ML20127P542
| ML20127P542 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/03/1974 |
| From: | Stello V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 9212020247 | |
| Download: ML20127P542 (3) | |
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13N Docket No.: 50-263 Karl R. Goller, Assistant Director for Operating Reactors. L MONTICELLO - SECOND RELOAD WITH 8 X 8 FUEL ASSDBLIES TRANS!ENT ANALYS!$
USING GETAB-GEXL Plant Name: Monticello Licensing Stage: Post OL Docket No.: 50-263 Responsible Branch and Project Manager: ORB-2, J. Shea Technical Review Branch Involved:
Reactor Systems Branch Applicant Response Date: N/A Requested Completion Date: December,1974 i
Description of Response: Request for Additional Information i
Review Status: Awaiting Information We are reviewing the preliminary transient analysis submittal for the Monticello plant. The report shows the establishment of safety and operating limits in tems of MCPR (minimum critical power ratio) values for the second core reload with 8 x 8 fuel assemblies.
Enclosed is the additional infonnation required in order to continue our review.
l
'orldnM wned by ytetor sa ilo Victor Stello, Jr., Assistant Director i
for Reactor Safety l
l Directorate of Licensing
Enclosure:
Monticello Plant Infomation Request DISTRIBUTION:
cc w/o enc 1:
Central Files %'m m A. Giambusso, L L Reading File W. Mcdonald, L RSB Reading File VStello cc w/ enc 1:
S. Hanauer, DRTA A 6
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F. Schroeder, L i
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J. Shea, L R. Reid L T. Novak, L W. Minners, L R. Frahm L A. Is natonis, L oe nu
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s M0t4TICELLO PLANT !!1FORI%T10tl REQUEST 1.
Identify the scram reactivity curve used to calculate the system response following a turbine trip at the end of the equilibrium cycle.
-Is it the design basis curve ("0" curve)?
2.
Provide the nominal values of the following parameters used in the derivation of MCPR = 1.06 and 1.36:
R factor, axial power shape, axial and loc al peaking factors, radial peaking factor, nonfuel power fraction, average power density, bundle power, bundle flow, and inlet enthalpy. Justify the parameters selected.
3.
Identif method)y the relative bundle to bundle power distribution (by histogram that-is employed in the application of the GETAB statistical analysis to Monticello.
4.
What is the relative bundle power distribution of the Monticello plant at the worst time of the fuel cycle?
Is it the same as the one used in the statistical rod boiling transition analysis.
If not, justify why it-is not used in the derivation of MCPR values.
5.
-The Tlp uncertainty of 8.6% is presumably-based on a symmetric, reload core, and LPRM extrapolated TIP data (based on the information shown in N ED0-20340). Justif Monticello reload core. y the assumption of. power symmetry for the 6.
Provide an explanation for the difference in uncertainty values for the following quantities when conoared to the values shown in NED0-10958 and GESSAR?
Standard Deviation Quantity Monticello 7BTAh flEDO-10958 Core inlet Temperature 0.2 0.6 0.6 Channel friction Factor liultiplier 3.0 5.0 5.0 7.
Provide a AMCPR value for the case of a misorientated fuel assembly.
If the resulting MCPR is less than 1.0, specify the expected number of fuel rod cladd ing failures. What is the limiting value of fission product release which can be detected by the steam line monitoring system which will cause the reactor to be scramned?
What is the expected fission product release if an assembly is misoriented.
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8.
Ju stify that the turbine trip without bypass transient is the most limiting which yields a maximum t.MCPR of 0.27 for a 7 x 7 fuel bundle and O. 30 for an 8 x 8 fuel bundle.
Provide AMCPR values for other transients.
They are:
(1) load rejection with bypass (2) turbine trip wi th bypass. (3) load rejection without bypass (4) inadvertent HPCI activation. (5) two pump trip, (6) loss of 100 F feedwater heaters, 0
and (7) rod withdrawal error.
9.
Provide a curve of MCPR values versus time for the most limiting transient.
Demonstrate that LMCPR is not sensitive to the initial MCPR v alue.
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