NUREG-0963, Forwards Comments on NRC Safety Research Program Budget for FY86-87, NUREG-0963, Review & Evaluation of NRC Safety Research Program for FY84-85, NUREG-1039, Review For... FY85 & NUREG-1080, Long Range Research Plan.... W/O Encl
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NUCLEAR REGULATORY COMMISSION .
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.JT.' 2 9 1334 Professor Richa h Wilson Physics Department Harvard University Cambridge, MA 02138
Dear Professor Wilson:
t Enclosed are the following reports on the NRC safety research program: .
' (1) "Coments on the NRC Safety Research Program Budget for Fiscal Years 1986 and 1987" (2) NUREG-0963, " Review and Evaluation of the Nuclear Regulatory Comission Safety Research Program for Fiscal Years 1984 and 1985" (3) NUREG-1039, " Review and Evaluation of the Nuclear Regulatory Cciaission Safety Research Program for Fiscal Year 1985" (4) NUREG-1080, "Long Range Research Plan, FY 1985-FY 1989."
Sincerely, Christopher P. Ryder Accident Source Tem Program Office Office of Nuclear Regulatory Comission P
Enclosures:
As stated 8507130231 FOIA 850415 PDR PDR ALVAREZBS-110
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Upton. Long Island. New York 11973 Deponment of Nuclear Energy 2147 July 2,1984 Mr. John Telford U.S. Nuclear Regulatory Commission Containment Systems Research 7915 Eastern Avenue Silver Springs, Maryland 20910
Dear Mr. Telford:
I am enclosing a summary of the calculational results performed at Brookhaven in support of the CLWG Standard Problem 4 (BWR Mark 1).
A detailed report describing the BNL contributions to the CLWG is in preparation and will be published late this fiscal year. Comparisons of BNL results with that of BCL and SNL are reported in the Appendix D of the Consen-sus Report. A copy of the report has been sent to you under separate cover.
Very truly yours, Kenneth R. Perkins Accident Analysis Group KRP:tr
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SUMMARY
OF BNL RESULTS FOR STANDARD PROBLEM 4 (BWRMark1)
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K. R. Perkins Department of Nuclear Energy Brookhaven National Laboratory Upton, New York 11973
, s Telephone (516) 282-2147 FTS 666-2147 i
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,, The BWR Mark I containment loads were calculated using the MARCH 1.1B code with concrete decomposition calculated separately with CORCON Mod 1 and input as gas generation "even+.s. A summary of the Mark I sensitivity study is given in Tab _le 1. Based on these results the following conclusions can be
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s Concrete Composition:
- 1. Much higher'cantainment temperatures and pressures are generated with limestene^ than with basalt.
ll) 2. Calculation:, with bmit concrete are very sensitive to free water in tha concrete.,
i Corium Disposition:
- 1. Spreading of the debris over the entire drywell floor leads to much
, more rapid gas ger.eration and correspondingly higher containment pressures but the c,ebris is also cooled more rapidly.'
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- 2. If the debr(s is confined within the pedestal wall, it stays hot (or
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heats up if it is cool) and maintains an aggressive attack on the concrete. \
Coriud Temperature:
- 1. The containment pressure and temperature is very sensitive to the initial temperature of the debris.
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' An estimate of the uncertainty range for Case 1 is included in Table 2.
Note' tMt Case 1 is, itself, an extreme case (maximum temperature, maximum H 2 generation, and maximum spreading) and should not be' confused with a best-es-timate. Thus, the "high estimate" corresponds to a limiting case of a limit-3 ing case and has an extremely,'10w probability of occurrence.
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Table 1 Summary of BWR Mark I Standard Problem Results '
Case Number 1 la le 2 3 3a~ 4 Corium Spread (m) 5 3 5 3 Debris Temperature (*F) 4130 2700 4130 2700 Concrete Type L L R B Free 110 2 (%) 3 6 3 4 8 4 Steel in Corium (Ib) 140K 140K 140K 140K Upward Radiation to No No Yes No No No No Structures RESULTS Peak Pressure (psia) 145* 154* 87 88* 108* 142* 65*
Peak Temperatures (*F)
Drywell Atmosphere 660 700 460 500* 400 450 280*
Drywell Liner 360 380 210 300* 270* 310* 240*
Wetwell Atmosphere 286* 270* 460 200* 220* 221* 220*
Wetwell Liner 175* 159* 139 138 142* 143* 143*
- Temperature or pressure is still rising after five hours
Table 2 Uncertainty in the High Temperature Limiting Case with Limestone 1
4 High Estimate
- Low Estimate * -
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Pressure Loading 164** 87 i
TemperatureLoading(*F) 700+ 460+
i (Drywell Atmosphere) l *Within five hours of vessel failure.
l? ** Note that this pressure exceeds the predicted ultimate capacity and is included.
l' i + Thermal radiation will raise local temperatures considerably above this value (to 1000'F or more).
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