ML20006B796
| ML20006B796 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 01/29/1990 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9002050362 | |
| Download: ML20006B796 (4) | |
Text
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Duke her Conrany flu & M a PO Bat 33998 lice hesident Charlotte, NC 2R 42 Nuclear Pwduction (Tl4)3t34531 DUKEPOWER January 29, 1990 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.:
20555
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Subject:
McGuire Nuclear Station Docket'Nos.. 50-369, 50-370 Catawba Nuclear Station.
Docket Nos. 50-413. 50-414 10CFR 50.46 (a)(3)(li)
ECCS Evaluation Model Changes
References:
- 1) DAP-89-661, " Duke Power Company McGuire Units 1 and 2 Reporting of ECCS Evaluation Model Revisions "
S. S. Kilborn (Westinghouse) to R. C. Futre11'(Duke) -
December 15, 1989
- 2) DCP-89-681, " Duke Power Company Catawba Units 1 and 2 Reporting of ECCS Evaluation Model. Revisions "'
S. S. Kilborn (Westinghouse) to R. C. Futrell (Duke),
December 15, 1989
- 3) NS-NRC-89-3463, "10 CFR 50.46 Annual Notification for 1989 of Modifications in the Westinghouse ECCS Evaluation.
Models," W. J. Johnson (Westinghouse) to T. E. Murley (NRC), September 5, 1989
- 4) NS-NRC-89-3464, " Correction of Errors and Modifications to the NOTRUMP code in the Westinghouse Small Break-LOCA ECCS Evaluation Model Which Are Potentially Significant "
W. J. Johnson-(Westinghouse) to T. E. Murley-(NRC),
September 5, 1989 Dear Sirst Attached are summaries of the latest ECCS-evaluation model changes for McGuire and Catawba which are submitted in accordance with the' requirements; of 10CFR 50.46 (a)(3)(ii). These summarize changes described by Westinghouse.in References 1 and 2.
Further.information has been previously-
-provided to your office per' Reference 3 and 4..
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.U. S.-Nuclear R:gulctory Commic2irn e
Jinuary 29,'1990 Page 2 I
FSAR updates for both stations will note the potentially increased peak clad temperatures resulting from these changes.
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Very truly yours, i
f C 44 /
VM Hal B. Tucker j
LTB28/lcs j
Attachment I
cci Mr. S. D..Ebneter Regional Administrator, RII e
U. S. Nuclear Regulatory Commission i
101 Marietta Street, NW, Suite 2900 i
Atlanta, Georgia. 30323 l
Mr. D. S. Hood r
Office of Nuclear Reactor Regulation
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U. S. Nuclear Regulatory Commission l
Washington, D.C.
20555 r
Dr. K. Jabbour i
Office of Nuclear Reactor Regulation u
l U. S. Nuclear Regulatory Commission-
. Washington, D.C.
20555
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Mr. P. K. VanDoorn Sr. NRC Resident Inspector.
McGuire Nuclear Station-1
.i Mr. W. 'i. Orders Sr. NRC Resident Inspector
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Catawba Nuclear Station.
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7, 1989 McGuire ECCS Evaluation Model Change Summary I. !
.1ARGE BREAK LOCA EVALUATION MODEL' s
t-A..
Several improvements were made to the BASH computer code to treat-special' analysis cases related to the tracking of fluid. Interfaces.
No,increaseinpeakcladgemperature.(PCT)isexpectedforthe majority of cases, but 30 F is' assumed as n' conservative estimate.
II.
SMALL BREAK LOCA EVALUATION MODEL A.
Modification'to preclude changing the region' designation.for a node 1 '
.:in a stack which does not contain the mixture-vapor interface (small PCT decrease).
B.
Correction of typographical errors <in the equations which calculate.
the heat transfer rate derivations for' natural convection conditions for ghe upper region of interior fluid nodes (PCT increase of uplto :
36.8 F).
C.
Correction of-an error in t.he implementation of-the equation describing-the calculation of the flow link friction parameter for-single phase flow in a non-critical flow link-(PCT decrease).-
D.
Implementation of new FORTRAN compiler which tregts numerical =
precision differently (PCT increase of up to 4.8 F).
E.
Correction of errors in. implementing equations' describing the partial derivatives of an interpolation parameter.with respect to pressure and' specific enthalpy;(PCT decrease).
r F.
Modifications to the small break ECCS Evaluation.Model version'of; LOCTA-IV'(very small PCT decrease).4 III. CHANGES IN THE APPLICATION'OF EVALUATION MODELS A,
Increaseinassumedgteamgeneratortube' plugging...fromSito64(PCT increase of up to 10.Fffor11arge break lOCA).'-
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1989 Catawba ECCS Evaluation Model Change Summary
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-1ARGE BREAK LOCA EVALUATION MODEL
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A.
Several improvements were made to the BASH computer code to treat special analysis cases related to.the tracking of fluid interfaces.
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Noincreaseinpeakcladgemperature.(PCT)isexpectedforthe majority of cases, but 10 F is assumed as a conservative estimate.
II.
SMALL BREAK LOCA EVALUATION MODEL
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' A.
Modification to preclude changing the region. designation for a' node.
in a stack which.does not contain the mixture-vapor interface (small-t
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PCT decrease).
B.' Correction of typographical errors'in the. equations which calculate the heat transfer rate derivations-for natural-convection conditions.
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for ghe upper legion of interior fluid' nodes- (PCT, increase of up to 36.0 F).
C.
Correction of an error in the implementation of the. equation' l;
describing the calculation of the flow: link friction parameter for.
single phase flow in a non-critical flow link (PCT decrease).-
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Implementation of new FORTRAN compiler which tregts numerical precision differently _(PCT increase of up to 4.8 F).
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E.
Modifications to the small break ECCS Evaluation'Model; version of LOCTA-IV (very small PCT decrease).-
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