | : 3. Af terheat equations used are based on the updated estimates approved by NRC for LETCR safety studies, which include substantial uncertainty factors.3 | ||
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I | I | ||
R. D. Scha=berger December 21, 1978 - | R. D. Scha=berger December 21, 1978 - | ||
Page Two | Page Two The results of the study are su=marized in Table 2, which shows peak predicted temperatures of interest for both the DBDA and the LOFC + FWCD accident. It should be noted that the predicted values of maximum cover plate temperatures are based on poorly-understood models of the plume heat transfer phenomena. Even so, the data shows clearly that eAch of the new postulated cases results in maximum temperatures that are no greater than the | ||
The results of the study are su=marized in Table 2, which shows peak predicted temperatures of interest for both the DBDA and the LOFC + FWCD accident. It should be noted that the predicted values of maximum cover plate temperatures are based on poorly-understood models of the plume heat transfer phenomena. Even so, the data shows clearly that eAch of the new postulated cases results in maximum temperatures that are no greater than the | |||
" FSAR-assumed worst case. | " FSAR-assumed worst case. | ||
Please let me know if there are any questions about the analysis, or if more detail about any of the runs is needed. | Please let me know if there are any questions about the analysis, or if more detail about any of the runs is needed. | ||
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2 Letter frem G. A. 3ramblett (CA) to S. J. Ball on FSV accident cases submitted to ::RC, Y.ay 1,1978. | 2 Letter frem G. A. 3ramblett (CA) to S. J. Ball on FSV accident cases submitted to ::RC, Y.ay 1,1978. | ||
3R. E. Sund, "Afterheat Calculations for the HTCR," Gulf CA-Al2499A (CA-LTR-4, Amend. A), July 1974. | 3R. E. Sund, "Afterheat Calculations for the HTCR," Gulf CA-Al2499A (CA-LTR-4, Amend. A), July 1974. | ||
Table 1. Initial Conditions for DBDA and LOFC Analyses. | Table 1. Initial Conditions for DBDA and LOFC Analyses. | ||
Equilibrium core (EQSB?) parameters. | Equilibrium core (EQSB?) parameters. | ||
Power to Flow T core inlet Power Flow Case ratio 'F % We % lb/ min Ref. 1.043 773.0 104.3 878.3 100 56,500 1 1.05 768.3 100 842.0 95.2 54,760 2 1.095 737.6 80 673.6 73.1 41,871 3 1.14 706.9 60 505.2 52.6 30,084 4 1.17 686.4 40 336.8 34.2 19,511 5 1.1 734.2 20 168.4 18.2 10,418 6 1.091 740.4 102 858.8 93.5 53,601 | Power to Flow T core inlet Power Flow Case ratio 'F % We % lb/ min Ref. 1.043 773.0 104.3 878.3 100 56,500 1 1.05 768.3 100 842.0 95.2 54,760 2 1.095 737.6 80 673.6 73.1 41,871 3 1.14 706.9 60 505.2 52.6 30,084 4 1.17 686.4 40 336.8 34.2 19,511 5 1.1 734.2 20 168.4 18.2 10,418 6 1.091 740.4 102 858.8 93.5 53,601 | ||
Table 2. Maximum Temperature Estimates for FSV DBDA and FWCD Accidents for Various Initial Conditions. Equilibrium (EQSB3) Core, LTR-4-A + 20/10 Afterh'est. | Table 2. Maximum Temperature Estimates for FSV DBDA and FWCD Accidents for Various Initial Conditions. Equilibrium (EQSB3) Core, LTR-4-A + 20/10 Afterh'est. | ||
Ref Case Case 1 Case 2 Case 3 Case 4 Case 5 Case 6 Inftial Power, 2 104.3 100 80 60 40 20 102 DBDA Max. Fuel Temp., 'F 2676 2617 2335 2094 1923 1826 2627 Max. Avg gas out, 'F 1768 1751 1664 1580 1512 1476 1758 Max. Region gas out, | Ref Case Case 1 Case 2 Case 3 Case 4 Case 5 Case 6 Inftial Power, 2 104.3 100 80 60 40 20 102 DBDA Max. Fuel Temp., 'F 2676 2617 2335 2094 1923 1826 2627 Max. Avg gas out, 'F 1768 1751 1664 1580 1512 1476 1758 Max. Region gas out, | ||
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@ t=2 hrs, 'F 2858 2808 2555 2317 2072 1840 2826 Max. Reverse Flow temp @ t=2 hrs, 'F 1950 1923 1762 1586 1417 1232 1929 Max. Cover Plate temp. @ t=2 hrs, "F 1619 1598 1474 1338 1209 1078 1599 Max. Forward Flow temp. af ter WCD, | @ t=2 hrs, 'F 2858 2808 2555 2317 2072 1840 2826 Max. Reverse Flow temp @ t=2 hrs, 'F 1950 1923 1762 1586 1417 1232 1929 Max. Cover Plate temp. @ t=2 hrs, "F 1619 1598 1474 1338 1209 1078 1599 Max. Forward Flow temp. af ter WCD, | ||
'F 2269 2235 2065 1926 1305 1757 2241 T-streak at time of max. Forward flow temp., *F 1924 1903 1829 1736 1646 1605 1913 | 'F 2269 2235 2065 1926 1305 1757 2241 T-streak at time of max. Forward flow temp., *F 1924 1903 1829 1736 1646 1605 1913 | ||
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1.00 4 15 25 50 75 100 | 1.00 4 15 25 50 75 100 PERCENTACE OF DESIGd CORE I | ||
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- FIC'JRE 3.1-2 | - FIC'JRE 3.1-2 | ||
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Latest revision as of 03:09, 22 February 2020
| ML19289C376 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/21/1978 |
| From: | Ball S OAK RIDGE NATIONAL LABORATORY |
| To: | Schamberger R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML19289C364 | List: |
| References | |
| NUDOCS 7901120107 | |
| Download: ML19289C376 (5) | |
Text
OAK RfDGE NATIONAL LABORATORY CEEPATCO SV UNION CARBIDE CORPORATici1 NUCLEAR HV1510N e
Po1T OFFICE sox Y cAE RioGE. TENNE 15EE 3700 Dece=ber 21, 1978 Dr. R. ' Schamberger, Chief Experimental Gas Cotied Reactor Safety Research Branch Division of Reactor Safety Research U.S. Nuclear Regulatory Commission Wasnington, D. C. 20555
Dear Bob:
Subject:
Response to DSS Request of November 21, 1978 for Assistance with Fort St. Vrain Reactor Licensing Review This letter responds to a request by DSS for CRNL to provide additional i
calculations of postulated D3DA and LCFC accidents for Fort St. Vrain (FSV).
The intent of ths request is to determine if initial conditions other than those specified in the FSAR could lead to worse conditions during a DBDA or LOFC accident. Specific conditions chosen are points along the power-to-flow ratio vs core thermal power curve (Fig. 3.1-2 from the FSV Technical Specifications),
shown in Attachment 1. The 5 points marked on the curve were chosen as initial conditions for the nalyses. A sixth point, with an initial power of 102 and an initial flow of ',3.5%, is also included to represent compounded worst-case measurement uncertainties.
Since detailed calculated core input parameters and functions are not available for these analyses, the following assumptions are made based on the GA dataz supplied for the FSV analyses done by ORNL last May:
- 1. Equilibrium core (EQSB3) peaking factors and associated refueling region curlet temperatures. In order to obtain a heat balan
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